ML17285B165
| ML17285B165 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/02/1990 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285B166 | List: |
| References | |
| NUDOCS 9004120176 | |
| Download: ML17285B165 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 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 licensee),
dated June 23, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954; as amended (the Act), and the Commission's regulatiors 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 author-ized 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.
9004 f20 f76 900402 PDR ADOCK 05000397 p
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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) of 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. 79
, 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.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q~iw4M/8. ~V'lA+
Charles M. Trammell, Acting Director Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 2, l990
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ENCLOSURE TO LICENSE Al<ENDt<ENT NO.
9 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Peplace 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 areas of change.
Also to be replaced are the following overleaf pages.
AMENDMENT PAGE 3/4 3-72 3/4 3-75 OVERLEAF PAGE 3/4 3-71'/4 3-76
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INSTRUMENT 1.
Reactor Vessel Pressure 2.
3.
Reactor Vessel Water Level Suppression Chamber Water Level TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION REQUIRED NUMBER OF CHANNELS MINIMUM CHANNELS OPERABLE 1,
2 1,
2 1, 2 80 80 80 APPLICABLE OPERATIONAL CONDITIONS ACTION Suppression Chamber Water Temperature 5.
Suppression Chamber Air Temperature 2/sector 1/sector 1, 2 1,
2 80 80 7.
8.
Drywell Pressure Drywell Air Temperature Drywell Oxygen Concentration 1, 2 1, 2 1, 2 80 80 9.
Drywell Hydrogen Concentration 10.
Safety/Relief Valve Position Indicators ll.
Suppression Chamber Pressure 2/valve*
1/valve 1; 2 1, 2 1, 2 80 80 80 CD m
CD CQ 12.
Condensate Storage Tank Level 2
1 1, 2 13.
Main Steam Line Isolation Valve Leakage Control System Pressure 2
1 1,
2
- NOTE - The acoustic monitors may be inoperable until the fifth Refueling Outage scheduled for No Later Than May 15, 1990 without applying the shutdown requirement of Action 80.a.
80 80
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TABLE 3.3.7. 5-1 (Continued)
ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT 14.
Neutron Flux:
RCIC Flow 16.
HPCS Flow 17.
LPCS Flow 18.
19.
20.
21.
Standby Liquid Control System Flow Standby Liquid Control System Tank Level RHR Flow RHR Heat Exchanger Outlet Temperature 22.
Standby Service Water Flow 23.
Standby Service Water Spray Pond Temperature 24.
REQUIRED NUMBER OF CHANNELS 1
1 1
1 1
1/loop 1/heat exchanger 1/1 oop 2
MINIMUM CHANNELS OPERABLE 1
1 1
1 1
1 1
1 1/1 oop 1/heat exchanger 1/loop 1
1, 2
1, 2
1 2
1 2
1 2
I, 2 1
2 1$
2 1,
2 1
2 80 80 80 80 80 80 80 80 80 80 80 80 APPLICABLE OPERATIONAL CONDITIONS ACTION 25.
26.
27.
28.
29.
Emergency Ventilation Damper Position Standby Power and Other Energy Sources Primary Containment Valve Position Primary Containment Gross Radiation Monitors¹ 2/duct 2/source 1/valve 2
1/duct 1/source 1/line 1
1, 2 1,
2 1,
2 1, 2, 3
80 80 80 81 30.
Effluent Noble Gas Radiation Monitor¹ 31.
Reactor Building Post LOCA Grab Sampler 1, 2, 3
1, 2, 3
81 81
¹High range monitors.
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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.
25.
Emergency Ventilation Damper Position 26.
Standby Power and Other Energy Sources 27.
Primary Containment Valve Position 28.
Primary Containment Gross Radiation Monitors 29.
30.
Effluent Noble Gas Radiation Monitored 31.
Reactor Building Post LOCA Grab Sampler CHANNEL CHECK CHANNEL CALIBRATION R
R R
R" APPLICABLE OPERATIONAL CONDITIONS 1
2 1,
2 1,
2 1
2
- l. 2 1
2 1,
2 1,
2 1
2 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.
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INSTRUMENTATION I
- Aa SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:
a.
In OPERATIONAL CONDITION 2", three.
b.
In OPERATIONAL CONDITIONS 3 and 4, two.
APPLICABILITY:
OPERATIONAL CONDITIONS 2", 3, and 4.
ACTION:
a.
In OPERATIONAL CONDITION 2" with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all inser table control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SURVEILLANCE RE UIREMENTS
- 4. 3. 7. 6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:
a.
Performance of a:
1.
CHANNEL CHECK at least once per:
a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2*, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.
2.
CHANNEL CALIBRATION""at least once per 18 months.
b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and 2.
At least once per 31 days.
c.
Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.5 cps'ith the detector fully inserted.
With IRM s on range 2 or below.
""Neutron detectors may be excluded from CHANNEL CALIBRATION.
O'Provided signal-to-noise ratio is > 2.
Otherwise, 3 cps.
WASHINGTON NUCLEAR - UNIT 2 3/4 3-76
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