ML17278A863

Amend 27 to License NPF-21,revising Tech Spec Table 3.8.4.3-1, Motor-Operated Valves Thermal Overload Protection, to Add Valves Previously Omitted,Add Valves Due to Sys Upgrades & Remove nonsafety-related Valves

ML17278A863
Person / Time
Site:	Columbia
Issue date:	05/23/1986
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML17278A864	List: ML17278A863 ML17278A865
References
TAC-60952, NUDOCS 8605300466
Download: ML17278A863 (9)

Text

UNITED STATES N U AR R EG ULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATINh LICENSE Amendment No. 27 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 January 17,

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 requlations 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,'he 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. 27, 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 Technical Specifications and the Environmental Protection Plan.

8605300466 860523l'l PDR ADOCH, 05000397, P

PDR~

K 1

0

3.

This amendment is e+fective as of the date o

issuance.

F~R THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Chanqes to the Technical Specifications Elinor G. Adensam, Director RMR Project Directorate No.

3 Division of BWR Licensing Date of Issuance:

May Z3, l986

I t

ENCLOSURE TO LICENSE AMENDMENT NO. 27 FACILITY OPERATINt.'ICENSE NO.

NPF-21 DOCKET NO. 50-397 Replace the following oages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by'mendment number and contain vertical lines indicatinq the area of chanqe.

REMOVE 3/4 8-26 3/4 8-27 3/4 8-28 INSERT 3/4 8-26 3/4 8-27 3/4 8-28

TABLE 3.8.4.3-1 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION a \\

b.

C.

d.

e.

VAIVE NUMBER CAC-V-2 CAC-V"4 CAC-V-6 CAC"V-8 CAC"V-11 CAC-V-13 CAC-V-15 CAC-V-17 CIA-Y-20 CIA-V-30A CIA-V-30B FPC-V"149 FPC-V-153 FPC-V-154 F PC-V-156 FPC-V-172 FPC-V-173 FPC-V-175 FPC-V-181A F PC-V-181B F PC-V-184 HPCS-V-1 HPCS"Y"4 HPCS-V"10 HPCS-V-11 HPCS-V-12 HPCS-V-15 HPCS-Y-23 LPCS-V-1 LPCS"V"5 LPCS-FCV-11 LPCS"V-12 MS-V-1 MS-V"2 MS-V-5 MS-V-16 MS-V-19 MS"V-20 MS-V-67A MS-V-67B MS-V-67C MS-V-670 MS-V-146 SYSTEM(S)

AFFECTED Containment Atmospheric Control System Containment Instrument Air System Fuel Pool Cooling System High Pressure Core Spray System Low Pressure Core Spray System Main Steam System h.

SYSTEM(S)

VALVE NUMBER MSLC-V"1A MSLC-V-1B MSLC-V-1C MSLC-V-1D MSLC-V-2A MSLC-V-2B MSLC-V"2C MSLC-Y-2D MSLC-V-3A MSLC-V-3B MSLC-V-3C MSLC-V-3D MSLC-V"4 MSLC-V"5 MSLC-V-9 MSLC"V-10 RCC-V-5 RCC-V-21 RCC"V-40 RCC-V"104 RCC-V-129 RCC-V-130 RCC"V-131 RCIC-V-1 RCIC"V-8 RCIC-V-10 RCIC"V"13 RCI C-V-19 RCIC-V-22 RCIC-V"31 AFFECTED Main Steam Isolation Valve Leakage Control System Reactor Closed Cooling Water System Reactor Core Isolation Cooling System WASHINGTON NUCLEAR - UNIT 2 3/4 8-26 Amendment No.

27

I K

TABLE 3.8.4.3-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE NUMBER RCIC"V-45 RCIC-V-46 RCIC-V-59 RCIC"V"63 RCIC-V-68 RCIC"V-69 RCIC-V-76 RCIC-V-110 RCIC-V-113 j.

RFW-V-65A RFW-V-65B k.

RHR-V-3A RHR"V-3B RHR"V-4A RHR-V-4B RHR-V-4C RHR"V"6A RHR-V-6B RHR"V-8 RHR-V-9 RHR-V-16A RHR-V-16B RHR-V-17A RHR-V-17B RHR-V-21 RHR-V-23 RHR-V-24A RHR-V-24B RHR-V-27A RHR"V-278 RHR-V-40 RHR-V-42A RHR-V-42B SYSTEM(S)

AFFECTED Reactor Core Isolation Cooling System Reactor Feedwater System Residual Heat Removal System VALVE NUMBER RHR-V-42C RHR-V-47A RHR-V"47B RHR"V"48A RHR-V-48B RHR-V-49 RHR-V-53A RHR"V-53B RHR-V-64A RHR-V-64B RHR-V-64C RHR-V-68A RHR-V-68B RHR-V-73A RHR-V-73B RHR-V"74A RHR-V-74B RHR-V-115 RHR-V-116 RHR-V-123A RHR-V-123B RHR-V-134A RHR-V-134B RRC-V-16A RRC-V-16B RWCU-V"1 RWCU-V-4 RWCU-V-40 SYSTEM(S)

AFFECTED Reactor Recirculation System Reactor Water Cleanup System WASHINGTON NUCLEAR - UNIT 2 3/4 8-27 Amendment No.'27

TABLE 3.8.4.3-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION SYSTEM(S)

VALVE NUMBER AFFECTED VALVE NUMBER SYSTEM(S)

AFFECTED n.

SGT-V-1A SGT-V"1B SGT-V-3Al SGT-V-3A2 SGT-V-3B1 SGT-V-3B2 SGT-V-4Al SGT-V-4A2 SGT-V-4B1 SGT-V-4B2 SGT"V"5A1 SGT-V-SA2 SGT-V-5B1 SGT"V"5B2 Standby Gas Treatment System o.

AS-V-68A AS-V-68B p.

SM-V-2A SW-V-2B SW-V-4A SW-V-4B SW-V-4C SW-V-12A SW"V"12B SW-V"24A SM-V"24B SM"V-24C SW-V-29 SM-V-44 SM-V-54 SM-V-75A SW-V-75B SM-V-90 SM-V"187A SM-V-187B SM-V-188A SW-V-188B Auxiliary Steam System Standby Service Mater System WASHINGTON NUCLEAR - UNIT 2 3/4 8-28 Amendment No. 27