mftc for m u.s. nucle 1h regulatory coamsisb0081 … · mftc for m u.s. nucle 1h regulatory...

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MftC For M U.S. NUCLE 1H REGULATORY COamsISB0081

APPROvfD OMG NO. 3190-4104' '~ ''*REs er3imaLICENSEE EVENT REPORT (LER)

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FACILITY Naast 111 rJOCKET NUGASER (2) PAGE (3B

EDWIN I. HATCH, UNIT 2 o is;o;o;o|3 p ;6 ijop|1|4TITLE 146

Failure of valves to pass Local Leak Rate Test

EVENT DATE (S) LER NUMGER (61 REPORT DATE 17I OTHER FACILITIES INv0LVED (0}

MONTM DAY YEAR YEAR '[ b MONTH DAY YEAR F ACILITV N AMES DOCKET NUM0ERES)880

0 15101010! | I

0|1 1| 7 84 8|4-

0| 0|4-

0|1 0|9 2| 8 8| 4 0 # 5 010:0 1 | |TMiG REPORT 18 $USMITTED PUR$UANT TO THE REQUIREMENTS OP 10 CFR | ICA.c4 eae or more of the fo#eimapJ |11)Opt R ATM

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LICENSEE CONTACT FOR TMit LER 412)

NAW1 TELEPHONE NUMSER

ARE A CODE

3|6 7 r 178p}Thons L. Elton, Acting Supt. of Regulatory Compliance 9|1 |2 1 1

COMPLETE ONE LINE FOR E ACH COMPONENT FAILURE DESCRISED IN TMit REPORT 113)

RE TA"L "'MA g[ *L #

'TCAUSE SYnTEM COMPONENT y pqD$ CAUSE SYSTEM COMPONENT TU E PR s

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X S lJ IIlS | V Rl3 14 10 Y X Af D [[ I S IV Rl314 10 - Y MSUPPta=8 ENTAL REPORT EXPECTED (148 MONTM DAY YgAR

$UBMISSION

VES (19 r.e, ea**pete EMPECTED SUOMI53 TON OATEI NO| | |

A TRACTa . .,, ,e. ,.. P ~ ,,e.,-e,,, ne..,,,n.i

While shutdown for a recirculation pipe replacement outage and during the performanceof the " PRIMARY CONTAINMENT PERIODIC TYPE B AND C LEAKAGE TESTS" procedure(HNP-2-3952), as required by Tech. Specs, section 4.6.1.2.d, plant pe rsonneldetermined that the results of numerous leakage tests for pr imary containmentisolation valves were in excess of the limits specified in either Tech. Specs.sections 3.6.1.2. b or c, or the ASME SEC. XI criteria specified in HNP-2-3952, or10CFR50, Appendix J, Paragraph III.C.3.b.

The cause for the unacceptable leakages is postulated to be the result of normalequipment wear.

The primary containment isolation valves (identified in the LER's text) were repaired,functionally tested satisf actorily, and returned to service prior to start up (startup cone.ienced at. approximately 03:36 CDT on 08/29/84). ;

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPaovEo oMe No. siso-oice. *

E X PIR E S. 3/31185

PACILITV Naast (1) DOCKET DsUMBER (2) LER NUnstgR W PAGE13)

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EDWIN I. HATCH, UNIT 2 o;5gagagag 36;6 8; 4 _ 0|0| 4 __ 0g1 0|2 1 |4g OF

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This report is required by 10CFR50.73 (a)(2)(v)(C) and 10CFR50.73 (a)(2)(ii) due to thececumption that the plant did not meet the requirements of Tech. Specs. sections3.6.1.2.b and 3.6.1.2.c,10CFR50 Appendix J, Article III, A.1.d, and ASME section XI.

When the " PRIMARY CONTAINMENT PERIODIC TYPE B AND TYPE C LEAKAGE TESTS" procedure(HNP-2-3952) was performed, the plant was in cold shutdown for the recirculation pipereplacement outage.

