ML20041D178

Amends 37 & 17 to Licenses NPF-4 & NPF-7,respectively, Changing Tech Specs to Remove Specific Values of Fxy & Axial Power Distribution Limits

ML20041D178
Person / Time
Site:	North Anna
Issue date:	02/05/1982
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20041D179	List: ML20041D178 ML20041D180 ML20041D181
References
NUDOCS 8203040442
Download: ML20041D178 (40)

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION p,

%*..*)j 74 WASHINGTON, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH'ANhAPOWERSTATION,UNITNO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 r

License No. NPF-4 t

1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licens' eel dated December 15, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended {the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;

.3F' B.

The facility will operate.in conformity with the application,i-the provisions of the Act,' and the rules and regulations of J.'

the Commission;

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C.

There is reasonable assurance (t) that the activities authorized

,5y this amendment can be conducted without endangering the heal.th and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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 t

E.

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

2'.

Accordingly, the license is amended by changes to the Technical

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~ Specifications as indicated in the attachment to this license amend-ment and paragraph 2.D.(2)'of Facility Operating License No. NPF-4 is hereby amended to read as follows:

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s r203040442 820205 il PDR ADOCK 05000338 P

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, (.2) Technical Specifica-tions The Technical Specifications contained in Appendices A and B, as revised through Amendment flo. 37, 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 fiUCLEAR REGULATORY C0f01ISSI0ft c

. t Robert A. Clark, Chief Operating Reactors Brancit #3 Division of Licensing

Attachment:

Changes to the Technical Specifications p.

Date of Issuance: February 5 198'2

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s ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 37 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 I

Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment num5er and contain. vertical lines indicating the area of change.

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

Pa ges 3/42-1 3/4 2-2 3/4 2-4 3/4 2-7.

i 3/4 2-16 3/4 2-17 3/4 2-18' B3/4 2-2 8 3/4 2-6 4

6-18 6-18a

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3/4.2 POWER DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE (AFD)

LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a 25% target band (fiux difference units) about the target flux difference.

APPLICABILITY: MODE 1 AB0VE 50% RATED THERMAL POWER

• ACTION:

a.

With the indicated' AXIAL FLUX DIFFERENCE outside of the 5%

target band about t,he. target flux difference and with THERMAL

- POWER:

i 1.

Above P % of RATED THERMAL POWER, within 15 minutes, where f

P =(0.9xP ); th,e value for P,is established in the Core f

Surveillance Report per Technical Specification 6.9.1.10.

a) Either restore the" indicated AFD to within the target band limits., or

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b). Reduce THERMAL POW'i.R to less than P % of RATED

.ey f

THERMAL POWER.

-f:

2.

Between 50% and P % of RATED THERMAL POWER:

_f a) POWER OPERATION may continue provided:

1) The indicated AFD has not been outside of the 25% target band,for more than'l hour penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2) 'The indica'ted'AFD is within the limits shown on Figure 3.2-1..Otherwise, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55%

l 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 />, b) Surveillance te' sting of the Power Range Neutron Flux Channels may be-performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1.

A jotal of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation may be accumulated with the AFD outside of the target band during this testing without penalty deviation.

.*See Special Test Exception 3.10.2.

NORTH ANNA - UNIT 1 3/4 2-1 Amendment No. 3, E, 22,3 7

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POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) b.

THERMAL POWER shall not be increased above P % of RATED THERMAL f

POWER unless the indicated AFD is within the 5% target band and ACTION 2.a.1, above,has been satisfied.

c.

THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD has not been cutside of the 15%

target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

z SURVEILLANCE REQUIREMENTS t

4.2.1.1 The indicated AXIAL. FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AF7 for each OPERABLE excore channel:

At least once per 7 da'ys when the.AFD-Monitor Alarm is' Ohh.E, 1.

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2.

At least once per hour for the first'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter restoring.

the AFD Monitor Alarm to OPERABLE status, b.

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each

. OPERA 3LE excore channel at least ence per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is ir a rahle. The logged values of the indicated AXIAL FLUX DIFFERF".E ul; be assumed to exist during the interval preceding each 1. 4

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4.2.1.2 The indicated AFD shall be considered outside of its tS% target band when at least 2 OPERABLE excore channels are indicating the AFD to be outside l

the target band. ~ Penalty deviatiion'outside of the 15% target band shall be accumulated on a time basis of:

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'a One minute penalty deviatidn for each one minute of 2MER OPERATION outside of the target b'and at THERMAL P'0WER levels equaA to or above 50% of RATED THERMAL POWER, and

.b.

One-half minute penalty deviation for each one* minute of POWER OPERATION outside of the target band at THEP3AL POWER levels between 15% and 50% of RATED THERMAL POWER.

l-NORTH ANNA - UNIT.1 3/4 2-2 Amendment No. 3 7 l

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i POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.1.3 The target flux dif ference of each OPERABLE excore channel shall be-determined by measurement at least once per 92 Effective Full

ower Days.

The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 ' The target flux difderence shall be updated at least once per 31 Effective Full Power Days by either determining the target ' flux difference pursuant to 4.2.1.3 above or by linear interpolation between the most recently measured.vaque and 0 percent at the end of the cycle l

life. - The provisions of Specific;ation 4.0.4 are not applicable.

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

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10 20-30 du 50 FLUX DIFFERENCE (111%

Figure 3.2-1 Axial Flux Difference Lirnits as a Function ofilated Thermal Power NORTH ANNA - UNIT 1 3/4 2-4 Ame'ndment No.3 7 1

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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

(b) At least once per 31 EFPD, whichever occurs first.

