regulatur@onformation distribution …penetrations and coaxial cable); 2) nureg-0737, item ii.f.1.6,...

REGULATUR@ONFORMATION DISTRIBUTION SI)TEM (RIDS)

ACCESSION NbR:8303040399 DOC,DATE: 83/02/28 NOTARIZED: NO FACIL:SO-263 Monticello Nuclear Generating Plant, Northern States AUTH.NAME AUTHUR AFFILIATION MUSOLFD, Northern States Power Co, RECIP,NAME RECIPIENT AFFILIATION

Office of Nuclear Reactor Regulation, Director

SUBJECT: Forwards response to IE Bulletin 79-01B,Suppl 3, "Qualification of TMI Action Plan Equipment," covering containment monitors,

DISTRIBUTION CODE: A0488 COPIES RECEIVED:LTR 4 ENCL TITLE: OR/Licensing Submittal: Equipment Qualification

DOCKET # 0500 0263

SIZE; -

NOTES:

RECIPIENT ID CODE/NAME

NRR ORB2 BC 12

COPIES LTTR ENCL

1 0

RECIPIENT ID CODE/NAME

NICOLARASH 01

COPIES LTTR ENCL

1 1

INTERNAL: ELD/HDS1 IE FILE NRR/DE/EQ8 NRR/DL

EXTERNAL: ACRS NRC PDR NTIS

12 09 07 06 04

15 02 31

1 1 2 1 1

8 1 1

1 1 2 1 1

8 1 1

GC NRR CALVOJ NRR/DL DIR NRR/DSI/AEB RGN3

LPDR NSIC

TOTAL NUMBER OF COPIES REQUIRED: LTTR

13 1 1

14 1 1 1

1 1 1 1 1

1 1

03 05

1 1

25 ENCL 24

(0) ()

NORTHERN STATES POWER COMPANY

February 28, 1983

Director Office of Nuclear Reactor Regulation Attn: Document Control Desk U. S.. Nuclear Regulatory Commission Washington, D.C. 20555

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22

Response to IE Bulletin 79-01B Supplement No. 3 - Qualification of TMI ACTION Plan Equipment

Supplement No. 3 to IE Bulletin 79-01B requires submittal of environmental qualification information for TMI Action Plan equipment not requiring preimplementation review by the NRC.

Attached is the requested information for additional Action Plan equipment located in a harsh environment. The following equipment is included: 1) NUREG-0737, Item II.F.1.3, High Range Containment Monitor (Containment Penetrations and Coaxial Cable); 2) NUREG-0737, Item II.F.1.6, Containment Hydrogen Concentration Monitor.

This submittal completes our response to IE Bulletin 79-01B, Supplement No. 3. Please contact us if you have any questions related to our response.

David Musolf Manager - Nuclear Support ervices

DMM/slv

cc: Regional Director-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G. Charnoff

