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REGULATO NFORMATION DISTRIBUTION " TEM (RIDS)

ACCESSION,NBR;8312280016'OG ~ OATEN'3/12/20 NOTARIZED'O DOCKETFACIL!50»'275 Diablo Canyon Nuclear Power Planti Uni,t ii Pacif)c Ga 05000275

50. 323 Diablo Canyon Nuclear 'Power Plant-p Uni;t 2'i, Pacific Ga 05000323:AUTH~ NAME AUTHOR AFFILIATION

'SCHUYLERrJ>0, 'Pacific Gas» 8 Electr ic Co,'RECIP'NAME RECIPIENT'FFILIATION

EISENHUT'iD I G. Division. of Licensing

'SUBJECT: Forwards addi info re near .term completion of Item 4 ~ 3<„"Reactor'Tr ip Sys, Reliabil,ity," of Genel ic Ltr 83 28 8

-addiesses 13 items listed.in final SER on shunt trip design,

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PACIFIC GA S AND ELECTRIC COMPANY77 BEALE STREET ~ SAN,FRANCISCO, CALIFORNIA94106 ~ (415) 781 4211 ~ TWX 910.372 6587

J. O. SCHUYLERVICKPRKSIOKNK

NVCLKAR POWKR OKNKRAKIOM

December 20, 1983

Mr. Darrell G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D.C. 20555

Re: Docket No. 50-275, OL-DPR-76Docket No. 50-323Diablo Canyon Units 1 and 2GL No. 83-28 - Generic Implications of ATWS EventsItem 4.3 "Reactor Trip System Reliability"

Dear Mr. Eisenhut:

PGandE's letter dated November 7, 1983 provided the status ofcurrent conformance and the schedule for improvements planned for DiabloCanyon Units 1 and 2 to assure compliance with Generic Letter 83-28. Thatletter indicated that PGandE would provide additional information relating tothe near term completion of item 4.3. This letter provides that informationand addresses the thirteen items listed in the NRC's final SER dated August10, 1983 concerning the Westinghouse Owners Group's generic shunt trip design.

In accordance with the requirements of Generic Letter 83-28, NRC

approval is required prior to implementation. PGandE's current implementationschedule, pending NRC approval, is April 15, 1984.

Kindly acknowledge receipt of this material on the enclosed copy ofthis letter and return it in the enclosed addressed envelope.

Sincerely,

Enclosure

cc: J. B. MartinService List

',.-"'3i22804ih 83i220PDR ADOCK 05000275P PDR

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-ENCLOSURE- December 20, 1983I

SHUNT TRIP MODIFICATION

1. Re uest for Drawin s

"Provide the electrical schematic/elementary diagrams for the reactortrip and bypass breakers showing the undervoltage and shunt coilactuation circuits as well as the breaker control (e.g., closing)circuits, and circuits providing breaker status information/alarms tothe control room."

PGandE Res onse

Attached are electrical drawings for the reactor trip and bypassbreakers showing the undervoltage and shunt coil actuation circuits aswell as the breaker control (e.g., closing) circuits, and circuitsproviding breaker status information/alarms to the control room.

2. Re uest for Class lE Power with Indication and Overvolta e Ca abilit"Identify the power sources for the shunt trip coils. Verify thatthey are Class 1E and that all components providing power to the shunttrip circuitry are Class 1E and that any faults within non-Class 1Ecircuitry will not degrade the shunt trip function. Describe theannunciation/indication provided in the control room upon loss ofpower to the shunt trip circuits. Also describe the overvoltageprotection and/or alarms provided to prevent or alert the operator(s)to an overvoltage condition that could affect both the UV coil and theparallel shunt trip actuation relay."

PGandE Res onse

A. Power Sources

The power supplies and all components providing power to theshunt trip circuitry are Class 1E. No change has been made tothe power supply portion of the circuitry. Drawing No. SK437610Rev. 9B shows the power supply for the shunt trip coil of 52/RTAis from Battery 11 thru CKT 129D. The power supply for 52/RTB isfrom Battery 12 via CKT 229D. Since the Class 1E circuitryprovided to the shunt trip is separated from non-Class 1Ecircuitry, a fault within non-Class lE circuitry will not degradethe shunt trip function.

