ML20236B291

Amend 29 to License NPF-30,revising Definition of Fully Withdrawn Shutdown & Control Rod Position from 228 Steps to 225 Steps or Higher

ML20236B291
Person / Time
Site:	Callaway
Issue date:	10/14/1987
From:	Wigginton D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236B293	List: ML20236B291 ML20236B300
References
NUDOCS 8710260062
Download: ML20236B291 (9)

Text

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o-UNITED STATES g

g NUCLEAR REGULATORY COMMISSION r.

p WASHINGTON, D. C. 20555

y...,.. j UNION ELECTRIC COMPANY-CALLAWAY PLANT, UNIT-1~

i DOCKET NO. STN 50-483

. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29.

License No.~NPF 1.

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

i A.

The application for amendment filed by Union Electric Company i

'(the_ licensee) dated June;18, 1987 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; ii 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 I'

will be conducted in compliance with the Commission's regulations; i

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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'this license amendment, and paragraph 2.C.(2) of Facility Operating License 1

No. NPF-30 is hereby amended to read as follows:

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' 2-H (2) Technical' Specifications and Environmental Protection Plan l

The Technical Specifications contained in Appendix A,- as revised-

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through Amendment No. 29, and the Environmental Protection Plan d

contained in Appendix B, both'of which are'. attached hereto, are!..

j hereby' incorporated fnto-the license.. UE shall operate _.the facility.-

in accordance with the: Technical' Specifications and the Environmental' j

Protection Plan.

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This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY.C0KMISSION

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David L. Wiggin on, Acting Director Project Directorate III-3 j

Division =of Reactor Projects

Attachment:

1 Changes to the Technical' Specifications Date of Issuance: Octobec 14, 1987 v

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'y l'E ATTACHMENT TO LICENSE' AMENDMENT NOT29 l'

"I OPERATING L'ICENSE'NO. NPF-30.

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DOCKET-NO. 50-483 l

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. Revise Appendix A Technical: Specifications.by removing the:pages' identified i

'below and inserting the enclosed pages.. The revised pages are identified bp-the captioned amendment number and contain marginal lines-indicating the area of change.

Corresponding overleaf pages are provided to' maintain documentL completeness.

1 REMOVE INSERT.

3/4 1-20 3/4 1 '!

3/4 1-22 3/4 1-22 1

B 3/4'l-3

'B.3/4 1 '

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d REACTIVITY CONTROL SYSTEMS 1

ROD OROP 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 shall be,less than or equal to 2.7 seconds from

.l beginning of decay of stationary gripper coil voltage to dashpot entry with:

T,yg greater than or equal to 551*F, and l

a.

b.

All Reactor Coolant pumps operating.

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APPLICABILITY: MODES ]. and.2.

ACTION:

a.

With the rod 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 with three reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 66% of RATED THERMAL POWER.

$ SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall"be demonstrated through measurement. prior to reactor criticality:

a.

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

For specifically affected individu'ai rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and c.

At least once per 18 months.

CALLAWAY - UNIT 1 3/4 1-19 Amendment-No. JE,2P L -

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' REACTIVITY CONTROL SYSTEMS

' SHUTDOWN R0D INSERTION LIMIT LIMITING CONDIT' ION' FOR OPERATION-'

. 3.1.3.5 'All shutdown rods'shall be fully withdrawn (22'5' steps or higher).

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APPLICABILITY:

M00ESi1* and 2*# -

ACTION:

With'a maximum of one shutdown rod not fully-withdrawn,'except forl surveil-

'l-d lance : testing pursuant.to Specification'4.1.3.1.2, within_.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. either:

a.

Fully withdraw the rod.

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Declare-the rod'to be inoperable and apply Specification 3.1.3.1.

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1 SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:

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a.

Within 15 minutes prior to withdrawal of any rods. in Control Bank

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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 Specifications 3.10.2 and 310.3.

- #With Keff greater than or equal to 1.

b CALLAWAY - UNIT 1 3/4 1-20 Amendment N_o. 29-O

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~ REACTIVITY CONTROL SYSTEMS CONTROL R0D INSERTION LIMITS LIMITING CONDITION FOR OPERATION

.3.1.3.6 The control banks shall b'e. limited in physical insertion as shown in Figure 3.1-1.

APPLICABILITY:

MODES 1*.and 2*#,

ACTION:

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,1 With the control banks inserted beyond the above. insertion limits, except for

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l surveillance testing pursuant to Specification 4.1. 3.1'.2: 1 q

a.

Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or H

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Reduce' THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />'to less than or equal to that

- fraction of RATED THERMAL' POWER which is ' allowed by the bank position using the above figure, or

-c.

Be in at least HOT STANDBY within 6. hours.

r SURVEILLANCE REQUIREMENTS l

l 4.1.3.6 The position of each control' bank shall1be determined to be within.

I the insertion-limits. at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals'-

1 when the Rod Insertion Limit Monitor is inoperable, then' verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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• See Special Test Exceptions Specifications-3.10.2 and 3.10.3.

1. With Keff greater than.or equal to 1.

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FULLYINSERTED RATED THERMAL POWER (Percent)

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,.o FIGURE 3.1-1 ROD BANK,1NSERTION LIMITS VERSUS s '-

RATED THERMAL POWER - FOUR LOOP ~ OPERATION CALLAWAY -' UNIT.l.

3/4 1-22 Amendment No. LB,29 c =_ -

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REACTIVITY CONTPSL S,YS7 EMS i

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E0MTION SYSTEt1S (Continued) s With tNe'RCS temperature below 200 F, one Boration System is acceptable without single failure consideration on the basis of the stable reactivity r, Aondition of Lt.he reactor and the additional, restrictions prohibiting CORE.

AG ERAT 10NS Mnd positive reactivity changeslin the? event the' single Boron

. Injection System becomes finoperable.M a

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m,u The limitation for a maximum of chd celltrifugal cha'eging pump.to be a

OPERABLE and the Surveillance Requirement to verify all charging pumps except-the required OPERABLE pump to be incperable in MODES 4, 5, and 5 provides assurance that a mass addition pressure trcnsient'can be relieved by the operation of.a s4gle PORV.or an RHR suction relief valve.

The boron capability required below 200'F is sufficient to provide a

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SHUTDOWN MARGIN of 1% Ak/k after xenon' decay and cooldown from 200 F to-1406F.

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This condition requires either 2968 gallons of 7000. ppm borated water from the boric acid storage-tanks or 14,076 gall 6ns of 2000 ppm borated water from the RWST.

The containedhate" volume limits include allonance for water not avail'cble because of discharse line location and other physical characteristics.

"dhe limits on contained water volume and boron concentration of tnenRWST also ensmp a pri value of between 8.5 and 11.0 for the-solution recirculated within Containment after 6 LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride' and caustic stress corrosion on s mechanical systems and components.

The OPERABILITY of one Boration System during' REFUELING ensures that this system is available for reactivity control while in MODE 6.-

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that: -(1) acceptable power y

distribution limits are maintained, (2) the minimum'SHUTD0WN MARGIN is main-tained,'and O) the potential effects of.ro'd misalignment'on associated acci-dent analyses are limited.. OPERABILITY of the coni;rol rod position-indicators is requked to determine control rad' positions ahd thereby ensure compliance 1

with~ the control rod alignment and insertion lim \\ts, Verification that the-Digital Rod Position Indicator agrees' with the demanded position within + 12 '

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steps at 24, 48,120 and 228 steps withdrawn for the4 Control. Banks and lE, j

210 and 228 steps withdrawn for the Shutdown Eanks' provides, assurance' that the' N

Digital Rod' Position Indicator 3is operating correctly over the full rang of ~

N indication.

Since the Digital ' Rod Ptsition System does not indicatenthe actual 1

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shutdown' rod position between 18 steps and 210 -steps,' only points in the indi-cated ranges' are picked' for verificMien'of' agreement with demanded position.

Shutdown and control rods are positiondd at 225 steps or higher for fully'with-p drawn.

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CALLAWAY'- UNIT 1:

.B 3/4 $-3 Amendment No.'29.

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MOVABLECONTROLASSEMBLIES(Continuedh

j The ACTION statements which permit limited variations frdm the basic-requirements are accompanied by' additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement a

of peaking factors and a restriction in THERMAL' POWER. -These restrictions.

1 provide assurance of fuel rod integrity during continued operation. 'In. addition, those safety analyses affected.by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

The niavimum rod drop time restriction is consistent with the' assumed rod drop time useo in the safety enalyses.

Measurement with T greater than or avg equal to 551 F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a Reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position i.ndicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.

4 CALLAWAY - UNIT 1 B 3/4 1-4

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