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Responds to 890418 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
	ML20245E967
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/23/1989
From:	Berry K; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GL-88-01, GL-88-1, TAC-69127, NUDOCS 8906280008
	Download: ML20245E967 (16)
	v • d • e

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. e' l l-COI1StimBIS Power Kenneth W Berry ym . Director ;

Nuclear Licensing y g General Officos: 1945 West Parnell Road. Jackson, MI 49201 (517) 788-1636 f

L June 23,'1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

RESPONSE TO A REQUEST FOR ADDITIONAL INFORMATION (RAI) DATED APRIL 18, 1989 CONCERNING GENERIC LETTER 88-01, NRC POSITION ON IGSCC IN BWR AUSTENITIC STAINLESS STEEL PIPING (TAC 69127)

NRC Staff review of Consumers Power Company's response to Generic' Letter 88-01' dated July 25, 1988 resulted in a Request for Additional.Information (RAI) dated April 18, 1989. The referenced RAI was concerned with our conformance to NRC position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR austenitic stainless steel piping. Consumers Power Company's response to the RAI is presented herein by Attachment 1.

77

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(

Kenneth W Berry Director, Nucitar Licensing l i

CC Administrator, Region III, USNRC NRC Resident I;spector - Big Rock Point Director, Safety and Reliability - Viking System Int'l Attachment f

OC0689-0005-NLO2 I

8906280008 890623 PDR ADOCK 05000155 1 p PDC _

_ _ _ _ _ _ _ ___________________a

3 1

CONSUMERS POWER COMPANY Big Rock Point Plant Docket 50-155 License DPR-6 Big Rock Point Plant Response on Generic Letter 88-01 (Tac 69127)

Request for Additional Information dated April 18, 1989 At the request of the Commission and pursuant to the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits our response to NRC letter dated April 18, 1989, enti+. led," Big Rock Point Plant Response on Generic Letter 88-01, (Tac 69127)." Consumers Power Company's response is dated June 23, 1989.

CONSUMERS POWER COMPANY ,

By a.Al - 4 - !

David P Hoffman, Vice it Nuclear Operations Sworn and subscribed to befo're me this 23rd day of June 1989.

A&ub' M.

Elaine E Buchrer, hotary Public Jackson County, Michigan My cot: mission expires October 31, 1989 i I

OC0689-0005-NLO2 4

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ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155

, RESPONSE TO A REQUEST FOR ADDITIONAL INFORMATION (RAI) DATED'APR.IL 18, 1989 June 23, 1989 l

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13 Pages OC0689-0005-NLO2 l 1

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l. ATTACHMENT A ITEM 1: Response is contained in Table 1.

ATTACHMENT A. ITEMS 2 & 3: Response is in. Table 2. Further note that Table 2 is all the IGSCC susceptible welds at BRP per )

the scope of Generic Letter 88-01. Table 2 is {

.not a complete listing of all the welds on the 3 or 4 subject systems as some systems change to carbon steel which is exempt. Note that Reactor Water Clean-up piping at Big Rock Point is three (3) inches, a-

, ATTACHMENT A. ITEM 4: Some welds at BRP are not accessible for inspection. j Methods for mitigation are discussed in following j 1 response to Attachment'B, Item 2 question. j ATTACHMENT'B. ITEM 2: In light of this, Big Rock Point performs a full system hydrostatic pressure test when returning from every refueling outage. This is approximately every 11-14 i months. System walkdowns during this 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> test i provide'the visual inspection noted by Item 4 of

, Attachment A. This pressure testing covers all welds )

in Table 2 (accessible and inaccessible).

ATTACHMENT A, ITEM 5: Response is by Table 3. Note that Generic Letter 88-01 endorses Regulatory Guide 1.45, leakage detection i criteria. NRC's evaluation of Systematic Evaluation' )

Program topic V-5 states Big Rock Point's leakage !

detection equipment resulted to acceptable conformance l to Regulatory Guide 1.45 by plant specific analysis. !

l (Reference Integrated Plant Safety Assessment Report, I

NUREG 0828, May 1984)

L l' ATTACRMENT B. ITDi 1: As stated earlier, a schedule of future examinations

~

j will not be published until the data from this outage l l is analyzed. This was the commitment made to the NRC ;

l in CPCo letter dated November 13, 1987. i 1:

' 1 ATTACH _ MENT B, ITEM 3: This is addresst?. in the response to Attachment A i iten .