2.

When the Fxy.19,less than or equal to the F limit for the xy appropriat'e measured core plane, additional power distribution C

RTP L

maps shall be taken and F compared to F and F at least once per 31 EFPD.

L e.

The F limits for Rated' Thermal Power (F RTP) shall be provided xy xy for all core planes containing Bank "D" control rods and all unrodded core planes, in a Core Surveillance Report per Technical Specification 6.9.1.10.

f.

The F limits of e, above, are not applicable in the following..

xy

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core plane regions as measured in percent 6f core height from I'-

the bottom of the fuel:

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Lower core region ~ffom 0 to 15%, inclusive.

2.

Upper core region from 85 to 100%, inclusive.

3.

Grid plane regions at 17.8 22%, 32.1 2%, 46.4t2%,

60.6!2% and 74.9!2%, inclusive (17 x.17 fuel elements).

4.

Core plane regions within 2% of core height (t2.88 inches) about the bank demand position of the bank "D" control rods.

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With F exceeding F the effects of F on F (Z) shall be y

q evaluated to determine if'.F (Z) is within its limit.

4.2.2.3 When F (Z) is measured f r other than F determination, an overall xy measured F (Z) shall be obtained frod a power distribution map and increased q

by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

l NORTH ANNA-UNIT 1 3/4 2-7 Amendment No. 76, 22,9 7

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NORTH ANNA - UNIT 1 3/4 2-8 Amendment No. 3, E,16 in

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.5 DNB PARAMETERS I

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51 I,.IMITS s.

2 Loops In. Operation **

2 Loops In Operation **

c-2; 3 Loops Iri

& Loop Stop

& Isolated Loop PARAMETER Operation Valves Open Stop Valves Closed 1

Reactor Coolant System T

< 585*F avg

, {v Pressurizer Pressure

> 2205 psig*

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i Reactor Coolant System

> 278c400,gpk Totgl Elow-Rate i

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• Limit not applicable during either a TilERMAL POWER ramp increase in excess of 5% RATED TilERMAL POWER s

per minute or a TilERMAL POWER step increase in excess of 10% RATED THERMAL POWER.

• • Val'ues dependent on NRC approval of ECCS evaluation for these conditions t * *

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l POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION' LIMITING CONDITION FOR OPERATION e

3.2.6 The axial power distribution shall be limited by the following relationship:

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[F (Z)]3 =

3 (R )(P )(].03)(1 + o3)(1.07) 3 L

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a.

F (Z) is the normalized axial power distribution from thimble 3

j at core elevati'o, Z.

b.

P is the fraction of RATED THERMAL POWER.

L c.

K(Z) is the function obta.ined from Figure 3.2-2 for' 1"?--

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a given core height loca, tion.

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d.

R, for thimble j,ris determined from at least n=6 in-core - 5:

j flux maps covering the full configuration of permissible rod patterns above p % of RATED THERMAL POWER in accordance with:

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n y =.l. [

R j

n ij.

5,3 Where:

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$3(Z)] Max ij LF and [Fjj (Z)] Max is $he giaximum value of the nonnalized axial distribution at elevation Z from thimble j in map -

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- i which had a measured peaking factor without uncertainties eas.

or densification allowance of F

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l NORTH ANNA - UNIT 1 3/4 2-16 Amendment No. 3, E,4, $p,9 7 L

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POWER DISTRIBUTION LIMITS LIMITINGCONDITIONFOROPERhTION(Continued)

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a) 1s the standard; deviation associated with thicble j, expressed e.

as a fraction or percentage of R, and is derived from n flux maps from the relationship below, or 0.02, (2%) whichever is greater.

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Oj E n 1 i 1( j - ij)

K.

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The factor 1.07 is' comprised of 1.02 and 1.05 to account for the axial power distribution instrumentation accuracy and the measure-ment uncertainty associated with F using the movable detector q

system, respectively.

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The factor 1.03 is,the engineering uncertainty factor.

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APPLICASILITY: MODE 1 AB0VE P %_0F RATED THERMAL POWER, where the vaTue for P, is esta$lished in the Core Surveillance Report ifer Technical Specification 6.9.1.10.

ACTION:

With a F (Z) factor exceeding [F (Z)]3 ty <,4 percent, reduce "a.

3 3

(

THERMAL POWER one percent for every percent by which the F (Z) 3 L'

factor exceeds its limit within 15 minutes and within the next two hours either reduce' the F (Z) factor to within its limit 3

L or reduce THERMAL POWER to P % or less of RATED -THEPJ4AL POWER.

t b.

WithaF(Z) factor. exceeding [F(Z)]3 by > 4 percent, reduce 3

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THERMAL POWER to P %jor less of RATED THERMAL POWER within 15

minutes, s'

1. The APDMS may be out of service when surveillance foi determining power distribution maps is being performed.

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NORTH ANNA - UNIT ~1 3/4.2-17 Amendment No. 7, p, pp, 3 7 4

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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.6.1 F (Z) shall be determined to be within its limit by:

3 a.

Either using the APDMS to monitor the thimbles required per Specification 3.3.3.8 at the following frequencies.

1.

At least on,ce' per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and t

l 2.

Immediately and at intervals of 10, 30, 60, 90, 120, 240 and 480 minutss fg11owing:

a)

IncreasingtkeTHERMALPOWERaboveP%ofRATED THERMAL POWER, or b)

Movement of control bank "D" more than an accumulated total of 5 staps in any one direction.

b.

