ML13331A066
| ML13331A066 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/30/1981 |
| From: | Nowicki S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8104080724 | |
| Download: ML13331A066 (10) | |
Text
+3 bUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 30, 1981 Docket No. 50-206 LICENSEE:
SOUTHERN CALIFORNIA EDISON COMPANY FACILITY:
San Onofre Unit No. 1
SUBJECT:
SUMMARY
OF FEBRUARY 25, 1981 MEETING TO DISCUSS STATUS OF THE SAN ONOFRE UNIT NO. 1 STEAM GENERATOR REPAIR PROGRAM NRC and Southern California Edison (SCE) representatives met in Bethesda, Maryland on February 25, 1981 to discuss the status of the steam generator repair program for the San Onofre Nuclear Generating Station Unit 1 (SONGS-1).
The meeting attendees are listed in.attachment 1.
SCE requested the meeting to present the status of the sleeving efforts in the SONGS-1 steam generators and to determine if-the NRC had objections to the use of leak limiting sleeves.
The meeting agenda is given in attachment 2.
SCE is continuing with sleeving and joining to produce leak tight sleeves outside the sludge pile.
SCE is applying NB-3200 as the acceptance criteria for their leak sleeves in leu of the acceptance criteria pre sented previously in their steam generator repair report. Westinghouse presented data to justify ultrasonic testing (UT) for joint inspection.
Westinghouse contends that all leak paths will be identified using UT.
SCE was unable to produce leak tight sleeves within the sludge due to various technical difficulties. SCE proposed to install leak limiting sleeves in tubes that would require proprietary joining within the sludge. This could result in up to approximately 4300 tubes using the new sleeving concept for repair. The exact configuration of the leak limiting sleeve was not yet determined, however, data was presented to demonstrate anticipated leak rates of the sleeves using the mechanical joining procedures and parameters. Leak rates were reported in drops per minute with the majority of samples demonstrating no leakage under pressure during the testing. If the staff concurs that installation of leak-limiting sleeves is an acceptable repair method, then SCE will install as many leak-limiting sleeves as possible during the limited schedule and will plug the remainder of the tubes to allow startup of SONGS-1 by May 15, 1981.
8104 08 0?,q
-2 After a brief caucass, the staff told SCE that there were no apparent objections to the installation of leak limiting sleeves in the SONGS-1 steam generators.
The staff did ask that SCE verify that the safety margins in Reg. Guide 1.21 are met with the leak tight sleeves or justify why not.
The staff also asked that SCE provide responses to five additional questions concerning the leak tight sleeves.
These questions are included in attachment 3.
At the meeting's conclusion, SCE stated that they may decide that they want to reduce the number of tubes requiring repair by re-examining previous inspection data. If SCE decides to take this approach they will inform the staff.
SCE presented their schedule (Attachment 4) which allows return to power by May 15, 1981.
According to the schedule, SCE will provide the staff with the return to power request including the secondary water chemistry program on March 20, 1981.
Stanley J. Nowicki, Project Manager Operating Reactors Branch #5 Division of Licensing Attachments:
As stated cc w/attachments:
See next page
Mr. R. Dietch 3 -
March 30, 1981 cc Charles R. Kocher, Assistant Director, Criteria and Standards General Counsel Division Southern California Edison Corpany Office of Radiation Programs Post Office Box 800 (ANR-460)
Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Washington, D. C. 20460 Samuel B. Casey Chickering & Gregory U. S. Environmental Protection Three Embarcadero Center Agency Twenty-Third Floor Region IX Office San Francisco, California 94111 ATTN:
EIS COORDINATOR 215 Freemont Street Jack E. Thomas San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Corrpany 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 Chairman 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
Attachmen ATTENDANCE Stan Nowicki NRC Russ Krieger SCE K. P. Baskin SCE D. Crutchfield NRC G. Lainas NRC W. Collins NRC S. Hinson NRS R. Cloud RLCA -
cons. SCE R. Begley Westinghouse R. Willson Westinghouse D. Malinowski Westinghouse M. Short SCE A. Klein Westinghouse R. DeRosa Westinghouse J. Houtman Westinghouse A. Villasor, Jr.
Westinghouse R. Timmons Westinghouse R. Gamble NRC E. Murphy NRC P. Wu NRC Earl Brown NRC/AEOD D. Smith NRC/MTEB J. Grant NRC/MTEB D. Huang NRC/MTEB D. Collins NRC/RAB G. Toth Westinghouse D. Porter Wisconsin Electric J. O'Neill Shaw, Pittman V. Noonan NRC AGENDA NRC/SCE MEETING -
STEAM GENERATOR REPAIR PROGRAM February 25, 1981
- 1.
