Text

Proposed Tech Specs,Supporting Implementation of Relaxed Power Distribution Control Methodology
	ML20195H375
Person / Time
Site:	North Anna
Issue date:	01/14/1988
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20195H364	List: ML20195H358; ML20195H375;
References
	NUDOCS 8801190284
	Download: ML20195H375 (31)
	v • d • e

i ATTACHMENT 2 TECHNICAL SPECIFICATION CHANGES l

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8801190284 880114 PDR ADOCK 05000338 P

DCD 130-JRH-23308-12

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference..................................

3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor...........................

3/4 2-5 3/4.1.;

Nuclear Enthalpy Hot Channel Factor....................

3/4 2-9 3/4.2.4 Quadrant Power Tilt Ratio..............................

3/4 2-12 3/4.2.5 DNB Parameters.........................................

3/4 2-14 1

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION........................................

3/4 3-15 3/4.3.3 MONITORING INSTRUMENTS Radiation Monitoring...................................

3/4 3-35 Movable Incore Detectors...............................

3/4 3-39 Seismic Instrumentation................................

3/4 3-40 Meteorological Instrumentation.........................

3/4 3-43 Auxiliary Shutdown Panel Monitoring Instrumentation....

3/4 3-46 Accident Monitoring Instrumentation....................

3/4 3-49 I

Fire Detection Instrumentation.........................

3/4 3-52 Loose Parts Monitoring System..........................

3/4 3-56 Radioactive Liquid Effluent Monitoring Instrumentation.

3/4 3-58 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-65 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCUI.ATION Startup and Power Operation............................

3/4 4-1 Hot Standby............................................

3/4 4-2 Shutdown...............................................

3/4 4-3 Isolated Loop..........................................

3/4 4-4 Isolated Loop Startup..................................

3/4 4-5 NORTH ANNA - UNIT 1 IV

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INDEX i

BASES SECTION PAGE 3 / 4. 0 AP P L I CAB I L I TY.............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.......................................B 3/4 1-1 3/4.1.2 BORATION SYSTEMS.......................................B 3/4 1-2 3/4.1.3 MOVEABLE CONTROL ASSEMBLIES............................B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXI AL FLU X D I F F ER EN CE.................................. B 3/4 2-1 3/4.2.2 and 3/4.2.3 Heat Flux and Nuclear Enthalpy E>t Channel Factors...................B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATI0..............................A 3/4 2-5 3/4.2.5 D N B P ARAM ET E RS......................................... B 3/4 2-6 l

NORTH ANNA - UNIT 1 XII

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 the allowed operational space defined by Figure 3.2-1.

l APPLICABILITY: MODE 1 AB0VE 50% RATED THERMAL POWER ACTION:

a.

With the indicated AXIAL FLUX DIFFERENCE outside of the Figure 3.2-1

limits,

1) Either restore the indicated AFD to within the Figure 3.2-1 limits within 15 minutes, or

2) Reduce THERMAL POWER to less than 50% of RATED THERHAL POWER within 30 minutes and reduce the Power Range Neutron Flux - High Trip setpoints to less than or equal to 55 percent of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

THERMAL POWEk shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the Figure 3.2-1 limits.

NORTH ANNA - UNIT 1 3/4 2-1

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS i

4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 50% of RATED THERMAL POWER by:

l a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1.

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status, b.

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hout for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes 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 limit when at least 2 OPERABLE excore channels are indicating the AFD to be outside of the limit shown in Figure 3.2-1.

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NORTH ANNA - UNIT 1 3/4 2-2

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NORTH ANNA - UNIT 1 3/4 2-3

Figure 3.2-1 is provided in the Core Surveillance Report as per Technical Specification 6.9.1.7.

Figure 3.2 Axial Flux Difference Limits as a Function of Rated Thermal Power KORTil ANNA - l' NIT 1 3/4 2-4

POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR - F (Z)

LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationships:

q F (Z) s [2.151 [K(Z)] for P > 0.5 q

P F (Z) s (4.30] [K(Z)] for P s 0.5 q

where P r-THERMAL POWER RATED THERMAL POWER and K(Z) is the function obtained from Figure 3.2-2 for a given core height location.

