ML20129E540
| ML20129E540 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/26/1996 |
| From: | Robert Schaaf NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129E543 | List: |
| References | |
| NUDOCS 9610010103 | |
| Download: ML20129E540 (7) | |
Text
-
p reg
+
3
- a UNITED STATES I
g g
NUCLEAR REGULATORY COMMISSION o
8 WASHINGTON, D.C. 206aHoot l
CONSUMERS POWER COMPANY j
QQCKET N0. 50-255 PALISADES PLANT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.172 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated February 6,1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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; 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; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9610010103 960926 PDR ADOCK 05000255 P
PDR 2
1 1
l Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 172, 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 license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert G. Schaaf, Project anager Project Directorate III-l Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 26, 1996 1
ATTACHMENT TO LICENSE AMENDMENT N0.172 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 3-29a 3-29a 3-32 3-32 3-34 3-34 3-35 3-35 i
3.3 EMERGENCY CORE COOLING SYSTEM (Cont'd) 3.3.2 During power operation the requirements of 3.3.1 may be modified to allow one of the following conditions to be true at any one time.
If the system is not restored to meet the requirements of 3.3.1 within the time period specified below, the reactor shall be placed in a hot.
shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the requirements of 3.3.1 are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a.
One safety injection tank may be inoperable fo a period of no more than one hour.
b.
One low-pressure safety injection pump may be inoperable provided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l c.
One high-pressure safety injection pump may be inoperable provided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l d.
One shutdown heat exchanger and one component cooling water heat exchanger may be inoperable for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Any valves, interlocks or piping directly associated with one of e.
the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as, listed for that component.
f.
Any valve, interlock or pipe associated with the safety injection and shutdown cooling system and which is not covered under 3.3.2e above but, which is required to function during accident conditions, may be inoperable for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 3-29a Amendment No. M, H,
172 O
3 3.3 EMERGENCY CORE COOLING SYSTEM Basis (continued) l ability to tolerate additional equipment failures.
If it develops that (a) the inoperable component is not repaired within the specified allowable time period; or (b) a second component in the same or related system is found to be inoperable, the reactor will initially be put in the hot shutdown condition to provide for reduction of the decay heat from the fuel and consequent reduction of cooling requirements after a postulated loss-of-coolant accident. This will also pemit improved access for repairs in some cases. After a limited time in hot shutdown,if the malfunction (s) is not corrected, the reactor will be placed in the cold shutdown condition utilizing normal shutdown and cooldown procedures.
In the cold shutdown condition release of fission products or damage of the fuel elements is not considere,d possible.
The plant operating procedures will require immediate action to effect repairs of an inoperable component and, therefore, in most cases, repairs will be completed in less than the specified allowable repair times. The limiting times to repair are intended to: (1) Assure that operability of the component will be restored promptly and yet, (2) allow sufficient time to effect repairs using safe and proper procedures.
The requirement for core cooling in case of a postulated loss-of-coolant accident while in the hot shutdown condition is significantly reduced below the requirements for a postulated loss-of-coolant accident during power operation.
Putting the reactor in the hot shutdown condition reduces the consequences of a loss-of-coolant accident and also allows more free access to some of the engineered safeguards components in order to effect repairs.
Failure to complete repairs within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of going to the hot shutdown condition is considered indicative of a requirement for major maintenance and, therefore, in such a case, the reactor is to be put into the cold shutdown condition.
With respect to the core cooling function, there is functional redundancy over most of the range of break sizes.i23 Adequate core cooling for the break spectrum up to and including the 42-inch double-ended break is assured with the minimum safety injection which is j
defined as follows: For the system of four passive safety injection tanks, the entire contents of one tank are assumed to be unavailable for emergency
+
}
core cooling.
In addition, of the two high-pressure safety injection pumps
)
i and the two low-pressure safety injection pumps, only one of each type is i
assumed to operate; and also that 25% of their combined discharge rate is lost from the primary coolant system out the break. The transient hot spot fuel clad temperatures for the break sizes considered are shown on FSAR Figures 14.17.9 to 14.17.13. These y
3-32 Amendment No. M, 447,172 i
4 4
e
~
3.4 CONTAIMENT COOLING Anolicability Applies to the operating status of the containment cooling systems.
Ob.iective To assure operability of equipment required to remove heat from the containment in normal operating and emergency situations.
i Soecifications Containment Coolina Systems 3.4.1 The reactor shall not be made critical, except for low-temperature physics tests, unless all the following conditions are met:
The following equipment associated with diesel generator 1-2 is a.
operable:
Containment Air Cooler VIA Containment Air Cooler V2A Containment Air Cooler V3A Service Water Pump P7A Service Water Pump P7C Containment Spray Pump P54A Component Cooling Water Pump P52B b.
The following equipment associated with diesel generator 1-1 is operable:
Service Water Pump P78 Containment Spray Pump P54B Containment Spray Pump P54C Component Cooling Water Pump P52A Component Cooling Water Pump P52C All heat exchangers, valves, piping and interlocks associated with c.
the above components and required to function during accident conditions are operable.
3.4.2 During power operation, one of the components listed in Specification 3.4.1 above may be inoperable for a period of up to seven days.
If the l
inoperable component is not restored to operability within 7 days, the reactor shall be placed in a hot shutdown condition.
3-34 Amendment No. M4, 172
3.4 CONTAIMENT COOLING (Cont'd)
I within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the inoperable component is not restored to l
operability within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 3.4.3 During power operation, the requirements of Specification 3.4.1 may be modified to allow a '.otal of two of the components listed in Section 3.4.la or b to be inopenble at any one time for a period of up to 24 i
hours.
If the operability of at least one of the two inoperable components ir, not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a hot shu'.down condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the operability of at least one of the two inoperable components is not restored within an additional 48 i;9urs, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Continued power operation with one component l
out of service shall be as spcified in Section 3.4.2, with the permissible period in inoperability starting at the time that the first of the two components became inoperable.
3.4.4 Any valves, interlocks and piping directly associated with one of the j
above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as listed for that component.
3.4.5 Any valve, interlock or piping associated with the containment cooling system which is not covered under Specification 3.4.4 above and which is required to function during accident conditions may be inoperable for a l
period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3-35 Amendment No. 24, M 4, 1i2 1