8303040399 930228 PDR ADOCK 05000263 a PDR

Rev. 1 12/18/82

Ic SYSTEM: NUREG 0737, Item II.F.1 Accident Monitoring

PLANT IDENTIFICATION LOCATION N GENERIC NAME INSIDE PRIMARY OUTSIDE PRIMARY

NUMBER CONTAINMENT CONTAINMENT

RE 7960A-B Radiation Monitor X

PT 725LA-B Pressure Transmitter X

LT 7338A-B Level Transmitter X

AT 4018A-B Hydrogen Analyzer X

Heat Tracing System

SV 4001A-B Solenoid Valve X






C

0Rev. 1 12/8/82

COMPONENTS

PLANT IDENTIFICATION LOCATION

GENERIC NAME INSIDE PRIMARY OUTSIDE PRIMARY NUMBER CONTAINMENT CONTAINMENT

Rockbestos Firewall III Control Cable X

Samuel Moore Saelo o #1952Instrument Cable X Dakorad #1952

Raychem Rachem Splices X WCSF-N

D. G. O'Brien D.6 G Odles Electrical Penetratim X M06 & M62 Modules

Rockbestos Firewall III Coaxial Coaxial Cable X

Rockbestos Freall EPPower Cable X Firewall EP

Samuel Moorex De oora #1Instrument Cable X Dekorad #1962

Revision 0 12/27/82 II.F.1-4-1

COMPONENT EVALUATION WORKSHEET

ENVIRONMENT DOCUMENTATION REF. QUALIFI- OUTSTANDCATION ING

EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- HMETHOD ITEMS PARAMETER CATION CATION CATION CATION

Containment

PLANT 1.D. NO.: AT 4018A-B

COMPONENT: Hydrogen Analyzer

MANUFACTURER: Comsip-Delphi

MODEL NO.: K IV

FUNCTION: Indication

Spec NA Demo 2%

Containment Hydrogen Concentration

Reactor Bldg 935' elev.

OPERATING TIME

180 days 100 days Reference 3

Reference

1

Sequential

Test

Note 3

TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 1 NA NA NA

PROVIDED

PRESSURE (PSIG) Note 1 NA NA NA

RELAT IVE HUMIDITY NA NA Note 1 NA NA NA

CHEMICAL SPRAY

RADIAT iON

(RADS)

AGING

NA

6.7 x 10 4

NA NA NA NA NA

1* I I -t *

1 x 106 Reference 2

Reference 1

NA NA

4. 4. 4 4 4 I

NA Various NA Reference 1

NA NA

SU 11MERGENCEj NA { NA NA NA NA NA

9

SYSTEM:

ACCURACY:

SERVICE:

LOCATION:

Revision 0 12/27/82 II.F.1-4-2

REFERENCES:

1. IEEE-323-1974 Prototype Qualification for Hydrogen Analyzer Systems K-III and K-IV, Project 1035-1, Revision 1, September, 1981.

2. Plant Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.

3. Combustible Gas Control System Design Specification NSP-63-105.

NOTES:

1. This equipment is not required to function for any event which results in a harsh pressure, temperature, or humidity environment.

2. Age sensitive components will be replaced at intervals, as recommended by the manufacturer.

3. The operating time specification is an extremely conservative assumption. However, additional testing is planned by the manufacturer to demonstrate operability for 180 days.

I*

40

ff

Revision 0 12/27/82 II.F.1-5-1

COMPONENT EVAL.UATION WORKSHEET

ENVIRONMENT DOCU4ENTATION REF. QUALIFI- OUTSTANDCATION ING

EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION JCATION _

SYSTEM: Containment

PLANT 1.D. NO.: NA

COMPONENT: Heat Tracing

MANUFACTURER: Thermon

MODEL NO.:

FUNCTION:

ACCURACY:

SERVICE:

LOCATION:

NA

Sample Line Heating

NA

H2 Analyzer Sample Lines

Reactor Building, 935' Elev. & Torus Room

OPERATING TIME


Note 1 Sequential

Test

None

TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 2 NA NA NA

PROVIDED


RELATIVE HUMIDITY NA NA Note 2 NA NA NA

(%)

CHEMICAL SPRAY NA NA NA NA NA NA

RADIATION78 1 x 10 2.5 x 10 Reference Reference Seqential None

(RADS) 2 3 Test

AGING NA 30 yrs. NA Reference 3

Sequential Test

None

I I I

SUBMERGENCE

S

NA NA NA NA NA NA

. I

Revision 0 12/27/82 II.F.1-5-2

REFERENCES:


2. Plait Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.

3. Nuclear Component Qualification Test Report for Process Temperature Control System, SWRI-7033-001, September 25, 1982.

I

NOTES:

1. Since the only accident parameter of concern is radiation, use of the 180 day integrated dose values of Reference 2 as a qualification requirement provides adequate consideration of operating time.