APPLICABILITY: MODE 1.

ACTION:

With F (Z) exceeding its limitt j

9 a.

Reduce THERMAL POWER at least 1% for each 1% v (Z) exceeds the l

g limit within 15 minutes 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 ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoint (value of K ) has been reduced at least 1% (in AT span) 4 for each 1% F (Z) exceeds the limit, q

b.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POER above the reduced limit required by a. above; THERMAL POWER may then be increased provided F (Z) is demonstrated q

through incore mapping to be within its limit.

NORTH ANNA - UNIT 1 3/4 2-5

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS - 4.2.2.1. The provisions of Specification 4.0.4 are not

.icable.

4.2.2.2 F (Z).shall be evaluated to determine if F (Z) is within its q

-limit by:

a.

Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b.

Increasing the measured F (Z) component of the power distribution map n

by 3% to acccunt for maHufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties, c.

Satisfying the following relati.>nship:

x K(z) for P > 0.5 0 (z) s 2.15 F

P x N(z)

F "(z) s 2.15 x K(z) for P s 0.5 0

N(z) x 0.5 where F "(z) is the measured F (z) increased by the allowances for 9

manufackuring tolerances and measurement uncertainty, 2.15 is the Fq limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL POWER, and N(z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.

This function is given in the Core Surveillance Report as per Specification 6.9.1.7.

d.

Measuring F "(z) according to the following schedule:

9 1.

_Upon achieving equilibrium conditions after exceeding the THERMAL POWER at which F (z) was last determined by 10% or more of RATED q

THERMAL POWER *, or 2.

At least once per 31 effective full power days, whichever occurs first.

e.

With measurements indicating fF (z) maximum over z K(z) has increased since the previous determination of F "(z) either of the 9

following actions shall be taken:

During power escalation, the power level may be increased until a power level l

for extended operation has been achieved and a power distribution map obtained.

NORTH ANNA - UNIT 1 3/4 2-6 L

D.

POWER DISTRIBUTION LIMITS SURVEILLANCE' REQUIREMENTS (Continued) 1.

F "(z) shall be increased by 2% over that.specified in 4.2.2.2.c, o9 dkys(z) shall be measured at least once per 7 effective full power 2.

F until 2 successive maps indicate that maximum F "(z) q is not increasing.

over z K(z) f.

With the relationships specified in 4.2.2.2.c above not being satisfied:

1.

Calculate the percent F (z) exceeds its limit by substracting one n

from the measurement / limit ratio and multiplying by 100:

f 1

maximum F "(z)

-1 x 100 for P 2 0.5 q

over z 2.15

(

P x N(z) maximum F "(z)

-1 x 100 for P < 0.5 9

I i over z 2.15 x (ggz

(

0.5 x N(z) 2.

Either of the following actions shall be taken:

a.

Power operation may continue f.covided the AFD limits of Figure 3.2-1 are reduced 1% AFD for each percent F (z) q exceeded its limit, or b.

Comply with the requirements of Specification 3.2.2 for F (z) exceeding its limit by the percent calculated above.

g.

The limits specified in 4.2.2.2.c, 4.2.2.2.e, and 4.2.2.2.f above are not applicable in the following core plane regions:

1.

Lower core region 0 to 15 percent inclusive.

2.

Upper core region 85 to 100 percent inclusive.

4.2.2.3 When F (z) is measured for reasons other than meeting the requirements n

of Specification 4.2.2.2, an overall measured F (z) shall be obtained from a n

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

NORTH ANNA - UNIT 1 3/4 2-7 l

THIS PAGE DELETED NORTH ANNA - UNIT 1 3/4 2-16

i PAGES 3/4 2-17 AND 3/4 2-18 ARE DELETED NEXT PAGE IS 3/4 3-1 NORTH ANNA - UNIT 1 3/4 2-17

4 THIS PAGE DELETED l

NORTH ANNA - UNIT I 3/4 3-54

7 THIS PAGE DELETED I

fiORTH ANNA - UNIT 1 3/4 3-55

EPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group

height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, and 3.2.4 may be suspended during the l-performance of PHYSICS TESTS provided:

a.

