ML20150F171

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Safety Evaluation Supporting Amend 119 to License DPR-35
ML20150F171
Person / Time
Site: Pilgrim
Issue date: 07/08/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20150F168 List:
References
NUDOCS 8807180166
Download: ML20150F171 (4)


Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 119 TO FACILI T OPERATING LICENSE NO. DPR-35 BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 1.0 INTx0 DUCTION By letter (BECo 88-026) dated December 23, 1985 the Boston Edison Company (BEC0) submitted a proposed change to the Pilgrim Nuclear Power Station (PNPS) Technical Specifications (TS). The proposed change adds equipment allowable out of service times for calibration and testing of the Reactor Protection System (RPS) and the Primary Containment Isolation System (PCIS).

At present the PNPS TS do not provide a formal time limit for keeping RPS and PCIS equipment out of service for calibration and testing.

BEC0 requested a six hour inoperable status for RPS and PCIS equipment based on the General Electric Licensing Topical Report NEDC-30851P.

In a NRC Safety Evaluation for General Electric Company Topical Report; NEDC-30844P, "BWR Owners Group Response to Generic Letter 83-28," and NEDC-30851P, "Technical Specification Improvements for BWR RPS," dated July 15, 1987, the NRC accepted the six hour out of service concept, however each licensee must show specific applicability of this report to their plant.

BEC0 had not adequately shown specific applicability of NEDC-30851P to PNPS.

The licensee submitted supplementil information in a letter (BEC0 87-026) dated February 22, 1988, addressing the applicability of NEDC-30851P to PNPS. This clarification as to the applicability of the topical report did not affect the substance of the proposed amendment as noticed.

2.0 EVALUATION The staff reviewed the BECO proposed TS changes in accordance with section 7 of the Standard Review Plan.

As a result of the staff's review of the BEC0 submittals, the following has been noted:

1)

Present PNPS TS do not provide a formal time limit for keeping RPS and PCIS equipment out of service for testing and calibration.

2)

The standard allowable out of service time for testing and calibration is two hours. BECO has requested six hours based on GE Licensing Topical Report NEDC-30851P.

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3)

Safety Evaluation Report (SER), dated July 15, 1987 reviewed NEDC-30851P and conditionally accepted the Topical Report for use by GE Owner's (roup Licensees.

Each licensee is required by the SER to show applicabilit,' of the Topical Report to their particular plants.

4)

- In licensee letter BEC0 87-026, dated February 22, 1988, BEC0 submitted an applicability review of PNPS to the Topical Report NEDC-30851P. The staff reviewed this submittal and has concluded that adequate similarity of PNPS to cystems analyzed by NEDC-30851P justifies the use of the recommended six hour out of service time for testing and calibration.

5)

The staff agrees with the licensee's contention that the addition of an allowable out of service time for testing and calibration is a TS improvement, This change requir s action by the licensee in a finite time, which precludes excessive periods of time before compensatory measures or restoration of a safety system are implemented.

Defining an allowable out of service time limit will also reduce the potential for disputes on what constitutes a reasonable time for an instrument channel to remain intentionally inoperable during normal maintenance activities.

6)

The staff believes this TS change will not increase the probability or consequences of an accident previously evaluated.

In fact, by specifying an allowable out of service time (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) versus an indefinite period of time, this should actually be a decrease in the probability of an accident.

7)

This proposed TS change does not create the possibility of a new or different kind of accident from any previously evaluated. The TS change dces not change setpoints, plant operation, or plant configuration and therefore, cannot create a different kind of accident from any previously evaluated.

The staff finds the specifying of an allowable out of service time for testing and calibration to be an overall PNPS TS improvement. Based on the GE Licensing Topical Report NEDC-30851P and the acceptability of iAPS submittal to this Topical Report, the staff finds the use of a six hour allowable out of service time for testing cnd calibration to be acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

S This amendment invo.lves a change in the installation or use of a facility component located Athin the restricted area as defined in 10 CFR Part 20.

The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any eftiuents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Comission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR $51.22(c)(9).

Pursuant to 10 CFR 651.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

4.0 CONCLUSION

We have ccncluded, based on the consideratier.s discussed above, that (1) th.

is reasonable dssurance that the health or v safety of the public will not be endangered by operation in the proposed tor ner, and (2) such activities will be conducted in compliance with the Commission's regulations, dnd the issuance of this amendment will not be inimical to the commun aefense and security or tc the health and safety of the public.

5.0 Acknowledgment Principal Contributor:

R. Lasky Dated: July 8, 1988 L

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p AMENDMENT N0. 119 TO FACILITY OPERATING _ICENSE DPR : PILGRIM NUCLEAR PCKER STATION DISTRIBUTION:.w/ enclosures:

Docket No.-50-293:

NRC PDR Local PDR..

PDI-3 r/f-PWessman MRushbrook DMcDonald OGC-15B-18' T. Barnhart-(4)

E. O. Jordan-B. Grimes

0. Hagan ACRS (10)

E. Butcher Wanda Jones

.0PA LFMP Tech. Review Branch - R. Lasky, SICB l

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