A. At the time of discovery, plant personnel assumed that the leakage of thefollowing tests was such that the plant could not mee t the .60 La requirement ofTech. Specs. section 3.6.1.2.b.l. (Refer to Table 1 for " VALVE DESCRIPTION", "ASFOUND LEAKAGE", "AS LEFT LEAKAGE", and " REPAIR SUMMARY", The table is arrangedin alphanumeric order by valve MPL number.)

1. On 01/17/84, RHR Return to Recirculation Isolation Valve (2 Ell-F015B) wastested.

2. On 01/17/84, Core Spray Inboard Isolation Valve (2E21-F005A) and Core SprayIsolation Check valve (2E21-F006A) (i.e., both valves in penetration X-16A)were tested.

3. On 01/19/84, RCIC Steam Supply Inboard Isolation valve (2E51-F007) and RCICSteam Supply Oistboard Isolation Valve (2E51-F008) were tested.

4 On 01/26/84, RHR Shutdown Cooling Suction Isolation Valve (2 Ell-F008) wastested.

5. On 01/28/84, Vent Purge Return Inboard Isolation valve (2T48-F319) and VentPurge Return Outboard Isolation valve (2T48-F320) (i.e., both valves inpenetration X-26) were tested.

6. On 01/31/84, Vacuum Relief Inboard Isolation Valve (2T48-F310) was tested.i

7. On 01/31/84, Vent Purge Outlet Inboard Isolation Valve (2T48-F318) wastested.

8. On 02/01/84, LOCA H2 Recombiner Inboard Isolation Valve (2T49-F002B) wastested.

9. On 02/01/84, H /02 Sample Outboard Isola tion valve (2P33-F010) was2tested.

10. On 02/01/84, Vacuum Relief Inboard Isolation Valve (2T48-F309) and VacuumRelief Outboard Isolation Valve (2T48-F324) were tested (one test forPenetration X-205). Following the repair and cleaning of Vent Purge SupplyInboard and Outboard Isolation Valves, 2T48-F307 and 2T48-F103, the X-205penetration had an as-lef t leakage of 700 ACCM which was acceptable.

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MAC Form 388A U.S. NUCLEAR 6:EOULATORY COMMISSION""

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AreRovEo oue no. aiso-oio., ,

EXPIRES $/31/95

FACILITV NAast H) DOCLET NUMBER 12) LER NUMSER (g) PAGE(3)

"yY,*e aVEAR - SE N8 [,'' : i,

EDWIN I. HATCH, UNIT 2 o |5 ja jo ja | 3|6 | 6 8|4 _ 0 |0 | 4 _ 0|1 0|3 OF 1 |4|

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11. On 02/02/84, Drywell Differential Pressure System Discharge InboardIsolation Valve (2T48-F209) was tested.

12. On 03/01/84, the CRW Pump Discharge Inboard Isolation Valve (2Gil-F019) wastested.

13. On 03/02/84, TIP Drive Ball Inboard Isolation valve (2C51-J004A) was tested.

14. On 03/02/84, TIP Drive Ball Inboard Isolation valve (2C51-J004B) was tested.

15. On 03/02/84, TIP Drive Ball Inboard Isolation Valve (2C51-J004C) was tested.

16. On 03/02/84, TIP Drive Ball Inboard Isolation Valve (2C51-J004D) was tested.

17. On 03/02/84, TIP N2 Purge Outboard Isola tion Solenoid Valve (2C51-F3012)was tested.

18. On 03/02/84, Containment Spray Inboard Isola tion Valve (2 Ell-F016A) wastested.

19. On 03/10/84, Containment Spray Isolation Valve (2 Ell-F028B) was tested.

20. On 03/05/84, Chemical Pump Discharge Outbcard Isolation Valve (2Gil-F852)was tested. The redundant valve was operable. Further investigationproved 2Gil-F851 to be the cause of failure, thus 2 Ell-F852 was operable.

