ML13331A991
| ML13331A991 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/30/1987 |
| From: | Baskin K Southern California Edison Co |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML13316B830 | List: |
| References | |
| NUDOCS 8711030321 | |
| Download: ML13331A991 (3) | |
Text
REGULATORY *ORMATION DISTRIBUTION SYS *
(RIDS)
ACCESSION NBR:8711030321 DOC.DATE: 87/10/30 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 AUTH.NAME AUTHOR AFFILIATION Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Amend Application 144 to License DPR-13,consisting of Proposed Changes 168 & 172,revising Tech Spec 4.16 to delete special insp requirements & Tech Specs 3.1.4 & 4.1.13 to delin to limitl g condi i ns for operation.Fee paid.
DISTRIBUT ON ODE. AO ID CrP1 RECEIVED TR ENCL SIZE:
+/- ;
TITLE: O Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109.
05000206 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
0 PD5 PD 5
5 BRADFUTEJ 1
1 INTERNAL: ARM/DAF/LFMB 1
0 NRR/DEST/ADS 1
1 NRR/DEST/CEB 1
1 NRR/DEST/MTB 1
1 NRR/DEST/RSB 1
1 NRR/DOEA/TSB 1
1 NRR
/ILRB 1
1 OGC/HDS2 1
0 EG FILE 01 1
1 RES/DE/EIB 1
1 EXTERNAL: EG&G BRUSKE,S 1
1 LPDR 1
1 NRC PDR 1
1 NSIC 1
1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 18
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 KENNETH P. BASKIN TELEPHONE VICE PRESIDENT 818-302-1401 October 30, 1987 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Amendment Application No. 144 SEP Topic V-5, RCS Leakage Detection San Onofre Nuclear Generating Station Unit 1
Reference:
NUREG-0829, "Integrated Plant Safety Assessment, Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1," December 1986 Enclosed is Amendment Application No. 144 to Provisional Operating License No. DPR-13. Amendment Application No. 144 consists of Proposed Change Nos. 168 and 172 which request revision of the Appendix A, Technical Specifications.
Proposed Change No. 168 is a request to revise Appendix A Technical Specification 4.16, "Inservice Inspection of Steam Generator Tubing," to delete the special inspection requirements. Recent steam generator operating and inspection results indicate that the special inspection requirements of Specification 4.16.C are no longer justified. Proposed Change No. 172 is a request to revise Appendix A Technical Specification 3.1.4, "Leakage" and create a new Specification 4.1.13, "Leakage and Leakage Detection Systems," in order to delineate the limiting conditions of operation (LCOs) and surveillance requirements for reactor coolant system (RCS) leakage and the leakage detection systems.
The imposition of these requirements is necessary to close out a Systematic Evaluation Program (SEP) issue associated with technical specification requirements for RCS leakage detection systems.
The referenced document indicates that the leakage detection systems identified as part of the SEP Topic V-5, Leakage Detection, do not meet the recommendations of Regulatory Guide 1.45 with regard to operability following a seismic event.
The NRC's position indicated that SCE should provide one 8711030321 671030 PDR ADO3CK 05000206 p
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Document Control Desk October 30, 1987 leakage detection system that will remain operable following a safe shutdown earthquake. Accordingly, the containment sump level monitors LIS 2001 and 3001, which are to be operable per the LCO proposed in Proposed Change No. 172, will be operable following a safe shutdown earthquake (SSE).
These monitors were installed in response to post-TMI requirements and their application has been previously reviewed by the NRC, both as part of post-TMI reviews and SEP reviews. These monitors are the instrumentation that the SEP review (see reference) concludes have sufficient sensitivity, but are dependent upon plant operators noticing any changes because no alarms are provided. In order to resolve this NRC concern, the San Onofre Unit 1 SSE recovery procedures will require that the control room indication from LIS 2001 and 3001 be monitored on a frequency commensurate with any leakage hazard, until such time that it can be verified that alternate leakage detection systems identified in Proposed Change No. 172 are operable, it is verified that there is no leakage, or the plant is in Mode 5 operation. In procedural form this will require a once per hour monitoring of LIS 2001 and 3001, until it is established that there is no leakage (at least three consecutive indications), when the frequency will be relaxed to once per eight hours.
The monitoring of LIS 2001 and 3001 will be discontinued when it is established that the remaining leakage detection systems described in Proposed Change No. 172 are operable or the plant is in Mode 5. This procedure revision will be completed prior to the implementation of these proposed changes. This information resolves the remaining open issues for this SEP topic that were identified in the referenced document.
Pursuant to 10 CFR 170.12, the review of Proposed Changes 168 and 172 contained in Amendment Application No. 144 have been determined to require a fee of $150.00. Accordingly, SCE's check in the amount of $150.00 is enclosed.
Very truly yours, Enclosure cc: J. 0. Bradfute, NRR Project Manager, San Onofre Unit 1 J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3
- 3. 0. Hard, California Department of Health Services