ML19345D144

Amend 35 to License DPR-66,modifying Tech Specs Re Operation & Surveillance of Control Rod Indicator Channels

ML19345D144
Person / Time
Site:	Beaver Valley
Issue date:	11/15/1980
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML19345D146	List: ML19345D144 ML19345D147 ML19345D150
References
NUDOCS 8012120020
Download: ML19345D144 (10)

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LIGHT "0MPANY OHIO EDISON COMPAM PENNSYLVANIA POWER COMPAftY DOCKET 10. 50-334 BEAVER VALLEY PC:iE. STATION, U'IT NO.1 AMEN. MENT TO FACILITY OP'EPATIf;3 LICEY.E Amendment No. 35 License No. DPR-66 1.

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

The application for amen. ent by Ouqunne Light Company, Ohio A..

Edison Ccmpany, and Pennsivania Power Company (the licensees) dated November 14, 1980, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rul., and regulations set forth in 10 C. R Chapter I; B.

The facility will operate in conformity with the application, the~ provisions of the Act, and the rules and regulations of the Cornission; C.

There is reasonable assurance (i) that the activities authorized by this ".endment can b. conde-ts.' without endangering the r alth and s&fety of the public, and (11; that such activities will be conducted in compliance with the Commission's regulations; 4

D.

The issuance.of this amendment wil not be inimical to the common defense and security or to the heal.1 and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR F et 51 of the Commission s regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specificatica as indicated in the attachment to this license i

l Inendment, at paragraph 2.C.(2) of Facilit" Operating License d

i No. OPR-66 is hereby amended to read as f.

.ows:

4 (2) Techn* cal t ecifications The Technical Specifications contained in Appendices 4

A and 3, as revised through Amendment 'io. F, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technic 1 Specifications.

3.

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

.MMISSION FqRTHENUCLtARRETJLATORY O

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Attachment:

Changes to the Technical l

Specifications Date of Issuance:

November 15, 1980

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h ATTACHMENT TO LICENSE AMENDME'T I

AMEND. ENT NO. 35 TO FAC!LITY OPERATING LICENSE NO. OPR-66 v

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00CKE7 NO. 50-334 Revise Appendix A as follows:

Remcve Pages Insert Pages 3/4 1-18 3/4 1-18 3/4 1-20 3/4 1-20 3/4 1-20A B 3/4 1-4 8 3/4 1-4 t

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l REACTIVITY CONTROL SYSTEMS SURVLlLLANCE REQUIREMENTS (Continued) a.

At least once per 7 days by:

1.

Verifying the baron concentration in each water source, Ver' f ng '.he wat'- level in each water source, and i

2.

3.

Verifying the bcric acid storage system solution temperature, b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the RWST ambient air temperature is < 43*F.

BEAVER VALLEY -' UNIT 1 3/4 1-17

REACTfVITY CONTROL SYSTEMS 3/4.1. 3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPEPATION 3.1.3.1 All full Sngth (shutdown and control) rods which are inserted in the core shall be OPERABLE and positioned within + 12 steps (determined in accordance with Specification 3.1.3.2 of their group step counter demand position.

APPLICABILITY: MODES 1* and 2*

ACTION:

a.

With one or more full length rods inoperable due to being ininovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With more than one full length rod INOPERABLE or indicated to be misaligned from any other rod in its group by more than

+ 12 steps (determined in accordance with Specification 3.1.3.2),

Fe in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With one full length rod inoperable or indicated to be misaligned from its group step counter demand height by more than + 12 steps (determined in accordance with Specification 3.1.3.2), F0WER OPERATION may continue provided that within one hour either:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is decle. red inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

l a)

An analysis of the potential ejected rod worth is performed within 3 days and the rod worifn is determined to be < 0.95". ak at zero power and

< 0.20". ak at RATED THERMAL POWER for the remainder of the fuel cycle, and b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and

• See Special Test Exceptions 3.10.2 and 3.10.4 BEAVER VALLEY - UNIT 1 3/4 1-18 AMENDMENT NO. 35

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_a LIMITING CONDITION FOR OPERATION (Continued)

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The THERMAL POWER level is reduced to < 75% of RATED THERMAL POWER within ene hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to 1 85% of RATED THERMAL POWER, or d)

The remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the incperable rod within ene hour while maintaining the red sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL PCWER level shal' A restricted pursuant to Speci'ication 3.1.3.E curing subsequent operaticn.

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SURVEILLANCE REQUIREMENTS The position of each full length rod shall be determined to 4.1. 3.1.1 be within the group demand lim'.t by verifying the individual rod positi s

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 when the Rod Position Deviation Monitor is inoperable, then ver1fy the group 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 />.

j Each full length red not fully inserted shall be determined 4.1.3.1.2 to be OPERABLE by movement of at least 10 steps in any one direction at j

least once per 31 days.

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BEAVER VALLEY - UNIT 1 3/4 1-19 Amendment No.17 i

" REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.2 For Cycle 2 cperation, all shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the control rod positions within

+ 12 steps by direct analog indication or as a backup by measurement of channel detector primary voltages.

If a rod position indicator analog channel indicates 12 steps or more deviation from the group demand indicator, rod positions for the affected rods shall be detennined by measuring detector primary voltages, as follows:

a a.

innediately, b.

if associated rods move greater than 6 steps (greater than 12 steps if all rods in the group have been determined to be within 6 steps of the group demand indicator by primary voltage measure-ments within the previous 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />),

at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals if the affected rod (s) are not fully inserted c.

or fully withdrawn, d.

at 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> intervals if the affected rod (s) are fully inserted or fully withdrawn.