Or using the movable incore 'detectorstat the -following fret _~

quencies when the'.APDMS'is inoperable:.

.. '2.

1.

At least oncq per_ 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and

. 'E 2.

At intervals of 30, 60, 90, 120, 240 and 480 minutes-following:

a)

Increasing the THERMAL POWER above.p % of RATED m

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THERMAL POWER, or b)

Movement of control bank "D" more than an accumulated total of 5 st,eps in any one direction.

4.2.6.2 When the movable incore detectors are used to monitor F (Z),

3 at least 2 thimbles shall be monitored and an F (Z) accuracy equivalent I

3 to that obtained from the APDMS shall be maintained.

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NORTH ANNA - UNIT 1 3/4218 Amendment No. 3, '/,//,

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3/4.2 POWER DISTRIBUTION LIMITS BASES l

The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:

(a) maintaining the minimum DNBR in the core > 1.30 during nomal op'eration and in short term transients, and (b) 1Tmiting the fission gas rel. ease, fuel pellet temperature & cladding mechanical properties to within assumed design criteria.

In addition, limiting the peak linear power density during Condition I events provides assurance that the initial. conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200 F is not exceeded.

l The definitions of certain hot channel and peaking factors as used in these specifications ar as follows:

F (Z)

Heat Flux Hot Channel Factor, is defined as the maximum local 0

heat flux on the surface of a fuel rod at core elevation Z -

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divided by the average fuel. rod heat, flux, allowing for mane

• ufacturing tolera6ces on fuel pellets ind rods.

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NuclearEnthalpyRiseHotChannelFactor,isdefinedasthei g

ratio of the integral ~of linear power along the rod with the~

highest integrated. power to the average rod power.

• Y(Z)

Radial Peaking Factor, is defined as the ratio of peak power F

density to average power density in the horizontal plane at core elevation Z.

3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)

The limits on AXIAL FLUX' DIFFERENCE assure that the F boundenvelopeof2.10timesthenormalizedaxialpeakingha(Z) upper ctor is not exceeded during either normal operation or in the event of xenon redis-tribution following power charigesi Thifulllengthrodsmaybepo[sitionedwithinthecoreinaccordanceTarget flux diff

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with their respective insertion-limits and should be inserted near their nomal position for steady state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup condi-tions. Target flux differences for other THERMAL F0WER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

l NORTH ANNA'- UNIT 1 B 3/4 2-1 Amendment No. 3, 5, 16 i'

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4 POWER DISTRIBUTION LIMITS i

BASES 7

i Although it is intended that the plant will be operated.with the AXIAL FLUX DIFFERENCE within the + 5% target band about the target flux difference, during rapid plant THERMAL POWER reductions, ctitrol rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels, This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the devi-ation is limited. Accordingly, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumu-4 lative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of

.i the target band but within the limits of Figure 3.2-1 while at THERMAL POWER levels between 50% and.P % of RATED THERMAL POWER.

For THERMAL f

POWER levels between 15% an'd 50% of rated THERMAL POWER, deviations of the AFD outside of the target band are less significant.

The penalty of

.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.

Provisions for monitoring the AFD on an automatic basis 'are derived.. ~

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from the plant process compJter through the AFD' Monitor Alarm.

Th'e 135 -

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computer determines the one 'minutg average of-each'of the OPERABLE

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excore detector outputs and provides an alarm message immediately if--the AFD for at least 2 of 4 or 2'of 3 OPERABLE excore channels are outsideL-the target band and the THERMAL POWER is great'er than P THERMALPOWER..DuringoperationatTHERMALPOWERlevel[%ofRATED between 50% and P,i: and.15% and 50% RATED THERMAL POWER, the computer outputs an alarm ~

mbssage wi.en the penalty deviation accumulates beyond the limits 'of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.

Figure B 3/4 2-1 shows a typical monthly target band.

' 'i.

1 k

NORTH' ANNA - UNIT 1 B 3/4 2-2 Amendment No. 3, 6,ee,.:e 4

._j

3

+

i i:

I POWER DISTRIBUTION LIMITS BASES i

4

[

abnormalperturb'ationsingheradialpowershape,such.asfrom a.

rod misalignme'nt, effect F m re directly than F,

i aH q

l b.

although rod movement has a direct influence upon limiting F to withfn its limit', such control is not readily available tb 1

limit FaH, and errors in prediction for control power shape detected ifuring c.

4 startup physics tests can be compensated for in F byregtri-n is eting axial flux distritiutions.

This compensatioM for FAH less readily available.

3/4.2.4 QUADRANT POWER TILT. RATIO

~

distribution satisfies the design v,aluit assures.that the radi'al power. :. -

The quadrant power tilt ratio, lim

~

es used :iii'the power capability '3--

j analysis. Radial power distributio,n measurements >are made during start *,-

up-testing and periodically during power operation.

Q The limit of 1.02 at which corrective action is required provides i

DNB and linear heat generation -rate protection with x-y plane power i-til ts.

j-The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09.is provided to allow identificaticn

?4 and corretion of a dropp.ed or misaligned rod.

In the' event such action i

is rein-does not correct the tilt, the margin for uncertainty on Fg stated by reducing the power by 3 ' percent for each percent of tilt in excess of 1.0.

il 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 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-ll, H-3, H-13, L-5, L-ll, and N-8.

i l

t NORTH ANNA - UNIT 1

~

B 3/4 2-5 Amendment No.- 3. 5

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m-,

,-m.-w.~

_gw--,

.,,vy--. < -

.-er

-,w-.y,

l

_. _.. =. - ~. -.