21. On 08/11/84, Drywell Pneumatic Return Inboard Isolation Check Valve(2P70-F091) was tested.

22. On 01/31/84, Vacuum Relief Inboard Isolation valve (2T48-F311) was tested.

B. At the time of discovery, plant personnel assumed that the leakage of thefollowing tests was such that the plant could not meet the .009 La requirement ofTech. Specs section 3.5.1.2.b.2.:

1. On 01/19/84, Dirty radwaste pump discharge outboard isolation valve(2Gil-F004) was tested. The dirty radwaste pump discharge inboardisolation valve (2Gil-F003) was found with an accep table leakage of 20ACCM; thus, this penetration remained leaktight.

2. On 02/10/84, Primary feedwater inboard isola tion valve (2B21-F010A) wastested.

3. On 02/11/84, Primary feedwater outboard isola tio n valve (2B21-F077A) wastested. This leakage test failed due to the leakage of valve 2B21-F010A.

4. On 02/10/84, Primary feedwater inboard isola tion valve (2B21-F010B) wastested.

5. On 02/12/84, Primary feedwater outboard isolation valve (2B21-F077B) wastested. This leakage test failed due to the leakage of valve 2B21-F010B.

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Areaoveo ous no siso-oio..

EXPIRES S/31/95

FACIL8Ty asAa g (y DOCKET NUGESER (2; Lgn NynaggR |g) PAGE 13)

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C. At the time of discovery, plant personnel assumed that the leakage of thefollowing test was such that the plant could not meet the 11.5 SCFH requirementof Tech. Specs, section 3.6.1.2.c.:

On 1/16/84, Primary leakage test on penetration X-7C showed a leakage rate of 30SCFH. This tested the inboard MSIV (2B21-F022C), the outboard MSIV(2B21-F028C), and a MSIV leakage control system isolation valve (2E32-F00lK).After the as-found test was performed, 2B21-F022C and 2B21-F028C were rebuilt aspart of a pre planned maintenance schedule. The X-7C penetration was retested on5/30/84 with an as-found leakage rate of 0 SCFH.

D. At the time of discovery, plant pe rsonnel assumed that the leakage of thefollowing tests was such that the plant could not meet the requirements of theindividual valve leakage rates specified as a result of ASME section XI:

1. On 01/20/84, the suction inboard isolation valves (2 Ell-F004A and2E11-F030A) for the "A" RHR pump would not pressurize. Furtherinvestigation revealed that only the 2 Ell-F004A was leaking significantly.

2. On 01/26/84, the core spray test line inboard isolation valve (2E11-F007A)was tested.

3. On 01/19/84, the HPCI pump suction outboard isolation valve (2E41-F042) andthe HPCI pump suction inboard isolation valve (2E41-F051) (i.e., bothvalves in penetration X-207) were found to have a combined leakage of 1600ACCM. Further investigation revealed that only 2E41-F051 was leakingsignificantly.

4. On 01/20/84, the torus purification suctio n inboard isola tion valve(2G51-F002) was tested.

5. On 01/27/84, the suction inboard isolation valves (2E11-F004B and2E11-F030B) for the "B" RHR pump would not pressurize. Furtherinvestigation revealed that only the 2 Ell-F004B was leaking significantly.

6. On 02/04/84, the "A" RHR testable check valve (2 Ell-F050A) was tested.

7. On 02/04/84, the "B" RHR testable check valve (2E11-F050B) was tested.

8. On 02/29/84, the HPIC turbine exhaust inboard isolation valve (2E41-F021)and the HPCI turbine exhaust outboard isola tion valve (2E41-F049) (i.e.,both valves in penetration X-214) were found to have a combined leakage of1750 ACCM. This leakage did not exceed the requirements of ASME section XI(1800 ACCM); however, on 07/09/84, the valves were overhauled and thensuccessfully retested with an as-left leakage of 40 ACCM.

9. On 02/29/84, the RCIC turbine exhaust inboard isolation valve (2E51-F001)and the RCIC turbine exhaust outboard isola tion valve (2E51-F040) (i.e.,both valves in penetration X-212) would not pressurize.