When the rod position indicato.' channel is INOPERABLE, the position of not more than three control rods per bank which are not fully inserted or fully withdrawn may be detennined by use of the detector primary voltage measurements.*

APPLICABILITY: Modes 1 and 2*

ACTION:

If greater than 3 rod position indicators per bank, for banks a.

not fully withdrawn or fully inserted, are INOPERABLE, then

' declare the rod position indicator system to be INOPERABLE l

and be in HOT STANDBY within i hour after the allcwed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stabili::ation period and in COLD SHUTDOWN in the following l

Submit a Special Report to the NRC by telephone and in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or by the close of the next business day, whichever is later. Restore all affected Rod Position Indicators l

to OPERABLE status prior to entry to Mode 2.

b.

If the position of a maximum of one rod cannot be determined by either the direct reading of the rod position indicators or by reading primary detector voltage measurements, either:

1.

Determine the position of the non-indicating rod indirectly by the movable incore detectors immediately and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and innediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce THERMAL POWER TO < 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

BEAVER VALLEY - UNIT 1 3/4 1-20 AMENDMENT NO. 35

4 REACTfVITY CONTROL SYSTEMS ACTION:

(Continued)

With a maximum of one demand position indicdtor per bank c.

inoperable, either:

1.

Verify that all rod position indicators for the affected

-bank are OPERABLE and that the most withdrawn red and the least withdrawn rod of the bank are within a maximum of 12 steps of each other innediately after rod motion

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greater than 6 steps (greater than 12 steps if all rods in the group have been determined to be within 6 steps of the group demand indicator by voltage measurements within the previous a hours) and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.

Reduce THERMAL POWER TO < 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

d.

If the position of more than one rod cannot be detemined by either the direct reading of the rod position indicators or by reading primary detector voltage measurements, then Specification 3.0.3 is applicable.

SURVEILLANCE REQUIREMENTS 4.1.3.2 Each rod position indicator channel shall be detemined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within 12 steps 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 when the Red Position Deviation Monitor is INOPERABLL or is in a continuous state of alarm), then compare the demand position indication system and tne rod position indicator channels at approximately 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals, as follows:

If an individual rod position indicator analog channel does not I

a.

settle to within 112 steps within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, then declare that channel INOPERABLE.

b.

For any INOPERABLE channel, no repairs or adjustments shall be pe mitted without being followed immediately by a full range calibration.

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• For Core PHYSICS TESTING in Mode 2, primary detector voltage measurements I

may be used to detemine the position of rods in shutdown banks A and B and control banks A and B for the purpose of satisfying Specification 3.1.3.2.

During Mode 2 operations, rod positten indicators for shutdown banks A and B and control banks A and 8 may deviate from the group demand indicators by greater than i 12 steps during reactor startup i

and shutdown operations, while rods are being withdrawn or inserted.

If the rod position indicators for shutdown banks A and B and control banks A and B deviate by greater than 1 2 steps from the group demand 1

indicator, rod withdrawal or insertion may continue until the desired l'

l group heigt,)t is achieved.

BEAVER VALLEY - UNIT 1 3/4 1-20A AMEN 0 MENT NO.-35 (l

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REACTIVITY CONTROL SYSTEMS 1

BASES 3/4.1.2 B0 RATION Sv5TEMS (Continued) i The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN from all operating conditions of 1.0% ak/k after xenon The maximum boration capability requirement decay and cooldown to 200*F.

occurs at EOL from full power equilibrium xenon conditions and requires 11,336 gallons of 7000 ppm borated water from the boric acid storage tanks or 49,917 gallons of 2000 ppm borated water from the refueling water storage tank.

With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

The boron capabili

• required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1%.k/k after xenon decay and cooldown from 200*F to 140*F. This condition requires either 5000 gallons of 7000 ppm borated water from the boric acid storage tc.nks or 175,000 gallons of 2000 ppm borated water from the refueling water storage tank.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of a red ejection accident.

OPERASILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

i The ACTION statements which permit limited variations fran'the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met. Misalignment of a rod requires measure-ment of peaking factors or a restriction in THERMAL POWER; either of these restrictions provide assurance of fuel rod integrity during continued The reactivity worth of a misaligned rod is limited for the i

operation.

remainder of the fuel cycle to prevent exceeding the assumptions used in the accident analys;s for a rod ejection accident.

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REACTIVITY CONTROL SYSTEMS BASES 3 / 4.1. 3 MOVABLE CONTROL ASSEMBLIES (Continued)

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses.

Measurement with T

> 541*F and with all reactor coolant pumps operating ensures that the med, Ered drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and GPERABILITY of the rod position indicators 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 LCO's are satisfied.

Flexibility in the methods of determination of rod position by using primary voltage measurement is provided in this specification to allow for known drifts which are characteristic of the rod position indication Use of detector primary voltage measurements for rod position system.

determination for up to 3 rods is allowed for extended periods provided that increased surveillance is maii:tained. This flexibility does not alter the basic accuracy assumptions of the rod position indication system.

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BEAVER VALLEY - UNIT 1 S 3/4 1 4 AMENDMENT NO. 35 i

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