ML20081J487
| ML20081J487 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081J483 | List: |
| References | |
| NUDOCS 8311080586 | |
| Download: ML20081J487 (3) | |
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Mt%q'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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i WASHINGTON, D. C. 20555 Q..ox]
SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENOMENT NO. 54 TO FACILITY OPERATING LICENSE NO. DPR-70 PUBLIC SERVICE ELECTRIC AND GAS COMPANY.
PHILADELPHIA ELECTRIC COMPANY, DELPCURA FOUElt AND LIGHT COMPANY, AND_
ATLANTIC CITY ELECTRIC COMPANYS
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SALEM NUCLEAR GENERATING STATION, UNIT N0. I
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DOCKET NO. 50-272 INTRODUCTION
.In February of 1983, Salem Unit 1 experienced an extended outage that was required for the investigation and the development of a corrective action program relating to failure of the unit to automatically trip on two demands.
This, in additien to other unforseen delays in the restart of Salem Unit 1 following its fourth refueling outage, would require a four-to-five-week plant shutdown for the sole purpose of performing the Type A test origin' ally scheduled in October 1983, after only about five months of full power operation.
In view of the potentiil shutdown and associated cost, the
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Public Service Electric and Gas Company (PSE&G) submitted a request (1) for a one-time extension of the 40 t:10 month interval between periodic Type A tests, and proposed that the required test be performed at the next (fifth) refueling outage, which will commence on May 31, 1984. On August 19, 1983, PSE&Gsubmittedanotherletter(2)transmittingadditional infomation in support of their request.
The staff has reviewed these submittals and the review results are provided below..
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EVALUATION
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Appendix J to 10 CFR 50 requires that a set of three periodic Type A tests be performed at approximately equal intervals during each 10 year service period.
The purpose of the Tfpe A test is to provide confimation of the overall containment integrity after a period of plant service.
It also provides a i
l measure of the effectiveness of the more frequently perfomed Local Leak Itate Test program. Therefore, minor alterattoris of the interval between two Type A tests would be considered acceptable if containment integrity has been demon-strated b.y orevious Type A tests and verified by an effective tocal Leak Rate Test Program.
We have reviewed.the bases presented in submittals (1) and (2) above, to justify the one-time relief from the Technical Specifications (75) limit of 40 t 10 months for a periodic Type A test interval, and find the following bases acceptable for granting the one-time extension of the Type A test interval requested by PSE&G:
e 8311090586 831031 PDR ADOCK 05000272 P
o Acceptable integrated leakage tests nave been performed for both the pre-operational Tyoe A test and the first Type A retest. The results of these tests indicate that containment integrity has been maintaine3 within
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the TS limits. The first Type A retest roulted in a leakage rate (at j
r.he 95% upper confidence level) of 0.62 La; tne acceptance criterion for a Type A Test is that the measured ~ltakage rate be less'than 0.75 La.
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1 A complete Local Leak P. ate Test Program was completed on all penetrations o
and valves during the most recent refueling outage. The combined test results were well within the TS limits.of 0.6 La; the measured leakage rate for the local leakage test program was 0.069 La.
An increased surveillance program for Local Leak Rate tests will be
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o implemented until the ndxt refueling outage.
Surveillance will be increased for those containment isolation valves that can be tested during plant operation and which,have exhibited high or moderately high leakage during previous local leak rate testing. This includes valves IVC-1, IVC-2, IVC-3, IVC-4, IVC-7, IVC-8, IVC-9 and IVC-10. Valves which are not testable during plant operation will be tested when the earliest opportunity arises, e.g., unscheduled cold shutdowns with affected portions of the system drained. This includes valves 12 CS-2, 11 CA-330, 12 CA-330, ICC-138, ICC-215, ICV-71, IFP-147 and IFP-148. Surveillance will be increased by reducing the scheduled intervals from once every 24 months for valves IVC-7 through -10, and from once every 6 months for valves IVC-1 through
-4, to once every three months.
PSE&G has reviewed its records as far back as start of comercial operation o
and found that no repairs have bben made to the concrete containtrent or the contaimaent liner. Further, since start of comercial operation, they have had no indications of any kinds of problems that would, in some manner,-
affect a Type A Test.
From the above bases, we find that the Salem Unit I containment integrity has been maintained through the existing programs and that the increased surveillance program for local leak rate tests should further reduce the likelihood of a loss of containment integrity until the next refueling outage.
We find that the request by PSE&G for a one-time extension of the Type A test interval to the next refueling outage on May 31, 1984 is acceptable.
SUMMARY
The containment structure is a passive mitigating feature and its primary function is to impede the release of fission-products to the environs in the event of a LOCA inside the containment. The Containment, therefore, does not influence the initiation or progression of any accident.
Consequently, the proposed extension of the Type A test interval would neither increase the probability of an accident previously evaluated; nor create the possibility of a ne<.# or different kind of accident from any accident previcusly evaluated.
The purpose of the Type A test is to provide periodic confirmation of over all containment leakage integrity and verify the effectiveness of the Local Leak Rate Testing Program. Since containment leakage would most likely occur p
l through containment penetrations ar isolation valves, an effective local Leak Rate Testing Program, which is conducted at a greater frequency than l
the Type,A test, will provide continued assurance of containment integrity.
,Therefore, the proposed extension of the Type A test interval, supplemented with increased surveillance o.f certain containment isolation valves, would not reduce the margin of safety provided by the Salem containment, and it is not likely that the consequence to the public would be increased.
On these bases, the staff concludes that the amendment does not involve a significant hazards consideration, and therefore, is' acceptable.
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A petiticn to intervene has.been received from the State of Delaware relative to this amendment request. We have considered the comments contained in the petition and have concluded that the comments do not affect our determination that this amendment does not involve a significan' itazards consideration.
t ENVIRONMENTAL CONSIDERAT' ION We have determined that the amer.dments do not authorize a change in effluani types or total amounts nor'aa increase in power level and will noc result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 951.5(d)(4), that an environmental impact statement or negative declaration and environmental impact aporaisal need not be prepared in connection with the issuance of this amendm'ent.
CONCLUSION We have concluded, based on tne considerations discussed above, that: (1) there is reascnable 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 this amendment will not be inimical to ths common' defense and security or to the health and safety of the public.
Date: October 31, 1983 Princ.ipal Contributor:
J. Huang
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