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softC Form mea U S. NUCLEAR KEIULATOdY COMMIS$10N |I

|"'LICENSEE EVENT REPORT (LER) TEXT CONTINUATION areaovso oMe No sinom..

EXPIRES 8/31/85

FACILITY MAABE til DOCKET NuesBER up LER NUMSER (6) PAGE13)

YEAR ',A' - .nIV *II I, y

EDWIN I.- HATCH, UNIT 2 o |s |o |0 jo | 3|6 | 6 8|4 - 0 |0 | 4 - 0|1 0|5 OF 1 [4TUT I# more amo e M use estamanst NE Fame mW tin

E. At the time of discovery, plant personnel assumed that the leakage of thefollowing test was such that the plant could not meet the requirements of 10CFR50Appendix J, Article III. A 1.d. :

On 08/07/84, the Chilled Water Supply loola tion Valve (2P64-F045) and ChilledWater Supply Isolation Valve (2P64-F047) were tested.

NOTE: The component failure information data and the " IDENTIFICATION OF EACH FAILEDCOMPONENT " sheets are arranged in the same order as Table 1.

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FACILtTV NAttt W OOCKET NueIBER (H LER NUMSER (S) PAGE 133

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IDENTIFICATION OF EACH FAILED COMPONENT

MPL NUMBER MANUFACTURER MODEL NUMBER

..g.g............................g.g...............................g.;....g ...., , ,

..g.g.g.........................g.g...............................g.g. g . ....g ,, ,

.........................................................................................

. 2B21-F022C Rockwell 1612 JMMNTY. . .

.........................................................................................

. 2B21-F028C Rockwell 1612 JMMNTY. . .

... g . g ............................g..........................g... g .g. g ....., , ,

.........................................................................................

. 2C51-J004B General Electric .112C2391P001 Rev. 20..

,

.........................................................................................

. 2C51-J004C General Electric .112C2391P001 Rev. 20..

.........................................................................................

. 2C51-J004D General Electric .112C2391P001 Rev. 20..

.........................................................................................

. 2C51-F3012 General Electric CAT 117C1. . .

.........................................................................................

. 2 Ell-F004A Walworth Comp. Fig. S206WE. . .

.........................................................................................

. 2 Ell-F004B Walworth Comp. Fig. S206WE. . .

.........................................................................................

. 2 Ell-F007A Walworth Comp. Fig. S206WE. . .

.........................................................................................

. 2 Ell-F008 William Powell 19023 WE. . .

.........................................................................................

. 2 Ell-F015B William Powell 19023 WE. . .

.........................................................................................

2 Ell-F016A Walworth Comp. 5281 WE. . .

| .........................................................................................

. 2 Ell-F028B Walworth Comp. 5206 WE. . .

.........................................................................................

. 2 Ell-F050A Rockwell . Fig. 970(WCC) JMMNTY..

.........................................................................................

. 2 Ell-F050B Rockwell . Fig. 970(WCC) JMMNTY..

.........................................................................................

. 2E21-F005A William Powell Fig. 16023 WE. . .

.........................................................................................

. 2E21-F006A Rockwell . Fig. 970(WCC)JMMNTY ..

.........................................................................................

NTC FCRM 384aC43)

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IDENTIFICATION OF EACH FAILED COMPONENT

MPL No. MANUFACTURER MOPEL NO.

.........................................................................................

. 2E41-F021 Atwood & Morrell & Comp. DWG 21212-C; . . .

.........................................................................................

. 2E41-F049 Walworth Comp. Fig. 5341. . .

.........................................................................................

. 2E41-F051 Fisher Controls Comp. Fig. 9120. . .

.........................................................................................

. 2E51-F001 Walworth Fig. 5312. . .

.........................................................................................

. 2E51-F007 William Powell Fig. 19023. . .

.........................................................................................

. 2G11-F004 Pacific Valves 153G-7-WE-CC. . .

.........................................................................................

