Text

Amends 69 & 55 to Licenses NPF-4 & NPF-7,respectively, Revising Tech Spec 3/4.2.3 by Eliminating Rod Bow Penalty on Nuclear Enthalpy Hot Channel Factor Through Use of Improved Fuel Rod Bowing Evaluation Methodology
	ML20138P483
Person / Time
Site:	North Anna
Issue date:	10/24/1985
From:	Butcher E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20138P487	List: ML20138P483; ML20138P502;
References
	NUDOCS 8511070196
	Download: ML20138P483 (19)
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION E

'r j WASHINGTON, D. C. 20555

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,o VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1

_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Comp'any, et al., (the licensee) dated February 14, 1985, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

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

9" 8511070196 851024 PDR ADOCK 05000338 P

PDR

, 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment.

and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Edward J. Butcher, Acting Chief Operating Reactors Branch #3 l

Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 24, 1985 m.

e

i ATTACHMENT TO LICENSE AMENDMENT N0. 69 TO FACILITY OPERATING LICENSE N0. NPF-4 DOCKET NO. 50-338 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.

The corresponding overleaf pages are also provided to maintain document i

completeness.

Remove Pages Insert Pages 3/4 2-9 3/4 2-9 3/4 2-11 3/4 2-11 B 3/4 2-5 8 3/4 2-5

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POWER DISTRIBUTION LIMITS BASES a.

abnormal perturbations in the radial power shape, such as from rod misalignment, effect F m re directly than F,

AH q

b.

although rod movement has a direct influence upon limiting Fn to wgthin its limit, such control is not readily available to l'fmit FaH, and c.

errors in prediction for control power shape detected during startup physics tests can be compensated for in Fg by restricting axial flux distributions. This compensation for F is less readily available.

AH Fuel rod bowing reduces the value of the DNB ratio. Credit is available in the form of retained generic margin totaling 9.1% DNBR to completely offset any rod bow penalty (including the worst case which occurs at a burnup of 33,000 MWD /MTU). This margin includes:

1.

Design Limit DNBR of 1.30 vs 1.28 2.

DNBR Multiplier of 0.865 vs 0.88 3.

Thermal Diffusion Coefficient of 0.038 vs 0.051 4.

Pitch Reduction 5.

Extra Grid 3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

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

The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate 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 correc-tion of a dropped or misaligned rod.

In the event such action does not correct the tilt, the margin for uncertainty on F0 is reinstated by reducing the porter by 3 percent for each percent of tilt in excess of 1.0.

For purposes of monitoring QUADRANT POWER TILT RATIO wher. one excore detector is inoper'bk, the moveable incore detectors are used to confirr that the normalized symetric 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 symetric thimbles. The two sets of 4 symetric thimbles is a unique set of 8 detector locations. These loca-tions are C-8, E-5, E-11, H-3, H-13, L-5, L-11, and N-8.

NORTH ANNA - UNIT 1 B 3/4 2-5 Amendment No. M,69

l POWER DISTRIBUTION LIMITS BASES f

3/4.2.5 DNB PARAMETERS s

The limits on the DNB related parameters assure that each of the i

arameters are maintained within the normal steady state envelope of operat on ssumed in the transient and accident analyses.

The limits are consistent l

p with the initial FSAR assumptions and have been analytically demonstrated a

adequate to maintain a minimum DNBR of 1.30 throughout each analys 4

transient.

hour periodic surveillance of these parameters thru instrument hi readout is sufficient to ensure that the parameters are restored within t e r The 12 The 18 4

limits following load changes and other expected transient operation.

J detect month periodic measurement of the RCS total flow rate is flow will provide sufficient measured flow such that the indicated percent 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 _

F will be controlled

.The limit on axial power distribution ensures that q

and monitored on a more exact basis through use of the APDMS when operatin Above P,%

of RATED THERMAL POWER.

This additional limitation on F is q

necessary in order to provide assurance that peak cigd temperatures will remain below the ECCS acceptance criteria limit of 2200 F in the event of a is based on the cycle dependent potential violation of I

LOCA. The value for P The amount the FgK(Z) limit, whee K(Z) is the graph shown in Figure 3.2-2.

i of pot'ential violation is determined by subtracting 1 fro l

This amount of potential violation, in percent, is

,l n

linit. ~

If P is equal to 100%,

K(Z) to the F from 100% to determine the value for P. required.IP will not exceed subtract is axial power distribution surveillance no i

100%.

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t B 3/4 2-6 Amendment No. 7, 5, 22, e 7.

