ML20010C037

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Safety Evaluation Supporting Amend 37 to License DPR-70
ML20010C037
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/30/1981
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20010C036 List:
References
NUDOCS 8108190043
Download: ML20010C037 (2)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENCMENT N0. 37 TO FACILITY OPERATING LICENSE NO. DPR-70 PUBLIC SERVICE ELECTRIC AND GAS'CC."PANY PHILACELPHIA ELECTRIC CC"PANY DEL!'ARV; POWER AND LIGHT CO.PANY, AND ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-272 1.0 Introduction As a consequence of the accident at TMI-2, implementaticn of a number of new requ.irements has been reccamended for operating reactors.

These new require-men.s are described in NUREG-0660, "NRC Action Plan Developed as a Result of the TNI-2 Accident," May 1980, and NUREG-0737, " Clarification of TMI Action Plan Requiremersts," November 193C.

The NRC staff has also requested licen-sees to submit information sufficient to permit an independent evaluation of their respcnse to these new requirements. This report provides an evaluation of the response to Action Plan Item II.E.4.2, position 5, and the Technical Specification revisions crocosed by the licensee (Public Service Electric 3rd Gas C: cany) in a letter dated June 15, 1931, 2.0 Evaluation In its letter of /pril 23, 1981, the licensee procosed to change the minimum pressure set point for initiating containment isolation from the present value of < 4.7 osi to < a psi.

The proposed value is the sum of three ccaponents:

(1) 0.3 psig maximum allcwed by Technical Specifications (2) 2.49 psi potential instrument error (3) 1.2 psi cossible small pressure transient Our consultant, the EG&G Energy Measurements Group (a subcontractor to Lawrence Livermore Nationai Laboratory, which has the TMI Action Plan contract) has reviewed the licensee's submittals and prepared the attached technical evaluation report of the licensee's containment pressure setpoint used to isolate nonessen-tial containment penetrations. We have reviewed this evaluation and concur in its basis and findings.

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-2 3.0 Conclusions' 75e information submitted by the licensee provided sufficient details et the licensee's containment isolation pressure for the staff to cor.clude that the requirements of Item II.E.4.2(5) of NUREG-0737, with the additional guidelines r a v i d. a. d.

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