ML20012G680
| ML20012G680 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/08/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012G678 | List: |
| References | |
| NUDOCS 9303110322 | |
| Download: ML20012G680 (2) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION f
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WASHINGTON, D. C. 20555 f
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE NO. NPF-49
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,i NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 I
DOCKET NO. 50-423 i
1.0 INTRODUCTION
By letter dated September 22, 1992, the Northeast Nuclear Energy Company-(NNEC0/ licensee), submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 3 Technical Specifications (TS). The requested changes would revise the Technical Specification for Millstone Unit 3 to -
change the measurement range from Ig to 29 for a seismic monitoring instrument, the triaxial peak accelerograph at the P/A2 Safety Injection Accumulator Discharge Line.
2.0 EVALUATION I
i iable 3.3-7 of the Technical Specifications lists seismic monitoring i
instrumentation, and includes the measurement range for.each instrument. The
'l present Technical Specifications list lg as the range for triaxial peak l
accelerograph P/A2.- P/A2 is located on the safety-injection accumulator t
discharge line at the minus 22' 10 elevation.
The licensee has compared the range of the instrument with the range of accelerations needed to span i
anticipated seismic events. The comparison has shown that 19 is'not adequate, but that 29 is adequate. There are eight other active / passive devices.
available for seismic motion analysis at Millstone Unit No. 3.
The other.
devices are considered more reliable. All of these devices' provide. data i
following an earthquake, and do not impact the operation of the plant.
Changing the range of triaxial peak accelerograph P/A2 to'a range that is adequate to span expected responses would. improve the usefulness of the device, and has no adverse safety co1 sequences..The increased range of the 1
instrument could add to the confidence of evaluation'of building / equipment
-i response data following an earthquake.
Based on the above,'.the staff finds the proposed change acceptable.
3.0 STATE CONSULTATION
i In accordance with the Commission's regulations, the Connecticut State official. was notified of the proposed issuance of the amendment. The State official had no comments.
9303110322 930308 PDR ADOCK 050004 3 e
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no e
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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 48822). 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 ccnsiderations 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
Gus Giese-Koch Vernon Rooney Date:
March 8, 1993 6
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