ML17146A819
| ML17146A819 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/28/1987 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A820 | List: |
| References | |
| NUDOCS 8706040161 | |
| Download: ML17146A819 (9) | |
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+p**W UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8
Light Company, dated May 14,
- 1987, as supplemented by letters dated May 19 and 21, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 regulations of the Commission; 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 Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment"wi11 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 65 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PPKL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
8706040161 870528 PDR ADOCK 05000387 P
3.
This license amendment became effective May 22, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
may 28. l987
/s/
Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects I/II POI g/+87 DI-2/PM MThadani y u~i87 0~GO L, /gjp/87 PDI-2/D Wgut r
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3.
This license amendment became effective May 22, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
my 28, 1987 Bruce A. Bo er, Assistant Director for Region I Reactors Division of Reactor Projects I/II
ATTACHYIENT TO LICENSE AYIENDMENT NO. 65 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The overleaf page is provided to maintain document completeness.
RENOVE 3/4 6-19 3/4 6-20 INSERT 3/4 6-19 3/4 6-20 (overleaf)
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TABLE 3. 6. 3-1 PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER a.
Automatic Isolation Valves MSIV HV-141F022 A, B, C, D HV"141F028 A,B,C,D MSL Drain HV-141F016 HV"141F 019 RCIC Steam Su l
HV-149F007 HV-149F008 HV-149F088 HPCI Steam Su 1
HV-155F002" HV"155F003 HV-155F100 RHR - Shutdown Coolin Suction HV-151F008 HV-151F009 RMCU Suction(')
HV-144F001 HV-144F004 RHR - Reactor Vessel Head S ra HV-151F022 HV-151F023 MAXIMUM ISOLATION TIME (Seconds) 10 10 20 20 3
50 50 3
52 52 30 30 30 20 ISOLATION( )
SIGNAL s X,C,D,E,P,UA X,C,D,E,P,UA X,C,D,E,P,UA X,C,D,E,P,UA K,KB K,KB K,KB L,LB L,LB L,LB A,M,UB A,M,UB B,J,W I,B,J,W A)M,UB,Z A,M,UB,Z
- The HPCI HV-155F002 valve may be considered OPERABLE with its current minimum torque switch setting for the period beginning May 23, 1987 unti 1 an outage of sufficient duration to revise the setting occurs but no later than the next refueling outage scheduled on or about September 12, 1987.
SUSQUEHANNA - UNIT 1 3/4 6"19 Amendment No. 65 Effective Date:
May 22, 1987
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER MAXIMUM ISOLATION TIME Seconds ISOLATION( )
SIGNAL s Automatic Isolation Valves (Continued)
Containment Instrument Gas HV-12603 SV-12605 SV-12651 SV-12661 SY-126?1 RBCCW HV-11313 HV"11314 HY-11345 HV-3.1346 Containment Pur e
HV", 15703 HY-15704 HY"15705 HV-15711 HV-15713 HV-15714 HY-15721
HY-15722 HV-15723 HV-15724 HV"15725 RHR - Dr ell S ra
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HV-151F016 A, 8 RB Chilled Mater HY"18781 Al,A2,Bl,B2 HV-18782 Al,A2, B1,B2 HV"18791 Al,A2,81, B2 HV-18792 Al,A2,81, 82 20 N/A N/A H/A N/A 30 30 30 30 15 15 15 15 15 15 15 15 15 15 15 90 40 6
15 4
X,Z X,Z X,Z Y,B Y,B X,Z X,Z X,Z X,Z B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R X,Z X,Z X,Z Y,B Y,B SUSQUEHANNA - UNIT 1 3/4 6-20 Amendment No.
36