. 2Cll-F019 Pacific Velves 153G-7-WE-CC. . .

.......................................... ..............................................

. 2Gil-F852 Hancock Mfg. Co. Type 950W.. .

.........................................................................................

. 2G51-F002 William Powell Fig. 1503WE. . .

.........................................................................................

. 2P33-F010 Fisher Controls Comp. 657-ES.. .

.........................................................................................2P64-F045 Walworth Comp. Fig. 5275.

. .

.........................................................................................

. 2P70-F091 Rockwell Fig. 36274.. .

.........................................................................................

. 2T48-F209 Pacific Valves 1536-7-WE-CC.. .

.........................................................................................

. 2T48-F307 Fisher Controls Comp. Fig. 9220. . .

.......................................................................................... . 2T48-F103 Fisher Controls Comp. Fig. 9220.

!. .

.......................................................................................... 2T48-F310 Fisher Controls Comp. Fig. 9220.. .



......................................................................................... |. 2T48-F.,19 Fisher Controls Comp. Fig. 9220 |.

. .


.......................................................................................... 2T49-F002B William Powell Fig. 1503 WE.. .

.........................................................................................|

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NRC Form 3eSS U.S. NUCLE A1 KliUL4=f oRY COMaslSSION

' ' ' ' . LICENSEE EVENT REPORT (LER) FAILURE CONTINUATION j"],v'o o",* *o3'"-*'o*-

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FACILITY NAME (1) DOCKET NUMSER (2) LER NUMSER (SI PAGI 133

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M C. RE RTABLE MA C. RE RTABLECAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT g y pq g

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EXPsRES s/3146

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TALLE NUMBER 1

(sheet 1 of 6)

PRIMARY CONTAINMENT PERIODIC TYPE B & TYPE C LEAKACE TESTS FAILURE SUMMARY

..................................................................................................VALVE DESCRIPTION AS AS REPAIR SU4tARY. . . . .

FOUND LEFT.. . . .

LEAKAGE LEAKACE-

. . . . .

..................................................................................................

.. . . .

1. Primary Feedwater Inboard Isolation. . . . .

Valve 2B21-F010A ** * 40 acem . Installed new valve .. . .

..................................................................................................2. Primary Feedwater Inboard Isolation. . . . .

Valve 2821-F010B ** * 0 . welded up steam cut. . , .

. on seat area; then. . . .

. machined seat;. . . .

. replaced hinge pina;.. . .

. then repacked valve .. . .

..................................................................................................3. Main Steam Inboard Isolation Valve. . . . .

2B21-F022C *** 30 SCFd 0- . rebuilt , and. . . .

. repacked valve. . . . .

..................................................................................................4 Main Steam Outboard Isolation Valve. . . . .

2821-F028C *** 30 SCFH 0 . rebuilt, and. . . .

. repacked valve. . . .

..................................................................................................5. Tip Drive Ball Valve Inboard Isolation. . . . .

2C51-J004A ** 750 acca 0 . New ball valve. . . .

. Installed. . . .


2C51-J004B ** 300 acca 0 . New ball valve. . . .

. installed. . . .


2C51-J004C ** 2150 aces 0 . New ball valve. . . .4

. Installed. . ..


2C51-J004D ** 2100 aces 0 . New ball valve. . . .

. Installed.j. . .

.................................................................................................. |

1* Would not pressurize!

.

** Redundant isolation valve / barrier in penetration was operable, j*** Both valves in penetration failed test.**** ASME test only.

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ***aeveo ous No mio-oio. |- -

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FactLif f Isaast m oocRET Nunasta (2) LI A NVWs4R tal PAGE (36

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TABLE NUMBER 1

(sheet 2 of 6)

PRIMARY CONTAINMENT PERIODIC TYPE B & TYPE C LEAKACE TESTS FAILURE SUMMARY

..................................................................................................VALVE DESCRIPTION AS AS REPAIR SUMMARY. . . .

.

FOUND LEFT. . ...

LEAKAGE LEAKAGE. . ...

