ML20070S909
| ML20070S909 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/25/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070S904 | List: |
| References | |
| NUDOCS 9104030127 | |
| Download: ML20070S909 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT fl0.129 TO FACILITY OPERATitlG LICENSE NO. OPR 28 VERMONT YAllKEE NUCLEAR POWER CORPORATION VEPMONT YANKEE flVCLEAR POWER STATION DOCKET NO. 50-271 1.0 It4TRODUCTION By letter deted January 15, 1991, the Vermont Yankee Nuclear Power Corporation (the licensee) proposed changes to the Technical Specifich-1 tions (TS) for Vermont Yankee. The proposed changes would reme.e the valve position monitor surveillance requirement from the Technical Specifications for the low ressure coolant injection (LPCI) system crosstie line valve (RHR-20.
Valve RHR-20 was intended only for use in the LPCI loop select logic, which was an Energency Core Cooling System control feature of the plant that was removed in 1974 Since that time RHR-20 has been required to be maintained locked, in a closec position, with its motor power leads disconnected. However, current Technical Specifications Table 4.2.1 requires that the position of the valve be confirmed once each day by an
'nstrument check.
Following a reportable event (LER 89-023) in which failure to perform daily instru-ment checks on the LPCI system crosstie monitor occurred, the licensee reexamined the surveillance requirement and proposed corrective action which included submitting for NRC review a Technical Specification change to remove the Technical Specification surveillance requirement. NRC Region I review of the event concluded that licensee corrective actions for LER 89-023 were appropriate and comprehensive and adequately addressed the issues (Inspection Report 50-271/89-17).
This proposed change follows from the above described corrective actions.
2.0 EVALUATION The purpose of the subject surveillance requirement is to confirm the position of valve RHR-20. The licensee states that:
1.
Valve RHR-20 is chained and locked shut.
2.
The RHR-20 motor leads are disconnected.
3.
The RHR-20 key lock switch is defeated.
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2 Current licensee administrative procedures require surveillance for the RHR-20 valve position at a minimum frequency of once per operating cycle.
For comparison with practice at other plants for such situations, standard Technical Specifications require no verification of valve position for LPCI system valves that are locked, sealed, or otherwise secured in the correct position.
BecausetheRHR-20valveissecuredinthecorrectposition(closed)Ition, and there is suf ficient assurance that the valve will remain in that pos removal of the daily surveillance of valve position indication from the Technical Specifications is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involver. a change in a requirement with respect to the installation or use of a f acility component located within the restricted area as defined in 10 CFR Part 70.
T3e staff has determined that the amendment involves no.significant increase in the amounts, and no signi-ficant change in the types, of any effluents that may be released offsite, and that there is no significant increase ir, individual or cumulative occupational radiation ex>osure. The Commission has previously oublished a proposed finding that tie amendment involves no significan; unards consideration and there has been no public coment on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusionsetforthin10CFR51.22(c)(9),
pursuantto10CFR51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
S We heve reviewed the request by the Vermont Yankee Nucle r power Corporation to remove the surveillance requirement for position indication of valve RHR 20 from Technical Specification Table 4.2.1 and conclude that the change is acceptable.
The Comission made a proposed ' determination that the amendment involves no significant hazards consideration which was. published in the Federal Register (56FR6882)onFebruary 20. 1991 and consulted with the State oT Vermont. No public coments were received anc-the-State of Vermont did not have any coments. The staff concludes that-the proposed change i
to the Technical Specifications is acceptable.
principal Contributor:
V. L. Rooney Dated:
March 25', 1991
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AMENDMENT 110.129 TO 0FR-20 VERMONT YAtWIE NUCLEAP, POWER STATION DATED March 25, 1991 DISTRIBUTION Docket file 50-271 4~
NRC PDR Local PDR PDI-3 Reading S. Varga E. Greentnan H. Rushbrook M. foirtile S. Shankman 000 15-G-18 4
Dennis Hagen, MNBB 3006 E. Jordan, MNBB 3701 B. Grimes, 9A3 G. Hill (4),P1-37 Wanda JoneF, MNBC 7103 J. Calvo, 11-F-23 ACRS (10), P1 35 GPA/PA,2-G-5 0C/LTMB,MNBB i
J. Johnson, Region 1 R, Jones l
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