The THERMAI POWER is maintained s 85% of RATED THERMAL POWER, and b.

The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: MODE 1.

ACTION:

With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6 and 3.2.4 are l

suspended, either:

a.

Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or i

b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1 SURVEILLANCE 2EQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be s 85% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 The Surveillance Requirements of Specifications 4.2.2 and 4.2.3 shall be performed at the following frequencies during PHYSICS TESTS:

a.

Specification 4.2.2 - At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Specification 4.2.3 - At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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NORTH ANNA - UNIT 1 3/4 10-2

3/4.2 POWER DISTRIBUTION LIMITS 3

BASES 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 from going beyond the design limit DNBR during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature 8. 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.

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 q

heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods.

F"H Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.

'~

l 3/4 2.1 AXIAL FLUX DIFFERENCE (AFD)

The limits on AXIAL FLUX DIFFERENCE assure that the F (Z) upper bound q

envelope, as given in Specification 3.2.2, is not exceeded during either normal operation or in the event of xenon redistribution following power changes.

1 NORTH ANNA - UNIT 1 B 3/4 2-1

POWER DISTRIBUTION LIMITS BASES I

' 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 provides an alarm message immediately if the AFD for at least 2 of 6

4 or 2 of 3 OPERABLE excore channels are outside the alloved AI-power operating.

space and the THERMAL POWER is' greater than 50% of RATED THERMAL POWER.

a k

NORTH ANNA - UNIT I B 3/4 2-2

,.2 THIS PAGE DELETED NORTH ANNA - UNIT I B 3/4 2-3

POWER DISTRIBUTION LIMITS BASES

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

misalignment, effect rdH "

Y Q'

b. although rod movement has a direct influence upon limiting F to n

w thin its limit, such control is not readily available to IImit AH, and

c. errors in prediction for control power shape detected during startup physics tests can be compensated for in F by restricting axial flux q

distributions.

This compensation for F is less readily available.

SH 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 (1.57 and 1.59 for thimble and typical cells, respectively) and the limiting design DNBR values (1.39 for thimble cells and 1.42 for typical cells).

The applicable value of rod bow penalties can be obtained from the FSAR.

M The hot channel factor F is measured periodically and increased by a cycleandheightdependentpowe9(fketor,N(Z),toprovide assurance that the limit on the hot channel factor, F (Z),

is met.

N(Z) accounts for the 0

non-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.

3/4.2.4 QUADRANT POWER TILT RATIO

.i The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability i

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 j

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 n

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

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incare 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 I

E-5, E-11. H-3, H-13, L-5, L-11, and N-8.

NORTH ANNA - UNIT 1 B 3/4 2-5

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 normr.1 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 greater than the design limit throughout each analyzed transient.

Measurement uncertainties must be accounted for during the periodic surveillance.

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 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

NORTH ANNA - UNIT I B 3/4 2-6

\\

INSTRUMENTATION BASES 3/4.3.3.6 P0ST-ACCIDENT INSTRUMENTATI_0N The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

j In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

l r

3/4.3.3.9 LOOSE PARTS MONITORING SYSTEM f

OPERABILITY of the Loose Parts Monitoring System provides assurance that loose parts within the RCS will be detected.

This capability is designed to ensure that loose parts will not collect and create undesirable flow blockages.

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

- ADMINISTRATIVE CONTROLS CORE SURVEILLANCE REPORT 6.9.1.7-The' N(Z) function for normal operation and the Axial Flux Difference limits (T.S. Figure 3.2-1) shall be provided to the NRC in accordance with the applicable provisions of 10CFR50.4 at least 60 days prior _to cycle initial criticality unless otherwise approved by the Commission by letter.

In the event that this information would be submitted at some other time during the core i

life, it shall be submitted 60 days prior to the date the information would become effective unless otherwise approved by the Commission by letter.

Any information needed to support N(Z) and/or the Axial Flux Difference limits will be by request from the NRC and need not be included in this report.