..................................................................................................9. Tip N2 Purge Outboard Isolation.

Solenoid valve 2C51-F3012 ** 60 acca 25 aces cleaned internals., . . ..

inspected seat and .. . ..

orfices; then .. . ..

reassembled .. . ..

..................................................................................................

. 10. BER Pump Suction Inboard Isolation . . . .

* 350 acem nachined seats,Valve 2E11-F004A **** . .. ..

aligned wedge and .. . .

.

repacked the valve .. . ..

..................................................................................................

. 11. RFR Pump Suction Inboard Isolation . . .. . .

Valve 2E11-F004B *** * 230 acca polished seating. . . ..

surfaces and wedge; .. . ..

then repacked the .. . ..

valve .. . ..

..................................................................................................

. 12. Core Spray Test Line Inboard Isolation . . . .

2E11-F007A **** * 30 acca cleaned and. . . ..


..................................................................................................

. 13. RHR Shutdown Cooling Suction Isolation . . . .

Valve 2E11-F008 ** 3600 aces 50 acca repolished seats,. . . ..

wedge, and cleaned .. . ..

the pressure seal .. . ..

area; then repacked .. . ..

the valve .. . ..

..................................................................................................

. 14 RHR Return to Recirculation Isolation . . . .

Valve 2E11-F0158 ** 1950 acca 0 repolished seats.. . . ..

wedge, and cleaned .. . ..

the pressure seal .. . ..

area .. . ..

..................................................................................................

Would not pressurire*

Redundant isolaticn valve / barrier in penetration was opeyable.**

*** Both valves in penetration failed test.**** ASME test only,

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TABLE NUMBER 1

(sheet 3 of 6)

PRIMARY CONTAINMENT PERIODIC TYPE B & TYPE C LEAKAGE TESTS FAILURE SUP.ARY

..................................................................................................VALVE DESCRIPTION AS AS REPAIR SUMMARY. . . ..

FOUND LEFT~

.. .. .

LEAKAGE LEAKAGE. . .. .

..................................................................................................

. 15. Containment Spray Inboard Isolation . . . .

Valve 2E11-F016A ** 1000 acca 220 acca . replaced dise,. . ..

. polished st em, and .. . .

. repacked the valve .. .

..................................................................................................

. 16. RHR Test Line laolation Valve . . . .

2E11-F0288 ** 1200 acca 800 acem . replaced packing. . ..

. and 0 rings .. . .

..................................................................................................

. 17 RHR Testable Check Valve 2E11-F050A ****. * O . replaced the entire ..

. valve .. . .

......................... ........................................................................

. 18. RHR Testable Check Valve 2E11-F0505 ****. * 0 . replaced the entire ..

. valve. . . .

..................................................................................................

. 19. Core Spray Inboard Isolation valve . . . .

2E21-F003A *** 16}0 acca 20 acca . cleaned wedge and. . ..

. seat, then .. . .

(PEKETRATION I-16A) . repacked valve. . ..

..................................................................................................

. 20. Ccre Spray outboard Isolation Valve . . . .

2E21-F006A *** * 1200 aces . realigned hinge. . ..

(PENETRATION I-16A) . pin, repscked valve .. ..

..................................................................................................

. 21. KPCI Turbine Exhaust Inboard Isolation . . . .

Valve 2E41-F021 **** 1750 acem 40 acem . polished seat and. . ..

. disc, repacked valve.. . .

..................................................................................................

22. EicI Turbine Exhaust outboard Isolation . . . .

Valve 2E41-F049 **** 1750 acca 40 aces . cleaned valve,. . ..

. machined seat, .. . .

repaired disc,. . . . ,

repacked valve. . . . .

..................................................................................................

Would not pressurize*

Redundant isolation valve / barrier in penetration was opgrable.**

=** Both valves in penetration failed test.-

**** ASME test only.

nec romu mm.SaJ1

_ _ _ _ _ . _ . _. . . , _ . _ . , . , . -

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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION amoveo ous =o mo-e oa.

