Text

Amends 35 & 15 to Licenses NPF-4 & NPF-7,respectively, Revising Tech Specs Requirements for Determining Quadrant Power Tilt Ratio When Above 75% of Rated Thermal Power W/One Power Range Channel Inoperable
	ML20040B098
Person / Time
Site:	North Anna
Issue date:	12/31/1981
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20040B099	List: ML20040B098; ML20040B103; ML20040B106;
References
	NUDOCS 8201250147
	Download: ML20040B098 (20)
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UfflTED STATES y 79 e (, ' i NUCLEAR REGULATORY CCMMISSICtJ

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VIRGIt1IA ELECTRIC AtiD PC'WER CCMPAtiY OCCXET ti0. 50-333 flCRTH Atit1A PC'WER STATI0tl, UrlIT NO.1 AMEtt0ME!iT TO FACILITY OPERATItiG LICE!15E Arend= enc l10. 3E License ilo. li?F 1.

The riuclear Regulatory Cc=issicn (the Cc=issien) has fcund that:

A.

The acclicaticn for amendment by Virginia Electric and Pcwer Company (the licensee) dated September 21, 1981 (Serial No. 491) complies with the standards and requirements of the Atc aic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; 3.

The f acility will cperate in confomity with the a:plicz.ti on, the provisiens of the Act., and the rules and regulaticns of the Ccmission; C.

There is reascnable assurance (i) that the activities autherf:ed by this amenc en can be concucted witneut endangering the nealth and safety of :ne ;u:li:, and (ii) that sucn activities will be ccnducted in c mpliance with the Commissien's regulations; D.

The issuance of this amen: ment will not be inimical to the ecmmon defense and security or :: :he health and safety cf the public; and E.

The issuance f this amendment is in acc:rdance with 10 CFR Part 31 of the Cc=issicn's regulations and al' 1;plicaole re uirements have been satisfied.

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8201250147 811231 PDR ADOCK 05000 P

2 2.

Acccrdingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragrach 2.D.(2) of Facility Opertting License fic. fGF-4 is hereby amended to read as folicws:

(2)

Technical Scecificatiens The Technical Scecifications centained in Accendices A and B, as revised through Amendment fic. ?5, are hereby incorscrated in the license. The licensee shall cperate the facility in accordance with the Technical Specificaticns.

3.

The license amendment is effective 7 days frem the date of its issuance.

FOR THE liUCLEAk T.iGL'LATORY CC'tMISSICri G

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Rccert A.' Clark, Chief Operating Reacters Branch #3 Division cf Licensing

Attachment:

Chan;es to the Technical necificatiens Date of Issuance:

December 31, 1981

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i ATTACHt/EtiT TO LICE?lSE AMEtlCMEth AMEftDMEtiT f;0. 35 TO FACILITY OPERATIriG LICE?lSE t:0. tiPF 4 DOCKET ti0. 50-339 Replace the following pages of the Appendix "A" Technical Specifications 1

with the enclosed pages as indicated.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain dccument c0mpleteness.

I Paces 3/4 2-13 3/4 3-5 l

8 3/4 2-5 j

B 3/4 3-2 i

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PCWER DISTRIBUTION i

LIMITING CONDITION FOR OPERATION (Continued) p reduce THERMAL POWER to less than 50% of. RATED THERMAL P0hER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range 3

i Neutron Flux-High Trip Setpoints to 0 55% of RATED l

THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i 3.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL PC'ER; subsequent 3

POWER OPERATION above 50% of RATED THERSL POWER may

1 i

proceed provided that the QUADRANT PCWEK TILT RATIO is verified within its limit at least once per hour for _12 hours or until verified acceptable at 95% or greater RATED THERMAL POWER.

j c.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shut-

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j down or control rod:

1.

Reduce THERMAL POWER to less than 50% of. RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . and reduce the Power Range Neutron Flux-High Trip Setpoints to 5 55% of RATED THERMAL POWER i

within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

j 2.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL PCWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT P0'dR TILT RATIO is verified within its limit at least once per hour for 12

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j hours or until verified as 95% or greater RATED THERMAL j

POWER.

i SURVEILLANCE REOUIREMENTS t

I 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be wichin the j

j limit above 50% of RATED THERMAL POWER by:

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a.

