ML20072L395
| ML20072L395 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/23/1994 |
| From: | Thadani M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072L398 | List: |
| References | |
| NUDOCS 9408310244 | |
| Download: ML20072L395 (7) | |
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E UNITED STATES lQ
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NUCLEAR REGULATORY COMMISSION g*..../
S WASHINGTON, D.C. 20555-0001
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STAT!0N. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated June 6, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authoriz'ed by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical'to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
L 9408310244 940023
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PDR ADOCK 05000352 p
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications T'.ie Technical Specifications contained in Appendix A and the invironmental Protection Plan contained in Appendix B, as revised through tmendment No. 74, are hereby incorporated into thi:: license.
Pni1adelphia Electric Company shall operate the facility in accorcance with the Technical Specifications and the Environmental Protectin i Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
Mohan C. Thadani, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 23, 1994
J ATTACHMENT TO LICENSE AMENDMENT N0. 74 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*
Remove Insert 3/4 3-79 3/4 3-79*
3/4 3-80 3/4 3-80 3/4 6-29 3/4 6-29*
3/4 6-30 3/4 6-30
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I Table 3.3.7.4-1 (Continued)
RCIC SYSTEM (Continued)
HV-49-1F080 Control-Vacuum breaker outboard isolation valve HV-49 1F084 Control-Vacuum breaker inboard isolation valve FIC-49-13001 Controller-RCIC discharge flow control E51-545 RCIC Turbine Trip Bypass 1
NUCLEAR BOILER SYSTEM H55-41-191 Control-Transfer switch PSV-41-1F013A Control-Main steam line safety / relief valve PSV-41-1F013C Control-Main steam line safety / relief valve P5V-41-1F013N Control-Main steam line safety / relief valve
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t RHR SYSTEM HSS-51-192 Control-Transfer switch t
H55-51-193 Control-Transfer switch HSS-51-194 Control-Transfer switch HSS-51-195 Control-Transfer switch HSS-51-196 Control-Transfer switch H55-51-197 Control-Transfer switch H55-51-198 Control-Transfer switch HV-51-1F009 Control-RHR pump shutdown cooling suction inboard isolation HV-51-1F008 Control-RHR shutdown cooling suction outboard isolation HV-51-1F006A Control-1A RHR loop shutdown cooling suction HV-51-1F0068 Control-18 RHR loop shutdown cooling suction HV-51-1F004A Control-1A RHR pump suction 1AP202 Control-1A RHR pump LIMERICK - UNIT 1 3/4 3-79
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TABLE 3.3.7.4-1 (Continued)
RHR SYSTEM (Continued)
HV-43-lF023A Control-Recirculation pump A suction valve HSS-43-191 Control-Transfer switch HV-51-lF007A Control-1A RHR pump minimum flow bypass valve HV-51-lF048A Control-1A heat exchanger shell side bypass HV-51-lF015A Control-1A shutdown cooling injection valve HV-51-lF016A Control-Reactor containment spray HV-51-lF017A Control-1A RHR loop injection valve HV-51-lF024A Control-1A RHR loop test return HV-51-lF027A Control-Suppression pool sparger isolation HV-51-lF047A Control-1A Heat exchanger shell side inlet HV-51-lF003A Control-1A Heat exchanger shell side outlet HV-51-lF049 Control-RHR Discharge to radwaste outboard isolation HV-51-125A Control-1A/lc test return line to suppression pool RHR SERVICE WATER SYSTEM HSS-12-015A-2 Control-Spray pond / cooling tower select HSS-12-015C-2 Control-Spray pond / cooling tower select HSS-12-016A-2 Control-Spray / bypass select HSS-12-016C-2 Control-Spray / bypass select 9
LIMERICK - UNIT 1 3/4 3-80 Amendment No. N, 65, 74
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,o-t aalt 3.6.3-1 (Con Innss)
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PART A - PRIMARY CONTAINMENT ISOLATION VALVES 9
M x
INBOARD OUTBOARD ISOL.
PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S) NOTES P & 10 c-25 NUMBER BARRIER BARRIER TIME.IF APP. IF APP.
-d (SEC)(26)
(20) s 237-1 SUPPRESSION POOL CLEANUP HV52-127 60 B,H 4,11,22 52 PUMP SUCTION PSV52-127 NA 11,22 HV52-128 60 B,H 11,22 237-2 SUPPRESSION POOL HV52-139 45 10 52 LEVEL INSTRUMENTATION SV52-139 6
10 238 RHR RELIEF VALVE HV-C-51-lF1048 NA 11 51 l
u, DISCHARGE PSV51-106B NA 19 2
os 4,
239 RHR RELIEF VALVE HV-C-SI-IF103A NA 11 51 l
c)
DISCHARGE PSV51-106A NA 19 241 RCIC VACUUM RELIEF HV49-lF084 40 H,KA 4,11,24 49 HV49-lF080 40 H,KA 11,24 k
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