ML17157A462
| ML17157A462 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/05/1990 |
| From: | Greenman E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157A463 | List: |
| References | |
| NUDOCS 9012130215 | |
| Download: ML17157A462 (9) | |
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+y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 PENNSYLVANIA POWER 8[ LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
70 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power It Light Company, dated October 30, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set for'th in 10 CFR Chapter I; B.
C.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; 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 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.
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-22 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. 70 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
9012130215 901205 PDR ADOCK 05000388 P
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3.
This license amendment became effective on October 30, 1990.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 5,
1990
/s/
Edward G.
- Greenman, Acting Assistant Director for Region I Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
/LA ien 90 PDI-2/PM G
+NThadani:tlc PDI-2/D Region I Butler Acting ADRI EGreenman
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3.
This license amendment became effective on October 30, 1990.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Edward G. Greenman, Acting Assistant Director for Region I Reactors Division of Reactors Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 5,
1990
ATTACHMENT TO LICENSE AMENDMENT NO. 7O FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised page is identified by Amendment number and contains 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*
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TABLE 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER a.
Automatic Isolation Valves MSIV HV-241F022 A,B,C,D HV-241F028 A,B,C,D MSL Drain HV"241F016 HV-241F019 RCIC Steam Su 1
HV-249F007 HV-249F008 HV-249F088 HPCI Steam Su l
HV-255F002 HV-255F003 HV-255F100 RHR - Shutdown Coolin Suction HV-251F008 HV"251F009 RWCU Suction(
)
HV-244F001" HV-244F004 RHR - Reactor Vessel Head S ra HV"251F022 HV-251F023 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 "For the RWCU HV-244 F001 valve, the ACTION statement 3.6.3.a need not be fol-lowed for the period beginning October 30, 1990 until an outage of sufficient duration to revise the current torque switch setting occurs.
SUSQUEHANNA - UNIT 2 3/4 6"19 Effective Date:
October 30, 1990 Amendment No.
70
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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-22603 SV-22605 SV-22651 SV-22661 SV-22671 RBCCM HV-21313 HV-21314 HV-21345 HV-21346 Containment Pur e
20 N/A N/A N/A N/A 30 30 30 30 X,Z X,Z X,Z Y,B Y,B X,Z X;Z
-X,Z X,Z HV-25703 HV-25704 HV-25705 HV-25711 HV-25713 HV-25714 HV-25721 HV-25722 HV-25723 HV-25724 HV-25725 RHR -
D ell S ra ( )
15 15 15 15 15 15 15 15 15 15 15 B,Y,R B,Y,R B,Y,R B,Y,R B,YBR B,Y,R HV-251F016 A,B RB Chilled Mater HV-28781 Al,A2,81, 82 HV-28782 Al,A2,Bl,B2 HV-28791 Al,A2,B1,82 HV-28792 Al,A2,Bl,B2 90 40 6
15 X,Z XBZ X,Z Y,B Y,B SUS)UEHANNA - UNIT 2 3/4 6-20