Calculating the ratio at least once per 7 days when the alarm is J

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OPERABLE.

b.

Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state f

operation when the alarm is. inoperable.

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4.2.4.2.

The QUADRANT POWER TILT RATIO shall be determined to.be within the limit when above 75 percent of RATED.THERST POWER with one Power Range Channel inoperable by using the moveable incore detectats to confim that the normalized l~,~.

synmetric power distribution;"obta~ined from 2 sets of 4 sy: netric thimble loca-tions or a full-core flux map, is consistent with the indir.ated QUADRANT POWER i

TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I NORTH ANNA - UNIT 1 3/4 2-13 A:aendment No. 75, 3 5

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i POWER DISTRIBUTION LIMITS l-DNB PAPMETERS l

LIMITING CONDITIO!l FOR OPERATI0fl i

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f 3.2.5 The following DNS related parameters shall be maintained within i

the limits shown on Table 3.2-1:

l' a.

Reactor Coolant Syster T I

avg

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Pressurizer Pressure i

c.

Reactor Coolant System Total Flow Rate j

APPLICABILITY: MODE 1 ACTION:

With any of the above parameters exceediric its limit, restore the param-eter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less i

than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

t SUR'/EILLANCE RECUIREMENTS 4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.2 The Reactor Coolant System total flow rate shall be determned to be within its limit by measurement at least once per 18 months.

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NORTH ANNA - UNIT 1 3/4 2 -

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TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

xx The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be.placed in t.Se tripped condition.

The provisions of Soecification 3.0.4 are not applicabl'e.

1. High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than re-reqLired by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1.

ACTION 2 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

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The inoperable channal is placed in the tripped a.

condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirer.:ent is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the redundant channel (s) per Specification 4.3.1.1.1.

c.

Either, THERMAL POWER is restricted to c 75% of RATED THERMAL and the Power Range, Neutron Flux trip setpoint is reduced to s 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the move-able incore detectors to confirm that the normalized symmetric power distribution, obtained frem 2 sets of 4 symmetric thimble locat. ions or a full-core flux map, is consistent with the i-indicated QUADRANT. PC'fjR TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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ACTION 3 -

With the number of thannels OPERABLE one less than re-

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required by ths Min'imum Channels OPERABLE-requirement and with the THERMAL POWER level:

NORTH ANNA - UNIT 1 3/4 3-5 Amendment No. 3 5

i TABLE 3.3-1 (Continued)

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a.

Belcw P-6, restore the inoperable channel to OPERABLE status prior to increasing THERFAL POWER above the P-6 Setpoint.

5.

Above P-6 but below 5% of PATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5". of RATED THERMAL POWER.

c.

Above 5% of RATED THEPJdAL POWER, POWER OPERATI0tl may continue.

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ACTIO!l 4 -

With the number of channels OPERABLE one less than re-quired by the Minimum Channels OPEPABLE requirement and with the THERMAL POWER level:

l a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the l

P-6 Setpoint.

b.

Above P-6, operation may continue.

ACTION 5 -

With the number of channels OPEPABLE one less than re- -

quired by the Minimum Channels OPEPABLE requirement, verify compliance with the SHUTDOWil MARGIf1 requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTI0il 6 -

ilot applicable.

ACTI0ti 7 -

With the number of OPERABLE channels one less than the Total flumber of Channels, STARTUP and POWER OPERATI0ft may proceed until performance of the next required CHAtiNEL FUNCTI0tlAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 8 -

Not applicable i

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P0_WER DISTRIBUTION LIMITS i

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abnormal perturbations in ghe radial power shape, such as from a.

rodmisalignment,effectFig more directly than F,

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although rod movement has a direct influence upon limiting F limit F[jn its limit, such control is not readily available tb to with.

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errors in prediction for control power shape detected during startup physics tests can bE compensated for in F by regtri-i cting axial flux distributions.

Thiscompensatic0forFlH is less readily available.

3/4.2.4 OUADRANT POWER TILT RATIO l

The quadrant power tilt ratio limit assures that the r'adial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during start-up testing and periodically during power cperation.

The limit of 1.G2 at which corrective action is required provides DNS and linear heat generation rate pro'ection with x-y plane power til ts.

The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned rod.