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EDWIN I. HATCH, UNIT 366 o |5 go go go | 3|6 | 6 8|4 _ 0|0|4 0 |1 1|2 oF 1 |4TEXT f# mom eness a w use assesnw mec psen ws; tin

TABLE NUMBER 1

(sheet 4 of 6)

PRIMARY COff7AINMENT PERIODIC TY*E B & TYPE C LEAKACE TESTS FAlt.I'RE S"MMARY

..................................................................................................VALVE DESCRIPTION AS AS REPAIR SUMKARY, . . .

.

FOUND LEFT. . ...


..................................................................................................

. 23. EPCI Pump Suction Inboard Isolation . . . .

Valve 2E41-F051 **** 1600 acca 0 installed new liner,.. . .

.

flapper, shaf t. .. . ..

tappered pins; .. . ..

replaced 0 rings, .. . ..

and repacked valve .. . ..

..................................................................................................

. 24 RCIC Turbine Exhaust Inboard Isolation . . . .

* 450 acca replaced disc seat.valve 2E51-F001 **** . .. .. .replaced valve seat,.. . .

.

then repacked valve .. . .

.

..................................................................................................

. 25. RCIC Steam Supply Inboard Isolation . . . .,,

* 30 acca wedge was notValve 2E51-F007 ** . .. ..

hitting the seat .. . ..

correctly. .. . ..

Realigned and .. . ..


..................................................................................................26. DRW Pump Discharge Outboard Isolation less than. . . .

* 20 acca lapped wedge,Valve 2011-F004 ** . .. ..

cleaned valve, .. . ..

repacked valve .. . ..

..................................................................................................

. 27 CRW Pump Discharge Inboard Isolation . . . .

valve 2G11-F019 ** 750 acca 40 aces cleaned wedge and. . . .

.

repacked the valve .. . . .

..................................................................................................28. Chemical Pump Discharge Inboard . . . .

Isolation Valve 2C11-F852 ** * 25 acca cleaned the seat. . , ., .

; and bonnet of the. . . . .

Iblocking valve

. . . . .

(2G11-F851); then .. . ..


..................................................................................................

* Would not pressurireRedundant isolation valve / barrier in penetration was operable.**

Eoth valves in penetration failed test.***

**** ASMI test only.

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION a**aoveo ows No vio-om..

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EDWIN 1. HATCH, UNIT 366 o |s |o |0 jo | 3|6 | 6 8|4 0|0|4 - 0|1 1|3 0F 1 |4-

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TABLE KUMBER 1

(sheet 5 of 6)

PRIMARY CONTAINMENT PERIODIC TYPE B & TYPE C LEAKACE TESTS PAILURE St'MMARY

* " " " " ' ' ' 'viivi' 6iiiiiiii 6k" ' " ' ' " " " " " '. " ' * li" " " ' ' ' ' "IS''"'''.'"'iiPiii'i6 AA.iii"':.

FOUND LEFT. . .. .


..................................................................................................

. 29. Torus Purification Suction Inboard . . . .

Isolation Valve 2G51-F002 **** 300 acca 25 acca Cleaned and. . . . .

repacked valve. . . . .

..................................................................................................

. 30. H022 Sample outboard IsolationValve 2P33-F010 ** 300 acca 20 acca Cleaned valve.. . . . .

replaced gaskets.. . . . .

and packing; then. . . . .

set up valve. . . . .

via a bench test. . . . .

..................................................................................................

. 31. Chilled Water Supply Isolation Valve . . . .

2P64-F045 ** 2200 acca 120 acca Machined seat and. . . ..

globe; repacked'. . . . .

valve. . . . .

..................................................................................................

. 32. Drywell Pneumatic Return Inboard . . . .

Isolation valve 2P70-F091 ** * 190 aces cleaned and. . . . .

repacked the valve. . . . .

..................................................................................................

. 33. Dryvell Differential Pressure System . . . .

Discharge Inboard Isolation Valve . . . ..

