ML17278B090
| ML17278B090 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/06/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278B091 | List: |
| References | |
| TAC-60050, NUDOCS 8611180190 | |
| Download: ML17278B090 (8) | |
Text
~pR Argy
~
~
0
~ F 0
3
%p*yW UNITEDSTATES 0 ~
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWFR SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATINA LICENSE
"'mendment No.
31 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The applications for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),
dated October 28,
- 1985, and February 24,
- 1986, comply 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 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.
Accordingly, the 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. 3l, 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.
8611180190 861106 PDR ADOCK 05000397 '
- PDR,
~
II I
~ p
3.
This amendment is effective as of the date of issuance.
FOR THE NUCI EAR REGULATORY COYNISSION
Enclosure:
Changes to the Technical Specifications Elinor G. Adensam, Director BWR Proiect Directorate No.
3 Division of BWR Licensing Date of Issuance:
November 6, l986
ENCLOSURE TO LICFNSE AMENDMENT N0.31 FACILITY OPERATINt'ICENSE 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 a vertical line indicating the area of change.
RENOYE 3/4 6-19 3/4 6-39 INSERT 3/4 6-19 3/4 6-39
40
~
'I k
i I
l I
0 ~
CONTAINMENT SYSTEMS 3/4.6.~-
PRIMARY CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The primary containment isolation valves and the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one or more of the primary containment isolation valves shown in Table 3.6.3-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
Restore the inoperable valve(s) to OPERABLE status, or
'I Isolate each affected penetration by use of at least one de-activated automatic valve secured in the isolated position,"
or b.
3.
Isolate each affected penetration by use of at least one closed manual valve or blind flange",
and 4.
The provisions of Specification 3.0.4 are not applicable pro-vided that the affected penetration is isolated in accordance with ACTION a.2.
or a.3.
- above, and provided that the associ-ated system, if applicable, is declared inoperable and the appropriate ACTION statements for that system are performed.
Otherwise, 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
II With one or more of the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 inoperable, operation may continue and the provisions of Specifications 3.0.3 and 3.0.4 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either; 1.
The inoperable valve is returned to OPERABLE status, or 2.
The instrument line is isolated and the associated instrument is declared inoperable.
Otherwise, 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative control.
WASHINGTON NUCLEAR " UNIT 2 3/4 6-19 Amendment No. 31
~ 0 CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES LiMITING CONDITION FOR OPERATION 0
3.6.5.2 The secondary containment ventilation system automatic isolation valves shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.5.2-1.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3 and ".
ACTION:
With one or more of the secondary containment ventilation system automatic isolation valves shown in Table 3.6 '.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:
a.
Restore the inoperable valves to OPERABLE status, or b.
Isolate each affected penetration by use of at least one deactivated valve secured in the isolation position, or c.
Isolate. each affected penetration by use of at least one closed manual valve or blind flange, and d.
The provisions of Specification 3.0.4 are not applicable provided that the affected penetration is isolated in accordance with ACTION
- b. or c.
- above, and provided that the associated system, if.appli-cable, is declared inoperable and the appropriate ACTION statements for that system are performed.
Otherwise, in OPERATIONAL CONDITION 1, 2,- or 3, 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Otherwise, in OPERATIONAL CONDITION ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
The provisions of Specifica-tion 3.0.3 are not applicable.
SURVEILLANCE RE UIREMENTS
- 4. 6. 5. 2 Each secondary containment ventilation system automatic isolation valve shown in Table 3.6.5.2-1 shall be demonstrated OPERABLE:
Prior to returning the valve to service after maintenance, repair,.
replacement work is performed on the valve or its associated
- actuator, control, or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.
b.
C.
During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation valve actuates to its isolation position.
By verifying the isolation time to be within its limit when tested pursuant to Specification 4. 0. 5 3/4 6-39 When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
WASHINGTON NUCLEAR " UNIT 2 Amendment No. 3l