ML20062A278

Safety Evaluation Supporting Amend 145 to License DPR-32

ML20062A278
Person / Time
Site:	Surry
Issue date:	10/11/1990
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062A275	List: ML20062A268 ML20062A278
References
NUDOCS 9010190273
Download: ML20062A278 (2)

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NUCLEAR REGULATORY COMMISSION -

UNITED STATES

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 145 T0 FACILITY OPERATING LICENSE NO. DPR-32 n

VIRGINIA ELECTRIC AND POWER COMPANY O

SURRi POWER STATION, UNIT NO. 1 DOCKET NO. 50-280

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1.0 INTRODUCTION

E By letter dated June 26, 1990, Virginia Electric and Power com ny (the

' licensee).requestedchangestotheTechnicalSpecifications(T Section 3.23,

" Main Control Room and Emergency Switchgear Room Ventilation'and Air l.

Conditioning Systems." The proposed changes would eliminate the present i

. operational restrictions on the Unit 1 main control room (MCR).and emergency

switchgear. room (ESGR) air handling units. Thes

:3erational restrictions.

were an! interim measure. imposed by a previous specification change (License-L

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Amendment.No.1129)-approved by the staff on May 30, 1989, 2.0" EVALUATIONI

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The MCR and:ESGR air conditioning' system is a shared system that cools the

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Surry Unit l1 and. Unit 2 main; control rooms, emergency switchgear rooms, and

. relay rooms. 'The: system was originally desi ned to consist of two 100 percent-

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capacity trains..Each train.contains one ch 11er refri.geration unit and four air. handling units (AHU) - a dedicated AHU.for each of the' areas served, i.e.,

.the Unit 1 MCR Unit-2 MCR,-Unit 1 ESGR and Unit 2 ESGR (the ESGR includes the.

. relay rooms).,A third chiller is provided as'a maintenance. swing chiller.

r As identified in the staff':, May -30,.1989 evaluation, the-licensee determined by testing that each air. conditioning train did not,provire the required 100

' percent; heat removal. capacity. As an interim measure, mojifications to the-p existing equipment were made to meet the system design br. sis. The interim-n' modifications required the operation of two air handline, units in each J

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. emergency switchgear. room and'two chillers to maintain ESGR temperatures under

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design heat load conditions' As a result of these interim modification.s, h

, interim limiting conditions for operation were also required to address t

.different failure modes..

! Permanent modifications are being made to the Unit 1-AHUs such that each AHU

. for Unit I will-be capable of:100' percent. heat removal capacity in accordance

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..;with?the original. design basis. These modifications will be complete prior i,

' to restart from the fall.1990 refueling outage. The proposed TS change reflects the' permanent modifications and restores the Unit I specification to its y

rinitial operating restrictions,-i.e., with one Unit 1 AHU inoperable, operation M4+

of Unit 1 may continue for up to 7 ' days. Unit 2 still contains the interim l

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operating restrictions which allow a Unit 2 MCR AHU to be-inoperable for up'to-1 7 days but require two ESGR AHU drive motors to be operable for each AHU unit and require Unit-2 shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> whenever an ESGR AHU becomes inoperable.' The Unit 2 permanent r:cdifications will be made during the Unit 2-1991 refueling outage. TS 3.23 will be modified at that time to delete the-

~ interim operating restrictions for Unit 2.

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3.0

SUMMARY

Based on its evaluation, the staff concludes that the proposed TS change is j

- conservative and in accordance with the permanent modifications to meet the j

original do-ign basis criteria of the MCR and ESGR air conditioning. systems.

j The proposed '/. cay limiting condition for operation (LCO) with one AHU inoperable is consistent with other engineered safety' features LCOs for the Surry plant.and with the original Surry MCR and ESGR specification. The staff, j

therefore, concludes that the proposed change is-acceptable.

4.0 EMVIRONMENTAL CONSIDERATION This amendment involves a change to a requirement with respect to installation l-

'or use of a facility component located within the restricted area as defined'in l'

10 CFR Part 20.- We have xtermined that this amendment involves no significant

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. increase-in the amounts, Oad 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 Connission has i

previously: issued a proposed finding,that this amendment involves no significant-a hazards consideration 'and there-has been no public connent on such finding.

R Accordingly, this amendment meets the-eli l

" exclusion set forth in.10 CFR 51.22(c)(9)gibility criteria for categorical Pursuant to 10 CFR 51.22(b), no

- environmental impact statement or environmental assessment.need be prepared in i

connection with the issuance of this amendment.

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5.0-CONCLUSION j

H 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 Connission's regulations and the issuance of s thisJamendment will not be' inimical to the connon defense and security orL to b

the. health and safety of the public.

i Dated: October 11, 1990 i

iPrincipal Contributor:

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W. LeFaye 0,

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