ML20072U192
| ML20072U192 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/06/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072U188 | List: |
| References | |
| NUDOCS 9409160162 | |
| Download: ML20072U192 (3) | |
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UNITED STATES I )D E
NUCLEAR REGULATORY COMMISSION ih I
WASHINGTON, D.C. 20555-0001 wj SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.195 TO FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO.172 TO FACILITY OPERATING LICENSE NO. DPR-69 BALTIM0RE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS. 1 AND &
DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By letter dated June 8,1994, the Baltimore Gas and Electric Company (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Units Nos. I and 2, Technical Specifications (TSs). The requested changes would revise Section 4.8.1.1.1.b to extend the alternate 69 kV offsite power circuit surveillance frequency to accommodate the 24-month fuel cycles currently in use at Calvert Cliffs. As requested in Generic Letter (GL) 91-04, " Changes In Technical Specification Surveillance Intervals To Accommodate a 24-month Fuel Cycle," the licensee provided an evaluation in support of the change which concludes the effect on safety is small and does not invalidate any assumption in the plant licensing basis.
2.0 EVALUATION Subsequent to increasing the refueling interval from 18 months to 24 months, the licensee requested amendments to the TSs of both units which added the definition " Refueling Interval - at least once per 24-months" to Table 1.2 of TS Definition 1.22, " Frequency Notation." The definition for "R - at least once per 18-months" remains. This is necessary to assure the safety-related systems and components which have not yet been approved for 24-month surveillance intervals, have their surveillances performed at the required 18,jonths intervals.
This is accomplished during scheduled mid-cycle surveillance / maintenance outages until all the safety-related systems and components have been approved for the 24-month refueling interval. The Commission issued Amendment No. 133 to Facility Operating License No. DPR-53 and Amendment No. 114 to Facility Operating License No. DPR-69 for Units Nos. I and 2, respectively, by letter dated December 21, 1988, which included the definition for a 24-month Refueling Interval.
The changes were consistent with the current guidance in GL 91-04 and, therefore, no other changes are necessary in relation to defining the existing surveillance intervals in the TS to support the requested changes to the alternate 69 kV offsite power circuit surveillance interval.
9409160162 940906 PDR ADOCK 05000317 P
PDR l
1
] The 69 kV Southern Maryland Electric Cooperative power source is an independent energy source for safe shutdown of the plant and to provide the ability to maintais a safe shutdown condition if no 500kV line is available.
Upon loss of all three 500 kV power sources, the 69 kV line can be transferred to any of the two 4 kV Engineered Safety Features Actuation System busses, one for each unit. The 69 kV line is also routinely used during scheduled outages, and the remotely operated breakers are used during normal plant operations.
GL 91-04 states that for cases where 18-month surveillances do not involve calibration of instruments that perform safety functions, licensees should evaluate the effect on safety of the change in surveillance intervals which supports a conclusion that the effect on safety is small.
Licensees should confirm that historical maintenance and surveillance data do not invalidate i
this conclusion.
Since 1983, the 18-month interval surveillance which manually transfers offsite power supply from the normal 500 kV to the alternate 69 kV circuit has been performed 10 times. One surveillance identified an equipment problem associated with the manual breaker closure mechanism, which was corrected.
The staff has determined that the increase in the surveillance interval from 18-months to 24-months for the alternate 69 kV offsite power circuit surveillance as specified in TS 4.8.1.1.1.b is acceptable. This determination J
is based on the historical data detailed above which indicates the overall reliability of the 69 kV circuit does not invalidate the conclusion that the change in surveillance interval has a small effect on safety.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Maryland State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requkements. The NRC staff has determined that the amendments involve 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 issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR 37063). 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.
5.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
J. Harold Date:
September 6, 1994 i
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R. Denton September 6,1994 A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, i
Original signed by j
Daniel G. McDonsid, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation Docket Nos. 50-317 l
and 50-318
Enclosures:
1.
Amendment No.195 to DPR-53 2.
Amendment No.172 to DPR-69 3.
Safety Evaluation cc w/encls:
See next page Distribution:
See attached sheet l
i DOCUMENT NAME: G:\\CCl-2\\CC89651.AMD j
- See previous concurrence l
To r:ceive a copy of this document, Indicate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy 0FFICE LA:PDI-1, E PE:PDI-l l
PM:PDI-llf,MRR/EELB l.,
- 0GC l
D:PDI-1 l
NAME CVogan W p.
JHarold: avl DMcDonald MtBerlingerWg MCase/6-DATE 09/(p/94 N 09/ /94 09/eG/94 0' '09/0h/94 09/01/94 09L6/94 0FFICIAL RECORD COPY
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