ML20236N241

From kanterella
Jump to navigation Jump to search
Safety Evaluation Supporting Amend 118 to License DPR-16
ML20236N241
Person / Time
Site: Oyster Creek
Issue date: 11/06/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236N232 List:
References
NUDOCS 8711160079
Download: ML20236N241 (2)


Text

,

DR Rf C

\\

UNITED STATES E

g NUCLEAR REGULATORY COMMISSION h

i.j WASHINGTON, D, C. 20555

\\...../

SAFETY EVALUATION BY TNE OFFICE OF NUCLEAR REACTOR REGULATION RELA 1ED TO AMENDMENT NO.118 TO FACILITY 0PERATING LICENSE NO. DPR-16 l

JERSEY CENTRAL POWER & LIGHT COMPANY l

OYSTER CREEK NUCLEAR GENERATING STATION

.j l

DOCKET NO. 50 919 i

~

Introduction The April 20, 1981, Order for Modification of License Concerning Primary Coolant System Pressure Isolation Valves required the licensee to implement i

Technical Specifications (TS) to perform periodic leak testing of the Primary 1

Coolant System Pressure Isolation Valves. The TS requirements for test'

]

frequency imposed by the April 20, 1981, Order were derived.from the Franklin Research Center report TER-C5257-252 (Rev.1). The test frequency criteria in the report, however, included ~a recommendation for leak testing, "...each time any check valve may have moved from the fully closed position..." which was'not

~

incorporated into the TS requirements imposed by the April 20, 1981, Order.

This inconsistency was identified during NRC inspection 50-219/85-36 when the Core Spray System air operated check valves.(classified as Primary Coolant System Isolation Valves in the TS) had been exercised twice without' subsequent leakage testing. The Itcen'.ee's TS 4.3-G did act include the requirement for leak testing after each Primary Coolant System Pressure Isolation-Valve movement.

In response to the above NRC inspection concern, by letter dated June 19, 1987,.

GPU Nuclear Corporation submitted Technical Specification Change Request No.146 to Provisional Operating License No. DPR-16 to amend the factitty's TS to require leak rate testing after each primary coolant system pressure isolation valve movement. This SE addresses the additional proposed testing.

Proposed Changes The proposed change is to add "...whenever a valve is' moved whether by manual actuation or due to flow conditions...." to Technical Specification 4.3-G, to leak test the primary coolant system pressure isolation valves.

Review Criteria / Requirements (1) Order for Modif t:ation of License Concerning Primary Coolant System Pressure Isolation Valves (w/ attachments), April 20, 1981.

8711160079 871106 PDR ADOCK 05000219 P

PDR i

E i

1 2

l

'l Evaluation The additional requirement' for leakage testing of the Primary. Coolant System -

Pre >sure Isolation Valves after each. movement of the valves will' provide confidence that the valves are properly seated.

The change will also make the Oyster Creek Nuclear Generating Station Technical Specifications. consistent with the test frequency criteria in TER-C5257-252 (Rev. 1) which formed the basis.of the April 20, 1981, Order imposing the original -leak. test requirements. Based upon the above, theLstaff finds theilicensee's: proposed 1

l amendment to be acceptable.

. Environmental Consideration 1

This amendment involves a change in a surveillance requirement.

The staff-has determined that the amendment involves no sig,nificant-increase in the amounts, and no sigr.ificant change in the types, of any effluents that may be released '

offsite, and that there is' no significant increase in individual. nr cumulative occupational radiation exposure. The Commission has previously issued a pro-posed finding that this amendment involves no significant hazards consideration and there has been no public comment on such-finding. Accordingly, this amend-ment meets the eligibility criteria for categorical exclusion set forth in 10 l

CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22 or environmental assessment need be prepare (b).no environmental impact statement d in connection with the issuance of this amendment.

4 Conclusion We have concluded, based on the considerations dl> cussed 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 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.

l Date:

bov enb er 6,1987 Principal' Contributor: John G. Hunter, III, Division of Reactor Safety, RGI.

1 1

m_.___________---__.-----_--_----

- - - - -