ML20245G968
| ML20245G968 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/22/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245G961 | List: |
| References | |
| NUDOCS 8906290336 | |
| Download: ML20245G968 (2) | |
Text
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gv.....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.113 TO FACILITY OPERAT!NG LICENSE NO. DPR-28 VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 l.0 INTRODUCTION By letter dated Januar.y 12, 1967 and clarified on January 29, 1988, Vermont Yankee Nuclear Power Corporation (VYNPC) (the licensee) submitted a request for revision of the Technical Specifications, Appendix A to Operating License DPR-28 for the Vermont Yankee Nuclear Power Station (VY). The proposed changes would incorporate surveillance and operability requirements for post-accident monitoring instrumentation installed to satisfy Regulatory Guide (R.G.) 1.97; extend the rance of torus water level instrumentation to the range required by new emergency operating procedures; and make administrative corrections.
2.0 EVALUATION The ifcensee has proposed to provide Technical Specification surveillance and operability requirements appropriate to instrumentation modifications stemming from Regulatory Guide 1.97.
Modifications requiring changes are:
1)
The torus pressure instrumentation was upgraded to provide two i
redundant, fully qualified instrument channels.
2)
The torus air temperature instrument channel was upgraded to include a redundant fully qualified instrument channel.
3)
The reactor vessel water level instrumentation range was upgraded to provide an expanded range indication.
4)
The drywell atmospheric temperature instrumentation was upgraded to provide two redundant, fully qualified instrument channels.
5)
The torus water temperature instrumentation was upgraded to provide two redundant, fully qualified irstrument channels.
Proposed redundancy, ranges, and calibration freovencies are consistent with staff requirements. The staff agrees that Technical Specifications should be revised to reflect these changes, j
1 NUREG-0737, Supplement I required symptom-besed Emergency Operating Procedures (EOPs). These E0Ps require the ability to measure water level to at least 22.4 feet in the torus. Therefore, the torus water level instrumentation was changed to provide a range of 0-25 feet, and Technical Specifications which d
8906290336 890622 l
PDR ADOCK 05000271 P
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SAFETY EVALUATION EY TFE OFFICE OF NUCLEAR REACTOR REGULATION REtATED TO AMENDMENT NO. 113 TO FACILITY OPERAT!kG LICENSE NO. DPR-28 VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
1.0 INTRODUCTION
By letter dated January 12, 1967 and clarified on January 29, 1988, Vermont Yankee Nuclear power Corporation (VYNPC) (the licensee) submitted a request for revision of the Technical Specifications, Appendix A to Operating License DPR-28 for the Vemont Yankee Nuclear Power Station (VY). The proposed changes would incorporate surveillance and operability requirements for post-accident monitoring instrumentation installed to satisfy Regulatory Guide (R.G.) 1.97; extend the rance of torus water level instrumentation to the range required by new emergency operating procedures; and make administrative corrections.
2.0 EVALUATION The licensee has proposed to provide Technical Specification surveillance and operability requirements appropriate to instrumentation modifications steuning from Regulatory Guide 1.97. Modifications requiring changes are:
1)
The torus pressure instrumentation was upgraded to provide two redundant, fully qualified instrument channels.
2)
The torus air temperature instrument channel was upgraded to include a redundant fully qualified instrument channel.
3)
The reactor vessel water level instrumentation range was upgraded to provide an expanded range indication.
4)
The crywell atmospheric temperature instrumentation was upgraded to provide two redundant, fully qualified instrument channels.
5)
The torus water temperature instrumentation was upgraded to provide two redundant, fully qualified instrument channels.
Proposed redundancy, ranges, and calibration freopenties are consistent with staff requirements.
The staff agrees that Technical Specifications should be revised to reflect these changes.
NUREG-0737, Supplement I required symptom-based Emergency Operating Procedures (EOPs). These E0Ps require the ability to measure water level to at least 22.4 feet in the torus. Therefore, the torus water level instrumentation was changed to provide a range of 0-25 feet, and Technical Specifications which 8906290336 890622 PDR ADOCK 05000271
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refer to torus water level were revised accordingly. Also corrections to instrumentation numbers were proposed for drywell pressure indicators and drywell atmospheric temperature recorders.
The staff finds that Technical Specification revisions to correct the torus water level range and provide correct instrumentation numbers for drywell instrumentation are acceptable and desirable. The staff also concludes that the proposed changes in the January 12, 1987 and January 29, 1988 submittals are acceptable and conform to the R.G. 1.97, Revision 3, criteria.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment irvolves a change in the installation or use of a facility l
component located within the restricted area as defined in 10 CFR Part 20.
l The 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 published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR $51.22(c)(9). Pursuantto10CFR51.22(b)no environmer.tal impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
V. Rooney a
Dated: June 22, 1939
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