STATUS OF FIELD OPERATIONS
- OUT OF SLUDGE STATUS
- ACCEPTANCE CRITERIA
- PROCESS.PARAMETERS
- QUALIFICATION TESTS
- UT RESULTS AND CORRELATIONS
- 2.
LEAK LIMITING SLEEVES
- DESIGN CRITERIA o LABORATORY TEST PROGRAM AND RESULTS
- FIELD TEST PROGRAM
- 3.
TUBE PLUGGING
- 4.
LICENSING INFORMATION SCHEDULE
Att ment 3 SAN ONOFRE UNIT 1 STEAM GENERATOR SLEEVING PROGRAM FOLLOW-UP QUESTIONS AND ADDITION DATA REQUIRED
- 1. During the October 23 and 24 design review, Westinghouse indicated that the case of a severed (outer) tube (at the top of the tubesheet) had not been considered in their flow induced vibration analysis. Because the severed tube case is a likely possibility for a large number of tubes during the remaining 30 years of operation, the case should be considered in the design verification analyses.
- 2. The report of the above analysis should include a description of the boundary condition assumptions empl6yed at the tubesheet and support plates. If the sleeve is assumed to be laterally supported at the top of the tubesheet, please provide justification for this assumption in view of the sleeve to tube to tubesheet clearances which exist at that location.
- 3. Please provide vibration analysis resuIts in an appropriate format to permit a direct comparison with the previous analytical results for unsleeved tubes presented in Table G-1 of the SCE report dated April 17, 1978. These result should include the vibration response for both normal operation and steam line break accident conditions, and also include the case where neither the first nor the second support plate is assumed to provide lateral support to the tube. Provide discussion as appropriate.
- 4. Evaluate the impact of the severed tube assumption.(with the appropriate boundary conditions) on any bending moments which might be induced in the tubes during an SSE or blowdown conditions. Should the resulting bending stresses be significant, how do they affect the structural analyses presented in Sections 6.2 and 6.3 of the design report.
- 5. Calculations presented in Section 6.3.5 of the design report do not address allowable degradation (allowable defect depth, and allowable lenth in the case of cracks) beyond which the margin to burst under normal operating pressure in reduced to less than 3.0.
Will the
.3 gpm primary to secondary leakage rate limit assure a margin to burst of 3.0 at normal operating pressure for a through wall crack? Margins against tube collapse during LOCA for a degraded tube have not been addressed. Each of the above issues must be addressed before Technical Specifications plugging limits can be established. Where compliance with Regulatory Guide 1.121 margins cannot be demonstrated, appropriate justification must be provided.
Att ment 4 LICENSING INFORMATION SCHEDULE TASK DATE NRC MEETING TO REACH AGREEMENT ON 2/25/81 LEAK LIMITING SLEEVES SUBMIT TECHNICAL INFORMATION REPORT ON 3/04/81 LEAK LIMITING SLEEVES INITATE PRODUCTION 3/ 11/81 FIELD INSTALLATION OF LEAK LIMITING SLEEVES SUBMIT RETURN TO POWER REPORT 3/20/81 NRC MEETING TO REVIEW FINAL STEAM 4/15/81 GENERATOR CONFIGURATION NRC APPROVAL TO RETURN TO POWER 5/15/81
MEETING
SUMMARY
DISTRIBUTION Docket NRC PDR Local DPR ORB REading JOlshinkki SVarga TIppolito RClark JStolz DCrutchfield SNowicki OELD OI&E (3)
HSmlth ACRS (10)
NS IC TERA 0
W. Collins 97 SHinson RGamble EMurphy PWu C
EBrown DSmith JGrant DHuang DCollins VNoonan OFFICE L
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I D : 0.
URNAME o
DC 1de DATEO SFORM 318 lio80) NRCMe40 OFFICIAL RECORD COPY USGPO: 1980-329-8
MEETING
SUMMARY
DISTRIBUTION Docket/
NRC PDR Local DPR ORB REading JOlshinski SVarga TIppolito RClark JStolz DCrutchfi el d SNowicki OELD OI&E (3)
HSmith ACRS (10)
NSIC TERA W. Collins SHinson RGamble EMurphy Pwu EBrown DSmith JGrant DHuang DCollins VNoonan