ML20059K174

Amends 83 & 76 to Licenses NPF-20 & NPF-8,respectively, Redefining Fully Withdrawn Position of Rod Cluster Control Assembly (Rcca) Banks to Minimize Localized Rcca Wear

ML20059K174
Person / Time
Site:	Farley
Issue date:	09/07/1990
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059K180	List: ML20059K174 ML20059K184
References
NUDOCS 9009210202
Download: ML20059K174 (12)

Text

_.

p CIO UNITED STATES j

8 NUCLEAR REGULATORY COMMISSION a

r W ASHING TON, D. C. 2MS6 i

ALABAMA POWER COMPANY t

DOCKET N0. 50-348 1

JOSEPW M..FARLEY. NUCLEAR PLANT c VNIT.1 AMENDMENT TO FACILITY OPERATING LICENSE I

l Amendment No. 83 License No. NPF-2 1.

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

f A.

The application for amendment by Alabama Power Company (the licensee), dated June 12, 1990, complies with the. standards and requirementsoftheAtomicEnergyActof1954,asamerded(theAct),

and the Comission's rules and regulations set forth in 10 CFR t

Chapter Is B.

The facility will o>erate in conformity with the application, the provisions of tie Act, and the. rules and regulations of the.

Comission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and I

safety of the public, and (ii) that such activities will be conducted j

in compliance with the Cosmiission's regulations

.i D.

The issuance of this license amendment will not be inimical to the

.l common defense and security or to the health and safety of the i

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, t

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-2 is hereby.

amended to read as follows:

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.2-i (2) Technical. Specifications l

1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 83, are hereby incorporated in the license. The licensee shall operate the facility in accordance with l

the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall l

be implemented within 30 days of receipt of the amendment.-

FOR THE NUCLEAR' REGULATORY COMMISSION' 4

Ronnie H. Lo/for i

Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II l'

Office of Nuclear Reactor. Regulation e

Attachment:

Changes to-the Technical Specifications e

Date of Issuance: September 7, 1990

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ATTACWMENT.TO. LICENSE.AMENDNENT.NO. R2 TO FACILITY 0PERATING. LICENSE N0 WPF-2 i

DOCKET.NO. 50-348

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1 Replace the following pages of the Appendix A Technical Specifications with i

the enclosed pages. The revised areas are. indicated by marginal lines.

Remove.Pages Insert Pages 3/4 1-19 3/4 1-19 3/4 1-20 3/4 1-20 3/4 1-22 3/4 1-22 4

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t REACTIVITY CONTROL SYSTEMS ROD DAOP TIME l

LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from the fully withdrawn position (225 to 231 steps, inclusive)* shall l-be:less than or equal to 2.2 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

i T,,, greater t an or equal to.541'F, and h

a.-

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b.

All reactor coolant pumps operating.

f APPLIC BII.ITY: MODES 1 and 2.

ACTION:

I a.

With the drop time of any full length-rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined'vith 2 reactor coolant pumps operating, operation may. proceed provided THERNAL POWER is restricted to less than or equal to_66% of RATED THERMAL POWER.

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t SURVEILLANCE REQUIREMENTS 4.1.3.4 The red drop time of full length rods shall be. demonstrated _throughx measurement prior to reactor criticality a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual-rods following any.

maintenance on or modification to the control rod drive system which could affect the drop time of_thos. specific-rods, and c.

At_least once per 18 months.

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• The fully withdrawn position used for determining rod drop time'shall-be greater than or equal to the fully withdrawn position used during subse-quent plant operation.

l FARLEY-UNIT 1 3/4 1-19 AMENDMENT NO. 83 l

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REACTIVITY CONTROL SYSTEMS SHUTDOVN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be fully withdravn'(225 to 231 steps, inclusive).

APPLICABILITY ' MODES 1* and 2*#.

ACTION:

Vith a maximum of=one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour i

either:

i a.

Fully withdraw the rod, or j

b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdt.vn'(225 to 231 steps, inclusive):

Vithin'15 minutes prior to withdrawal.of any rods in control banks a.

A, B, C or D during an approach to reactor criticality, and-b.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

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• See Special Test Exceptions 3.10.2 and 3.10.3, tWith K;,, greatwr than or equal to 1.0 i

FARLEY-UNIT 1=

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NUCLEAR REGULATORY COMMISSION 5

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l ALABAMA. POWER. COMPANY DOCKET.NO. 50-364 i

' JOSEPH M. FARLEY NUCLEAR. PLANT UNIT.2 i

AMENDMENT.TO. FACILITY.0PERATING. LICENSE

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Amendment No. 76.

