ML17290A194
| ML17290A194 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/09/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17290A195 | List: |
| References | |
| NUDOCS 9304150215 | |
| Download: ML17290A194 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 UCLEAR PROJECT NO.
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 License No. NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated April 1,
- 1993, 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 rules and 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; 2.
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.
Accordingly, the license is amended by changes to the Technical Speci-fications 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:
9304iM2fS 930409 PDR ADQCK OSOOO397 P
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
114 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.
This amendment is effective as of the date of issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 9, 1993 FOR THE NUCLEAR REGULATORY COMMISSION P P~~
heodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation T
'l I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. i14 TO 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 vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE 3/4 7-8 INSERT 3/4 7-8
,l
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 2.
Verifying that on each of the below pressurization mode actuation test signals, the train automatically switches to the pressurization mode of operation and the control room is maintained at a positive pressure of 1/8 inch water 'gauge relative to the outside atmosphere during train operation at a flow rate less than or equal to 1000 cfm:
a)
Drywell pressure-high, b)
Reactor vessel water level-low, and c)
Reactor Building exhaust. plenum-high radiation.
3.
Verifying that the heaters dissipate 5.0 + 0.5 kW when tested in accordance with ANSI N510-1980.
f.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the, inplace penetration and bypass leakage testing acceptance criteria of less than 0.05K in accordance with ANSI N510-1980 while operating the train at a flow rate of 1000 cfm + lOX.
g.
After each. complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05K in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the.train at a flow rate of 1000 cfm + lOX.
WASHINGTON NUCLEAR - UNIT 2 3/O 7-7 Amendment No.
36 JAR 21 Nl
t PLANT SYSTEMS 3 4.7.3 REACTOR CORE SOLA ION COOLING SY TE LIMITING CONDITION FOR OPERATION 3.7.3 The reactor core isolation cooling (RCIC) system shall be OPERABLE with an OPERABLE flow path capable of automatically taking suction from the suppression pool and transferring the water to the reactor pressure vessel +*
~PPLICABILIT:
OPENNTIONAL CONOITIOIIC I, 2, d 2 Itt t
t d
pressure greater than 150 psig.
~CTI ON:
With the RCIC system inoperable, operation may continue provided the HPCS system is OPERABLE; restore the RCIC system to OPERABLE status within 14 days 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 /> and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.7.3 The RCIC system shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
l.
Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.
2.
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked,
- sealed, or otherwise secured in position, is in its correct position.
3.
Verifying that the pump flow controller is in the correct position.
b.
When tested pursuant to Specification 4.0.5 by verifying that the RCIC pump develops a flow of greater than or equal to 600 gpm in the test flow path with a system head corresponding to reactor vessel operating pressure when steam is being supplied to the turbine at 1000
+ 20, - 80 psig.*
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s after reactor steam pressure is adequate to perform the test.
- The ability of automatically taking RCIC suction from the suppression pool is not a requirement for RCIC OPERABILITY until May 17, 1993 or the beginning of the spring 1993 refueling outage when RCIC OPERABILITY is no longer required; whichever occurs first.
WASHINGTON NUCLEAR UNIT 2 3/4 7-8 Amendment No. ""4