ML20059G788
| ML20059G788 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/04/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059G787 | List: |
| References | |
| NUDOCS 9009130153 | |
| Download: ML20059G788 (3) | |
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' UNITED STATES H
V.s @4 ' "'ri NUCLEAR REGULATORY COMMISSION r[
j WASHING TON, D. C. 20555
-l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION' w
SUPPORTING AMENDMENT NO.
44 TO FACILITY OPERATING LICENSE NO. NPF-39 i
t PHILADELPHIA ELECTRIC COMPANY t
LIMERICK GENERATING STATION, UNIT 1 DOCKET N0. 50-352 l
1.0 tINTRODUCTION I
By letter dated July 11, 1990, Philadelphia Electric Company (the licensee)
- requested an amendment to Facility Operating License No. NPF-39 for the 1
Limerick Generating Station, Unit 1.
The proposed amendment would modify the Technical. Specifications (TS) for Limerick Generating Station, Unit 1 (LGS-1) to reflect a planned modification to install new suppression pool l
waterlevelindicationattheRemoteShutdownPanel(RSP)tosupportsafe' s
shutdownain the, event of a fire. This modification is planned to be performed' during.the next (third) refueling outage for LGS, Unit.1, currently scheduled.to begin in September 1990, based on a connitment in LGS Unit 1: Licensee; Event Report-(LER) No. 1-89-023, " Lack of Protected
- Suppression Pool Level and Temperature Indication in the Event of a Fire," dated May 5 1989, and results in the need to add a new-i containmentisolatIonvalvetotheappropriateTSSection. The planned modification:will require changing the existing primary containment isolation valve arrangement for the Suppression Pool Level Monitoring i
System (SPLMS). Two new motor-operated valves will be installed. 70ne of the new valves will be tagged HV-55-121 and will be used to isolate the existing: electrical Division 2 SPLMS instrumentation and process lines.
Existing motor-operated valve HV-55-121 will-be retagged 55-1092 and left in place with the capability for manual-operation. :The power and control
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cables associated with this valve will be terminated at the new valve.
HV-55-121'. The other new valve will be tagged HV-55-126 and will be used 1
to isolate the.new electrical' Division 1 SPLMS level transmitter and its process line. - Both new valves HV-55-121 and HV-55-126 will be primary containment isolation valves. Thus, these valves need to be added to the table of isolation valves in the TS that must be operable.
TheproposedchangeistoTSTable3.6.3-1,"PartA-PrimaryContainment
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-Isolation Valves, TS page 3/4 S-28,-to add the new outboard primary containment isolation valve, HV-55-126, to this table for penetration l-number 219A. TS Table 3.6.3-1 currently lists outboard primary containment L
isol.ation valve, HV-55-121, for penetration number 219A. Therefore, no change is required to-this table for the new valve HV-55-121 since all requirements specified in TS Table 3.6.3-1 for existing valve HV-55-121 (to be converted to a non-containment isolation manual valve 55-1092)are applicable to.the new valve.
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-2.0 EVAltfATION 4 H'
c The proposed TS change results from a planned modification to install a new electrical. Division 1 SPLMS instrumentation loop. This new level a
-instrumentation loop, in conjunction with the existing electrical
- 1 Division 2 SPLMS-instrumentation loop will-ensure that suppression pool; water level indication is available to support safe shutdown of the plant 4
in the event of~a fire. The original function of.the SPLMS, as described 1
in the FSAR _will remain unchanged. -This planned modification does not 1
involve any, physical change to the existing channels of suppression pon1 water level instrumentation that-are relied on for Emergency Core Cooling
. System (N CS) actuation, post-accident monitoring, or remote shutdown capability (in accordance with GDC 19 of 10 CFR 50, Appendix A).
This planned modification will not add any new electrical interfaces with.
l systems not related to suppression pool water level monitoring. This-planned modification will not adversely affect the operation of any safety-related plant equipment, and will not introduce any new failure mode for the existing systems associated with fire protection safe
. shutdown methods A, B, C, D,and R.
1 The'desiInofthisplannedr.odificationmeetstheexistingdesigncriteria-i for the SPLMS, the primary containment isolation system for instrument lines, and the CAC system, and meets the existing seismic and dynamic qualification requirements for the components of these systems.
i The new level instrumentation. loop will be powered from an electrical Division 1 Class 1E source, and therefore, its design conforms to
. applicable criteria for physical separation, redundancy.. and divisionalization.
Theproposed.changetoaddthenewvalvetoTSTable3.6.3-1(thelistof primary containment isolation valves) is acceptable.
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-3.0 ENVIRONMENTA1. CONSIDERATION
-This amendment involves.a change to a requirement with respect to the installation or use of a facility component located within the restricted area'as defined in~10 CFR Part 20. 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 nor environmental assessment need be
. prepared in connection with the issuance of this amendment.
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! 4.0. CONCLUSION i
>:The' Commission.made a proposed' determination.that the amendment involves ~
no significant hazards consideration which was published in the Federal Register (55 FR 30306) ion July 25,'1990 and consulted with the CommonwealthL i-of Pennsylvania. ' No public comments ~ were received and the Commonwealth; of Pennsylvania did not have any comments.
a The staff has concluded, based on the consideration discussed above,.
o that' (1):thereisreasonableassurancethatthehealthandsafetyof-i h
.t e public will not be endangered by operation in the proposed manner, and'(?) such' activities will be conducted in compliance with the
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Commission's regulations and the issuance'of this amendment will not be j
o inimical to the common defense and.the' security nor to the health erd safety of the public.
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. Principal Contributor.:
D. Clark Dated:' September 4 '1990 1
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