ML13331A837
| ML13331A837 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/06/1985 |
| From: | Medford M Southern California Edison Co |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512100026 | |
| Download: ML13331A837 (6) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8512100026 DOC.DATE: 85/12/06 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 AUTH.NAME AUTHOR AFFILIATION MEDFORD,M.O.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION ZWOLINSKI,J.A.
Office of Nuclear Reactor Regulation, Director (post 851125
SUBJECT:
Application for amend to License DPR-13,changing Tech Specs in support of extended refueling outageto include seismic mods & replacement of equipment for environ qualification.
Tech Spec changes will be submitted separately.
DISTRIBUTION CODE: AOO1D COPIES RECEIVED:LTR ENCL _
SIZE:
mo TITLE: OR Submittal: General Distribution NOTES:NRR/DL/SEP Icy.
05000206 OL:03/27/67 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PWR-A PD1 PD 01 5
5 INTERNAL: ACRS 09 6
6 ADM/LFMB 1
0 ELD/HDS2 1
1 NRR PWR-A EB 1
1 NRR PWR-B EB 1
1 NRR/DHFT/TSCB 1
1 NRR/DSRO DIR 1
1 NR J RRAB 1
1 NRR/ORAS 1
0 04 1
1 RGN5 1
1 EXTERNAL: 24X I
I EG&G BRUSKES 1
1 LPDR 03 1
1 NRC PDR 02 1
1 NSIC 05 1
1 NOTES:
1 1
TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 25
/1 Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER. NUCLEAR LICENSING (818) 302-1749 December 6, 1985 Director, Office of Nuclear Reactor Regulation Attention:
Mr. J. A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 San Onofre Nuclear Generating Station Unit 1 San Onofre Unit 1 is currently shutdown for an extended refueling outage. In addition to refueling, the outage will include seismic modifications, replacement of equipment in connection with environmental qualification, fire protection modifications and other backfits. In support of this outage, several licensing actions including changes to the technical specifications will be necessary prior to return to service.
The purpose of this letter is to inform the NRC staff of the licensing actions which will require their review and approval prior to return to service and to identify proposed changes to the technical specifications which will be submitted in the near future. Provided as Enclosure 1 are the licensing actions including proposed changes required prior to return to service. to this letter is a listing of the proposed changes which will be submitted in the near future, but do not require approval prior to return to service. A brief description of the licensing actions, the reason they are required and a schedule for submittal for those proposed changes required prior to return to service is also provided. A separate proposed change to the technical specifications will be submitted for each proposed change. Your staff's prompt attention to the licensing actions including proposed changes which are required prior to return to service would be appreciated such that a timely review and approval can be obtained.
6512100026 851206 PDR ADOCK 05000206 P
Mr. 3.
December 6, 1985 If you have any questions or would like to discuss the enclosure with us please call me or Mr. 3. L. Rainsberry of my staff.
Very truly yours, Enclosure cc:
R. Dudley, NRC Project Manager F. R. Huey NRC Resident Inspector LICENSING ACTIONS REQUIRED PRIOR TO RETURN TO SERVICE SAN ONOFRE UNIT 1
- 1. Steam Generator Inspections - As part of this refueling outage a steam generator inspection will be conducted per License Condition 3.E. The results of the inspection will be submitted to the NRC for review by February 15, 1986.
NRC approval of the results will be required prior to return to service.
- 2. Additional Fire Protection Changes Related to Appendix R - The requirements of Appendix R will result in the addition of new detection, suppression and fire barrier systems.
These new systems will be included in the fire protection technical specifications and should be implemented prior to startup since the equipment will be required to be operable at that time. In addition, technical specifications for Alternate/Dedicated Shutdown Systems should also be implemented prior to return to service.
The proposed changes will be submitted as the new system technical specifications are identified, but no later than February 1, 1986.
- 3. Safety Injection Surveillance Requirements - The Technical Specification requiring 92 day SIS testing also requires SCE to propose a revision to the Technical Specification to establish a long-term surveillance program. The Technical Specification states that it is the intent that the existing interim requirements be supplanted by a long-term program. A proposed change was submitted on November 20, 1985.
ACL:4678F PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS SAN ONOFRE UNIT 1
- 1. Testing of Large Snubbers - Testing of large bore snubbers is currently impracticable due to the lack of on-site testing equipment. Upon successful installation of a snubber tester capable of testing large snubbers, these large snubbers will no longer be exempt from testing.
