ML20080G434

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Amend 47 to License NPF-85,removing Controls for Remote Shutdown Sys Control Valve & Primary Containment Isolation TS Tables 3.3.7.4-1 & 3.6.3-1
ML20080G434
Person / Time
Site: Limerick Constellation icon.png
Issue date: 01/27/1995
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co
Shared Package
ML20080G436 List:
References
NPF-85-A-047 NUDOCS 9502070298
Download: ML20080G434 (6)


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S UNITED STATES ii' NUCLEAR REGULATORY COMMISSION

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wassiscTos. o.c. 2ossmi PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSF, A w.dment No 47 License No. 'JF-85 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated June 30, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission'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 Comission; C.

There is reasonable assurance (i) that the activities authorized 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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.

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. 2.

Accordingly, the license is amended by changes to the Teu..ical i

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised chrough Amendment No. 47, are hereby incorporated into this license.

Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR TH UCLEAR REGULATORY COMMISSION d. /-

or John F. Stolz, 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:

January 27, 1995

i ATTACHMENT TO LICENSE AMENDMENT N0. 47 1

FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached page. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 3-80 3/4 3-80 3/4 6-29 3/4 6-29 3/4 6-30 3/4 6-30

e Table 3.3.7.4-1 (Continued)

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RHR SYSTEM (Continued)

HV-43-2F023A Control-Recirculation pump A suction valve j

HSS-43-291 Control-Transfer switch HV-51-2F007A Control-2A RHR pump minimum flow bypass valve HV-51-2F048A Control-2A heat exchanger shell side bypass

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HV-51-2F015A Control-2A shutdown cooling injection valve l

HV-51-2F016A Control-Reactor containment spray HV-51-2F017A Control-2A RHR loop injection valve HV-51-2F024A Control-2A RHR loop test return HV-51-2F027A Control-Suppression pool sparger isolation HV-51-2F047A Control-2A Heat exchanger shell side inlet i

HV-51-2F003A Control-2A Heat exchanger shell side outlet HV-51-2F049 Control-RHR Discharge to radwaste outboard isolation HV-51-225A Control-2A/2C test return line to suppression pool RHR SERVICE WATER SYSTEM j

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 LIMERICK - UNIT 2 3/4 3-80 Amendment No. 47

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C TABLE 3.6.3-1 (Continued)

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2 i

3 PART A --PRIMARY CONTAllmENT ISOLATION VALVES n

7 IN8OARD OUTBOARD ISOL.

PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.

SIGNAL (S),

NOTES P & ID c2 NUMBER BARRIER BARRIER TIME.IF APP. IF APP.

g I

(SEC)(26)

(20) m 226A RHR MINIMUM RECIRC HV51-205A 40 4,22,29 51 226B RHR MINIMUM RECIRC HV51-205B 40 4,22,29' 51 227 ILRT DATA ACQUISITION 60-2073 NA 60 SYSTEM 60-2074 NA l

2280 HPCI VACUUM RELIEF HV55-2F095 40 H,LA 4,11,24 55 w2 HV55-2F093 40 H,LA 11,24

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229A INSTRUMENTATION -

SV57-201 5

10 57

=

SUPPRESSION POOL PRESSURE SUPPRESSION POOL LEVEL 2.'0B INSTRUMENTATION - DRYWELL --

HV61-212 45 23,29 61 SUMP LEVEL HV61-232 45 23,29 g

231A DRYWELL FLOOR DRAIN HV61-210 30 B,H 11,22 61 g

SUMP DISCHARGE HV61-211 30 8,H 11,22 231B DRYWELL EQUIPMENT DRAIN

' HV61-230 30 B,H 11,22 61 E

TANK DISCHARGE HV61-231 30 B,H 11,22 235 CS PUMP MINIMUM RECIRC HV52-2F031A 45 LFCH 5,22,29 52 236 HPCI PUMP MINIMUM RECIRC HV55-2F012 15 LFHP 5,22 55 m

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TABLE 3.6.3-1 (Continued) 3 PART A - PRIMARY CONTAINMENT ISOLATION VALVES E

E INBOARD OUTBOARD ISOL.

Z PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.

SIGNAL (S),

NOTES P & ID NUMBER BARRIER BARRIER TIME.IF APP. IF APP.

m (SEC)(26)

(20) 237-1 SUPPRESSION P0OL CLEANUP HV52-227 60 B,H 4,11,22 52 PUMP SUCTION PSV52-12i NA 11,22 HV52-2* e 60 B,H 11,22 t

237-2 SUPPRESSION POOL HV52-239 45 10 52 LEVEL INSTRUMENTATION SV52-239 6

10

.t' 238 RHR RELIEF VALVE HV-C-51-2F104B 18 CG 51 DISCHARGE PSV51-206B NA 19 239 RHR RELIEF VALVE HV-C-51-2F103A 18 C,G 51 DISCHARGE PSV51-206A NA 19 k

241 RCIC VACUUM RELIEF HV49-2F084 40 H,KA 4,11,24 49 E

HV49-2F080 40 H,KA 11,24 e

.