B. Indication

Indications on the Main Control Board for breaker operation arethe red and green position lights. The green light indicatesthat the breaker is open and power is available to the closingcircuit of the breaker. The red light indicates that the breakeris closed, and power is available to the shunt trip device. Thered lamp is connected in series with the shunt coil and an "a"auxiliary contact. This provides detectability of power failure

'I

to the shunt trip coil. A red indicating light (non-Class 1E)failure will not impact the shunt trip coil function. Forexample, if the breaker is closed, the green light is off and thered light is on. If the red light goes out with the green lightremaining off, either a power loss to the shunt trip coil or adiscontinuity in the shunt trip coil or a burned out bulb wouldbe indicated. Verification of bulb operability is readilydetermined by replacing the bulbs.

C.,

Overvolta e Conditions

The added shunt trip circuitry is powered from the reactorprotection logic voltage supply. Components in the added shunttrip circuitry have been selected based on their ability toperform their intended function up to a voltage as high as115% of nominal voltage. The reactor protection logic voltage isregulated with overvoltage protection set at 115% of normalvoltage characteristic of the SSPS.

The shunt trip coils in the reactor trip breakers are poweredfrom 125 VDC via the station batteries. Normally the shunt tripcoils are in a de-energized condition. When the trip breakersare closed, the red lamp current (approx. 50 m.a.) flows throughthe trip coil to monitor the circuit continuity. This current isnot large enough to actuate the trip coil armature. The reactortrip signal applies a nominal voltage of 125 VDC to each shunttrip coil in the redundant trains. As the breaker trips, itsauxiliary switch opens to de-energize the shunt trip coil. Sincethe 125 VDC voltage is supplied from the battery system, it maytemporarily rise to the battery equalizing voltage (not exceeding115% of the nominal voltage). The reactor trip breaker shunttrip coil can operate at this overvoltage condition withoutdeleterious effects since it is energized for a very smallinterval.

3. Re uest for Information on Added Rela s

"Verify that the relays added for the automatic shunt trip functionsare within the capacity of their associated power supplies and thatthe relay contacts are adequately sized to accomplish the shunt tripfunction. If the added relays are other than the Potter 8 BrumfieldMDR series relays (P/N 2383A38 or P/N 955655) recommended byWestinghouse, provide a description of the relays and their designspecifications."

PGandE Res onse

The added relays specified by Westinghouse are the Potter andBrumfield MDR series relays (P/N 2383A38 [125 VDC] or P/N 955655 [48VDC]). Due to the excessive time required to obtain relays throughWestinghouse, MDR5134 relays were ordered directly fromPotter-Brumfield. These relays are the same as Westinghouse P/N955655 (48 VDC). Westinghouse has verified that the relay contactsare adequately sized for the shunt trip function and are within thecapacity of their associated power supplies.

2I Page 2 of 6

4. Re uest for Test Procedure Pro osed b WOG

"That whether the test procedure/sequence used to independently verifyoperability of the undervoltage and shunt trip devices in response toan automatic reactor trip signal is identical to the test procedureproposed by the WOG. Identify any differences between the WOG testprocedure and the test procedure to be used and provide therationale/justification for these differences."

PGandE Res onse

PGandE plans to implement a test procedure that is functionallysimilar to the WOG proposed procedure. The test procedure will be ineffect prior to completion of the installation of the shunt tripmodification in Diablo Canyon Unit 1.

5. Re uest for Class 1E Shunt Tri Function

Verify that the circuitry used to implement the automatic shunt tripfunction is Class 1E (safety related), and the procurement,installation, operation, testing, and maintenance of this circuitrywill be in accordance with the quality assurance criteria set forth inAppendix B to 10CFR Part 50.

PGandE Res onse

The circuitry used to implement the automatic shunt trip function isClass 1E (safety related), and the procurement, installation,operation, testing, and maintenance of this circuitry will be inaccordance with the quality assurance criteria set forth in Appendix B

to 10CFR Part 50.

6. Re uest for Seismic uglification

"Verify that the shunt trip attachments and associated circuitryare/will be seismically qualified (i.e., be demonstrated to beoperable during and after a seismic event) in accordance with theprovisions of Regulatory Guide 1.100, Revision 1 which endorses IEEEStandard 344, and that all non-safety related circuitry/components inphysical proximity to or associated with the automatic shunt tripfunction will not degrade this function during or after a seismicevent."

PGandE Res onse

The Westinghouse Owners Group is performing seismic qualificationtests to demonstrate operability of the shunt trip in accordance withthe provisions of Regulatory Guide 1.100 Rev. 1. These tests will beperformed on a generic system encompassing the Diablo Canyon features.

3I Page 3 of 6

'3

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7. Re uest for Environmental uglification

"Verify that the components used to accomplish the automatic shunttrip function are designed for the environment where they are located."