- -. ~..

POWER DISTRIBUTION LIMITS BASES 3/4.2.5 DNB PARAMETERS The. limits on the DNB. related parameters assure that each of the i

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. -

l The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters thru instrument readout is, sufficient to enstire 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 indicat,ed. percent flow will provide sufficient

~ ~ ~ ~ -

verification.of flow rate on d'12 ho,ur basis.

?-

~

z.

3/4.2.6 AXIAL POWER DISTRIBUTION--

4 The limit on axial power ' distribution ensures that F will be controlled q

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

This additional. limitation on F is q

necessary in order to provide assurance that peak clad temperatures will 1

remain below the ECCS acceptance criteria limit of 2200 F in the event of a LOCA. The value for P is based on the cycle dependent potential violation of the F xK(Z) limit, whEre K(Z). is 'the graph shown in Figure 3.2-2.

The amount of pohential violation is detemined by subtracting i from the maximum _ ratio-of the predicted F (Z) analysis (flyspeck) results for a patticular fuel cycle n

to the F xK(Z) liihit.

This amount. of potential violation, in percent, is g

subtracted from 100% to detemine' the value for P,

If.P is equal to 100%,

no axial power distribution surveillance is required.

E will not exceed 100%..

e NORTH ANNA - UNIT 1 B 3/4 2-6 Amendment No. 3, E, 22, t 7 i'

a t

b

.D-

e' O

ADMINISTRATIVE CONTROLS j

~ :

b.'

Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition 'for operation established in the technical specific,ations.

c.

Abnormal degradation discovered in fuel cladding, reactor coolant pressure bodndary, or primary containment.

d.

Reactivityanomaliesinvolvingdisagreementwiththepredicted value of reactivity balance under steady-state conditions

--.during power operation greater than or equal to 1% ak/k; a calculated reactivity baiance indicating a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor

' period of less than 5 seconds or, if subcritical, an unplar.J reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.

- :.m e.

Failure or malfunction of 6ne.oi moreTomponents which prevent 4-or could prevent, by.itself, the fulfillment of the functiona6 requirements of system (s)'used to cope with accidents analyze 6 in the SAR.

2. -

f.

Personnel error or p~rocedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

g.

Conditions arising from natural or man-made events that, as a direct result of the event, require plant shutdown, operation of safety systems, or other protective measures required by technical spe'cifications.

h.'

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described,in the safety analysis report-or in the bases for the technical specifications that haye or could have permitted reactor opera-tion in a manner less conservative than assumed in the analyses.

i.

Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses in the safety analysis report or technical spdcifica-tions bases; or discovery during plant life of conditions NORTH ANNA _- (JNIT 1

~

6-17'

~.

..,. -.. ~. - - -. - - - -. --

- * ^ ~ *-

4 ADMINISTRATIVE CONTROLS not specifically c nsidered f.the safety analysis report or technical specifications nat require remedial action or corrective measures to prevent the existence or development of an unsafe condit$on.

THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events 1,isted below shall be the subject of written reports to the Director of the', Regional Office within 30 days of occurrence of the event.

The written report shall include, as a minimum, a completed copy of the licensee event report form.

Information provided on.the licensee event report form shall be ' supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

Reactor protection system or engineered safety feature instru-a.

ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillnent of the functional requirements of affected systems.

y.

7_

b.

Conditions leading to, operation in a-degraded mode permitted ~.tn by a limiting condition fo'r operation, or plant shutdown

- E, required by a liniting-condition for operation.

L' Observed inadequacies.in the implementation of administrative c.

or procedural controls which threaten to cause reduction of

^

degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d.

Abnormal degradation of systems other than those specified in item 6.9.1.8(c) above designed to contain radioactive materialresultingfro,mtpefissionprocess.

CORE SURVEILLANCE REPORT limit for Rated Thhrmal Power (FRTP) 6.9.1.10 The F y planes containing Bankt"D". control rods and in all unrodded core planes, the survefilance power level, P, for Technical Specifications 3.2.1 and 3.2.6, and the F f3yspeckbasis asdeterminedusingthe,definitionsandm0thodologyin WCAP 8385 and Westinghouse letter to NRC dated April 6',

1978, Serial No. NS-CE-1749 shall be provided to the Regional Administrator, Region II, with a copy to:

Director,' Office of Nuclear Reactor Regulation Attention: Chief, Core Performance Branch U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NORTH ANNA - UNIT 1 6'-18 Amendment No. 37

ADMINISTRATIVE CONTROLS (Continued) at least 60 days prior to cycle initial criticality.

In the event that the limits would be submitted at some other time during core life, they shall be submitted 60 days prior to the date the limits would become effective unless otherwise approved by the Commission.. :

RTP Any additional information needed to support the F and P submittal will be by request from the NRC and need not bE included in this report.

SPECIAL REPORTS e

6.9.2 Special reports shall-be submitted to the Regional Administrator, Region II, within the time peri.od specified for each report. These reports shall be submitted coverind the activities identified below

{

~

pursuant to the requirement of the applicable reference specification:

a.

Inservice Inspection Program Reviews shall be reported within 90 days of completion.

Specification 4.4.10.1.