Ia the event such action does not correct the tilt, the margin for uncertainty on F is rein-g stated oy reducing the power by 3 percent for each percent of tilt in excess of 1.0.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are' used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of 4 syrmetric thimbles. The two sets of 4 syrmetric thimbles is a unique set of 8 detector locations. These locations are C-8, E-5, E-Il, H-3, H-13, L-5, L-il, and N-8.

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NORTH ANNA - UNIT 1 B3[42-5

' Amendment No. 3 5 f

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POWER DISTRIBUTION LIMITS i

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BASES 3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.

V The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic su"veillance of these parameters thru in-strument readout is sufficient to ensure that the parameters are re-stored within their limits following load changes and other expected i

transient operation.

The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlaticn of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

3/4.2.6 AXIAL POWER DISTRIBUTION The limit on axial power distribution ensures that F will be controlled and monitored on a more exact basis through ush of the APDMS when operating above 92" of RATED THERMAL POWER.

This additional limi-tation on F is necessary in order to provide assurance that peak clad g

temperatures will remain below the ECCS acceptance criteria limit of 2200'F in the event of a LOCA.

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l NORTH ANNA - UNIT 1 B 3/4 2-6 Amendment No. 3, 5, 22

3/4.3 INSTRUMENTATION

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3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION The OPERABILITY of the protective and ES"F instrumentation systems l

and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by sach channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a I

channel to be out of service for testing or maintenance, and 4) suf-ficient system functicnal capability is available for protective and ESF 3

purposes from diverse parameters.

The OPERABILITY of these systems is required to pr vide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is con-sistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability.is maintained ccmparable to the original design standards.

The pericdic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed witnin the time limit assumed in the accident analyses.

No credit was taken in the analyses for those chan-nels with response times indicated as not applicable.

Response time may be demonstrated by any s: ries of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response time verification may be demonstrated by either 1) in place, onsite or effsite test measurements or 2) utilizing replacement sensors with certified response times.

i 3/4.3.3 MONITORING INSTRUMEflTATION

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3/4.3.3.1 RADIATION MONITORING INSTRUMENTATICM k

.u a The OPERABILITY, of the radiaticn monitorjng channels ensures that m,

1) the radiation levels are'c~ontinually measured in the areas served j

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NORTH ANNA - UNIT I B 3/4 3-l'

INSTRUMENTATION BASES RADIATION MONITOR!flG INSTRUMENTATION (Continur:d) by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of tne movable incore detectors witti the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial =cutron flux distribution of the rea tor core.

The OPFRABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.

N For the purpose of measuring F (Z) or F

, a full incore flux map is Quarter-core flux maps, as d9 fined in$ CAP-8648, June 1976, may be used.

used in recalibration of the excore neutron flux detectictn syst.em, and full incore flux maps or symmetric incore thimbles may be us4 for monitoring the QUADRANT POWER TILT RATIO when one Power Range Chann;l is inoperable.

3/4.3,3.3 SEISMIC INSTRUMENTATICN The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is available to promptly determine the r.agnitude of a' seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant tc Appendix "A" of 10 CFR Part 100.

The instrumentation is generally consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes," April 1974.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiadon doses to the public as a result of routine or accidental release of radioactve materials to the atmosphere.

This capability is required to evaluate the need for initiating protective n: ensures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs,"

February 1972.

3/4.3.3.5 AUXILIARY SHUTDOWN PANEL MONITORING INSTRUMENTATION The OPERABILITY of't'he remofe shutdEwYinstrumentation ensures that

, 2,_

sufficient capability is available to permit shutdown and maintenance of HOT STAND 8Y of the facility (Fom'l'ocations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.

NORTH ANNA - UNIT 1 B 3/4 3-2 toendment No. 3 5

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J UNITED STATES i

NUCLEAR REGULATORY COMMISSION y$e 3

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VIRGINIA ELECTRIC At!D PCWER CCPPAtiY CCCXET NO. 50-33_9 t:0RTH ANNA PCWER STATION, UNIT NO. 2 AMENOMENT TO FACILITY CPERATING LICENSE Amendment fio.15

- License No. NPF-7 1.

The Nuclear Regulatory Ccenissien (the Cceraissicn) has fcund that:

A.