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OC0689-0005-NLO2 l

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. Responses'to NRC Staff Positions-Licensee Response

Licensee Has/Will**

Accept Requests with Alternate Applied Consider for Staff Position Accept Provisions Position in Past Future Use

1. Materials Yes No Yes

12. Processes' .Yes No. Yes

3. Water Chemistry Yes No Nol

4. Weld Overlay Yes Yes-

;5. Partial Replacement .Yes No Yes

6. Stress Improvements of Yes. No Yes2 Cracked Weldments 7.: Clamping Devices Yes No Yes

'8. Crack-Evaluation and Yes No8 - Yes Repair Criteria

9. Inspection Method Yes Yes Yes and Personnel

10. Inspection Sche-dules No N

.11. Sample Expansion Yes No8 Yes

12. Leak Detection No - See Table 3 13.. Reporting Requirements' Yes Nos y,,

Answer with "yes". " check mark" or "X" in appropriate column for each of the 13 NRC Staff Positions. List and explain each provision and/or alternate position (or reference original submittal if it contains the listing and explanation). Use separate page(s) if needed.

- Answer with "yes" or "no", as appropriate, in each column for each of 13 RRC Steff Positicae.

I Based upen past IGSCC examination results at BRP, Consumerr. Power Company - .j cont.ludes that Hyd'. ogen Water Chemistry is not needed to maintain coolant chemistry effective at precluding ICSCC.

2 Cracked welds will be evalueted on a cane-by-case basis. Actions will be in j concu?rence with NRC. 5

[ s BRP supports this position / criteria.but has not had to apply in the pest since 4 all IGSCC examinations have shown acceptable results.

L.

L

" BRP IGSCC inspection schedule will be evaluated following the results of the examinations being conducted in the current refueling outage. (See CPCo submitttal dated' July 25, 1988, Page 2. Item 2).

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a, 3 ,

Table 3 Licensee Positions on Leakage Detection Already TS will be Alternate Contained Changed Position Position in TS. to include Proposed

1. Conforms with Position C of Yes - by NRC Systematic Evaluation Regulatory Guide 1.45 Program; (See Note 1)

2. Plant shutdown should be initiated when:

a) within any period of 24 Yes --- ---

hours or less, an increase is indicated in the rate of unidentified leakage in excess of 2 gpm, or b) the total unidentified Yes --- ---

leakage attains a rate of 4 5 gpm.

(See Note 1) (See Note 2)

3. Leakage monitored at least four hour No No intervals or less.

4. . Unidentified leakage includes all except:

a) Leakage into closed systems, or Yes --- ---

h) leakage into the containment Yes --- ---

atmosphere from sources that are io::ated, do not interfere '

with monitoring systems, or not from throughwall crack.

5. Provisions for shutdown within 24 No No (See Note 3) hours due to inoperable measurement ,

instruments in plants with Category f D, E, F, or G welds.

j

\

instructions: l l

Picce "X" or "yes" under appropriate column for each item. Provide 1

{'

description and justification for alternative positions if not already provided.

i l

I 1

MIO689-0293A-BT01 A-8

o

\ ..

1

[ NOTES l

k l

1) No changes in the leak detection system are planned. Plant Specific evaluation of this system by the NRC during the Systematic Evaluation Program resulted in acceptable conformance to current criteria.

(Reference IPSAR NUREG 0828, May 1984).

2) Leakrate calculations are performed daily. Leakage is continually I monitored by sump pump run times, tank levels, radiation monitoring, and temperature /due point sensors. Should monitors indicate leakage increase, calculations are performed more frequently at the discretion of operating personnel, i

3) Leakage calculations are performed daily to insure compliance with f Technical Specification 4.1.2(c). Consumers Power Company's position is L that the current Big Rock Point Technical Specifications format and surveillance requirements adequately control instrumentation operability to ensure that plant operation is in compliance with the 4.1.2(c) leakage limits.

l l

I 1

/

l l

I-l 1

l i

i i

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MIO689-0293A-BT01 A - 8A '

1

______-_-_-.

v t e Letter Sequence Request
TAC:69127, (Open)
Initiation Request Acceptance... Administration Questions 18 April 1989 Answers Results Approval... Other:
MONTHYEAR1989-04-18 [Table View]

ML20245E967

Text

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