5

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NORTH ANNA - UNIT 1 6-18a Amendment No. 17 l

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j.9 g

o UNITED STATES y

g NUCLEAR REGULATORY COMMISSION g

j WASHINGTON, D. C. 20555 4,**..* /

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.17 License No NPF-7 t

1.

The Nu~ clear Regulatory Commission (the Commission) has found that:

A.

The application for, amendment by Virginia Electric and Power Company (the licenseel dated December 15, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)'and the Commission's rules and regu-lations set forth in 10 CFR Chapter I; c

t_

B.

The facility will operate f.n confonnity with the application, 7.

the provisions of the Act,'and the rules and regulations of

!~

the Commission; E-C.

There is reasonable assurance (il 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 Commissio,n's regulations; D.

The issuance of this amendme~nt will not be inimical to the common defense and security or to the health and safety of the public; and g

E.

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

2.. Acco'rdingly, the license is$ame,nded by changes to the Tech,nical Specifications as indicatediin 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:

O b

/*

a

. g

- - + -.

... ~..

, (2) Technical Specificat' ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No.17, are hereby incorporated in thu 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

_/

n 4

R bert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

~

Changes to the Technical Specifications g_

Date of Issuance: February '5,1932

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ATTACHMENT TO LICENSE AMENDMENT AMENDt1ENT NO.17 TO FACILITY OPERATING LICENSE NO. NPF-7 i

DOCKET NO. 50-339 Replace the following page's of the Appendix "A" Technical Specifications

^

with the enclosed pags as indicated. ' The revised pages are identified by Amendment number and contains vertical lines indicating the area of change.. The corresponding ov,erleaf pages are also provided to maintain document completeness.

Pages t

3/4 2-1 i

3/4 2-2 3/4 2-4 i

3/4 2-7 l

3/4 2-17 3/4 2-18 3/4 2-19 i

3/4 2-20

~"-

1. i -

B3/4 2-2 B3/4 2-6

.t.

6-18

-i 6-1.8a

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3/4.2 POWER DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE (AFD) i LIMITING CONDITION FOR OPERATION 1

3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a 25% target band (flux difference units) about the target flux difference.

APPLICABILITY: MODE 1 ABOVE 50% RATFD THERMAL POWER

• l

~

ACTION:

a.

With the indicated AXIAL FLUX DIFFERENCE outside of the 15%

target band about the, target flux difference and with THERMAL j'

P,0WER:

i i

1.

Above P % of RATED TliERMAL POWER, within 15 minutes, where P =(0.9xP ); th,e value for P is established in the Core f

m m

Surveillance Report per Technical Specification 6.9.1.10.

a) Either restore the indicated AFD to within the 1

target band limits,, or g_

y,..

b), Reduce THERMAL POWER t'o less th n P % of RATED Y.

4' g

THERMAL POWER.

T 2.

Between 50% and P % of RATED THERMAL POWER:

g a) POWER OPERATION may continue provided:

1)

~

~

The indicated AFD has not been outside of the 15% target band for more than'1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty i

deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2) The indicdted AFD is within the limits shown on Figure 3.2-1..Otherwise, reduce THERMAL POWER to '.ess than 50% of RATED THERMAL POWER within-30 minutes and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55%

of RATED TilERMdL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b)

Surveillance te' sting of the Power Range Neutron Flux.

j Channels may be performed' pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Fi ure 3.2-1.

A t'otal of 16. hours of operation may be accumulated with the~AFD outside of the target band during this testing without penalty

.i deviation.

i f.

• See Special Test Exception 3.10.2.

NORTH ANNA - UNIT 2 3/4 2-1 Amendment No.17 p'

/

i

4 POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) b.

THERMAL POWER shall not be increased above P % of RATED THERMAL f

POWER unless the indicated AFD is within the 5% target band and ACTION 2.a.1, above has been satisfied.

THERMAL POWER sha'll not be increased above 50% of RATED THERMAL c.

POWER unless the indicated AFD has not been outside of the tS%

target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t SURVEILLANCE REOUIREMENTS L

4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERNIION above 14 of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore channel:

At least once per 7 days when the AFD Monitor Ala'rm is, OPERABLE',

1.

and

~

~

"~-

~T_*- -

tv 2.

At least once per hour' for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter restorthg the AFD Monitor Alarm to OPERABLE status.

U b.

Monitoring and loggirig the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24' hours and at least once per-30 ninutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.

The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.

4.2.1.2 The indicated AFD shall be ' considered outside of its 5% target band when at _least 2 OPERABLE excore channels are indi'cating the AFD to be outside the target band.

Penalty deviation,outside of the 25% target band shall be accumulated on a time basis of:

v One ' minute penalty deviation for each one minute of POWER OPERATION a.

outside of the target b)nd'at THERMAL POWER levels equal to or above 50% of RATED THERMAL P0bT.R, and f*

b.

One-half minute penalty deviation for each one pinute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

NORTH ANNA - UNIT 2 3/4 2-2 i

Amendment No.17 D

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O 1

~,

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

4. 2.1. 3 The target flux difference of each OPERABLE excore channel shall be determined by measurement at.least once per 92 Effective Full Power Days.

The provisions of Specificatio 4.0.4 are not applicable.

4.2.1.4 The target flux d'ifference shall be updated at least once per 31 Effective Full Power Days by 'either determining the target flux difference pursuant to 4.2.1.3 above or by T;inear interpolation between the most recently measured value and 0 percent at the end of the cycle life. The provisions of Specification 4.0.4 are not, applicable.