NORTH ANNA - UNIT 1

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POWER DISTRIBUTION LIMITS NUCLEAR ENTHALPY HOT CHANNEL FACTOR - FN 3

LIMITING CONDITION FOR OPERATION 3.2.3 F shall be limited by the following relationship:

aH F"Ha1 1.55 [1 + 0.3 (1-P)]

where P = THERMAL POWER RATED THERMAL POWER APPLICABILITY: MODE 1 ACTION:

With F exceeding its limit:

AH Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER a.

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

Demonstrate through in-core mapping that [ is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit b$ reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and Identify and correct the cause of the out of limit condition c.

prior to increasing THERMAL POWER above the reduced limit required by a or b, aboge; subsequent POWER OPERATION may proceed provided that F is demonstrated through in-core mappingtobewithinit$Hlimit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95% or greater RATED THERMAL POWER.

l WORTH ANNA - UNIT 1 3/4 2-9 Amendment No. 44',69 I

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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS shall be determined to be within its limit by using the N

.2.3.1 F

4ovable inb$re detectors to obtain a power distribution map:

m Prior to operation above 75% of RATED THERMAL POWER after each a.

fuel loading, and At least once per 31 Effective Full Pow!r Days.

b.

The provisions of Specification 4.0.4 are not applicable.

. c.

of 4.2.3.1 above, shall be increased by 4% for 4.2.3.2 The measured F H

measurement uncertainty O

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, NORTH ANNA - UNIT 1 3/4 2-10

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3 NORTH ANNA'- UNIT 1-3/4 2-11 Amendment No. J6,69 1

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POWER DISTRIBUTION LIMITS QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION THE QUADRANT POWER TILT RATIO shall not exceed 1.02.

3.2.4 MODE 1 AB0VE 50% OF RATED THERMAL POWER

APPLICABILITY:

ACTION:

With the QUADRANT POWER TILT RATIO determined to a.

but i 1.09:

1.

Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

Either reduce the QUADRANT POWER TILT RATIO to a) within its limit, or Reduce THERMAL POWER at least 3% from RATED T POWER for each 1% of indicated QUADRANT POWER T b)

RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce 2.

THERMAL POWER to less than 50% of RATED THERMA 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 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 .

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent 3.

POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADPANT POWER TILT RATIO is 2

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 acceptable at 95% or greater RATED THERMAL POWER.

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

b.

Reduce THERMAL POWER at least 3% from RATED T for each 1% of indicated QUADRANT POWER TILT RAT 1.

excess of 1.0, within 30 minutes.

Verify that the QUADRANT POWER TILT RATIO is within its limit within.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the limit or 2.

See Special Test Exception 3.10.2.

Amendment No. 16 3/4 2-12 NORTH ANNA - UNIT 1

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+

UNITED STATES

- [

g NUCLEAR REGULATORY COMMISSION 3

E WASHINGTON, D. C. 20555 1

VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.55 License No. NPF-7 1.

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

I A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated February 14, 1985, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; j

C.

There is reasonable assurance (1) 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 Comission's regulations; D.

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

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Comission's regulations and all applicable requirements have been satisfied.

I

. 2.

Accordingly, the license is amended by changes to the Technical Spect-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION M

Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 24, 1985 l

ATTACHMENT TO LICENSE AMENDMENT NO. 55 TO FACILITY OPERATING LICENSE NO. NPF-7 a

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.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Pages Insert Pages 3/4 2-9 3/4 2-9 3/4 2-11 3/4 2-11 B 3/4 2-5 8 3/4 2-5 g'

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POWER DISTRIBUTION LIMITS 4

BASES When F is measured, 4% is the appropriate experimental error allowance for a full core map taken with the incore detection system. The specified limit for 3g 3H also contains an 8% al owance for uncertainties which means that normal 4

N F

less than or equal to 1.55/1.08. The 8% allowance j

operation will result in F H j

is based on the following onsiderations:

I abnormal perturbations in the radial power shape, such as from rod a.

misalignment,effectFfHmoredirectlythanFg, b.

.although rod movement has a direct influence upon limiting [n to within itslimit,suchcontrolisnotreadilyavailabletolimitF%,and errors in prediction for control power shape detected during startup l

c.

by restricting axial flux physics tests can be compensated for in Fg is less readily available.

distributions. This compensation for FaH Fuel rod bowing reduces the value of the DNB ratio. Credit is available L

in the fonn of retained generic margin totaling 9.1% DNBR to completely offset any rod bow penalty (including the worst case which occurs at a burnup of i

33,000 MWD /MTU). This margin includes:

1.