Installation of this testing machine is scheduled for this outage.
Accordingly, the large snubbers must be included in the representative sample of snubbers to be tested during this outage. A Technical Specification change which removes exemption from testing will be submitted subsequent to successful testing of large snubbers.
This change to the specifications is not required prior to return to service.
- 2. Safety Injection and Containment Spray Systems Maintenance Provisions The Technical Specifications allow maintenance on specific equipment in the Safety Injection and Containment Spray Systems for a limited time period during operation. This equipment does not include the containment spray valves and the feedwater and safety injection pumps. A change to the Technical Specifications would allow maintenance for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period on these items.
This change to the specifications is not required prior to return to service.
- 3. Use of the Auxiliary Saltwater Cooling Pump in Modes 5 and 6 - The Technical Specifications do not specifically address the use of the auxiliary saltwater cooling pump during Modes 5 and 6. A proposed change to the Technical Specifications would address the use of the auxiliary saltwater cooling pump in place of a saltwater cooling pump during Modes 5 and 6. This would allow maintenance to be performed on both saltwater cooling pumps during shutdowns.
This change to the specifications is not required prior to return to service at this time.
However, modifications in the area of the intake structure may necessitate the need for approval of this proposed change during the outage.
- 4.
Personnel Air Lock - Presently 10 CFR 50, Appendix J requires testing of the air lock prior to return to service following periods when containment integrity is not required. The technical specifications do not address this requirement. The proposed change will revise the technical specifications to provide for exemption from the regulation.
This is in accordance with the standard technical specifications.
This change to the technical specifications is not required prior to return to service.
- 5. Appendix 3 Leakage Acceptance Criteria - Design changes to the personnel air lock will be made during the outage in order to minimize air leakage. Subsequent to these changes, leakage acceptance criteria will be developed and a proposed change will be submitted to incorporate these criteria in the technical specifications.
Further, acceptance criteria for the seal tests of the active and passive containment ventilation isolation valves will be developed and included with the above proposed
-2 change. Also included will be a specification to reflect the limitation on the opening angle of the vent valves. This change to the specifications is not required prior to return to service.
- 6. Channel Functional Testing of Reactor Trip System and Engineered Safety Features - The current Technical Specifications do not address several Reactor Trip System and Engineered Safety Feature channel testing, checking and calibrating requirements which are performed by station procedures. A proposed change will be submitted to incorporate these actions into the Technical Specifications. This change is not required prior to return to service.
- 7. Reactor Trip System Surveillance Intervals - Plant specific Technical Specifications will be submitted to incorporate the NRC approved portions of WCAP-10271 regarding the surveillance intervals and out-of-service times identified by the reactor trip system specifications. This change is not required prior to return to service.
- 8. Core Related - A number of changes to the technical specifications will be submitted revising specifications associated with core operation.
These changes will include Control Group Insertion Limits, Core Average Burnup, Incore Instrumentation and Continuous Power Distribution Monitoring. These changes to the technical specification are not required prior to return to service.
- 9. Gross Activity Sample - Gross activity samples of the containment atmosphere are required every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during all modes of operation.
Due to the duration of the periodic containment Integrated Leak Rate Test (ILRT) there is a potential conflict in that a containment air sample may be necessary during this test. The next ILRT is currently scheduled for 1988.
The Technical Specifications should be modified prior to the test to require 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> gross activity samples during Modes 1 through 4 only (consistent with Westinghouse STS).
This change is not required prior to return to service. In the event it becomes necessary to perform an ILRT during this outage a proposed change will be submitted which requires approval prior to conduct of the ILRT.
- 10.
Diesel Generator - The technical specifications for the surveillance testing of the diesel generators will be revised to comply with the NRC Generic Letter 84-15.
These specifications will reduce the frequency of surveillance starts upon partial loss of A.C. power required for plant auxiliaries and provide new limits for diesel generator down time. This change is not required prior to return to service.
- 11.
SEP Technical Specifications - Technical specifications as a result of SEP will be submitted to the NRC.
These specifications will address leakage detection systems, overpressure mitigation system, reactor protection system and containment spray actuation system. These changes are not required prior to return to service.
ACL:4678F