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F NORTH ANNA.-: UNIT 2 3/4 2-3

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10 20 30

.to 50 FLUX DIFFERENCE (.11W.

Figure 3.2-1 Axial Flux Difference Limits as a Function of fiated Thermal Power NORTH ANNA - UNIT 2 3/4 2-4 Amendment No.17

0 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (. Continued)

(b) At least once per 31 EFPD, whichever occurs first.

2.

When the F tid less than or equal to the F limit for the xy xy appropriate measured core plane, additional power distribution L

maps shall be taken and F compared to F and F at least xy xy xy once per 31 E5PD.

t t

e.

The F limits for Rated Themal Power (Fxy ) shall.be provided xy i

.for all core plane's containing Bank "D" control rods and all unrodded core planes, in a Core Surveillance Report per Technical Specification 6.9.1.10..

f.

The F limits of e, above, are not app,licable in the following xy

.g.

core plane regions as measure'd in percent.of core height from^t.

.the bottom of the fuel: I

~

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~

1.

Lower core region from 0 to 15%, inclusive.

2.

Upper core region from 85 to 100%, inclusive.

3.

Grid plane regions at 17.8 22%, 32.1 !2%,.46.4 2%,

60.6~!2% and 74.9 2%, inclusive (17 x ?17 fuel elements).

4.

Core pla:2 regions within 2% of core height (!2.88 inches) about the bank demand position of the bank "D" control rods,

~

0 g.

With F exceeding F xy xy 1.

The effects of F on F (Z) shall be evaluated to detemine if

.The(Z)iswithin IEs*limkt,and F

F (Z) limit shall,be reduced at least 1% for o.ach 1%

2.

q C

F exceeds F xy xy.

P 4.2.2.3 When F (Z) is measured for other than F detereination, an overall q

measured F (Z) shall be obtained from a power distribution map and increased q

by 3% tc account for manufacturing ^ tolerances and further increased by 5% to account for measurement uncertainty.

NORTH ANNA-UNIT 2 3/4 2-7 Amendment No. 1'7

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n:

... y .l. l i o.2 .- i . -.t..- i g } .z. J.- ..-. j.. t-i i j i ~. f - "l - e -I - {- l l I i- 't 0 2 4 6 8 10 12 14 ' CORE HEIGHT (FT) Figure,3.2-2 K(Z) - Normalized Fo(Z) as a Function of CoIe Height l 6 e ,e NORTH ANNA - UNIT 2 3/4 2-8

C. .l._ E L POWER DISTRIBUTION LIMITS-AXIAL POWER DISTRIBUTION LIMITING CONDITION FOR OPE' RATION 3.2.6 The axial power distribution shall be limited by the following relationship: h U [F (Z)]3 = j (R.)(P )(h 0$)(1.+ aj)(1.07) J L t Where: a. F (Z) is the normalized axial power distribution from thimble j j at core elevation Z. b. P is the fraction of RATED THERMAL POWER. - ~.,.. ~ g 3_ c. K(Z).is the function obtdined from F.igure-3.2-2 for 'l-a given core heighte location. . f, d. ii, for thimble j, is determined from at least n=6 in-core j flux maps covering the full configuration of permissible rod patterns'above P % of RATED THERMAL POWER in accordance l with: n -R) 1 I,

8. i )

j=) Where: t Meas p R)= Qi [Fjj(Z)] Max and [F ) (Z)] Max is the maximum value of the normalized 9 . axial distribution at elevation Z from thimble j in map 3/4 2-17 Amendment No.1 7 e NORTH ANNA - UNIT 2

l POWER DISTRIBUTION LIMITS j .j. LIMITING CONDITION FOR OPERATION (Continued) i which had a measured peaking factor without uncertainties eas or densification allowance of F 9 is the standard d.ev'iati'on_ associated with thimble j,. expressed as e. c) fraction or perceritage of R, and is derived from n flux maps from-a j . the relationship below; or,0.02, (2%) whichever is greater. e gI)2] 2 1 (R R E 3 c.= n-1 i=1 ^ Nj i ~ f. The factor 1.07 is compriseh 'of.'1.02 arid'5705 to ' account for thh- ~ axial power distribution initrumentation accuracy and the measure-ment uncertainty associated with F using the movable detector r, 9 ~ 1' system, respectively.- g. The fac' tor 1.03 is the engineering uncertainty factor. APPLICABILITY: MODE 1 ABOVE P % OF RATED THERMAL POWER, where.the value for m P is established in the Core Surveillanca Report per Technical Specification 6.9.1.10. i, ACTION: J With a F (Z) f acto'r exceeding'-F (Z)g by less than or equal to 4 a.

• reduce THERMAL POWER'one percent for every percent by which percent; P

1. The APDMS nay be out of service when surveillance for dgtermining power distribution maps is being performad.

NORTH ANNA - UNIT 2 3/4-2-18 Amendment No.; 7 .t g , y[

+- I POWER DISTRIBUTION LIMITS ACTION (Continued) which the F (Z) factor exceeds its limit within 15 minutes and within 4 the next two hours either reduce the F (Z) factor to within its limit y or reduce THERMAL POWER to P,% or less of RATED THERMAL POWER. l b. With a F.(Z) factor exceeding [F.(Z)]e by greater thari 4 percent, l reduce T$ERMAL POWER to P,% or ldss of RATED THERMAL POWER within 15 l minutes. t t 4 SURVEILLANCE REQUIREMENTS 4.2.6.1 F (Z) shall be determined t.o be within its limit by: j

r..

