ML20092N056

Amend 73 to License NPF-58,revising TS to Make Them More Restrictive Re CRD Scram Time Testing

ML20092N056
Person / Time
Site:	Perry
Issue date:	09/26/1995
From:	Hopkins J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20092N059	List: ML20092N056 ML20092N061
References
NUDOCS 9510040323
Download: ML20092N056 (7)

Text

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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINoTON. D.C. 2066dM)001 49.....,o THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.

DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-58 1.

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

A.

The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated June 1,1995, 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; 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; 1

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health ind 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:

9510040323 950926 PDR ADOCK 05000440 P

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(2) Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 73 are hereby incorporated into this license.

The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION -

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Jon B. Hopkins, Senior Project Manager b Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: September 26, 1995

ATTACHMENT TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 1-7 3/4 1-7 3/4 1-7a B 3/4 1-2 B 3/4 1-2 B 3/4 1-2a s

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9.

j REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) i ACTION:

(Continued) l b.

With a " slow" control rod (s) not satisfying ACTION a.1, above:

l 1.

Declare the " slow" control rod (s) inoperable, and 2.

Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with three or more " slow" control rods declared inoperable.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

With the maximum scram insertion time of one or more control rods l

exceeding the maximum scram insertion time limits of Specification i

3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue l

provided that:

1.

" Slow" control rods, i.e., those which exceed the limits of 4

j Specification 3.1.3.2, do not make up more than 20% of the 10%

i sample of control rods tested.

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2.

Each of these " slow" control rods satisfies ACTION a.1.

i 3.

The eight adjacent control rods surrounding each " slow" control rod are:

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a) Demonstrated through measurement within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to satisfy the maximum scram insertion time limits of Specification 3.1.3.2, l

and b)

OPERABLE

4. The total number of " slow" control rods, as determined by Specification 4.1.3.2.c, when added to the total number of ACTION a.3, as determined by Specification 4.1.3.2.a and b, does not exceed 7.

Otherwise,.be in at least 110T SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

d.

The provisions of Specification 3.0.4 are not applicable.

4 PERRY - UNIT 1 3/4 1-7 Amendment No. -64,73

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE0VIREMENTS i

4.1.3.2 The maximum scram insertion time of the control rods shall be demonstrated and, during single control rod scram time tests, the control rod drive pumps shall be isolated from the associated scram accumulator:

a.

For all control rods with reactor coolant pressure greater than or equal to 950 psig and prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or after a reactor shutdown that is greater than 120 days, b.

For each affected control rod after work on the control rod (s) or control rod drive system that could affect scram time:

1.

At any reactor coolant pressure prior to declaring control rod (s)

OPERABLE, and 2.

With reactor coolant pressure greater than or equal to 950 psig*,

and c.

For at least 10% of the control rods, on a rotating basis, at least once per 120 days of POWER OPERATION, with reactor pressure greater i

i than or equal to 950 psig.

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• The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITIONS I and 2 provided this surveillance is completed prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER.

PERRY - UNIT 1 3/4 1-7a Amendment No. 73

i REACTIVITY CONTROL SYSTEMS i

i BASES j

3/4.1.3 CONTROL RODS The specification of this section ensure that (1) the minimum SHUTDOWN MARGIN is maintained, (2) the control rod insertion times are consistent with those used in the safety analyses, and (3) limit the potential effects of the i

rod drop accident. The ACTION statements permit variations from the basic i

requirements but at the same time impose more restrictive criteria for i

continued operation. A limitation on inoperable rods is set such that the 1

resultant effect on total rod worth and scram shape will be kept to a minimum.

The requirements for the various scram time measurements ensure that any indication of systematic problems with rod drives will be investigated on a timely basis, j

Damage within the control rod drive mechanism could be a generic problem, therefore with a control rod immovable because of excessive friction or mechanical interference, operation of the reactor is limited to a time period which is reasonable to determine the cause of the inoperability and at the same time prevent operation with a large number of inoperable control rods.

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Control rods that are inoperable-for other reasons are permitted to be i

taken out of service provided that those in the nonfully-inserted position are consistent with the SHUTDOWN MARGIN requirements.

i The number of control rods permitted to be inoperable could be more than the eight allowed by the specification, but the occurrence of eight inoserable rods could be indicative of a generic problem and the reactor must be slutdown for investigation and resolution of the_ problem.

l The control rod system is designed to bring the reactor subcritical at a rate fast enough to prevent the MCPR from becoming less than the Safety Limit MCPR during the limiting power transient analyzed in Chapter 15 of the USAR.

This analysis shows that the negative reactivity rates resulting from the scram with the average response of all the drives as given in the specifications, provide the required protection and MCPR remains greater than i

the Safety Limit MCPR. The occurrence of scram times longer than those specified should be viewed as an indication of a systematic problem with the rod drives and therefore the surveillance interval is reduced in order to i

prevent operation of the reactor for long periods of time with a potentially i

serious problem.

For control rod drive scram time testing at less than 950 l

pounds per square inch - gauge (psig), the following scram times to notch q

position 13 should be used as acceptance criteria:

0 psig -.94 seconds 4

600 psig - 1.13 seconds 4

950 psig - 1.40 seconds Acceptable scram times when testing at pressures between the values given above should be linearly interpolated.

PERRY - UNIT 1 B 3/4 1-2 Amendment No. 20, 51, 73 i

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k REACTIVITY CONTROL SYSTEMS BASFS 3/4.1.3 CONTROL R005 (Continued)

The scram discharge volume is required to be OPERABLE so that it will be available when needed to accept discharge water from the control rods during a reactor scram and will isolate the reactor coolant system from the containment when required.

Control rods with inoperable accumulators are declared inoperable and Specification 3.1.3.1 then applies. This prevents a pattern of inoperable accumulators that would result in less reactivity insertion on a scram than has been analyzed even though control rods with inoperable accumulators may still be inserted with normal drive water pressure. Operability of the accumulator ensures that there is a means available to insert the control rods j

even under the most unfavorable depressurization of the reactor.

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PERRY - UNIT 1 B 3/4 1-2a Amendment No. 73

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