ML20245G583
| ML20245G583 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek |
| Issue date: | 08/09/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245G586 | List: |
| References | |
| NUDOCS 8908160108 | |
| Download: ML20245G583 (8) | |
Text
- _ _ _
o a.
[(psitay (y'%
. [
UNITED STATES g
NUCLEAR REGULATORY COMMISSION
, h ;, y,t j WASHINGTON, D. C. 20555
_ %g..v 4/
WOLFCREEKNUCLEAROPERATING_CpRP0_ RATION WOLF CREEK GENERATING STATION DOCKET N0. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No'.-NPF-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating SNtion (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation),
dated March 28, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter'I; 8.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
.There is reasonable assurance:
(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inir ical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
8908160108 890809 PDR ADOCK 05000482 P
_1__________________
m
i
. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION is$> 2:
$b:Y.-
t Frederick J. Hebdon, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation Attac Went:
Changts to the Technical Specifications Date of Issuance: August 9,1989 I
l
- t ATTACHMENT TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482
- Prvise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 6-2
-3/4 6-2 3/4 6-2a 3/4 6-16 3/4 6-16 l
I I
1 1
0 1
1
-l
t 4
3/4,6 CONTAINMENT SYSTEMS
]
3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY 1.IMITING CONDITION FOR OPERA 7 ION f
i i
3.6.1.1
.bimary CONTAINMENT INTEGRITY shall be maintained.
i 1
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTE'iRITY, restore CONTAINMENT INTEGRITY-within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated nutomatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3; b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; and c.
After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at a pressure not less than P,, 48 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined leakage rate is less than 0.60 L,.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
WLLF CREEK - UNIT 1 3/4 6-1
= _
i:
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE.
LIMITING CONDITION FOR OPERATION
- 3. 6.1. 2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1)
Less than or equal to L,, 0.20% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 48 psig, or i
2)
Less than or equal to L, 0.020% by weight of the containment t
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 24 psig, g
b.
A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P ' 40 P5i9' a
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
a.
If Reactor Coolant System temperature is at or below 200 F, with l
either the measured overall integrated containment leakage rate exceeding 0.75 L r 0.75 L, as applicable, or the measured combined leakage rate for a
t all penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than L, as applicable, and the combined leakage rate for all penetrations subject t
to Type B and C tests to less than 0.60 L prior to increasing the Reactor a
Coolant System temperature above 200 F.
b.
If the Reactor Coolant System temperature is above 200 degrees F, with the measured combined leakage rate for all penetrations and valves subject to Types B and C test exceeding 0.60 L,,
1)
Restore the combined leakage rate to less than 0.60 L within a
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by one of the following methods:
a)
Repairing the failed containment isolation component, or b)
Isolating the penetration containing the failed component by closing and the deactivating one automatic valve, or c)
Isolating the penetration containing the failed cu ponent by closing one manual valve, or d)
Isolating the penetration containing the failed component by using a blind flange.
2)
If the combined leakage rate is not restored to less than 0.60 L a within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
WOLF CREEK - UNIT 1 3/4 6-2 Amendment No.33
-,..-71 A
k t
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE-
' SURVEILLANCE REQUIREMENTS I
' 4.6.1.2 The containment leakage. rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part.50 using the methods and provisions of ANSI N45.4-1972:
~
a.
Three Type A tests (0verall Integrated Containment Leakage Rate) shall be conducted at 40 i'10 month intervals during shutdown at a pressure not less than either P, 48 psig, or P, 24 psig, during each 10 year 3
t service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection; 1
i i
t WOLF CREEK - UNIT 1 3/4 6-2a Amendment No.33
~
4 4
CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE with two fan systems to each group.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With one group of the above aequired containment cooling fans inoperable and both Containment ~ Spray Systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With two groups of the above required containment cooling fans inoperable and both Containment Spray Systems OPERABLE, restore at least one group of cooling fans to 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With one group of the above required containment cooling fans inoperable and one Containment Spray System incperable, restore the inoperable Containment Spray System to 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of ini-tial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1)
Starting each non-operating fan group fro" the control room, and
{
verifying that each fan group operates for at least 15 minutes, and 2)
Verifying a cooling water flow rate of greater than or equal to 2200 gpm to each cooler group.
j b.
At least once per 18 months by verifying that on a Safety Injection test signal, the fans start in slow speed or, if operating, shift j
to slow speed and the cooling water flow rate increases to at least 4000 gpm to each cooler group.
l WOLF CREEK - UNIT I 3/4 6-15
\\
4 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves specified in Table 3.6-1 shall be
' OPERABLE with isolation times
- as shown in Table 3.6-1.
I APPLICABILITY:
MODES 1,.2, 3, and 4.
ACTION:
With one or more of the containment isolation valve (s) specified in Table 3.6-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:
l Restore the inoperable-valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, a.-
or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least c.
one closed manual valve or blind flange, or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time.
i i
)
I
- For valves with excessive leakage, refer to Technical Specification 3.6.1.2.
WOLF CREEK - UNIT 1 3/4 6-16 Amendment No.33 i