2T48-F209 ** 2200 acca 80 acca Replaced wedge and. . . ..

packing. . . . .

..................................................................................................

. 34 Vent Purge Supply Inboard Isolation . . . .

Valve 2T48-F307 *** 125 acca 0 Replaced 0 rings. . . ..

and glands.. . . . .

polished shaft,.,

. . . .

then repacked the. . . . .

(PENYTRATION X-25) valve. . . . .

..................................................................................................

. 35. Vent Purge Supply outboard Isolation . . . .

Valve 2T48-F103 *** 3800 accm 700 aces Cleaned and. . . . .

(PENETRATION X-25) repacked the valve. . . . .,

..................................................................................................

Would not pressuriae*

** Redundant isolation valve / barrier in penetration was operable.*** Both valves in penetration failed test.**** ASME test only.

esoc pine assaWa3)

._~ _ _ _ . - _

, _ _ _ . - . - - _ _ _ _ _ - - _ - _

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EDWIN I. HATCH, UNIT 366 o |s |o |o jo | 3|6| 6 8|4 0|0|4 - 0|1 1|4 0F 1 |4-

mm - . .s,. ., isi,

TABLE NUMBER 1

(sheet 6 of 6)

PRIMARY CONTAINMENT PERIODIC TYP B & TYPE C LEAKAGE TESTS FAILURE SUMMARY

..................................................................................................VALVE DESCRIPTION AS AS RIPAIR SU N Y. . . . .

FOUND LEFT. . . . .

LEAKACE LEAKAGE. . , . .

..................................................................................................

. 36. Vacuu. Relief Inboard Isolation Valve . . . .

2T48-F310 ** 360 aces 80 acca Replaced "0" rings;. . . . .

cleaned and. . . . .

repack 6d the valve. . . . .

..................................................................................................

. 37 Vacuum Relief Inboard Isolation Valve . . . .

2T48-F311 ** 2200 acca 0 Repleced "O" rings; .. . . .



........ .......................................................................................... 38. Vent Purge outlet Inboard Isolation . . . .

Valve 2T48-F318 ** 70 aces 0 Reple ed "O" rings; .. . . .



...... ...........................................................................................39. Vent Purge Return Inboard Isolation . . . .

Valve 2T48-F319 *** * 0 Replaced "0" rings;. . . . .


(PENETRATION I-26) repacked the valve. . . . .

..................................................................................................40. Vent Purge Return Outboard Isolation . . . .

Valve 2T48-F320 *** 690 acca 0 Replaced "O" rings;. . . . .


(PENETRATION X-26) repacked the valve. . . . .

...................................................................................................41. LOCA R2 Recombiner Inboard Isolation . . .

valve 2749-F0028 ** 350 acca 160 acem Cleaned, repo11shed .. . . .

and repacked valve. . . . .

..................................................................................................

* Would not pressurize** Redundant isolation valve / barrier in penetration was operable.*** Both valves in penetration failed test.**** ASME test only.

!

:

__

ls 43B

____

- . - . - - . . .

El Georgia Power Compsey -*j'~Post Office Box 439

,

Bexley, Georgia 31513_- Telephone 912 367-7781-

~912 537-9444

- Edwin 6. Hatch Nuclear Plant

September 28, 1984GM-84-862

PLANT E. I.-HATCHLicensee-Event ReportDocket No. 50-366

United States Nuclear Regulatory CommissionDocument Control DeskNashington, D.C. 20555

Attached is Licensee Event Report No. 50-366/1984-04, Rev. 1. Thisreport is required by 10 CFR 50.73(a)(2)(v)(C) and 10 CPR50.73(a)(2)(li).

m-H. C. NixGeneral Manager.

blD..

|HCN/TLE/djs'

xc: ~R.'J. KellyR. E. Conway

i J. T. Beckham, Jr.t .P. D. Rice'

K. M. Gillespie

| S. B. Tipps| R. D. Baker

Control Room,'

Document Control,

-

c F[ |*

,

5,

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