ML20029C012
| ML20029C012 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/12/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029C011 | List: |
| References | |
| NUDOCS 9103220289 | |
| Download: ML20029C012 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION o
f WASHINGTON, D. C. 20565 r
t SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEN 0 MENT NO. 54 TO FACILITY OPERATM LICENSE NO. NPF-47 GULF STATES UTILfTIES COMPANY RIVER BEND S1Ai10N, UNIT I DOCKET NO. 50-458 i
1.0 INTRODUCTION
By letter dated January 7, 1991, Gulf States Utilit es Company (GSU) (the licensee) requested an amendment to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1.
The proposed amendment would add the chilled water return from the drywell isolation valve, 1HVN*V543, to Technical Specification (TS) Table 3.6.4-1, "Drywell and Containment Isolation Valves,"
and correct the identifying title for the ISWP*V206 valve in thc TS table.
The 1HVN*V543 isolation valve had apparently been omitted from the Safety Analy.is Report (SAR) Table 6.2-51, "Drywell Isolation Provisions for Fluid Lines," and when the TS table was developed from the SAR table the omission was carried over.
2.0 EVALUATION On January 25, 1990, GSU identified that the chilled water return from the drywell isolation valve, 1HVN*V543, had been omitted from TS Table 3.6.4-1.
The 1HVN*V543 manual isolation va he performs the function of isolating chilled water returning from the s.rywell.
After discovery of the omission on January 25, 1990, GSU determined the event to be reportable since the surveillance requirements of TS 4.6.2.1, "Drywell Integrity," had not been performed on the valve.
Subsequently, GSU submitted Licensee Event Report (LER)90-025 dated September 7, 1990.
TS Surveillance Requirement 4.6.2.1.a requires that once every 31 days, drywell penetrations that are not capable of being closed by automatic isolation valves and are required to be closed during accident conditions, be verified closed.
As described in the LER and the amendment request, GSU verified that valve 1HVN*V543, which is normally closed, was already included in Station Operating Procedure (50P)-0066, " Plant and Control Building HVAC Chilled Water System." This S0P is used during normal system lineups to. ensure correct valve position of the valves in the system.
On April 4, 1990, Surveillance Test Procedure (STP)-000-0201, " Monthly Operating Log," was revised to include valve 1HVN*V543 on the list that verifies valve position once every 31 days.
This in essence ensures compliance with TS 4.6.2.1.a.
On_ January 30, 1990, GSU issued a Temporary Change Notice to the Operations Section Procedure (OSP)-0013, "CTMT/ECCS/ Diesel Generator Valves verification,"
l to include valve 1HVN*V543 on the list of containment penetrations that are locally verified quarterly.
9103220289 910312 PDR ADOCK 05000458 P
GSU also verified the chilled water supply line valve, 1HVN*V542, was included in both the TS and SAR tables and that the appropriate surveillances had been performed.
Based on the staff's review of the licensee's submittal LER 90-025, the applicable sections of the RDS SAR and Safety Evaluation Report, and th Standard Review Plan, the addition of the chilled water return from the drywell isolation valve, 3HVN*V543, to 15 Table 3.6.4-1 is acceptable.
The editorial change requested by the licensee would revise the identifying title of valve 1SWP*V206 from service water supply to service water return.
This change in identify'nQ titles is acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Louisiana 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 areas 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, anJ 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 comments on such finding (56 FR 4865).
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 reasonabla 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.
Date:
March 12, 1991 Principal Contributor:
Claudia M. Abbate, PDIV-2 l
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