ML20247J280
| ML20247J280 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/23/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247J286 | List: |
| References | |
| NUDOCS 8906010095 | |
| Download: ML20247J280 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
WASMNG TON, D. C. 20555
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DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 21 License No. NPF-58 1.
The Nuclear Regulatory Comission (the Comission) ha's found that:
A.
The. application for amendment by The Cleveland Electric Illuminating Cor.;pany, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated January 18, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comis-sion'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 Commission'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 l
been satisfied.
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) l of facility Operating License No. NPF-58 is hereby amended to read as follows:
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, (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 21 are hereby incorporated into this license. The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license anendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w
John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of' Issuance:
May 23, 1989 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 21 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 i
provided to maintain document completeness.
l Remove Insert 3/4 3-75 3/4 3-75 (Table 3.3.7.4-1 (continued)
(Table 3.3.7.4-1(continued)
Remote Shutdown System Controls)
RemoteShutdownSystemControls) 3/46-30(Table 3.6.4-1 3/46-30(Table 3.6.4-1 Containment Isolation Valves)
ContainmentIsolationValves)
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TABLE 3.3.7.4-1 (Continued)-
REMOTE SHUTDOWN SYSTEM CONTROLS R
MINIMUM CHANNELS OPERABLE i
CONTROL Division 1 Division 2 ESW Pump 1
1 ESW Pum 1
I RHR HX'p Discharge Valve 2((a) 2(a) s ESW Inlet / Outlet Valves a) 3(a)
RHR HX's Inlet / Outlet /8ypass Valves 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 Suction 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 Valve 1-1 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 Pump Discharge to L.O. Cooler Valve 1
NA RCIC Exhaust Vacuum Breaker Inboard Isolation Valve NA 1*
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 Np,)
3,)
1*
Control Room to Shutdown Panel Transfer Switches 14 APRM Power Supply Breakers 1**(b) 2* (b) yan Inboard Main Steam Isolation Valve NA 2( )
Diesel Generator Room Fan 1A Ten,perature Controller 1
NA Suppression Pool Cleanup Isolation Valve 1
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(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.
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PERRY - UNIT 1 3/4 3-75 Amendment No. 21
TABLE 4.3.7.4-1 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Reactor Vessel Pressure M
g 2.
R 3.
Safety / Relief Valve Position M
NA 4.
Suppression Pool Water Level M
g 5.
Suppression Pool Water Temperature M
R 6.
Drywell Pressure M
R 7.
Drywell Temperature M
R 8.
RHR System Flow M
R 9.
Emergency Service Water Flow to RHR M
R 1
Heat Exchanger i
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Emergency Service Water Flow to Emergency M
R Closed Cooling Heat Exchanger 11.
RCIC System Flow M
g 12.
RCIC Turbine Speed M
g 13.
Emergency closed Cooling System Flow M
R 14.
Inboard MSIV Position M
NA i
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1 PERRY - UNIT 1 3/4 3-76 i
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9 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.4.1 Each isolation valve shown in Table 3.6.4-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.
4.6.4.2 Each automatic isolation valve shown in Table 3.6.4-1 shall be demon-strated OPERABLE at least once per 18 months by verifying that on an isolation test signal each automatic isolation valve actuates to its isolation position.
4.6.4.3 The isolation time of each power operated or automatic valve shown in Table 3.6.4-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
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