Either using the APDMS to,minito'r thi'iltiinbles ' required per }- a. Specification 3.3.3.8 at the following frequencies. t~- ~ i ~~ 1. At least once pert hours, and 2. 'Immediately and'at intervals of 10, 30, 60, 90~, 120, 240 and 480 minutes following: ~ a) Increasing the THERMAL POWER above P*% of RATED THERMAL l POWER, or b) Movement of control bank D" more than an accumulated { total of 5 st6p"s in any one direction. b. Or using the movable incore detectors at.the following frequencies' j when.the APDMS is inoperable: 7 1. At least once per: 8 hours, and e 2, _At intervals of 30, 60, 90, 120, 240_and 480 minutes ~ following: e l NORTH ANNA . UNIT 2 3/4 2-19 Amendme.nt No.17 .. s 8 3_' a

POWER DISTRIBUTION LIMITS ~ SURVEILLANCE REQUIREMENTS (Continued) ? a) Increasing the THERMAL POWER above P*% of RATED THERMAL POWER, or i b) Movement of control bank "D" more than an accumulated total of 5 steps in any one direction. t 4.2.6.2 When the movable incore detectors are used to monitor F (Z), j t at least 2 thimbles shall be monitored and an F (Z) accuracy equivalent j to that obtained from the APDM,5 shall be maintained. 3 .. r. _ _~ .m 1 ' i, ~; v NORTH ANNA - UNIT 2 3/4 2-20 Amendment No.17 mJ

~ f 3/4.2 POWER DISTRIBUTION LIMITS : 4 BASES t The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (a) maintaining the minimum DNBR in the core greater than or equal to 1.30 during normal operation,and iri short term transients, and (b) limiting the fission gas release, fuel pellet temperature & cladding mechanical properties to within assumed design criteria., In addition, limiting the peak linear power density during Condition I e'ents provides assurance that the initial v conditions ass 0med for the LOCA analys'es are met and the ECCS acceptance criteria limit of 2200 F is not exceedea. The definitions of certain hot channel and peaking factors as used in these specifications are as follows: F (Z) Heat Flux Hot Channel Factor, is defined as the maximum local 9 heat flux on the surface of a' fuel rod at-core elevation Z divided-l _' by the average fuel rod. heat flux, allowing for manufacturing tole"rances on fuel p'ellets and rods.' i ,] F NuclearEnthalpyRiseHothannelFactor,isdefinedastheratioIf g the integral of linear power along the rod with the highest integrated power to the average rod power. FxY(Z) Radial Peaking Factor, is defined as the ratio of peak power density -to average power density in the horizontal plane at core elevation Z. 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD). s. The limits on AXIAL FLUX DIFFERENCE assure that the F (Z) upper bound 0 envelope of 2.10 times the normalized axial peaking factor is not exceeded during either normal operation or irif the event of xenon redistribution following power changes. P Target flux difference is determined at equilibrium xerion conditions. The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady state operation at high power.avels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core barnup conditions. Target flux differences for other l NORTH ANNA - UNIT 2 B 3/4 2-1 W += =

e POWER DISTRIBUTION LIMITS BASES THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value', by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference val,ue'is hecessary to reflect core burnup considerations. Although'it is intended that the plant will be operated with the AXIAL FLUX DIFF.ERENCE within the + 5% target band about the target flux difference, during rapid plant THERMAL POWER red 6ctions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels. This deviation will not affect.the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited.' Accordingly, a 1 hour penalty deviation limit cumulative during the previous 24 hours is provided for operation outside. + of the target band but within the limits of Figure-3.2-1 while at THERMAL;iC _ POWER levels between 50% and P % of RATED ' THERMAL POWER. For THERMAL POWER, 'l levelsbetween15%and50%ofha.t'edTH'ERMALPOWER',deviationsoftheAFD.~l.' outside of the target band are 1,ess significant. The penalty of 2 hours E-actual time reflects this reduced significance. Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer determines the one minute average of each of the OPERABLE excore detector outputs and provider an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than P % of RATED THERMAL POWER. During operation at THERMAL r0WER f levels between 50% and P % and 15% and 50% RATED TWERMAL POWER, the computer f outputs an alarm message when the'penhlty deviation accumulates beyond the limits of 1 hour and 2 hours, respectively. Figure B 3/4 2-1 shows a typi' cal monthly target band. 1-a NORTH ANNA - UN'I'T 2 B 3/4 2-2 "*" Amendment No. 17

m. d i l* POWER DISTRIBUTION LIMITS i BASES When F is measured 4% is the appropriate experimental error allowance H for a full core map taken with the incore ' detection system. The specified limit for F also contains an 8% allowance for uncertainties which means that norma.1 j g j' operation will result in FaH.less than or equal to 1.55/1.08. The 8% allo'wance is based on the followirg coosiderations: l' r a. abnormal perturbations in the radial power shape, such as from rod ~ misalignment,effedtF m re directly than F, H g b. although rod movement Has a direct influence upon limiting F to g within its limit, such control is not readily available to limit N FAH, and c. errors in prediction for control power shape detected during startup g by. restrlicting axgal. flux physics tests can be comp.ensated for_jn F j; distributions. This compensation for F3g.is less readily a}ailable. 3/4.2.4 QUADRANT POWER TILT' RATIO ~5-I 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 star'.up testing and periodically during power operation. j l The limit of 1.02 at which coriective action is required provides DNB and i linear heat generation rate protection with x-y plane power tilts. The two hour time allowance hor operation with a tilt condition greater, 4 than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned rod. I,n the event such action.does not correct the tilt, the margin for uncertainty-on F is reinstated by, reducing the power by 0 ll