License No. NPF '

1.

The Nuclear Regulatory Comission (the Comm'ission) has found that:

A.

The application for amendment by Alabama Power Company (the i

licensee),datedJune12 1990.. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Connission's rules and regulations set forth-in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the.

provisions of the Act, and the rules and regulations of the Commission; C.

Thereisreasonableassurance'(1):thattheactivitiesauthorizedby J

this' amendment can be conducted without endangering the health and i

i safety of the public, and (ii) that such activities will be conducted i

in compliance with the Comission's regulations; D.

The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and y

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.

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.0perating License No. NPF-8 is hereby i

amended to read as follows:

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, are hereby incorporated in the license. Alabama Power Company shall operate the facility in accordance with the Technical Specifications, 3.

This. license amendment is effective as of its date of issuance and shall be implemented within 30 days of receipt of the amendment.

FOR THE NUCLEAR REGULATORY COMMISSION Ronnie H. Lo/for Elinor G. Adensam, Director r

Project Directorate 11-1 Division of Reactor Projects. I/II

' Office of Nuclear Reactor Regulation-Attact.mnt:

Changes to the Technical l

Specifications Date of Issuance: September 7, 1990 l

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p ATTACHMENT.TO LICENSE. AMENDNENT.NO. 76 -

T0. FACILITY OPERATING. LICENSE.N0.'.NPF-8 b

DOCKET.N0. 50-364 y:

Replace the following pages of the Appendix A: Technical Specifications with the enclosed pages. The revised areas _are indicated by marginal lines.

Remove Pages Insert Pages 3/4 1-19

.3/4'l-19 3/4 1.20 3/4 1-20 I

3/4 1-22

-3/4 1 22 l

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> REACTIVITY CONTROL SYSTEMS o

ROD DROP TIME

" LIMITING CONDITION FOR OPERATION 3.1. 3. 4-The individual full length (shutdown and control): rod drop -time.

l from theifullyLvithdrawn position (225 to 231 steps, inclusive)* shall l;

be less than_or equal to 2.2 seconds from beginning of decay of' stationary grippericoll: voltage'to dashpot entry with:

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T,,, greater:than-or equal to 541'F, and b.

All reactor coolant pumps operating.

- APPLICABILITY MODES 1 and 2.

J ACTION:

i n.

LVith1 the drop time of any full length rod determined to' exceed the4 above-limit, restore-the rod drop time to within theisboveilimit prior to proceeding-to MODE.1 or 2.z h.

With the rod drop times within 11mits but-determined with:2!.

. reactor coolant pumps operating, operation may proceed provided:

'THERNAL POWER is restricted to less-than or equal to 66%'of RATED.

THERMAL POWER.

SURVEILLANCE REQUIREMENTS l

x 4.1.3.4 The rod drop time of full length rods:shall be demonstrated:;through measurement prior to reactor criticality:

t For all rods.folleving each removal'of the reactor: vessel l head, a.

1 b.;

For specifically affected: individual rods following any maintenance on or modification to the control rod drive. system-which could. affect:the drop time of'those specific rods,land c.

At least once per 18 months.

• The fully withdravn-position used for determining rod drop time shall be

, greater than or. equal to the fully withdrawn position used during subse-.

.quent; plant operation.

.FARLEY-UNIT 2 3/4 1-19 AMENDMENT NO. 76 a

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REACTIVITY CONTROL SYSTEMS-i SI:UTD0VN ROD INSERTION LIMIT JLIMITING CONDITION FOR OPERATION-3.1.3.5'All-shutdownrodsshallbefully: withdrawn'.(225~to[231 steps, inclusive).

APPLICABILITY:

1. MODES 1* and 2*#.:

ACTION:

.Vith a maximum of one shutdownLrod not fully withdrawn.except for.~

q surveillance testing pursuant'to Specification 4.1.3.1~.2, within one hour:

i either:

a.

Fully withdraw the rod, or.

i b.-

DeElare the rod to be-inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined;toibe-l fully withdrawn (225-to 231-steps,. inclusive):

Within 15 minutes prior'to vithdrawal.oftanyirods"in control. banks.

- a.

A, B, C or D duris.g an approach.'to' reactor criticality, and-

~

b.-

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ~thereafter.-.

"*See Special Test Exceptions 3.10.2'and 3.10.3.

1. Vith K,,,. greater than or equal'to 1.0

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FARLEY-UNIT'2 3/4 1-20 AMENDHENT NO. 76 o

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