2. This equipment is not required to function for any event which results in a harsh pressure, temperature, or humidity environment. 0

0s

Rev. 0 12/27/82 II.F.1-6-1



EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS PARAMETER CATION CATION CATION CATION

SYSTEM: Containment OPERATING TIME 180 days >180 days Reference Note 1 Sequential None

PLANT I.D. NO.: See Below 1 Test

COMPONENT: Solenoid Valve TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 2 NA NA NA

MANUFACTURER: Valcor PROVIDED

MODEL NO.: V-526-5295-67 PRESSURE

FUNCTION: Sample Line Isolation (PSIG) Note 2 NA NA NA

ACCURACY: N/A RELATIVE HUMIDITY NA NA Note 2 NA NA NA

SERVICE: H2 Analyzer Sample

Lines CHEMICAL SPRAY NA NA NA NA NA NA

Plat ID-Nos:

SV 400ZA-B SV 4003A-B RADIATION 7 SV 4004A-B 1 x 10 2 x 108 Reference Reference Sequential None

SV 4005A-B (RADS) 2 3 Test

SV 4020A-B

AGING NA 8 yrs NA Reference Sequential Note 3

LOCATION: Reactor Bldg. 935' elev. 3,4 Test

SUBMERGENCE NA NA NA NA NA NA

Rev. 0 12/27/82 II.F.1-6-2

REFERENCES: I NOTES:



3. Valcor Qualification Report QR52600-5940-2 with Valcor Comparison Report SK10848.

4. Letter, N. H. Boroson (Valcor) to P. M. Donnelly, Nutech, dated March 20, 1981.


2. This equipment is not required to function for any event which results in a harsh pressure, temperature of humidity environment.

3. Age sensitive materials will be replaced as recommended by the manufacturer.

0

0

Revision 1 2/7/82 Comp-4-1


ENVIRONMENT DOCUMENTATION REF.. QUALIFI- OUTSTAND


SYSTEM: Components OPERATING 180 days Sequential TIME Note 1 15 days Note 2 Reference Test/ None

PLANT 1.D. NO.: JX-106, JX-107 1,2,3 Analysis

COMPONENT: Electrical Penetration TEMPERATURE SEE ACCIDENT & USAR (OF) TEST PROFILES Figure Reference Sequential Note 4

MANUFACTURER: D. G. O'Brien PROVIDED 5.2-16 Reeec Test/ Note 3 Analysis

MODEL NO.: M06 M62 Modules PRESSURE USAR

FUNCTION: NA (PSIG) Figure Reference Sequential Note 4 5.2-15 1,2,3 Analysis

ACCURACY: NA RELATIVE FSAR HUMIDITY 100 100 Figure Reference Sequential

(%) 5232 123 Test/ None SERVICE: Drywell Radiation 1,2,3 Analysis

Monitor CHEMICAL 4000 ppm Sequential SPRAY Demin Boron Reference Reference Test/ None Wtr4 1,2,3 Water 2000 ppm Analysis

RADIATION 3.8 x 107 Reference 5 Reference Sequential

(RADS) gamma 8 2.2 x fo 8 Reference 4 1, 2, 3 Test/ Note 2 x 10 Analysis

AGING Reference Sequential NA 40 years NA 1,2,3 Test/ Note 5 LOCATION: Containment Analysis

FLOOD LEVEL ELEV: 922' SUBMERGENCE NA NA NA NA NA NA

ABOVE FLOOD LEVEL: YES X NO

0

0


REFERENCES: NOTES:

1. D. G. O'Brien, Inc., ER 287 Qualification Report.

2. D. G. O'Brien, Inc., Prototype Test Report, Low Voltage Power and Instrumentation Electrical Penetrations, DGO Report No. ER 268.

3. Letter, D. E. Dunfee & H. P. Hilberg (DGO) to G. W. Gunther (NSP) dated December 7, 1981, N-3423-63001.

4. Response to Equipment Qualification SER, EDS Report 04-0910-17, November 12, 1981.

5. Plant Shielding Design RLview, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.

1. Although the total required operating time is 180 days, the duration of the harsh pressure and temperature environment is approximately 12 days.

