ML20140C909
| ML20140C909 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/17/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20140C865 | List: |
| References | |
| NUDOCS 8603250528 | |
| Download: ML20140C909 (3) | |
Text
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E WASHINGTON, D C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 Maine Yankee Atomic Power Company (MYAPCo) has submitted proposed changes to the Technical Specifications (TS) for the auxiliary feedwater (AFW) system by letter to the Director of NRR on September 6,1985, as supplemented October 3, 1985 and December 16, 1985 (MN-85-209). These proposed Technical Specification changes contain the following requirements:
Technical Specification 3.8E The reactor may not be maintained in the power operation condition unless three emergency or auxiliary feedwater pumps are operable to supply emergency feedwater to all three steam generators. The three pumps consist of two emergency feedwater (motor driven) pumps (Part a) and one auxiliary feedwater (turbine driven) pump (Part b) with the emergency feedwater pumps capable of being automatically powered from separate operable emergency buses and the auxiliary feedwater pump capable of being powered from an operable steam supply system.
In addition, an inventory of over 100,000 gallons of primary grade feedwater must be available (Part c).
MYAPCo specifies the following remedial actions (Limiting Conditions for Operation) as part of Specification 3.8:
a.
With one auxiliary or emergency feedwater pump inoperable, the licensee is required to restore this pump to operable status within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> or have the plant in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one emergency and one auxiliary feedwater pump inoperable, the licensee is required to have the plant in hot standby in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With two emergency feedwater pumps inoperable, the licensee is required to have the plant in at least hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and.in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d With three auxiliary and emergency feedwater pumps inoperable, the licensee is required to initiate corrective action to restore at least one pump to operable status as soon as possible.
e.
With the emergency feedwater flow to a steam generator out of service, the licensee is required to return the flow path to service within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> or to have the plant in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
8603250528 860317 DR ADOCK O 39
2-It should be noted that the conditions for power operation, hot standby, and hot shutdown specified in the Maine Yankee TS are somewhat different from the conditions specified in the Standard Technical Specifications (STS) for Combustion Engineering (CE) Pressurized Water Reactors as shown in attached Table 1.
In addition, the licensee has incorporated TS item "e" above in order to assure that, in the event of inoperability of a single flow path to a steam generator from the EFW/AFW manifold, only a single flow path (and steam generator) is considered to be unavailable, even though all three pumps serve all flow paths.
Based on our review of the proposed Maine Yankee AFW TS changes against the CE STS and recommended technical specification for NUREG-0737, Item II.E.1.1 as contained in Generic Letter 83-37, the staff concludes that the TS will provide the required system reliability assurance and are comparable to those of other safety related systems and are, therefore, acceptable.
Environmental Conclusion This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or a change in an inspection or surveillance requirement. 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 issued a proposed finding that this amendment involves no significant hazards consideration and there has'been no public comment on such finding.
Accordingly, this 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 this amendment.
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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
March 17, 1986 Principal Contributor:
N. Wagner n
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'a TABLE 1 COMPARISON OF OPERATING CONDITIONS
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Maine Yankee TS CE STS Power Operation T
1 300*F AV Reactor Critical k,7f 1 0.99 Power > 2%
Power > 5%
Hot Standby TAV > 500 F TAV > 300 F Power < 2%
k,f f < 0. 99 Power =0%
Hot Shutdown TAV > 500*F 300*F > TAV > 200*F Reactor subcritical k,ff 4.99 by 5% Ak/k Power =0%
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