ML20195C840
| ML20195C840 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/03/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195C838 | List: |
| References | |
| NUDOCS 9906090005 | |
| Download: ML20195C840 (3) | |
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UNITED STATES j
j NUCLEAR REGULATORY COMMISSION i
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't WASHINGTON, D.C. 20S55-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.m AND oo TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS.1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated July 9,1998, as supplemented by letter dated March 31,1999, the Duquesne Light Company (the licensee; or DLC) submitted a request for changes to the Beaver Valley Power Station, Unit Nos.1 and 2, (BVPS-1 and BVPS-2) Technical Specifications (TSs). The requested changes would revise TS Table 3.7-1 by lowering the maximum allowable power level when one~or more main steam safety valves (MSSVs) are inoperable. The proposed changes would also revise the Bases for TS 3/4.7.1.1 to include the algorithm used for determining the new allowable values. The change to the Unit 1 TS 3.7.1.1 also deletes the current TS Table 3.7-2 applicable to 2-loop operation since 2-toop operation is not a licensed condition for either unit. The existing TS Table 3.7-3 is then renumbered as 3.7-2. The March 31,1999, letter did not change the initial proposed no signif; cant hazards consideration determination or expand the amendment beyond the scope of the initial notice. This letter
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included mark-up pages for the Unit 2 Bases pages which had been inadvertently left out of I
the original submittal, provided the final version of the changed TS pages, and withdrew a portion of the amendment request which would have removed the values of the orifice diameter of each MSSV from TS Table 3.7-3 (Unit 1) and Table 3.7-2 (Unit 2).
2.0 EVALUATION When one or more main steam line code safety valves is inoperable, the current TS 3/4.7.1.1 for BVPS-1 and BVPS-2 require that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valves be restored or the Power Range Neutron Flux High Setpoint trip be reduced to the values specified in TS Table 3.7-1. The requirement to reduce the trip setpoint indirectly requires power reduction to 9906090005 990603 FDR ADOCK 05000334 P
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f 'less than the specified values in this TS Table. The licensee's proposed change explicitly
. specifies maximum allowable reactor power level based on the number of operable main Esteam safety valves (MSSVs) rather than requiring reduction in reactor trip setpoint. This change is consistent with the Nuclear Regulatory Commission's (NRC) improved Standard Technical Specifications for Westinghouse plants (NUREG-1431, Revision 1).
_ Westinghouse has determined that the maximum allowable power level given in TS Table 3.7-1 may not be low enough to prevent a secondary side over pressurization during a loss of load /
j turbine trip transient. In its Nuclear Safety Advisory Letter (NSAL) 94-01 dated January 20, 1994, Westinghouse reported its determination that the maximum allowable initial power level is not a linear funchon of available MSSV relief capacity. It was further determined that the current TS provisions for reduced rea:: tor power levels with inoperable MSSVs may not preclude the secondary side pressure from exceeding 110% of its design value during a loss of 4
main feedwater transient, particularly at lower power levels. NSAL 94-01 also provided the licensee with an algorithm for determining revised maximum allowable power levels with.
The licensee has cale
- ed new maximum allowable power level values based on the algorithm contained i.
/estinghouse's NSAL 94-01. The new values are lower than the values in the current TSs. ' 3 process resulted in the maximum allowable power level values for
'.BVPS-1'of 100%,57%,39%, and 22% of rated thermal power for a minimum number of five, four, three, and two operable MSSVs, respectively, on any operating steam generator. For BVPS-2, the revised maximum allowable power level values are 100%, 58%, 4.1%, and 24% of rated thermal power for a minimum number of five, four, three and two operable MSSVs,
" respectively, on any operating steam generator..
The staff has found that the licensee's revised algorithm ensures that the maximum power level L allowed for operation with inoperable MSSVs is below the heat-removing capability of the
. operable MSSVs. This ensures that the secondary system pressure will not exceed 110% of its design value. In addition, the new allowable values are more conservative than the values specified in the current TSs. Therefore, the staff finds that the proposed changes to the TS Table 3.7-1 and Bases 3/4.71.1 are acceptable.
The licensee also proposes to delete the current BVPS-1 TS Table 3.7-2 applicable to 2-loop operation, and renumber the existing TS Table 3.7-3 to be Table 3.7-2. This is an administrative change necessary to make the TS consistent with plant operation which does not allow 2-loop power operation at either BVPS-1 or BVPS-2. The renumbering of TS _ Table 3.7-3
> is purely administrative and changes no TS requirements. Therefore, the NRC staff finds these changes acceptable.'
3.0 - STATE CONSULTATION L lIn accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve 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 amendments involve no'significant hazards consideration, and there has been no
. public comment on such finding (63 FR 43203).' Accordingly, the amendments meet 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 amendments.
4 5.0 ' CONCLOSION
- The Commiss' ion 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: C. Liang Date: June 3,1999