2. In FSAR Section 14-10.1.3, the post-accident cooling capability is evaluated for 180 days. This equipment could be required to operate for that period.

3. A margin of 20oF has been added to the referenced USAR figure. See Figure B.1, attached.

4. The test profile does not envelope the arbitrarily conservative accident profile of Figure B.1 from approximately 2.5 hrs. to 23 hrs. However, the total thermal stress resulting fromthe test profile is judged to be at least equivalent to that resulting from the accident profile. We are working with the supplier to resolve this outstanding item.

5. All radiation-sensitive materials are enclosed in metal or convered by Raychem sleeving with a wall thickness greater than 70 mi. Therefore, the beta dose to these materials is less than 1% of the gamma dose. The Raychem sleeving has been qualificed in other testing to 2.9 x 100 rads (Wyle Laboratories Report 58442-1).

0


TSAT +200 F 3j4 TFSAR +20OFA

TMAX = 309OF

- SEE NOTE1

-~ M-AX = 141. 5 PS IG

THE PLANT SPECIFIC LOCA RESPONSE IS KNOWN TO HAVE DEVIATED

FROM SATURATED CONDITIONS AT 5.4 x 101 SECONDS BECAUSE AT THIS POINT THE

WORST CASE CONTAINMENT TEMPERATURE RESPONSE CURVE IFSAR FIGURE 5-2-15 (E)1

DROPS BELOW 212'F. IT IS THEREFORE CONSERVATIVE TO ASSUME THAT THE CONTAINMENT

TEMPERATURE AT THIS POINT WILL BE 232*F (TFSAR+20'F MARGIN), 10 BE CONSISTENT

THROUGHOUT THE CURVE. IT IS ALSO CONSERVATIVE TO ASSUME THAT THE REMAINING

COOLDOWN TO AMBIENT CONDITIONS CAN BE APPROXIMATED BY THE PLANT SPECIFIC

TEMPERATURE RESPONSE IFSAR FIGURE 5-2-15 (E)1 BELOW 212*F BECAUSE THE AT

GENERATING' THAT RESPONSE is 20'F LESS THAN INDICATED HERE.

I I

I I I - I

0 I I3

10-1 100 101 102 10 104 5.4 05 106 2.5 7

TIME AFTER ACCIDENT (SECONDS)

FIGURE B-1 DRYWELL PRESSURE RESPONSE AND TEMPERATURE

PROFILE USED FOR EQUIPMENT QUALIFICATION

350

300

250

7

200

rn

3,

rn

,

Hn

150 p

60

50

z 3 m z

30~ m

rn

20

/ / / /

100

'"I

010

JO

1

E; l

I. .

Rev. 1 2/7/83 Comp -4-4

D. G. O BRIEN, INC.

SHEET _________ OF _________ TITLE Fic I

REPORT NO.

SHEET - OF

3190 F AT 66 P5IG.

400 SPRAY FOR RAPID COOL.

o F

400

300

250

200

150-

100

START

<705EC.

STEAM I LOCA EXPOSURE PROFILE QA-TN}- 220 ST7P

- APPLY HOT LOCA SPRAY

3400 F AT 66 PS/G OR SLIGHTLY HIGHER TO INSURE < 70 SEC. RISE IN TIME,

300-OF AT 52 P516 SATURATED,

2100 F AT ZERO PS/6 /00 % RH.

180 MIN. 15 DAYS

TE5T

14.0

350

300

350

200

150

100 -

END

BRIEF AS PRACTICAL TEST

0

< 70 SEC.

