ML20199C205
| ML20199C205 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/06/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199C202 | List: |
| References | |
| NUDOCS 9711190261 | |
| Download: ML20199C205 (3) | |
Text
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UNITED STATES j
,j NUCLEAR REGULATORY COMMISSION 4
WASHINGTON, D.C. Sumwo01 o
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,d SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.109 TO FACILITY OPERATING LICENSE NO. NPF-57 PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY 110PE CREEK GENERATING STATION DOCKET NO. $0-354
1.0 INTRODUCTION
By letter dated September 24, 1997, the Public Service Electric & Gas Company (the licensee) submitted a request for a change to the Hope Creek Generating Station (HCGS) Technical Specifications (TSs). The requested change would add a surveillance requirement (SR) to TS 3/4.5.1, " Emergency Core Cooling Systems", to perform a monthly valve position verification for the four residual heat removal (RHR) cross-tie valves.
2.0 DISCUSSION The RHR System functions during normal reactor shutdown conditions to remove heat from the reactor. During reactor operation, the RHR System is in rtandby and functions as part of the emergency core cooling system (ECCS) in the event of a loss-of-coolant accident. The RHR System is described in the HCGS Updated Final Safety Anklysis Report (UFSAR), Section 5.4.7, " Residual Heat (Removal) Systeo," as follows:
ihe Residual Heat Removal (RHR) System consists of four independent loops A, B, C and D as shown in Figure 5.4-13. Each loop contains a motor driven pump, piping, valves, instrumentation, and controls.
Each loop takes suction from the suppression pool and is capable of discharging water to the reactor vessel via separate low pressure coolant injection line.) nozzles, or back to the sup)ression sool via a full flow test (LPCI Loops A and B have heat exc1 angers t14t are ea::h cooled by an independent loop of the Safety Auxillaries Cooling System (SACS In addition, the loops A and C pump discharge headers and the loops).
B and D pump discharge headers are each cross-tied via two manual isolation valves. The purpose of these cross-ties is to permit the use of C pump with RHR heat exchanger A and the use of D pump with RHR heat exchanger B for alternate decay heat removal, h M N E50 $ 54 p
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i The cross-ties referenced above were added during the fifth and sixth refueling outages and are the subject of the TS change proposed by the licensee in the September 24, 1997 application. The proposed TS change would be added to the monthly surveillances of TS 4.5.1.a.1 as follown c)
Verify the RHR System cross tie valves on the discharge side of the pumps are closed and power, if any, is removed from the valve operators The SR is necessary to assure that the separation of the RHR loops is not compromised such that the ECCS function of RHR might become degraded. The specification of valves "...on the discharge side of the pumps..." is made to distinguish these cross ties from those located on the suction side of the pumps, which were a part cf the initial RHR design.
In addition, while the subject cross-tie vaives are manual, the requirement to verify that '... power, if any, is removed...' refers to the licensea's option to modify the cross-ties via installation of motor-operated valves.
3.0 EVALUATION The subject RHR cross-ties are major flow paths consisting of 1841nch piping.
As such, the mispositioning of the cross-tie valves could result in significant changes in RHR flow distribution. During an ECCS injection, this flow distribution change could lead to significant degradation of the ECCS function. The design of the RHR crost-ties includes two manual isolation valves per cross-tie which decreases the likelihood that the degradation of ECCS would occur via the cross tie line(s) since both valves in a cross-tic line would have to be mispositioned.
The addition of the proposed TS surveillance is justified to further reduce the likelihood of degraded ECCS, considering the potentially, significant nature of such degradation. The proposed TS surveillance is consistent with the NRC staff guidance in NUREG-1433, Rev.1, " Standard Technical Specifications, General Electric Plants, BWR/4*, April 1995.
Based upon the above, the proposed change to TS 4.5.1.a.1 is acceptable. The changa to the TS also includes a change to the Bases.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State Official was notified of the proposed issuance of the amendment.
The State Official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility con.ponent located within the restricted area as defined in 10 CFR Part 20 an,i changes surveillance requirements. The NRC 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
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3-j occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards l
- consideration, and there has be(n no public coment on such finding (62 FR 52162). Accordingly, the amendw nt meets the eligibility criteria for-categorical exclusion set forth 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be
_ repared in connection with the issuance of the amendment.
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6.0 CONCLUSION
l The Comission has concluded, based on the considerations discussed above, that:
there is reasonable assurance that the health and safety of the_-
public w(1)l not:be endangered by operation in the proposed manner, (2) such il activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common i
defense and security or to the health' and safety of the public.
Principal Contributor:
D. H. Jaffe Date: November 6, 1997 I
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