ML20151L798
| ML20151L798 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/14/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20151L793 | List: |
| References | |
| REF-GTECI-B-56, REF-GTECI-EL, TASK-B-56, TASK-OR GL-94-01, GL-94-1, NUDOCS 9708070220 | |
| Download: ML20151L798 (2) | |
Text
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WASHINGTON. D.C. 20565-0001
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 226 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 917 TO FACILITY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SE000YAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
By letter dated August 22, 1996, Tennessee Valley Authority (TVA, the licensee) proposed changes to the Technical Specifications (TS) for the Sequoyah Nuclear Plant Units 1 and 2.
The proposed changes would eliminate the accelerated testing and special reporting requirements for emergency diesel generators in TS 4.8.1.1.2.a in accordance with Generic Letter (GL) 94-01.
GL 94-01 was issued on May 31, 1994, in response to the Commission decision on SECY-93-044, " Resolution of Generic Safety Issue B-56, Diesel Generator Reliability." The letter advised licensees that they could request a license amendment to remove accelerated testing and special reporting requirements for diesel generators from plant TS, providing they committed to j
implement a maintenance program for monitoring and maintaining diesel generator performance in accordance with the requirements of 10 CFR 50.65.
2.0 EVALUATION i
2.1 Chance 1 (TS 4.8.1.1.2.a):
The licensee proposes to delete "In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:..." and to replace this phrase with "At least once per 31 days on a staggered test basis by:...".
This proposed change will elim the accelerated testing and special reporting requirements for dies,
,enerators as specified in Table 4.8-1 of l
the TS.
This proposed change is in accordance with GL 94-01 and is acceptable.
Removal of accelerated testing was recommended in GL 94-01 to eliminate unnecessary testing of diesel generators and to improve the overall reliability of diesel generators. Because the licensee is required to monitor and maintain diesel generator performance in accordance with 10 CFR 50.65,
" Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," there is no need to duplicate this requirement in a separate licensee commitment as stated in GL 94-01.
ENCLOSURE 970807G220 970714 PDR ADOCK 05000327 P
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2 4
2.2 Chanae 2 (Table 4.8-1): The licensee has proposed to delete Table 4.8-1 i
and the attachment to Table 4.8-1 from the TS for Sequoyah Units 1 and 2 (TS Pages 3/4 8-7 & 3/4 8-7b for Unit I and 3/4 8-8 & 3/4 8-8b for Unit 2), and insert "THIS PAGE INTENTIONALLY DELETED" where appropriate.
1 This proposed change is consistent with the elimination of accelerated testing and special reporting requirements for diesel generators, as recomended in GL i
94-01, and is acceptable. Since the table and its attachment are no longer needed, it is appropriate to delete them from TS.
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3.0 CONCLUSION
S The U. S. Nuclear Regulatory Commission (NRC) staff has evaluated the licensee-proposed changes documented in Section 2.0.
The changes proposed by i
the licensee and evaluated above are acceptable because (a) they are intended to improve the reliability of.the diesel generators; or (b) they are j
administrative and intended to clarify the TS.
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4.0 STATE CONSULTATION
i In accordance with the Commission's regulations, the Tennessee State official l
was notified of the proposed issuance of the amendments. The State official
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had no comments.
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5.0 ENVIRONMENTAL CONSIDERATION
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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 1
Part 20 and changes surveillance requirements.
The NRC staff has determined j
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
'i 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 (61 FR 52969 dated October 9, 1996). 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.
6.0 CONCLUSION
The Commission has 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, (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 Contributor:
Virgil Beaston Dated:
July 14,1997 i