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NORTH ANNA - UNIT 1 6-18

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.8 Routine Radiological Environmental Operating Reports ccvering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison (as appropriate) with preoperational studies, operational controls, and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1,

November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps **

covering all sampi ng locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the sampling scheduled of Table 4.12-1 and discussion of all analyses in which the LLD required by Table 4.12-3 was not achievable.

A single submittal may be made for a multiple unit station.

One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

NORTH ANNA - UNIT 1 6-19

ATTACHMENT 3 CORE SURVEILLANCE REPORT

NORTH ANNA UNIT 1 CYCLE 7 CORE SURVEILLANCE REPORT This Core Surveillance Report is provided in accordance with Section 6.9.1.7'of the North Anna Unit 1 Technical Specifications.

The burnup-dependent Cycle 7 N(z) function for Technical Specification 4.2.2.2.G is shown in Figures 1-4.

N(z) was calculated according to the i

procedure of VEP-NE-1-A for burnups greater than 3000 MWD /MTU.

The N(z) function

will be used to confirm that the heat flux hot channel factor, FQ(z), will be limited to the Technical Specifications values of 2.15 K(z)

FQ(z) s ----------,

P > 0.5 and P

FQ(z) s 4.30 K(Z),

P s 0.5.

The Cycle 7 Axial Flux Difference (AFD) limits for Technical Specification 3.2.1 are shown in Figure 5.

These limits were calculated according to the methods of VEP-NE-1-A.

The limits on Axial Flux Difference assure that the FQ(z) upper bound envelope is not exceeded during either normal operation or in the event l

of xenon redistribution following power changes, i.

I i

The N(z) function, when applied to a power distribution measured under equilibrium conditions, demonstrates that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFR50.46.

FIGURE 1 - N(Z) FUNCTION FOR N1C7 AT 2893 W FROM 3000 to 5000 SO/MTU BURNUP TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)

(FEET) 1.8 1.166 2.0 1.160 N

2.2 1.153 2.4 1.146 0

2.6 1.138 gj$

2.8 1.131

[

3.0 1.124 3.2 1.123 Q

3.4 1.126 0

3.6 1.130 3.8 1.132 11.4' 4.0 1.132

[

4.2 1.:131 I

4.4 1.128 4.6 1.123 4.8 1.122 0 l.3 5.0 1.127 l

5.2 1.135 5.4 1.146 g

5.6 1.156 N

5.8 1.164 6.0 1.171 1,2 '

6.2 1.175 y

g-g 6.4 1.178

/

s' s

9 i

\\

v 6.6 1.180

/,-

6.8 1.184

\\

?

[

x.%

7.0 1.187 I 1. I 7.2 1.188 a

7.4 1.186 l

7.6 1.181 p

7.8 1.176

~

L l

8.0 1.171 d

I 8.2 1.164 l J,0' 8.4 1.157

,,,,,,,,j,,,,,,,,,,,,,,,,,,,,,,,,

E ii.,

8.6 1.154 R

0 2

4 6

.S 10 12 8.8 1.154 9.0 1.151 QRE HEIGHT (FEET) 9:2 1:149 94 1 147 9.6 1.148 9.8 1.151 10.0 1.156 10.2 1.160

FIGURE 2 - N(Z) FUNCTION FOR NIC7 AT 2893 Mi FROM 5000 to 7000 M0/MTU BURNUP TOP MO BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)

(FEET) 1.8 1.166 2.0 1.160 N

2.2 1.153 2.4 1.146 0

2.6 1.138 N 1. 5 2.8 1.131 3.0 1.124

[

3.2 1.123 0

3.4 1.126 0

3.6 1.130 3.8 1.132 l j,4 4.0 1.132 b

4.2 1.:131

4 1.128 l

4.~

1.123 g

4.8 1.122 01.3 5.0 1.127 5.2 1.135 l

5.4 1.146 g

5.6 1.156 U

5.8 1.164 6.0 1.171 j ')

W

[h 6.!

!lf78

)

N

/

%s 6.6 1.180 s

0 j

\\

y/

6.8 1.184

(

j-7.0 1.187 I 1.1 '

7.2 1.188 7.4 1.186 l

7.6 1.181 E

7.8 1.176 L

8.0 1.171 8.2 1.164 l l ' ('(

8.4 1.157

]......j...,,,,,,,,,,,,,.....,z 8.6 1.154 t.