The apolication'for amendment by Virginia Electric and Power Company (the licensee) dated September 21, 1981 (Serial No. 491) complies with the standards and requirements cf the Atomic Energy Act of 1954, as amended (the Act) and the Ccmaission's rules and regulations set forth in 10 CFR Chapter I; 3.

The facility will operate in conformity with the a;plicatien, the provisiens of the Act, and the rules and reculations of

ne Ccaission; C.

Inere is reascna::le assurance (i) that the activicies authori:ed by this amendment can be conducted without endangering the health and safety of the public, and (ii) that sucn activities will be conducted in ecmoliance with the Cc=issicn's regulaticns; D.

The issuar.ce Of this amendment will not be inimical to the ecmmen defense and security or to the health and safety cf the ;ublic; and E.

The issuance of this amencment is in acccrdance with 10 CFR Part 51 of the Ccm.ssion's regulations and all acplicable requirements have been satisfied.

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Accordingly, the liccnse is amended by changes to the Technical Specificatiens as indicated in the attachment to this license amendment, and paragrash 2.C.(2) of Facility Ocerating License No. NPF-7 is hereby amended to read as follcws:

(2) Technical Scecifications The Technical Specificaticns ccntained in Ac:endices A and 3, as revised through Amendment No. 15, are hereby incer; crated in the license.

The licer.see shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective 7 days from the date of issuance.

FOR THE NUCLEAR REGULATORY CO:~. MISSION p

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/rd m Robert A. Clark, Chief

,N Operating Reacters Eranch !3 Divisien of Licensing

Attachment:

Changes to the Technical 5:ecificaticns Date of !ssuance:

December 31, 1931 4

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT f:0. 15 TO FACILITY OPERATING LICEf;SE NO. i:PF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. ihe corresponding overleaf pages are also provided to maintain dccument completeness.

Pages 3/4 2-14 3/4 3-5 8 3/4 2-5 e

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POWER DISTRIBUTI0tl i

LIMITIfiG CONDITION FOR OPERATION (Continued)

I j

hours and reduce the Power Range fleutron Flux-High Trip. set-points to less than or equal to 55% of RATED THERitAL POWER within i

i the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i 4

Identify and correct the cause of the out of, limit condition l

prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRAtlT POWER TILT RATIO is verified within its limit at least i

l once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95%

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or greater RATED THERMAL POWER.

j b.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of either a shutdown or control rod:

1 1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour 4

i until:

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(a)

Either the QUADRANT POWER TILT RATIC is reduced to within i

its limit, or (b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

2.

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for i

each 1% of indicated QUADRANT POWER TILT RATIO in excess of j

1.0, within 30 minutes.

I 3.

Verify that the QUADRANT POWER TILT RATI0 is within its limit i

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months af ter exceeding the limit or reduce THERMAL 1

POWER to less than 50% of RATED THER!!AL PCMEri within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High trip Setpoints j

to less than or equal to 55% of RATED THERI:AL POWER within the j

next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

1 4.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequ'ent POWER OPERATION 1

above 50% of RATED THERMAL POWER may proceed provided that tne

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QUADRANT POWER TILT RATIO is verified within its limit at least I

once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95%

I or greater RATED THEPJiAL POWER.

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POWER DISTRIBUTION i

LIMITING CONDITION FOR OPERATION (Continued) c.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shutdown or control rod:

1.

Calculate the QUADRANT POWER TI.LT RATIO at least once per hour until:

(a) Either the QUADRANT POWER TILT RATIO is reduced to within its limit, or (b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL F0WER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of' limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER.

SURVEILLANCE REOUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be witt.in the limit above 50% of RATED THERMAL POWER by:

Calculating the ratio at least once per 7 days when the alarm is a.

OPERABLE.

b.

Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state operation when the alarm is inoperable.

~

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the moveable incare detectors to confirm that the 1 normali:ed symmetric power distribution, obtained frcm 2 sets of 4 symmetric thimble locations or a full-core flux map, is censistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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5-NORTH ANNA - UNIT 2 3/4 2-14 Amendment No.15 l

TABEL 3.3-1 (Continued)

TABLE NOTATION A

With the reactor trip system breakers in tne closed position and the control rod drive system capable of rod withdrawal.

xx The channel (s) associated with the protective functions derived frcm the out of service Reactor Coolant Loop shall be.placed in the tripped condition.

