ML17291A180
| ML17291A180 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/28/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17291A181 | List: |
| References | |
| NUDOCS 9407070292 | |
| Download: ML17291A180 (10) | |
Text
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~o Cy j.:f ky*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 WASHINGTON PUBLIC POW R SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
127 License No.
NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washingt'on Public Power Supply System (licensee) dated May 5,
- 1994, 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:
9407070292 940628 PDR ADOCK 05000397 P
1
)
I
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 127 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.
This amendment is effective the date of issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
3une 28, 1994 FOR THE NUCLEAR REGULATORY COMMISSION I,
Theodore R. quay, Director Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
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AMENDMENT NO.
ATTACHMENT TO LICENSE AMENDMENT 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 6-24 3/4 6-33 INSERT 3/4 6-24 3/4 6-33
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VALVE FUNCTION AND NUMBER lhBl l 3.6.3-1 (Continu< d)
PRlMARY CONlhlNMlN1 lSOI hl lON Vhl VLS VALVf. GROUP ( a )
MAXIMUM ISOLAI ION TIME (Seconds Automatic Isolation Valves (Continued)
Reactor Closed Cooling RCC-V-5 RCC-V-21 RCC-V-40 RCC-V-104 Radiation Monitoring Supply 8 Return PI-VX-250 PI-VX-251 P I-VX-253 P I-VX-256 P I-VX-257 P I-VX-259 Residual Heat Removal RHR-V-123A,B(g)
RHR-V-8(g)(k)
RHR-V-9(g)
RHR-V"23(g)
RHR-V-53A,B(g)
RHR-V-24A,B(c)
RHR-V-21 RHR-V-27A,B(c)
Reactor Water Cleanup System RWCU-V-1(d)
RWCU-V-4 5
6 6
6 6
10 10 10 60 15 40 40 90 40 270 270 36 30( j) 2l(j)
TABLE 3.6.3-1 Contin~ued PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER a.
Automatic Isolation Valves (Continued)
Reactor Core Isolation Cooling RCIC-V-8 RCIC-V-63 RC IC-V-76 Low Pressure Core Spray LPCS-V-12 High Pressure Core Spray HPCS-V-23 b.
Containment Atmosphere PI-EFC-X29b PI-EFC-X29f PI-EFC-X30a PI-EFC-X30f P I-EFC-X42c P I-EFC-X42f P I-EFC-X61c PI-EFC-X62b P I-EFC-X69f P I-EFC-X78a VALVE GROUP a
10 MAXIMUM ISOLATION TIME Seconds 26 16 22 180 180 N.A.
TABLE 3.6.3-1 fCont~inned PRIMARY CONTAINHiENT ISOLATION VALVES VALVE FUNCTION AND NUMBER d.
Other Containment Isolation Valves (Continued)
Radiation Monitoring PI-V-X72f/1 PI-V-X73e/1 Transversing Incore Probe System TIP-V-6 TIP-V-7,8,9,10,11(e)
TABLE NOTATIONS
- But greater than 3 seconds.
O'Provisions of Technical Specification 3.0.4 are not applicable.
~LVE II MAXIMUM ISOLATION TIME Seconds N.A.
N.A.
(a)
See Technical Specification 3.3.2 for the isolation signal(s) which operate each group.
(b)
Valve leakage not included in sum of Type 8 and C tests.
(c)
Hay be opened on an intermittent basis under administrative control.
(d)'ot closed by SLC actuation signal.
(e)
Not subject to Type C Leak Rate Test.
(f)
Hydraulic leak test at 38.2 psig.
(g)
Not subject to Type C test.
Test per Technical Specification 4.4.3.2.2 (h)
Tested as part of Type A test.
(i)
Hay be tested as part of Type A test.
If so tested, Type C test results may be excluded from sum of other Type B and C tests.
(j)
Reflects closure times for containment isolation only.
(k)
During operational conditions 1,
2 8
3 the requirement for automatic isolation does not apply to RHR-V-8.
Except that RHR-V-8 may be opened in operational conditions 2
& 3 provided control is returned to the control room, with 'the interlocks reestablished, and reactor pressure is less than 135 psig.
CONTAINMENT SYSTEMS 3 4.6.4 VACUUM RELIEF SUPPRESSION CHAMBER - DRYWELL VACUUM BREAKERS LIMITING CONDITION FOR OPERATION 3.6,4.
1 Seven of the nine pairs of suppression chamber - drywell vacuum breakers shall be OPERABLE and all nine pairs shall be closed.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
'a
~
b.
C.
d.
With one or more vacuum breakers in up to two pairs of suppression chamber - drywell vacuum breakers inoperable for opening, verify both vacuum breakers of each pair to be closed within two (2) hours.
With one or more vacuum breakers in three or more pairs of suppression chamber - drywell vacuum breakers inoperable for opening but known to be closed, restore the inoperable pairs of vacuum breakers such that a
minimum of seven pairs are in an OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 /> 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 />.
With one suppression chamber - drywell vacuum breaker open, verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; restore the open vacuum breaker to the closed position within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 /> 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 />.
With one closed position indicator of any suppression chamber - drywell l
vacuum breaker inoperable:
1.
Verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per 15 days thereafter, or 2.
Verify the vacuum breaker(s) with the inoperable position indi-cator to be closed by conducting a test which demonstrates that the *P is maintained at greater than or equal to 0.5 psi for 1
hour without makeup within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 15 days thereafter.
3.
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 />.
WASHINGTON NUCLEAR - UNIT 2 3/4 6-34 Amendment No.
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