R 0

2 4

6

.S 10 12 8.8 1.154 9.0 1.151 9.2 1.149 COREHEIGHT(FEET) 9.4 1.147 9.6 1.148 9.8

1. 51 10.0 1.156 10.2 1.160 J

FIGURE 3 - N(Z) FUNCTION FOR NIC7 AT 2893 MW FROM 7000 to 15000 PMD/MTU BURNUP TOP AM) BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)

(FEET) 1.8 1.173 2.0 1.165 N

2.2 1.157 2.4 1.148 0

2.6 1.139 N l' b' 2.8 1.132 3.0 1.125

[

3.2 1.123 g

3.4 1.125 0

3.6 1.130 3.8 1.132 l 1,4 '

4.0 1.132 b

4.2 1:130 4.4 1.130 l

4.6 1.132 g

4.8 1.136 0 l.I 5.0 1.145 5.2 1.158 l

5.4 1.173 jj 5.6 1.183 5.8 1.188 N

m

/

\\

6.0 1.193 l ' '?

6.2 1.196

/

K 6.4 1.204 N

/

D' 6.6 1.211

'x

/

0 i

l

{

\\

/

6.8 1.217 j-7.0 1.220 1

7.2 1.222 I l.I j 7.4 1.222 l

7.6 1.221 4

P 7.8 1.218 l-l 8.0 1.214 4

l.

l l

8.2 1.209 l l,(t !

8.4 1.201

,,,,l,,,,

e

,,,,iiii, 8.6 1.192 L

R 0

2 4

6 S

10 12 8.8 1.181 9.0 1.166 9.2 1.155 COREHEIGHT(FEET) 9.4 1.150 9.6 1.152 9.8 1.155 10.0 1.160 10.2 1.163

FIGURE 4 - N(Z) FUNCTION FOR N1C7 AT 2893 MW FROM 15000 M 0/MTU BURNUP TO EOL TOP #0 BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)

(FEET) 1.8 1.173 2.0 1.165 N

2.2 1.157 2.4 1.148 0

6 4

N15 2.8 1.133 3.0 1.126 L

3.2 1.123 Q

3.4 1.117 V

3.6 1.114 3.8 1.115 l 1. 4 4.0 1.117

[

4.2 lil19 I

4.4 1.'124 4.6 1.130 8

4.8 1.137 R 1.3 5.0 1.143 l

5.2 1.158 5.4 1.173 y

5.6 1.183 N

5.8

188 m

/

\\

6.0 1.193

{ ' '7

/

\\

6.2 1.196 y

0

,\\

[

6.4 1.204

'v' 6.6 1.211

/

l

\\

/

6.8 1.217 b

7.0 1.220 I l. 4 7.2 1.222 I

7.4 1.222 l

7.6 1.221 p

4 7.8 1.218 L

8.0 1.214 8.2 1.209 l 1,0 8.4 1.201 ii....,,,,,

8.6 1.192 l

R 0

2 4

6 8

10 12 8.8 1.181 9.0 1.166 92 1'155 COREHEIGHT(FEET) 9.4 1.150 9.6 1.152 9.8 1.155 10.0 1.160 10.2 1.163

FIGURE 5 - AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER FROM 3000 SO/MTU BURNUP to EOL FOR NORTH ANNA UNIT 1 CYCLE 7 P

E R

C 120 !

E I

N 110 I T

(-12,1001

[4,1 30)

[

}

0 I

f 90 Uraccep~.able p

30 j Operation T

70

/

E O

60

^=ceotable o"ero ti m 1

\\

1 30 g

(-37,50)

(20,50)

E 40 R

a h.

A I

20]!

L P

10!

O I

I W

0 !,

E i

3

-50

-30

-10 10 30 50 FLUXOlFFERENCE(DELTA-l) PERCENT J

-~ -

,a ATTACHMENT 4 APPLICATION FEE I

i n

I i

n 9

I i

)

P 130-JRH-23308-14

-

ML20195H375

Text

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