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

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 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 -symmetric l 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-ll,and N-8. 1 B 3/4 2-5 Amendment No. 15 ~ NORTH' ANNA - UNIT 2 i' ^ j , -.. ~. _..._..._I.,_...,_...._,.._.-.,..__ .,..-,.---.-___~4 . ~. -. -

~ g 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 envelope of operation assumed in the transient and iccident analyses. The limits are consistent with the initial FSAR assusptions and have been analytically ' demonstrated adequate to maintain a minimumi DNBR of 1.30 throughout each analyzed transient. The 12 hour periclic 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 hdpr basis. 3/4.2.6 AXIAL POWER DISTRIBUTION The limit on axial power distribution ensures that F will be controlled q and monitiored on a more exact basis through use of the APDMS when operating cbove..P,% of RATED THERMAL POWER. This additional limitation. on F is q necessary in order to provide assuiance that peak clad temperatures will remain below the ECCS acceptance criteria limit of 2200 F in the event of a LOCA. The value for P is based on 'the cycle dependent potential violation of the F xK(Z) limit, whEre KfZ) is the graph shown in Figure 3.2-2. The amount of pohential 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) 1.161t. This amount' of potential violation, in percent, is g subtracted from 100% to determine the value for P. If P is equal to 100%, no axial power distribution suiyeillance is required. p* will not exceed 100%. 1 P NORTH ANNA - UNIT 2 B 3/4 2-6 Amendment No.1 7 e

ADMINISTRATIVE CONTROLS b. Operation of the' unit or affected systems when any parameter or operation subject to a limiting condition for operation is. less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications. c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment. d. Reactivity anomalles involving disagreement with the predicted value - of reactivity balance!under steady-state conditions during power operation greater than or equal to 1% delta k/k; a ca'1culated reactivity balance indicatjng a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% ~ delta k/k; or occurrence of any unplanned criticality.

-t.

-5; _ e. Failure or malfunction.of one or more components which prevents or co'uld prevent, by itself, the fulfillment of the functiona.lirequirements of system (s) used, to cope with accidents analyzed in the SAR). f. Personnel error or procedural inadequacy which prevents or could prevent, by itself~, the fulfillment of the functional requir.ements of systems required to cope with accidents analyzed in the SAR. i g. Conditions arising from natural or man-made events that, as a direct result of the event, require plant shutdown, operation of safety systems, or other protective measures required by technical specifications h. Errors discovered in t'he transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases,for the technical specifications that have or could have permitted reactor operation in a manner less conserv'ative than assumed in the analyses. ~ i. Performanceofstruhtures, systems,orcomponentsthatrequires remedial action or torrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition. e e NORTH ANNA - UNIT 2 6-17 .~. +, ~ y 9 -

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ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of,the Regional Office within 30 days of occurrence i of the event. The written report shall include, as a minimum, a completed copy of the licensee event repcrt form. -Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the [; event. Reactor protection', system or engineered safety feature instru-a. '[ ment settings which are found to.be less conservative than it those established by the' technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems. b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation, or plant shutdown a.. required by a limiting condition for operation.- . s. _ " Observed inadequacies.in the implementation of administrative.T,1 c. or proccdural controls whi'ch threaten to cause reduction of T, degree of redundancy.provided in reactor protection systems or engineered safety feature systems. d. Abnormal degradation of systems other than those specified in item 6.9.1.8(c) above designed to contain radioactive i material resulting from the fission proceps. CORE SURVEILLANCE REPORT 6.9.1.10 The F limit for Rate,d Thermal Power (F ) in all core xy xy planes containing Bank "D" control rods and in all unrodded core planes, the surveillance power level, P, for Technical Specifications 3.2.1 and.3:2.6, and the F flyspeckbasisas determinedusingthedefinitionsandmeth0dology*inWCAP-8385 .andWestinghouseletter[to'NRCdatedApril6,1978,SerialNo. NS-CE-1749 shall be proyided. co the Regional Administrator, Region II, with a copy to: Director, Office of Nuclear Reactor Regulation ' Attention: Chief,' Core Performance IIranch. U. S. Nuclear Regulatory Celeission Washington, D. C. 20555 at least 60 days prior to-cycle initial criticality. In the event that the limits would be submitted at some other time during! core life, they shall be submitted 60 days prior 'to the date the ~11mits' would become effective unless otherwise exempted by the Commission. 6'-18 ..-Amendmen't No.I 7 e-NORTH ANNA - UNIT 2 ..u . i. . ~

ADMINISTRATIVE CONTROLS (Continued) ~ RTP Any additional infor'mation needed to support the F and j P submittal will be by request from the NRC and nEEd not bE, included in this report. SPECIAL FIPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. i 6.10 RECORD RETENTION In addition to the applicable r*ecord retention requirements of Title 10, Code of Federal Regulations, the followitng records shall be re.tained for at least the minimum period indicated. 6.10.1 The following records'shall be retained for at least five years: a. Records and logs of facility operation covering time interval at each~ power level. l --T. b. Records and logs of principal maintenance activities, inspections, repair and replaccment of principal items of equipment related:f6 nuclear safety. 'f. i I! g 4 li l NORTH ANNA - UNIT'2 6-18a Amendment No.

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