ML19341B166
| ML19341B166 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/20/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341B160 | List: |
| References | |
| NUDOCS 8101300383 | |
| Download: ML19341B166 (2) | |
Text
p s* * * %g
?,
UNITED STATES
[1 j
NUCLEAR REGULATORY COMMISSION
, s.,,
E WASHINGTON. o. C. 20555
't SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPCRTING AMENOMENT NO.62 TO PROVISIONAL OPERATING LICENSE NO. CPb 20 CONSUMERS PCWER CCMPANY PALISADES PLANT 00CXET NO. 50-255 1.0 Introduction ISE Sulletin 79-06A, Revision 1, listed reveral areas of concern to be evaluated by licensees as a result of the Three Mile Island-2 accident including improvement of the reliability of auxiliary feedwater systems.
By letter dated July 31, 1979, the Consumers Power Comany (the licensee) proposed changes to Section 3.5 of the Technical Specifications appended to Provisional Operating License No. OPR-20 for the Palisades Plant which would revise the limiting conditions for operation for the auxiliary feed-water pungs. The proposed enanges an designed to further ensure the availanility of the auxiliary feedwater system by providing more coere-hensive and comlete limiting conditions for operation and surveillance requirements.
2.0 Discussion f
The changes precosed by the I!cansee would modify section 3.5 of the Technical Specifications to require that both auxiliary feed pues and the firewater makeup to the auxiliary feed cump suction be operable whenever primary plant temerature is above 325'F. This requirement could be relaxed to allow maintenance on one auxiliary feedwater pum or the fire.ums, but the licensee would be required to place the plant in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if an auxiliary feecwater pumo or the firewater l
makeuo would become inocerable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If one auxiliary feedwater pumo and the firewater makeuo sucoly were to both become in-t coerable, then the licensee wculd place the plant in hot standby witnin one hour, in hot shutdown within the next 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective actions are ccmoleted to restore r
redundancy to the auxiliary feedwater system. With both auxiliary feed-water cumos out of service, then power would be reduced within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
to the lowest level consistent with reliable main feedwater system coeration.
l "O
-2 D *
- D "D PV
.dj woJ w
o 3.0 Evaluation The proposed changes would improve the procability that adequate feecwater capability is availacle at all times Oy, spec 1fying more stringent limiting conditions for operation of the auxiliary feedwater system. The requirement that both auxiliary feedwater sucos and the firewater makeup to the auxiliary feedwater pump suction be coerable makes it more likely that scme source of auxiliary feedwater would be available at all times._ If one auxiliary feedwater pum and the firewater makeup supply were to both become incoerable, then a plant shutdown within one nour would be the mst prudent course of action, considering the lacx of redundancy wnica sculd then exist in the auxiliary feecwater system.
If both auxiliary feedwater pumos were to become inccerable, then the clant should be placed in a stable coerating condition anc acticn snould be taken imediately to restore at least one auxiliary feecwater cumo as soon as cossible. The plant cannot be cooled down in a normal fashicn without any auxiliary feedwater cumos and continued, stable, ocwer coeration using ne main feedwater system capability is therefore the oreferred made of coeration.
The proposed changes are consistent with current licensing requirements set forth in the Standard Technical Specifications for Concustion Based on this and the above considerations, we Engineering reacters.
find these changes acceptable for inclusion in the Palisades Technical Specifications.
4.0 Environmental Consideration We have determined that the amendment does not authori::e a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental incact and, pursuant to 10 CFR 151.5(d)(4), that an environmental incact statement or negative declaration and environmental igact appraisal l
need not be prepared in connectica with the issuance of this amendment.
I 5.0 Conclusion We have concluded, based upon the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant ha:llards consideration (2) there is l
reasonable assurance that the health and safety of the public will not be endangered by coeration in the proposed manner, and (3) sucn activities will be encucted in concliance with the Coninission's regulations and the issunce of this amencment will not be inimical to the comon defense and tecurity or to the health and safety of the public.
j l
Oate:
Octocer 20, 1980 i