ML13319A736

Summary of 800903 Meeting W/Util & BNL in Bethesda,Md Re Status of Steam Generator Repairs

ML13319A736
Person / Time
Site:	San Onofre
Issue date:	09/22/1980
From:	Nowicki S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8010280043
Download: ML13319A736 (5)

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'UNITED STATES NUCLEAR REGULATORY COMMISSI b

WASHINGTON, D. C. 20555

-f September 22, 1980 Docket No. 50-206 LICENSEE: Southern California Edison Company FACILITY:

San Onofre Unit No. 1

SUBJECT:

SEPTEMBER 3, 1980 MEETING TO DISCUSS THE STATUS OF STEAM GENERATOR REPAIRS AT SAN ONOFRE UNIT NO. 1 NRC and Southern California Edison (SCE)

Company representatives met in Bethesda, Maryland, on September 3, 1980, to discuss the status of steam generator repairs at San Onofre Unit No. 1. The meeting attendees are listed in Attachement 1.

The major items of discussion are described below.

1. SCE delivered with cover letter dated August 29, 1980, 20 copies of a report titled "Steam Generator Repair Report, for Southern California Edison, San Onofre Unit 1".

SCE requested that any comments or questions resulting from review of the report be trans mitted to them as quickly as possible.

2. SCE expects to start decontaminating the steam generator bowl around Saturday September 6, 1980 and sleeving about 10 days later.

3. The final restart report is still scheduled for October 7, 1980 and will include any proposed Technical Specification changes required plus the modified secondary water chemistry program.

4. The sleeve design has changed by using a hard rolled seal on the bottom joint instead of weld or braze. This change is expected to shorten the repair period by 4 to 6 weeks and to reduce radiation exposure to workers. The top joint will remain a brazed joint.

5. Test results conducted so far show that brazing can be successful within the sludge pile region. As a result of determining that brazing can be performed within the sludge pile another sleeve size will be used in the repair program. The sleeve lengths to be used in the repair program are now 36", 30" and 27".

By using the 27 inch sleeve in the peripheral region most of the affected tubes can now be sleeved. The number of tubes expected to be plugged has been reduced from 200-300 down to less than 50.

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6.

SCE described the sampling method to be-used to determine the quality of the sleeving process.

Level 1 inspection requires testing 35 tubes in a lot of 100.

Level 2 inspection requires testing 15 tubes in a lot of 100.

Level 3 inspection requires inspecting 5 tubes in a lot of 100. If one lot passes the level 1 inspection, level 2 is uesd for the second lot, and if the second lot passes inspection level 3 is used for the third lot. The NRC staff is reviewing the proposed sampling method for accpetability.

7. SCE described a leak test inspection that they propose to do initially 6.months after startup and then each refueling thereafter.

8. SCE briefly described the status of some of the tests conducted thus far. One tube had been brazed in situ and two more will be brazed the week of September 1, 1980. Strength tests conducted to determine if and by how much brazing weakens the tube were completed. Their results show that brazing does not weaken the joint, i.e., tube plus sleeve plus braze retains the same tensil strength as a new tube.

9. Since sleeving is considered to be a long term fix SCE is considering extending pot boiler tests beyond startup. The extent of the continued tests has not yet been determined.

10. The NRC staff discussed the anticipated schedule of review. Around September 10, 1980 the staff expects to issue a letter discussing our preliminary assessment of the repair program, the schedule for continued review, and any open'items that need to be addressed before startup.

Around October 1, 1980 the staff would issue a letter transmitting an evaluation of the sleeving operation and decontamination. On October 7, 1980 SCE plans to submit a letter request for restart to power with any proposed license changes. Around November 1, 1980 the NRC would transmit our evaluation of the request to return to power including a Safety Evaluation of integrity of steam generators including in-service inspection, ALARA and radiological evaluation, and the modified chemistry program. This transmittal will also include our evaluation of the environ mental impact.

Stanley J. Nowicki, Project Manager Operating Reactors Branch #5 Division of Licensing

Attachment:

List of Attendees D!-:

DL:

OFFICE

~fie SURNAME0..SNo i:cc DCr hfield DATE 9 /80 9/2 /80 {.

NRC FORM 318 (9-76) NRCM 0240

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GOVERNMENT PRINTING OFFICE: 1979-289-369

MEETING

SUMMARY

DISTRIBUTION Dock t NRC POR Local PDR rai t,

ORB Reading RGLATOR COPY NRR REading H. R. Denton E. G. CAse D. Eisenhut RPurple JRoe TNovak Rtedesco GLainas G. Zech J. Heltemes, AEOD SVarga RReid TIppolito RClark DCrutchfield OELD OI&E (3)

HSmith ACRS (16)

NRC Participant NSIC TERA cc: listing

Mr. September 22, 1980 cc Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459)

Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Crystal Mall #2 SSamuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN:

EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Conpany P. 0. Box 1831 San Diego, California 92112 Resident Inspector c/o U. S. NRC P. 0. Box AA Oceanside, California 92054 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 C ha i rria n Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814

ATTACHMENT 1 ATTENDANCE

1. S. J. Nowicki NRC

2. D. Crutchfield NRC

3. B. Curtis SCE

4. P. DeRosa W NSD

5. C. Hirst W NTD

6. A. W. Klein W SOD

7. D. Rooyen BNL

8.

B. Turovlin NRC

9. R. Krieger SCE

10. W. Collins IE/NRC

11.

J. Wing NRC

12.

B. Allen SCE

13. F. Wit NRC

14. L. Frank NRC

15. G. Frieling WEPCo

16. J. Taylor W NSD

17. J. S. Creswell AEOD

18. L. F. Miller NRC

19. E. J. Brown NRC

20. D. T. Huang NRC

21.

E. L. Murphy NRC

22. H. F. Conrad NRC

23. R. Emch NRC

24. B. D. Liaw NRC