TITLE


Revision 0 12/8/82 Comp -.5 -1

ENVIRONMENT DOCUMENTATION REF.. QUALIFI- OUTSTANDCATION ING


SYSTEM: NA OPERATING 180 days Reference Sequential TIME Note 1 30 days Note 3 1 Test None

PLANT 1.D. NO.: NA

COMPONENT: Coaxial Cable TEMPERATURE SEE ACCIDENT & USAR (OF) TEST PROFILES Figzure Reference Sequential

MANUFACTURER: Rockbestos PROVIDED 5.2-16 1 Test None

Note __

MODEL NO.: RSS-6-104-1081 PRESSURE

FUNCTION: NA (PSIG) USAR Reference Sequential Figure 1 Test None 5.2.15

ACCURACY: NA RELATIVE USAR HUMIDITY 100 100 Section Reference Sequential

(%) 5.2.3.2 1 Test None SERVICE: Drywell Radiation

Monitor (Nureg 0737, CHEMICAL 3000 ppm Item II.F.1) SPRAY Demin Boron Reference Reference Sequential

Na0H for 2 1 Test None pH 9-11 .

RADIATION 3.8 x 10 2.6 x 108 Reference 2 Reference 1 Sequential gamma Ts

(RADS) 2 x 108 gamma + Reference 3 Reference 4 Test N 2 0 eaEngr. None beta Analysis

Sequential AGING NA 40 years NA Reference Test None

LOCATION: Containment 1 Engr. Analysis

FLOOD LEVEL ELEV: 922' SUBMERGENCE NA NA NA NA NA NA

ABOVE FLOOD LEVEL: YES X NO

0

S


REFERENCES:

1. Report on Qualification Tests for Second Generation Solid Dielectric Coaxial Constructions and Cellular Dielectric Coaxial Constructions, Rockbestos Report #2806.

2. Response to Equipment Qualification SER, EDS Report 04-0910-17, November 12, 1981.


4. EDS Calculation File 0910-204-EQ-01.

NOTES:

1. Although the total required operating time is 180 days, the duration of the harsh pressure and temperature environment is approximately 12 days.

2. A margin of 200 F has been added to the referenced USAR figure. See Figure Bl, attached.

3. In FSAR Section 14-10.1.3, the post-accident cooling capability is evaluated for 180 days. This equipment could be required to operate for that period.

0

Revision 0 12/8/82 Conna-5-3

TSAT +200F ,j- TFSAR +20F

TMAX = 309OF

f- SEE NOTE1

- PMAX = 41.5 PSIG

350

300

250

r- 200

T4 m m rn

150

-n

100

50

010-1 100 10 102 103 1 105 106 2.5 18

TIME AFTER ACCIDENT (SECONDS)

FIGURE B-1 DRYWELL PRESSURE RESPONSE AND TEMPERATURE

PROFILE USED FOR EQUIPMENT QUALIFICATION

-i

60

50

m

En (on

rn

20/

/

-1

0-1 10

A

\11"

THE PLANT SPECIFIC LOCA RESPONSE IS KNOWN TO HAVE DEVIATED 14

FROM SATURATED CONDITIONS AT 5.4 x 10 SECONDS BECAUSE AT THIS POINT THE

WORST CASE CONTAINMENT TEMPERATURE RESPONSE CURVE IFSAR FIGURE 5-2-15 (E)l

DROPS BELOW 212*F. IT IS THEREFORE CONSERVATIVE TO ASSUME THAT THE CONTAINMENT

TEMPERATURE AT THIS POINT WILL BE 232*F (TFSAR+20'F MARGIN), TO BE CONSISTENT

THROUGHOUT THE CURVE. IT IS ALSO CONSERVATIVE TO ASSUME THAT THE REMAINING

COOLDOWN TO AMBIENT CONDITIONS CAN BE APPROXIMATED BY THE PLANT SPECIFIC

TEMPERATURE RESPONSE IFSAR FIGURE 5-2-15 (E)1 BELOW 212'F BECAUSE THE AT GENERATING THAT RESPONSE is 20'F LESS THAN INDICATED HERE.

