ML20149L638

Safety Evaluation Supporting Proposed Standby Liquid Control Sys Operation

ML20149L638
Person / Time
Site:	Oyster Creek
Issue date:	02/18/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20149L631	List: ML20149L629 ML20149L638
References
NUDOCS 8802240337
Download: ML20149L638 (1)

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ENCLOSURE 1 SAFFTY EVALUATION BY THE OFFICE OF NUCLEAR RFACTOP PEGULATION RELATING TO 10 CFR 50.62fc)(4), ATWS RULE GPU Fl! CLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219

1.0 INTRODUCTION

In letters dated Septenber 3, 1987 (5000-87-1361) and Decenber 30, 1987 (5000-87-1447) GPU Nuclear Corporation submitted a description of its plans for implementing the requirements of 10 CFD 50.6? at Oyster Creek Nuclear Generating Station. The proposed Standby Liquid Control System (SLCS) is designed to supply 30 gpm of enriched sodium pentaborate solution (35 atom percent of B-10) to the reactor vessel to meet ATWS reouirements.

2.0 EVALUATION The SLCS description provided by GPU for Oyster Creek has been reviewed by the staff against the requirements of the ATWS rule (10 CFR 50.67fe)(4), and Generic Letter 85-03, "Clarification of Equivalent Control Capacity for Standby Liquid Control Systems," dated January P8,1985. The licensee will increase the boron enrichment to a minimum of 35 aton percent of B-10, and proposes to supply 30 gpm of a minimum 15 weight percent of sodium pentaborate solution to the reactor vessel. Accounting for the physical size of the Oyster Creek reactor vessel which is 213 inches inside diameter, the aforementioned flow / enrichment combination satisfies the ATWS Rule equivalency requirement which is based upon 86 gpm pump flow,13 weight percent sodium pentaborate and 19.8 atom percent B-10, and a 251 inch diameter vessel, es  ;

discussed in Generic Letter 65-03. The proposed design is therefora  ;

acceptable.

The licensee should confirm that surveillance and positive verification will be perfonned periodically (once per month) to assure that the correct isotopic enrichment is maintained. When additional chemicals, e.g., boron or boric ,

acid are added to the storage tank, isotopic enrichment of B-10 in the solution should also be verified. This commitment as well as periodic veri-fication of the 30 gpm flow rate should be reflected in the plant Technical  !

Specifications, j

3.0 CONCLUSION

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The description of the proposed SLCS operation by GPU Nuclear Corporation for the Oyster Creek Nuclear Generating Station in letters dated September 3,1987 and December 30, 1987 is acceptable because it is consistent with the equivalency requirements of 10 CFR 50.62(c)(a).

Principle Contributor: M. McCoy g2240337 880219 ,

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