ML20207C198
| ML20207C198 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/29/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207C197 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8808050111 | |
| Download: ML20207C198 (3) | |
Text
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION, RELATEDTOAMENDMENTNO.144TOFACILITYOPERATINGLICENSENO.OPR-3 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENN5YLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-289 j
1.0 INTRODUCTION
By letter dated September 15, 1987, GPU Nuclear Corporation (GPUN/licensec) submitted a request for revision of the Technical Specifications Appendix A to Operating) Licensee DPR-50 for the Three Mile Island Nuclear Station Unit j
No. 1 (TMI-1.
The proposed changes would ir. corporate surveillance and opera-bility requirements for post-accident monitoring instrumentation installed to satisfy Regulatory Guide (R.G.) 1.97.
The proposed revision incorp(orates surveillance and operability requirementsRCS) c for reactor coolant system condensate storage tank water level, wide range neutron flux monitoring, RCS hot leg temperature, and RCS pressure instrumentation.
2.0 EVALUATION The licensee has proposed to include, in the Technical Specificaticas, instru-mentation for Type A variables RCS cold leg temperature, steam generator pressure, and condensate storage tank water level and for Category 1 variables wide range neutron flux monitoring, RCS hot leg temperature, and RCS pressure.
This proposal would incorporate, into the Technical Specifications, surveillance and operability requirements for the instrumentation the licensee identified as Type A variables. The proposal would also incorporate all Category i variabbs except for coolant inventory and containment valve position indication.
The incorporation of RCS cold leg temperature, steam generator pressure, condensate storage tank water level, wide range neutron flux Witoring, RCS hot leg temperature, and RCS pressure instrumentation, in the +:hical Specifications, provides a high degree of confidence that this instrumentation will be available in a post-accident situation, h80gCK05009y99 1 000m9 P
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. The licensee identified Category 1 variables coolant inventory and containnent valve position as not required for incorporation into the Technical Specifications.
The licensee's basis for non-incorporation is that these two variables do not meet the criteria delineated in NRC Proposed Policy Statement on Technical Specification Improvements of Nuclear Power Reactors, issued February 6,1987, for detennining the required scope of Technical Specifications. The licensee states that this position is consistent with the B&W Owners Group Technical Specification Comittee's Standard Technical Specification Disposition Patrix.
A letter from T. Murley, NRR, to W. Wilgus, B&W Owners Group, dated May 9,1988, with enclosure "NRC Staff Review of Nuclear Steam Supply System Vendor Criteria to Standard Technical Specifications" discussed the subject of the inclusion of Category 1 instronentation in the Technical Specifications. On page 6 of the enclosure, to the May 9,1988 letter, the staff concluded that it is unable to confim the Cwners Group's conclusion that Category 1 Post-Accident Monitoring Instrunentation is not of prine importance in limiting risk.
Recent PRAs have shown the risk significance of operator recovery actions which would require a kncwledge of Category 1 variables.
Furthermore, recent severe accident studies have shewn significant potential for risk reduction from accident eanagenent, which nay include knowledge of these variables. The B&W Owners Group has been requested to develop further risk-based justification in support of not including Category 1 variables in the Technical Specifications. Therefore, we find the licensee's request to not include coolant inventory and containnent valve position instronentation in the Technical Specifications to be premature. This subject is one of continuing discussion between the NRC and the B&W Cwners Group.
The outcone of those discussions will detennine if additional actions are necessary at TMI-1.
Based on the above evaluation, the staff concludes that the licensee's request to revise the TNI-1 Technical Specifications to include RCS cold leg temperature, steani generator pressure, condensate storage tank water level, wide range neutron flux monitoring, RCS hot leg temperature, and RCS pressure instrumentation is acceptable and confoms to the R.G.1.97, Revision 3, criteria.
The staff finds that the licensee's request to not include coolant inventory and containment valve position instrunentation in the Technical Specifications is prcmature for the reasons discussed above.
3.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51,32, and 51,35, an envirorrnental assessnent and finding of no significant impact have been prepared and published in the Federal Register on July 29, 1988 (53 FR 28733). Accordingly, based upon the environnental assessnent, the Conrnission has detennined that the issuance of this amendnent will not have a significant effect on the quality of the human environment.
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4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such
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activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
July 29, 1988 Principal Contributor:
Barry S. Marcus 4
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