ML20057F862
| ML20057F862 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/15/1993 |
| From: | Robert Stransky Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F863 | List: |
| References | |
| NUDOCS 9310190259 | |
| Download: ML20057F862 (5) | |
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j NUCLEAR REGULATORY COMMISSION w AssinoTon. o.c. 2ossmi g-THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-58 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and i
Toledo Edison Company (the licensees) dated March 16, 1992, 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 (1) 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 Comission's regulations and all applicable requirements have been ratisfied.
i 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
9310190259 931015 PDR ADDCK 05000440 P
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Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 51 are hereby incorporated into this license. The Cleveland Electric Illuminating Company shall 1
operate the facility in accordance with the Technical Specifi-1 cations and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
i FOR T AR REGULATORY COMMISSION
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ef J. Stransky, Project Manager Project Directorate'III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 15, 1993 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 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.
1 Remove Insert 3/4 3-75 3/4 3-75 I
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TABLE 3.3.7.4-1 (Continued)
REMOTE SHUTDOWN SYSTEM CONTROLS-MINIMUM CHANNELS OPERABLE CONTROL Dfvision 1 Division 2 ESW Pump 1
1 ESW Pump Discharge Valve 1
1 RHR HX's ESW Inlet / Outlet Valves 2(*)
2(*)
RHR NX's Inlet / Outlet / Bypass Valves 3(*)
3(*)
RHR Pump 1
1 RHR to Containment Shutoff Valve 1
1 RHR Pump Suppression Pool Suction Valve 1
1 LPCI Injection Valve 1
1 RHR A Shutdown Cooling Suction Valve 1
NA RHR Upper Pool Cooling Isolation Valve 1
1 RHR Head Spray Isolation Valve 1
1 Containment Spray First Shutoff 1
1 Shutdown Cooling to Feedwater Shutoff 1
1 RHR Test Valve to Suppression Pool 1
1 Shutdown Cooling Outboard Isolation Valve 1
NA RHR A to Radwaste Second Isolation Valve 1
NA Steam Condensing Shutoff Valve to RCIC 1
1 RHR HX's Steam Shutoff Yalve I
1 RHR Pump Minimum Flow Valve 1
1-ECC Pump 1
1 RCIC Turbine Gland Seal Compressor 1
NA RHR & RCIC Steam Supply Outboard Isolation Valve 1
NA RCIC Second Test Valve to CST 1
NA RCIC Turbine Trip 1
NA RCIC Steam Shutoff Valve 1
NA RCIC First Test Valve to CST 1
NA RCIC Pump CST Suction Valve 1
NA RCIC Injection Valve 1
NA RCIC Pump Suppression Pool Suction Isolation Valve 1
NA RCIC Turbine Trip Throttle Valve 1
NA RCIC Pump Minimum Flow Valve 1
NA RCIC Turbine Exhaust Shutoff Valve 1
NA RCIC Exhaust Vacuum Breaker Outboard Isolation Valve 1 NA RCIC Exhaust Vacuum Breaker Inboard Isolation Valve NA 1*
I RHR B Shutdown Cooling Suction Valve NA 1*
Shutdown Cooling Inboard Suction Isolation Valve NA 1*
RHR & RCIC Steam Supply Inboard Isolation Valve NA 1*
RHR & RCIC Steam Supply Warmup Isolation Valve NA 1*
Safety Relief Valves 3(*)
3")
Control Room to Shutdown Panel Transfer Switches 14 2*
APRM Power Supply Breakers 1***)
1** *)
Inboard Main Steam Isolation Valve NA 2 "'*
Diesel Generator Room Fan IA Temperature Controller 1 NA Suppression Pool Cleanup Isolation Yalve 1
NA (a) I per valve (b) One breaker constitutes one channel for ATWS Division 1 and Division 2.
(c) One switch for Solenoid "A" per 4 valves, one switch for Solenoid "B" per 4 valves.
These Division 2 controls are physically located on the Division 1 panel.
These breakers are physically located on ATWS Distribution Panels 1R14-S014 and IR14-5015.
j PERRY - UNIT 1 3/4 3-75 Amendment No. 27. 51
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