The provisions of Specification 3.0.4 are not applicable.

1. High voltage to aetector may be de energized above the P-6, (Block of Source Range Reactor Trip), retpoint.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than re-quired by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided ch; other channel is OPERABLE.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfiedr a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the redundant channel (s) per Specification 4.3.1.1.1.

c.

Either, THERMAL POWER is restricted to 5 75% of RATED THERMAL and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the moveable incare detectors to confirm that the normalized symmetric power _ distribution, obtained fr m 2 sets of 4 symmetric thible loca(ions or a full-core flux map, is consistent with the

~~~'

indicatad QUA0 RANT.PC'iEK TILT RATIO at least-once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

w_

4 NORTH ANNA - UNIT 2 3/4 3-5 Amendment No.15

9 TABLE.:.j-1 (Continued)

ACTION 3 With the number of channels OPERABLE one less than required by the Minimum Channeis OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6, (Block of Source Range Reactor Trip) set-point, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Sctpoint.

b.

Above the P-6, (Block of Source Range Reactor Trip) set-point, but below 5% of RATED THERttAL PCWER, restore the inoperable channel to PERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, PCWER OPERATION may continue.

ACTION 4 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

Below the P-6, (Block of Source Range Reactor Trip) set-a.

point, r estore the inoperable channel to OPERABLE status prior t) increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6, (Block of Source Range Reactor Trip) set-point, operation may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months there3fter.

ACTION 6 Not applicable.

ACTION 7 - With the number ot OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed I

until performance of the next required CHA"NEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION B Not applicable.

-a 3

s e-,

y NORTH ANNA - UNIT 2 3/4 3-6

POWER DISTRIBUTICil IMITS

~

BASES

?!

When F is measured, 4% is the appropriate experi:: ental error allowance 6g for a full core map taken with the incore detection systen.

The specified limit for F also contains an 8% allowance for uncertainties which means that normal H

operation will result in F l ess than or equal to 1.E5/1.08.

The 8% allow nce H

is based on the following considerations:

a.

abnormal perturbations in the radial power shape, such as from rod N

misalignment, effect F more directly than F,

g n

b.

although rod movement has a direct influence upon limiting F to q

within its limit, such control is not readily available to limit F g, and c.

errors in prediction for control power shape detected during startup physics tests can be compensated for in F by re'stricting axial flux q

distributions.

This compensation for F6g.is less readily available.

3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distri-bution satisfies the design values used in the power capa::ility analysis.

Radial poaer distribution measurements are made during startup testing and periodically during power operation.

The limit of 1.02 at which cc.crective action is required provides DNB and linear hea t genera tion ra te protection with x-y plane power tilts.

The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misalioned rod.

In the event such action does not correct the tilt, the margin for unc2rtainty on F is reinstati. by reducing the power by q

3 percent for each percent of tilt in excess of 1.0.

For purpores of monitering QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT.

POWER TILT RATIO.

The incore detector monitoring is done with a full incore flux map or two sets of 4 symmetric thimbles.

The two sets of 4 sy:vnetric thimbles is a unique set of S detector locations.

These locations are C-8, E-5 E-11, H-3, H-13,.L-5, L-ll, and.N-8 p

s

~

NORTH ANNA 4 UhIT' 2 B 3/4 2-5 Amen &ient No. I5 4

POWER DISTRIBUTION LIMITS BASES 3/4.2.5 DMB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout ecch analyzed transient.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of these parameters thru instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

The 18 i

month periodic mearurement of the RCS total flow rate is adequate to detect flow degradation an t ensure correlation of the flow indication channels with measured flow such tnat the indicated percent flow will provide sufficient l

verification of flow rite on a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

3/4.2.6 AXIAL POWER DISTRIBUTICd l

The limit on axial power distribution ensures that Ff will be controlled i

and monitored on a more exact basis through use of the APDt15 when operating above 90% of RATED THERMAL POWER.

This additional limitation of F is necessary q

in order to provide assurance that peak clad ' temperatures will remain below the ECCS acceptance criteria limit of 2200 F in the event of a LOCA..

i

, u w,

NORTH ANNA UNIT'2 B 3/4 2-6 w

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ML20040B098

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