ML17279A151
| ML17279A151 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/27/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A152 | List: |
| References | |
| TAC-61116, NUDOCS 8704020150 | |
| Download: ML17279A151 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS ILICLEAR PROJECT NO.
2 AMENDYENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No NPF-Pl 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 >arch 14,
- 1986, complies with the standards and requirements o
the Atomic Energy Act of 1954, as amended (the Act}, and the Commission's regulations set forth in 10 CFP, Chapter I; B.
The facility will operate in conformity with the application, the provisiors of the Act, and the requlatinns of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endanqering the health and safety of the public, and (ii) that such activities will he conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance o, this amendment will not be inimical to the common defense and security or to the health and safety of the public; ar d 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 hy changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph P.C.(2) of the Facility Operating License No.
NPF-21 is hereby amended to rear'.
as follows:
(2>
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised throuqh Amendment No. 37, 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.pecifications and the Environmental Protection Plan.
8704020150 870327 PDR ADOCK 05000397 P
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3.
This amendment is effective as o
the date of issuance.
FOR THE NUCLEAR PEGULATORY COVWISSION Fnclosure:
Changes to the Technical Specifications Elinor G. Adensam, Director Bk'R Project Directorate No.
3 Division of BhR Licensing Da.e of Issuance:
parch 27, lg87
ENCLOSURE TO LICENSE AMENDMENT NO.
37 FACILITY OPERATING LICFHSE 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 vertical lines indicating the area of change.
REYOVE INSEI?T 3/4 3 74 3/4 3-75 3/4 3-74 3/4 3-75
TABLE 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS O
INSTRUMENT 1.
Reactor Vessel Pressure 2.
Suppression Chamber Water Level 4.
Suppression Chamber Water Temperature 5.
Suppression Chamber-'Air Temperature 6.
Primary Containment, Pressure 7.
Drywell Air Temperature 8.
Drywell Oxygen Concentration 9.
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:
RCIC Flow 16.
HPCS Flow 17.
LPCS Flow CHANNEL CHECK M
M M
M M
CHANNEL CALIBRATION R
R R
R R
R APPLICABLE OPERATIONAL L
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,
2 1,
2 1
2 1,
2 1
2 1
2
l
TABLE 4.3.7.5-1 (Continued)
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 18.
Standby Liquid Control System Flow 19.
Standby Liquid Control System Tank Level 20.
RHR Flow 21.
RHR Heat Exchanger Outlet Temperature 22.
Standby Service Water, Flow 23.
Standby Service Water Spray Pond Temperature 24.
Post-Accident Sampling Containment Atmosphere Radiation Monitor 25.
Emergency Ventilation Damper Position 26.
Standby Power and Other Energy Sources 27.
Primary Containment Valve Position 28.
Primary Containment Gross Radiation Monitors 29.
Post Accident Sampling Primary Coolant Radiation Monitor 30.
Effluent Noble Gas Radiation Monitor¹ 31.
Reactor Building Post LOCA Grab Sampler CHANNEL CHECK CHANNEL CALIBRATION R
R R
R R*
APPLICABLE'PERATIONAL CONDITIONS 1
2 1) 2 1,
2 1,
2 1
2 1,
2 1
2 3
1, 2
1, 2
1 2
1 2
3 1, 2, 3
1, 2, 3
1 2
3 TABLE NOTATION
- CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma source.