ML20101K425
| ML20101K425 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/19/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20101K420 | List: |
| References | |
| NUDOCS 9207020261 | |
| Download: ML20101K425 (3) | |
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UNITED STATES 3
E NUCLEAR REGULATORY COMMISSION
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o WASHINGTON, D C. 20%5 SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT10fi RELATED TO AMENDMENT N0.181 TO FACILITY OPERATING LICENSE DPR-57 AND AMENDMENT NO 122TO FAClllTY OPERATING LICGSE NPF-5 GEORGIA POWER COMPANY. ET AL.
EDWIN 1. HATCH NUCLEAR PLANT. UNITS 1 ANDJ DOCKET N05, 50-321 AND 50-366
1.0 INTRODUCTION
By "HL-1664, Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS Section 4.6.L & Unit 2 [[TS" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Re Snubber Surveillance to Reflect Present Guidance Proposed in Encl B of Generic Ltr 90-09 Re Snubber Visual Insp|letter dated July 11, 1991]], as supplemented February 20, 1992, Georgia Power Company, et al. (the licensees), proposed license amendments to change the Technical Specifications (TS) for the Edwin 1. Hatch Nuclear Plant, Units 1 and 2.
The proposed changes would permit the licensee to revise its TS-required visual examination programs for safety-related snubbers for Hatch Units 1 and 2 in accordance with the guidelines set-forth in Generic Letter (GL) 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions," dated December 11, 1990.
2.0 EVALVATION The present snubber visual examination schedule in the TS is based on the number of inoperable snubbers identified in the previous visual examination.
The schedule is determined cnly by the absolute number of inoperable snubbers discovered during the previous visual examination irrespective of the size of the snubber population.
Therefore, licensees with a large snubber population find the schedule to be excessively restrictive.
GL 90-09 provides an acceptable alternative visual examination schedule that permits licensees to perform visual examinations and corrective actions during refueling outages without reducing the confidence level provided by the existing surveillance requirements.
The basic examination interval is the normal fuel cycle up to 24 months.
This interval may be extended to as long as twice the fuel cycle or reduced to as small as two-thirds of the fuel cycle depending on the number of unacceptable snubbers found during the visual examination.
The examination interval may vary by i25 percent to coincide with the actual outage.
9207020261 920619 PDR ADOCK 05000321 P
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If one or more snubbers are found inoperable during a visual examination, the present TS Limiting Conditions for Operation (LCO) require the licensee to restore or replace the inoperable snubber (s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or declare the attached system inoperable and follow the appropriate action statement for that system.
This LCO will remain in the TS.
- However, the permissible number of inoperable snubber (s) and the subsequent visual examination interval will now be determined in accordance with the new visual i
examination schedule (proposed TS Table 4.6.1).
As noted in the guidance of GL 90-09 for this line item TS improvement, certain corrective actions may have to be performed depending on the number of inoperable snubbers found.
All requirements for corrective actions and evaluations -associated with the use of the visual examination schedule, as stated in Footnotes 1 through 7 i
(Table 1 of GL 90-09) is proposed to be included in the TS.
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The-proposed changes to TS 3/4.6.L for Hatch 1 and TS_3/4.7.4 for Hatch 2 are consistent with the guidance provided in GL 90-09 for the replacement of the snubber visual examination schedule with Table 1 (including Footnotes 1 through 7) of GL 90-09.
The staff has reviewed the proposed amendments, ana finds that the proposed changes to the TS for Hatch Units 1 and 2 are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Georgia State official l
was notified of the proposed issuance of the amendments.
The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
1 The amendments change a requirement with respect to the installation or use of facility ccmponents located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase'in the amounts, i
l and no significant-change in the types, of any effluents that may be released off site, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involvt no significant hazards consideration, and there has been no public comment on such finding (57 FR 20512 dated May 13, 1992). 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, i
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.. 5.0 C.QNC L USI0f4 The Commission has concluded, based un the tonsiderations discussed above, that:
(1) there is reasonable assurance that the health and rafety of the public will not be cridangered 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 amendments will not be inimical to the common i
defense and security or to the health and safety of the public.
Principal Contributor:
H. Shaw, EMEB, NRR Date:
June 19, 1992 l
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