ML20108C148
| ML20108C148 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/01/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20108C146 | List: |
| References | |
| NUDOCS 9605060196 | |
| Download: ML20108C148 (3) | |
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4 UNITED STATES l
S NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D.C. 20066 0001
.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.199 AND 81 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDIS0N COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated December 27, 1995, the Duquesne Light Company (the licensee) 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 modify Tables 3.3-11 and 4.3-7 of BVFS-1 and BVPS-2 TS 3.3.3.8 (Accident Monitoring Instrumentation) such that only one valve position indication system for the power-operated relief valves and safety valves would be required to be operable. Minor editorial changes would also be made to BVPS-1 TS 3.3.3.8 and its associated Action Statements. The proposed changes to TS 3.3.3.8 and to TS Tables 3.3-11 and 4.3-7 would make them consistent with the NRC's Improved Standard Technical Specifications (NUREG-1431, Revision 1) and with the guidance of Regulatory Guide (R.G.) 1.97,
" Instrumentation For Light-Water-cooled Nuclear Power P. ants to Assess Plant and Environs Conditions During and Following an Accident," NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations," and NUREG-0737, " Clarification of TMI Action Plan Requirements."
2.0 BACKGROUND
The licensee proposes to delete the TS requirements for che operability of the BVPS-1 power-operated relief valves (PORVs) acoustic detectors, and BVPS-1 and BVPS-2 TS requirements for the operability of the safety valves (SVs) tailpipe temperature detectors.
BVPS-1 TS 3.3.3.8 presently requires that both redundant position indication i
systems for the PORVs and the SVs be operable or BVPS-1 shall be placed in at least HOT SHUTDOWN per the applicable Action Statement.
BVPS-2 TS 3.3.3.8 i
presently requires that the primary and backup SV position indication systems 9605060196 960501 PDR ADOCH 05000334
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be operable or BVPS-2 shall be placed in at least HOT SHUTDOWN per the applicable Action Statement.
Inoperability of any one of these systems is not a safety concern since they perform no safety function, and because the other position indication system is available to meet TS operability requirements.
The proposed amendment modifies TS 3.3.3.8 Action Statements and Surveillance Requirements, but does not affect the associated Bases. The proposed changes are limited to PORV and SV position indication and do not involve any physical changes to the PORVs, SVs, or their setpoints.
The licensee stated that the proposed an;endment is consistent with the NRC's Improved Standard Technical Specifications (NUREG-1431, Revision 1) and meets the guidance of R.G. 1.97, NUREG-0578, and NUREG 0737.
3.0 EVALUATION The primary purpose of the accident monitoring instrumentation is to display plant variables that provide information to the control room operators regarding plant status during accident situations. The instruments that monitor these variables are identified by the licensee in accordance with guidance contained in R.G. 1.97.
R.G.1.97 defines five types of variables (Types A, B, C, D, and E) to be monitored by the control room operator during the course of an accident and during the long term stable shutdown phase following the accident. Tha R.G.
also defines three categories (Category I, II, and III) of qualification criteria for this instrumentation, depending on the importance to safety of the measurement of a specific variable. Type A variables provide the primary information required for the control room operator to take specific manual action for which no automatic control is provided, and require Category I qualification which includes redundancy of the monitoring instrumentation.
The proposed amendment addresses instrumentation which is r,either Type A nor Category I because there is no required manual safety control action associated with the PORV and SV position indication system for which no automatic action is provided. Therefore, the NRC staff agrees that redundant PORV and SV position indication is not required since it is not relied on for the performnce of any safety functions.
TS 3.3.3.8 and TS Table 3.3-11 will continue to require operability of appropriate position indication for the PORVs and SVs as recommended by R.G.
1.97, NUREG-0578, and NUREG-0737.
Position indication for the PORVs on both units is provided by qualified limit switches on the valves.
For the SVs, in BVPS-1, position indication is provided by acoustic detectors and in BVPS-2 by a reed switch indicating device. Therefore, the proposed changes meet the recommendations of R.G. 1.97, the criteria contained in NUREG-0578 and NUREG-0737, and are consistent with the guidance provided in NUREG-1431, Revision 1.
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. 4.0 SUffiARY Based on review of the proposed amendment, the NRC staff concludes that the 1
deletion of the redundant PORV and SV position indication from TS Tables 3.3-11 and 4.3-7 is consistent with guidance provided by the NRC staff for non-Category I post-accident monitoring instrumentation in R.G. 1.97 since this position indication provides no safety function. The proposed TS change is also consistent with the guidance provided in NUREG-1431, Revision 1, and therefore, is acceptable.
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5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State 1
official was notified of the proposed issuance of the amendments. The State
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official had no comments.
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6.0 ENVIRONMENTAL CONSIDERATION
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The amendments change a requirement with respect to installation or use of a i
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 j
offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a prSposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (61 FR 3499). 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.
7.0 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 issu ice of the amendments will not be inimical to the common defense and sech.ty or to the health and safety of the public.
Principal Contributor: Mario C. Gareri Date: May 1, 1996 t
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