ML20198D186

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Safety Evaluation Supporting Amend 95 to License NPF-73
ML20198D186
Person / Time
Site: Beaver Valley
Issue date: 12/14/1998
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198D173 List:
References
NUDOCS 9812230027
Download: ML20198D186 (2)


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UNITED STATES p

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NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. Samma -1 f

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 95 TO FACILITY OPERATING LICENSE NO. NPF-73 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY I

THE CLEVELAND FI FCTRIC ILLUMINATik AOMPANY i

THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT 2 DOCKET NO. 50-412 4

1.0 INTRODUCTION

By letter dated September 24,1998, as supplemented November 3,1998, the Duquesne Light 3

Company (the licensee) submitted a request for changes to the Beaver Valley Power Station, i

Unit No. 2 (BVPS-2), Technical Specifications (TSs). The requested changes would revise TS d

3.1.2.8 in two places to change the term " contained volume" to " usable volume." This change would eliminate the potential for a non-conservative interpretation of the specification values for J

the Refueling Water Storage Tank (RWST) and Boric Acid Storage Tank (BAT) thereby eliminating the need for temporary administrative controls which have been used correctly to F

propedy interpret the specification values as usable volumes. The November 3,1998, letter provided a minor editorial change to the TS page that did not change the initLV proposed no 4

i significant hazards consideration determination or expand the amendment request beyond the scope of the November 4,1998, EgdgIgl Reaister notice.

2.0 EVALUATION i

The BVPS-2 accident analyses are based upon having a volume of 859,24S gallons of borated water available in the RWST for injection into the reactor coolant system and containment by the l

emergency core cooling system. TS 3.1.2.8.b specifies a minimum contained volume of 859,248 gallons in the RWST. However, due to the configuration of the RWST and quench spray system suction piping, the RWST also contains an unusable volume of 31,824 gallons. The licensee has i

been implementing interim administrative controls to ensure that the RWST actually contains a minimum of 891,072 gallons (859,248 usable gallons plus the 31,824 unusable gallons). The NRC staff has reviewed and found these administrative controls acceptable (see NRC Inspection Report 50 412/98-05). The licensee has now proposed to revise TS 3.1.2.8.b to clarify that the 859,248 gallons must be a usable volume. The NRC staff has reviewed the licensee's proposed change and has concluded that the proposed change to TS 3.1.2.8.b clarifies that the RWST must contain a usable volume of 859,248 gallons. This volume of water is consistent with the BVPS 2 accident analysis and therefore, the proposed change to TS 3.1.2.8.b is acceptable.

Similar to the requirements of TS 3.1.2.8.b regarding RWST water volume, TS 3.1.2.8.a specifies a minimum contained volume of 13,390 gallons of borated water in the BAT. This TS requirement is also intended to provide that the specified volume of water (13,390 gallons) be available for injection into the reactor coolant system for reactivity control. Like the RWST, the BAT also contains unusable volumes. The unusable volumes in each of the two tanke is 678 gallons for a combined unusable volume of 1356 gallons. The licensee has been implementing interim administrative controls to ensure that the BAT actually contLins a minimum 9812230027 991214 PDR ADOCK 05000412 P

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) k 5 of 14,746 gallons (13,390 usable gallons plus the 1356 unusable gallons). The licensee has now proposed to revise TS 3.1.2.8.a to clarify that the 13,390 gallons must be a usable volume. The NRC staff has reviewed the licensee's proposed change and has concluded that the proposed change to TS 3.1.2.8.a clarifies that the BAT must contain a usable volume of 13,390 gallons.

This volume of water is consistent with that required for the reactivity control specifed in the Bases forts 3.1.2.8.a and therefore, the proposed change to TS 3.1.2.8.a is acceptable.

3.0 STATE CONSULTATION

in accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 59591). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The Commission has 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: D. Brinkman Date:

December 14, 1998