Design Limit DNBR of 1.30 vs 1.28 i

2.

DNBR Multiplier of 0.865 vs 0.88 1

3.

Thermal Diffusion Coefficient of 0.038 vs 0.051 4.

Pitch Reduction 5.

Extra Grid l

3/4.2.4 QUADRANT POWER TILT RATIO i

The quadrant power tilt ratio limit assures that the radial power distribu-tion satisfies the design values used in the power capability analysis. Radial power distributhn measurements are made during startup testing and periodically during power operation.

The limit of 1.02 at which corrective action is required provides DNB and j

linear heat generation rate protection with x-y plane power tilts.

l 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. In the event such action does not correct the is reinstated by reducing the, power by l

tilt, the margin for uncertainty on Fg 3 percent for each percent of tilt in excess of 1.0.

r 1

i For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normal-ized syrenetric power distrit,ution 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 synenetric thimb4es is a unique set of 8 detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-ll and N-8.

NORTH ANNA - UNIT 2 B 3/4 2-5 Amendment No.15,55

)

POWER DISTRIBUTION LIMITS

[

BASES 3/4.2.5 DNB FARAMETERS 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 sinimum DNBR of 1.30 throughout each 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 j

month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and e.nsure correlation 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 q

and socitored on a more exact basis through use of the APDMS when operating l

above P,% of RATED THERMAL POWER.

This additional limitation on F is q

J necessary in order te provide assurance that peak cigd temperatures will remain below the ECCS acceptance criteria limit of 2200 F in the event of a LOCA. The value for F is based on ene cycle dependent potential violation of the F xK(Z) limit, whbe K(Z) is the graph shown in Figure 3.2-2.

The amount o

of potential violation is determined by subtracting i from the maximum ratio of the predicted F (Z) analysis (flyspeck) results for a particular fuel cycle n

to the F xK(Z) lilhit.

This amount of potential violation, in percent, is o

subtracteu from 100% to determine the value for P.

If P is equal to 100%,

i no axial power distribution surveillanca is required.

f will not exceed i

100%.

j i

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NORTH ANNA - UNIT 2 B 3/4 2-6 Amendment No.17 I

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I POWER DISTRIBUTION LIMITS j

NUCLEAR ENTHALPY HOT CHANNEL FACTOR -

H LIMITING CONDITION FOR OPERATION shall be limited by the following relationship:

3.2.3 FLH LH.1.55 [1 + 0.3 (1-P)]

F THERMAL POWER

, and where: P= RATED THERMu POWER i

l APPLICABILITY: MODE 1.

ACTION:

With exceeding its limit:

H

a. 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 less than or equalto 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 4

b.Demonstratethroughin-coremappingthat(His within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

c. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a.

b., above; subsequent POWER OPERATION may proceed provided that o

is demonstrated through in-core mapping to be within its limit 3a nominal 50% of RATED THERMAL POWER prior to exceeding this a

THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to NORTH ANNA - UNIT 2 3/4 2-9 haendment No. /gg,55

~

?

POWER DISTRIBUTION LIMITS 1

ACTION _ Continued 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95%

exceeding this 1HERMAL POWER and within or greater RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS by using the shall be determined to be within its limit distribution map:

F 4.2.3.1 movable incore detectors to obtain a power POWER after each H

Prior to operatiori above 75% of P.ATED THERMAL 4

fuel loading, and a.

At least once per 31 Effective Full Power Days.

licable.

The provisions of Specification 4.0.4 are not app b.

c.

for of 4.2.3.1 above, shall be increased by 4%

N The measured F g

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4.2.3.2.

measurement uncertainty.

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3/4 2-10 NORTil ANNA - UNIT 2

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POWER DISTRIBUTION LIMITS QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 THE QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY: MDDE 1 above 50% of RATED THERMAL POWER

ACTION:

With the QUADRANT POWER TILT RATIO determined to exceed 1.02 a.

but less than or equal to 1.09:

J Calculate the QUARANT POWER TILT RATIO at least once per hour 1.

1 until:

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

POWER.

R 2.

Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

a)

Either reduce the QUADRANT POWER TILT RATIO to within its limit, or f

b)

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in i

excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Verif', that the QUADdANT POWER TILT RATIO is within its limit 3.

l wittin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POVER to less than 50% of RATED THERMAL POWER within the next 2 i

\\

"See Special Test E.ception 3.10.7..

l l

l NORTH ANNA - UNIT 2 3/4 2-12

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ML20138P483

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