PGandE Res onse

The components used to accomplish the automatic shunt trip functionare designed for the environment where they are located.

8. Re uest for Se aration

"Describe the physical separation provided between the circuits usedto manually initiate the shunt trip attachments of the redundantreactor trip breakers. If physical separation is not maintainedbetween these circuits, demonstrate that faults within these circuitscan not degrade both redundant trains."

PGandE Res onse

Physical separation is maintained between redundant trains in the maincontrol board, reactor trip switchgear and reactor protection logicfor the shunt trip circuitry. All interconnected circuits are alsoseparated. All current modifications are within the reactor tripswitchgear. Separation includes:

1. Dual section manual Reactor Trip and Safety Injection switcheswith metal barriers and RTV silicon compound between redundanttrain switch decks.

2. Shunt trip attachments interposing relays and their associatedterminal blocks are mounted in separated metal enclosures.

3. Reactor Protection Logic outputs for energizing the shunt tripinterposing relays are housed in existing separate metalenclosures.

4. Wiring in panels is separated per PGandE Standard drawing.

5. Field cabling from the Main Control Board and Reactor Protectionlogic to redundant Train A and Train B Reactor Trip switchgearare routed in separate raceway systems.

9. Re uest for Test Procedure of Control Board Manual Switches

"Verify that the operability of the control room manual reactor tripswitch contacts and wiring will be adequately tested prior to startupafter each refueling outage. Verify that the test procedure used willnot involve installing jumpers, lifting leads, or pulling fuses, andidentify any deviations from the WOG procedure. Permanently installedtest connection (i.e., to allow connection of a voltmeter) are acceptable."

4I Page 4 of 6

I

PGandE Res onse

Surveillance test procedure STP I-16C Rev. 1 is in effect to addressthis request(*). This procedure is attached. This test is consistentwith the WOG procedure. One jumper is utilized in step 1.b.l of theprocedure (page 6) to bypass inputs to the UV trip coils. This jumperis relocated in step 2.c.l (page 8) and removed in Step 9.j (Page 28).The installation and removal are recorded on the summary sheet page 2for steps 1.b.l. and 9.j.

10. Re uest for B ass Breaker Testin

"Verify that each bypass breaker will be tested to demonstrate itsoperability prior to placing it into service for reactor trip breakertesting.

PGandE Res onse

FSAR page 7.2-31 describes the procedure for testing the tripbreakers. The bypass breaker is closed and tripped to verify itsoperation. After its operability is verified it can be reclosed, andtesting can begin on the reactor trip breakers of the same train.

ll. Re uest the Reactor Tri Breaker 0 erabilit Indication Test Procedure

"Verify that the test procedure used to determine reactor trip breakeroperability will also demonstrate proper operation of the associatedcontrol room indication/annunciation."

PGandE Res onse

No modifications are being made to any indication for the reactor tripswitchgear. No new procedures need to be written to verify properoperation of the associated control room indication/annunciation. Asdescribed in Item 2 above, it is standard practice in the applicationof Reactor Tr'ip switchgear in Westinghouse plants to indicate in theMain Control Room that the breaker is closed (by a red light) and thatthe breaker is open (by a green light). For the schematic refer tothe generic package submitted to the NRC by letter dated June 14, 1983by the WOG.

(*) Please note that the procedure submitted to the Staff in thissubmittal is unsigned and marked FOR INFORMATION ONLY. A signed currentcopy of the procedure is available to NRC inspectors at the Plant site.

'GandEexpects to make modifications to procedures where required for plantsafety, or for other appropriate reasons. We do not plant to submit thesemodifications formally to the NRC.

5I Page 5 of 6

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12. Re uest for Res onse Time Testin

"Verify that the response time of the automatic shunt trip featurewill be tested periodically and shown to be less than or equal to thatassumed in the FSAR analyses or that specified in the technicalspecifications."

PGandE Res onse

Verification of time response testing is plant specific. Should plantspecific life cycle testing show that breaker trip response timedegrades with operation, periodic on-line response time testing willbe considered by VOG.

13. Re uest for Technical S ecification Chan e

"Propose'Technical Specification changes to require periodic testingof the undervoltage and shunt trip functions and the manual reactortrip switch contacts and wiring."

PGandE Res onse

A Technical Specificatioon change request will be submitted to modifyTechnical Specification Table 4.3-1, Item 21, incorporating therequired testing of the reactor trip function.

Attachments:

1. Drawing No. SK 437610 Rev. 9B2. Drawing No. SK 66319733 Rev. 2A3. Surveillance Test Procedure STP I-16C

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