ML17279A263
| ML17279A263 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/21/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A264 | List: |
| References | |
| NUDOCS 8705290243 | |
| Download: ML17279A263 (13) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
4 2 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),
dated June 13 and 18, 1985 and October 7, 1986 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 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 enclosure to this license amendment; and paragraph 2.C.(2) of the Facility Operating License No.
NPF-21 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.
42, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Tcchnical Specifications and the Environmental Protection Plan.
8705290243 870521 PDR ADOCK 05000397, P
PDR I
CP 3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George W
- nighton, Di tor Project Directorate V
Division of Reactor Projects - III/IV/V 5 Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance:
May 21, 1987
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May 21, 1987 ENCLOSURE TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE 3/4 8-22 3/4 8-23 3/4 8-24 83/4 8-3 INSERT 3/4 8-22 3/4 8-23 3/4 8-24 B3/4 8-3
ELcCTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued 2.
By selecting and functionally testing a representative sample of at lea'st 10K of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be selected on a rotating basis.
Testing of these circuit breakers shall consist of injecting a current with a value equal to 300K of the pickup of the longtime delay trip element and 150X of the pickup of the short time delay trip element, and verifying that the circuit breaker operates within the time delay band-width for that current specified by the manufacturer.
The instantaneous element shall be tested by injecting a current equal to +20K of the pickup value of the element and verifying that the circuit breaker trips instantaneously with no inten-tional time delay.
Molded case circuit breaker testing shall also follow this procedure except that generally no more than two trip elements, time delay and instantaneous, will be involved.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10X of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
b.
At least once per 60 months by subjecting each circuit breaker to an
-inspection and preventive maintenance in accordance with procedures prepar ed in conjunction with its manufacturer s recommendations.
WASHINGTON NUCLEAR - UNIT 2 3/4 8-22 Amendment No. 42
TABLE 3.8.4.2-1 PRIMARY CONTAINMENT PENETRATION CONDUCTOR
~EUIPHENT PRIMARY PROTECTION a.
6900V Circuit Breakers BACKUP PROTECTION RRC-P-1A RRC-P-1B E-CB-RRA (Relay)
E-CB-RRB (Relay E-CB-S5 (Relay) E-CB-N2/5 (Relay)
E-CB-S6 (Relay)
E-CB-N2/6 (Relay) b.
480VAC Fused Disconnects MS-V-16 RWCU-V-1 RHR-V-9 RCIC-V-63 RCC-V-40 RHR-V-123B RCIC-V-76 RHR-V-123A MC-SB-A MC-SB-A MC-SB-A MC-8B-A MC-8B-A MC-8B-A MC-SB-A MC-SB-A Fused Fused Fused Fused Fused Fused Fused Fused MC-SB MC-SB MC-SB MC-SB MC-8B MC"8B MC-SB MC-SB 125ACB 125ACB 125AC8 125ACB 125ACB 125ACB 125AC8 125ACB WASHINGTON NUCLEAR - UNIT 2 3/4 8-23 Amendment No.
42
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THIS PAGE INTENTIONALLY LEFT BLANK MASHINGTON NUCLEAR - UNIT 2 3/4 8-24 Amendment No. 42
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ELECTRICAL POWER SYSTEMS BASES 3/4.8.4 ELECTRICAL E UIPMENT PROTECTIVE DEVICES Primary containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.
The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturers brand of circuit breaker.
Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested.
If a wide variety exists within any manufacturer's brand of cir-cuit breakers, it is necessary to divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.
The bypassing of the motor-operated valve thermal overload protection continuously or during accident conditions ensures that the thermal overload protection will not prevent safety-related valves from performing their function.
The surveillance requirements for demonstrating the bypassing of the thermal overload protection continuously and during accident conditions are in accordance with Regulatory Guide 1.106 "Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.
WASHINGTON NUCLEAR UNIT 2 B 3/4 8-3 Amendment No. 42