ML20154M484

Amend 186 to License DPR-40,revising TS 2.3 to Increase Allowed Outage Times for SIT

ML20154M484
Person / Time
Site:	Fort Calhoun
Issue date:	10/19/1998
From:	Wharton L NRC (Affiliation Not Assigned)
To:
Shared Package
ML20154M476	List: ML20154M472 ML20154M484 ML20154M488
References
NUDOCS 9810200306
Download: ML20154M484 (5)

Text

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, O ct:o m t UNITED STATES f t j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001 I

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%.....,l l OMAHA PUBLIC POWER DISTRICT l

DOCKET NO. 50-285

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FORT CALHOUN STATION. UNIT NO. t l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.186 License No. DPR-40

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated July 11,1995, 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; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l

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 ,

y regulations;  !

D. The issuance of this license 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 l Commission's regulations and all applicable requirements have been satisfied.  ;

9810200306 981019 =

PDR ADOCK 05000205 P PDR l

2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and >

paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as

. follows:

B. Technical Soecifications i The Technical Specifications contained in Appendix A, as revised through Amendment No. 186 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

<> 4A L. Raynard Wharton, Project Manager Project Directorate IV-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 19, 1998 '

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l ATTACHMENT TO LICENSE AMENDMENT NO. 186 i

FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 ,

i Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. l REMOVE INSERT 2-21 2-21 2-23 2-23 l l

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2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling Systen) (Continued)

(2) Modification of Minimum Reauirements 1 During power operation, the Minimum Requirements may be modified to allow one i of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within the time period specified below, the reactor I 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 minimum requirements 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 />. l 1

a. One low-pressure safety injection pump may be inoperable provided the pump l 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 />.  !

b. 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 />.

c. One shutdown 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 />.

d. Any valves, interlocks or piping directly associated with one of 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 l that component.

e. Any valve, interlock or piping associated with the safety injection and shutdown I cooling system which is not covered under d. 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 />.

e f. One safety injection tank may be inoperable for reasons other than g. or h.

below 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 />.

g. Level and/or pressure instrumentation on one safety injection tank may be inoperable for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

h. One safety injection tank may be inoperable due to boron concentration not within limits for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2-21 Amendment No. 49t M'4475,186

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l 2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooline System (Continued)

The SIRW tank contains a minimum of 283,000 gallons of usable water containing a boron concentration of at least the refueling boron concentration. This is sufficient boron concentration to provide a shutdown margin of 5 %, including allowances for uncertainties, with all control rods withdrawn and a new core at a temperature of 60'F.*

The limits for the safety injection tank pressure and volume assure the required amount of water injection during an accident and are based on values used for the accident analyses. The minimum 116.2 inch level corresponds to a volume of 825 ft' and the maximum 128.1 inch level corresponds to a volume of 895.5 ft' Prior to the time the reactor is brought critical, the valving of the safety injection system must be checked for correct alignment and appropriate valves locked. Since the system is used for shutdown cooling, the valving will be changed and must be properly aligned prior to start-up of the reactor.

The operable status of the various systems and components is to be demonstrated by periodic tests. A large fraction of these tests will be performed while the reactor is operating in the power range.

If a component is found to be inoperable, it will be possible in most cases to effect repairs and restore the system to full operability within a relatively short time. For a single component to be inoperable does not negate the ability of the system to perform its function. If it develops that the inoperable component is not repaired within the specified allowable time period, or 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 cooling requirements after a postulated loss-of-coolant accident. This will also permit 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 s.hutdown and cooldown procedures. In the cold shutdown condition, release of fission products or damage of the fuel elements is not considered possible.

The plant operating procedures will require immediate action to effect repairs of an e

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 assure that operability of the component will be restored promptly and yet allow sufficient time to effect repairs using safe and proper procedures.

The time allo _wed to repair a safety injection tank is based on the deterministic and probabilistic analyses of CE NPSD-994, "CEOG Joint Applications Report for Safety .

Injection Tank AOT/ SIT Extension," May 1995. These analyses concluded that the )

overall risk impact of the completion times are either risk-beneficial or risk neutral.

The requirement for core cooling in case of 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. i 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.

2-23 Amendment No. 32,39,47,49,74,179,186 i i

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