ML17279A596

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Amend 47 to License NPF-21,revising Tech Specs & Tables 3.3.7.5-1 & 4.3.7.5-1 to Allow Plant Operation W/Acoustic Monitor Inoperable for safety-relief Valve Until Repair at Next Refueling Outage
ML17279A596
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/16/1987
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17279A597 List:
References
NUDOCS 8710220290
Download: ML17279A596 (10)


Text

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Cy UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEN DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 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 October 13, 1987 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 for th 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.

8710220290 87l0l'b PDR ADOCK 05000397 P

h 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license athendment 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. 47, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION George W.

nighton, D

ctor Project irectorate V

Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Changes to the Technical Specifications Date of Issuance:

October 16, 1987

October 16, 1987 ENCLOSURE TO LICENSE AMENDMENT NO. 47 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 contains a vertical line indicating the area of change.

REYiOYE 3/4 3-71 3/4 3-74 INSERT 3/4 3-71 3/4 3-74

TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION CD n

I QP GO I

INSTRUMENT 1.

Reactor Vessel Pressure 2.

Reactor Vessel Water Level 3.

Suppression Chamber Water Level 4.

Suppression Chamber Water Temperature 5.

Suppression Chamber Air Temperature 6.

Drywel 1 Pressure 7.

Drywell Air Temperature 8.

Drywell Oxygen Concentration 9.

Drywell Hydrogen Concentration 10.

Safety/Relief Valve Position Indicators 11.

Suppression Chamber Pressure 12.

Condensate Storage Tank Level REQUIRED NUMBER OF CHANNELS 2/sector 2/valve" MINIMUM CHANNELS OPERABLE 1/sector 1/valve APPLICABLE OPERATIONAL CONDITIONS 1

2 1

2 1

2 1

2 1

2 1,

2 1,

2 1

2 1

2 1

2 1,

2 1

2 ACTION 80 80 80 80 80 80 80 80 80 80 80 80 13.

Main Steam Line Isolation Valve Leakage Control System Pressure 1,

2 80 CD

  • NOTE - The acoustic monitor for MS-RV-2D may be inoperable until the Third Refueling Outage scheduled for No Later Than May 15, 1988, or until the first forced outage of sufficient duration to effect repair/replacement prior to that date without applying the shutdown requirement of Action 80 '

~ ~

TABLE 4.3.7

~ 5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.

Reactor Vessel Pressure 2.

Reactor Vessel Water Level 3.

4.

5.

7.

8.

9.

Suppression Chamber Water Level Suppression Chamber Water Temperature Suppression Chamber Air Temperature Primary Containment Pressure Drywell Air Temperature Drywell Oxygen Concentration Drywell Hydrogen Concentration 10.

Safety/Relief Valve Position Indicators ll.

Suppression Chamber Pressure 12.

Condensate Storage Tank Level 13.

Main Steam Line Isolation Valve Leakage Control System Pressure 14.

Neutron Flux:

APRM IRM SRM 15.

RCIC Flow 16.

HPCS Flow 17.

LPCS Flow CHANNEL CHECK CHANNEL CALIBRATION APPLICABLE OPERATIONAL CONDITIONS 1,

2 1

2 1

2 1

2 1

2 1

2 1,

2 1

2 1,

2 1

2 1

2 1

2 1

2 1 j 2 1

2 1

2 l~)

2 1

2 1

2

  • Surveillance of the OPERABLE Tailpipe Temperature instrument channel for..SRV MS-RV-20 will be performed daily until the acoustic monitor for that valve is once again declared OPERABLE.