0

APPENDIX IV

LOCA Profile

*SPRAY APPLIED FOR FIRST 24-HOUR PERIOD


346*F/II3psig (min) WITHIN 3 TO 5 MIN

335F/93 psig

315*F/69 ps

---- 26

2800F/70 psig (min) WITHIN 10 SEC

Spray continuously*at rate of 0.15 &pm per square foot of spray area with solution of the following composition: 0.28 molar 113103 (3000 ppm boron) Na011 to make pil between 9-11 at 77o

5.F/28psig

212 OF/0 psi g

340L

320

250 Q

200

140

80 HR

II HR

V I

iR 4 DAYS

1 1I10

SEC

CD C

100 DAY

3 5 HR HR

1-'-

30 DAYS

1

/ . 212-F/Op5ig

I I I

I II

1


Rev. 0 12/8/82 Comnp-6-1



SYSTEM: NA

PLANT 1.D. NO.:

COMPONENT: Power Cable

MANUFACTURER: Rockbestos

MODEL NO.:

FUNCTION: P

ACCURACY:

Firewall EP

SERVICE: Heat Tracing and Hydrogen Analyzer (Nureg 0737, Item II.F.1)

OPERATING TIME


Note 1 Sequential Test

None

TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES

PROVIDED


RELATIVE HUMIDITY NA NA Note 2 NA NA NA

CHEMICAL SPRAY NA NA NA NA NA NA

RAIIATI ON 6 8 (RADS) 2 x 10 2 x 10 Reference Reference Sequential None

2 1 Test

AG LNG NA Note 3 NA NA NA Note 3

0

NA

A P

LOCATION: Various


Rev. 0 12/8/82 Comp-6-2

REFERENCES: = NOTES:

1. Cerro Wire & Cable Co., Rockbestos Products, Firewall EP Certified Test Report, December 22, 1976.

2. Plant Shielding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June 1981.

3. Combustible Gas Control System Design Specification, NSP 63-105.



3. Thermal aging performed during qualification of this cable is being evaluated to determine the qualified life. The results of this evaluation will be included in the surveillance and maintenance program as appropriate.

0


COMPONENT EVAIUATION WORKSHEET

ENVIRONMENT DOCUMENTATION REF. QUALIFI- OUTSTAND

CAT ION ING EQUIPMENT DESCRIPTION SPECIFI- QUALIFI- SPECIFI- QUALIFI- METHOD ITEMS

PARAMETER CATION CATION CATION CATION METHOD_ ITEM

SYSTEM: NA OPERATING 180 days 180 days Reference Note 1 Sequential None TIME 3 Test

PLANT 1.D. NO.: NA

COMPONENT: Instrument Cable TEMPERATURE SEE ACCIDENT & (OF) TEST PROFILES Note 2 NA NA NA

MANUFACTURER: Samuel Moore PROVIDED

MODEL NO.: 1962 PRESSURE

FUNCTION: NA (PSIG) Note 2 NA NA NA

ACCURACY: NA RELATIVE HUMIDITY NA NA Note 2 NA NA NA

(%) SERVICE: Heat Tracing

Temperature CHEMICAL Monitoring (Nureg 0737, SPRAY NA NA NA NA NA NA Item II.F.1)

RADIATION 7 8

(HADS) 1 x 10 2 x 10 Reference Reference Sequential None 2 1 Test

AGING NA Note 3 NA Reference Sequential Note 3

LOCATION: Various 1 Test


0


REFERENCES: NOTES:

1. Samual Moore Test Report, Qualification Test of Electric Cables under a Simulated LOCA/DBE, June, 1978.

2. Plant Shileding Design Review, Monticello Nuclear Plant, Bechtel Job 10040-048, June, 1981.


1. Since the only accident parameter of concern is radiation, use of the 180.day integrated dose values of Reference 2 as a qualification requirement provides adequate consideration of operating time.


3. Thermal aging performed during qualification of this cable is being evaluated to determine the qualified life. The results of this evaluation will be included in the surveillance and maintenance program, as appropriate.

regulatur@onformation distribution …penetrations and coaxial cable); 2) nureg-0737, item ii.f.1.6,...

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