ML20248D416

Amends 120 & 104 to Licenses NPF-4 & NPF-7,respectively, Reducing Tech Spec 3/4.2.5 Limit on Min Measured Flow Rate in RCS from 289,200 Gpm to 284,000 Gpm

ML20248D416
Person / Time
Site:	North Anna
Issue date:	07/31/1989
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248D420	List: ML20248D416 ML20248D422
References
NUDOCS 8908110022
Download: ML20248D416 (14)

Text

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UNITED STATES E

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r VIRGINIA ELECTRIC AND POWER COMPANY p

OLD DOMINION ELECTRIC COOPERATIVE DOCKET t;C. 50-338 NORTH ANNA POWER STATION, UNIT NO.1 f

AMENDMENT TO FACILITY OPERATING LICENSE Mendment No.120 License No. NPF-4 1.

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

A..

The. application for amendment by Virginia Electric'and Power Company et al., (the licensee) dated May 23, 1989, complies with.the standards and requirements of the Atomic Energy Act of 1954, as amended (tha Act), and the Comission'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 Comission; 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 will be conducted in conipliance with the Commission's regulations; D.

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

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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.

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Accordingly, the license is apended 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 rea6 as follows:

(2) Technical Specifications 1"

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.120, r c hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

- 3.

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

FOR THE NUCLEAR REGULATORY C0t911SSION

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/ He bert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation.

Attachment:

Changes to the Technical Specifications Cate of Issuance: July 31, 1989 er a 4

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ATTACHMENT TO LICENSE AMENDMENT tiO.120 TO FACILITY OPERATING LICENSE ?!0. NPF-4 1

- DOCKET NO. 50-338 P,eplace the following pages of the Appendix "A"~ Technical Specifications

.with the enclosed pages as indicated. ' The revised pages are identified by amendment nunber and contain' vertical lines indicating the area of change.

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

Page 3/4 2-15 B 3/4 2-6 4

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!DRTH ANNA - UNIT 1 3/4 2.16 Amendment Ho, 3,5,J5,22, 37,39,4,84, 105

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POWER DISTRIBUTION LIMITS BASES I

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

N misalignment, effect F more direct 4 thar, F,

g q

b.

although rod movement has a direct influence upon limiting F to wfthinitslimit,suchcontrolisnotreadilyavailableto19mit FaH, and errors in prediction for control power shape detected dring startup c.

physics tests can be compensated for in F by restricting axial flux q

distributions.

This compensation for F is less readily available.

Fuel rod bowing reduces the value of the DNB ratio.

Credit is available to offset this reduction in the margin available between the safety analysis design DNBR values (1.46 for Virginia Electric and Power Company statistical methods) and the limiting design D'lBR value (1.26 for Virginia Electric and Power Company statistical methods). A discussion of the rod bow penalty is presented in the FSAR.

l..e hot channel factor F " Z cycleandheightdependentpo0e(r) actor,N(2),toprovideassurancethattheis measure f

limit on the hot channel factor, F (Z), is met.

N(Z) accounts for the non-n equilibrium effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.

The N(Z) function for normal operation is provided in the Core Surveillance Report per Specification 6.9.1.7.

3/4.(4 QUADRANT POWER TILT RATIO 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 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 und 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 correction of a dropped or misaligned rod.

In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing the power by 0

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 moveatile incore detectors are used to confirm that the normal-ized 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 symmetric thimbles is a unique set of 8 detector locations.

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

I NORTH ANNA - UNIT 1 B 3/4 2-5 Amendment No. 25,69,84, 105, 112 L

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POWER DISTRIBUTION LIMITS 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 envelooe of operation assumed in the transient and accident analyses. The limits have been analytically demonstrated to be adequate to maintain a minimum DNBR greater.than the design limit throughout each analyzed transient. Measurement uncertainties are accounted for in the DNB design margin.

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

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l NORTH ANNA - UNIT 1 B 3/4 2-6 Amendment No. 3,5,22,37,i4,105.YY7, 120

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UNITED STATES NUCLEAR REGULATORY COMMISSION l

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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DCCKET NO. 50-339 NORTH ANNA POWER STATICN, UNIT NO. 2 AMENDMENT TO FACILITY GPERATING LICENSE Amendment No.104 License No. NPF-7 1.

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

4 A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated May 23, 1989, 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 conformity with the application, the provisions of the Act, and the rules anc regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be condumd without endangering the health and safety of the public, and (;;) 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 pthlic; and E.

Tis issuance of this amendment is in ar.cordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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. 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.C.(2) of Facility Operating License No. NPF-7 is hereS-amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, 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 issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/

Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 31, 1989 l

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ATTACHMENT TO LICENSE A'jENDMENT NO.104 TO FACILITY OPERATING LICENSE NO. NPF-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 5y amendment number and contain vertical lines indicating the area of change.

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

Page' 3/4 2-16 B 3/4 2-6.

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POWER DISTRIBUTION LIMITS DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DN8 related par 2 meters shall be maintained within the limits shown on Table 3.2-1:

Reactor Coolant System T,yg a.

b.

Pressurizer Pressure c.

Reactor Coolant System Total Flow Rate APPLICA8ILITY: MODE 1 ACTION:

With any of the above parameters exceeding its limit, restore the parameter to, within its limit w. thin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

NORTH ANNA - UNIT 2 3/4 2-15

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.j POWER DISTRIBUTION LIMITS

. Of.SES N

When F is measured, 4%.is the appropriate experimental error. allowance for a full \\$re map taken with the incore detection system. The specified limit for F

'inameasurh$cgntainsa4%errorallowance. Normal operationLwill result the following c8Ns.less than or equal to 1.49.

F The 4% allowance is based on iderations:

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

rod misalignment.effect-F more directly than F,

AH g

b. 1although rod movement has a direct influence upon limiting F to withgn its limit,"such control is not readily available th limit F3g, and-c.

errors in prediction. fc r control power shape detected during startup physics tests can be compensated for'in F9 restricting axial flux distributions. This compensation for F is'less aH readily available.

Fuel rod bowing reduces the value of the DNB ratio. Credit is available to.

offset this. reduction 16 the margin avail.able between the safety analysis design DNBR value (1.46 for Virginia Electric and Power Company statistical methods) and the l!imiting desigh DNBR value (1.26. for Virginia' Electric and Power Company statistical' methods). A disciJssion of the rod bow penalt'y is presented in the FSAR.-

The hot channel factor F M(Z) is measured periodically and increased by n

a cycle and height dependent power factor, N(Z), to provide assurance that the limit on the hot channel factor, Fg(Z)., is met. N(Z) accounts for the non-equilibrium effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup condi-tions. in the core. The N(Z) function for normal operation is provided in the Core Surveillance Report per Specification 6.9.1.7.

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 capability analysis.

Radial power distribution measurements are made during startup testing and periodicallyLduring 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 powcr 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 misaligned rod.

In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing the power 0

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

NORTH ANNA - UNIT 2 B 3/4 2-5 Amendment No. 75,55,6#,71',wu 4

A.-.

,a POWER DISTRIBUTION LIMITS SASES For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is' consistent with the QUADRANT POWER TILT RATIO.

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

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 have.been analytically demon-strated to be adequate.to maintain a minimum DNBR greater than the design limit throughout each analyzed transient. Measurement uncertainties must be accounted for during the periodic surveillance.

The 12. hour 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 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.

J NORTH ANNA - UNIT 2 B 3/4 2-6 Amendment No. 77, 6A 11.199, 104

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