ML20039C031

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Proposed Tech Spec Changes Re Power Distribution Limits
ML20039C031
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 12/15/1981
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20039C027 List:
References
NUDOCS 8112280337
Download: ML20039C031 (38)


Text

.

i ATTAC10ENT 2 Proposed Technical Specifications Power Distribution Limits Changes For North Anna Unit Nos. 1 and 2 e

8112280337 811215' PDR ADOCK 05000338 P PDR

i . ,

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 15% target band (flux difference units) about the target flux difference.

APPLICABILITY: MODE 1 ABOVE 50% RATED THERMAL POWER

  • ACTION:
a. With the indicated AXIAL FLUX DIFFERENCE outside of the 15%

target band about the target flux difference and with THERMAL POWER:

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

Pf =(0.9xP,); the value for P, is established in the Core Surveillance Report per Technical Specification 6.9.1.10.

a) Either restore the indicated AFD to within the target band limits, or b) Reduce THERMAL POWER to less than P f% of RATED THEPMAL POWER.

2. Between 50% and P % of RATED THERMAL POWER:

f a) POWER OPERai10N may continue provided:

1) The indicated AFD has not been outside of the 15% target band for more than 1. hour penalty deviation cumulative during the previous 24 c

hours, and 1

2) The indicated AFD is within the limits shown on l 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-t High Trip Setpoints to less than or equal to 55%

l of RATED TilERMAL 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 testing 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 total 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.

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

. - . . . .... ..~... - ...... ... -. .

.7

i . ,

POWER DISTRIBUTION LIMITS LIMITING CONDITION M)R OPERATION (Continued)

b. THERMAL POWER shall not be increased above P %f of RATED THERMAL 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 outside of the 25%

target band for more than I 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 />.

SURVEILLANCE REQUIREMENTS 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 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status,
b. Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each 4

OPERABLE excore channel 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 /> and at least once per 30 minutes thereaf ter, 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 indicating the AFD to be outside the target band. Penalty deviation outside of the 15% target band shall be accumulated on a time basis of:

a. One minute penalty deviation for each one minute of POWER OPERATION cutside of the target band at THERMAL POWER levels equal 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 THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

NORTH ANNA - UNIT 1 3/4 2-2

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RL=RU+ /

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  • r n1= - t:

2 q: . : ::n .!nnur: :g .-- _:

0- - -

-50 -40 -30 -2u -10 0 10 20- 30 40 50 FLUX DIFFERENCEL111%

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

s POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

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

C

2. When the F,y is less than or equal to the limit for the appropriate measured core plane, additional power-distribution maps shall be taken and F,C compared to F, and F, at least once per 31 EFPD.
e. The F limits for Rated Thermal Power (FXyRTP) shall be provided i XY l 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 r.ot applicable in the following core plane regions as measured in percent of core height from the bottom of the fuel:
1. Iower core region from 0 to 15%, inclusive.

~2. Upper core region from 85 to 100%, inclusive.

3. Grid plane regions at 17.8 12%, 32.1 i2%, 46.4!2%,

60.6 2% and 74.912%, inclusive (17 x 17 fuel elements).

4. Core plane regions within 12% of core height (22.88 inches) about the bank demand position of the bank "D" control rods.
g. With Fgy exceeding F, the effects of F,y on F q(Z) shall be evaluated to determine ifqF (Z) is within its limit.

4.2.2.3 When qF (Z) is measured for other than F,y determination, an overall measured qF (Z) shall be obtained from a 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

s.. < ,

POWER DISTRIBUTION LIMITS, AXIAL POWER DISTRIBUTIO11 LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following relationship:

F3 (Z) g = (R )(P )(1.03)(1 + c )(1.07)

)

Where:

a. F (Z) is the normalized axial power distribution fron. thimble j at core elevation Z.
b. P is the fraction of RATED THERMAL POWER.

K(Z) is the function obtained from Figure 3.2-2 for c.

a given core height location.

d. ' R , for thimble j , is determined from at least n=6 incore flu:: maps covering the full configuration of permissible rod patterns above P % of RATED THERMAL POWER in accordance with:

n

~

j ij i=1 Where: ,,

R =- Ei t ij F (Z) g and F (Z) g is the maximum value of the normalized axial distribution at elevation Z from thimble j in map i which had a measured peaking factor without uncertainties or densification allowance of F q eas ,

3 NORTH ANNA - UNIT 1 3/4 2-16

i. <,

POWER DISTRIB1TIION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

e. o is the standard deviation associated with thimble j , expressed 3

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.

n oj .

1 E

.n-1 i=1(Rj -R ij) _

R j

f. 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.

g. Tha factor 1.03 is the engineering uncertainty factor.

APPLICABILITY: MODE 1 ABOVE P % OF RATED THERMAL POWER , where the value for P, is established in the Core Surveillance Report per Technical Specification 6.9.1.10.

ACTION:

a. With a F (Z) factor exceeding F (Z) g by less than or equal to 4 percent, reduce THERMAL POWER one percent for every percent by which the F (Z) factor exceeds its limit within 15 minutes and within the next two hours either reduce the F (Z) factor to within its limit or reduce THERMAL POWER to P,% or less of RATED THERMAL POWER.
b. With a F (Z) factor exceeding F3 (Z) 3 by greater than 4 percent, 3

reduce THERMAL POWER to P,% or less of RATED THERMAL POWER within 15 minutes.

  1. The APDMS may be out of service when surveillance for determining i

power distribution maps is being performed.

NORTH ANNA - UNIT 1 3/4 2-17 I , . - - - .

i* ,.

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

a. Either using the APDMS to monitor the thimbles required per Specification 3.3.3.8 at the following frequencies.
1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 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 POWER, or

  • b) Movement of control bank "D" more than an accumulated total of 5 steps in any one direction.
b. Or using the movable incore detectors at the following fre-quencies when the APDMS is inoperable:
1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
2. At intervals of 30, 60, 90,120, 240 and 480 minutes following:

a) Increasing the THERMAL POWER above P % of RATED THERMAL POWER, or

  • b) Movement of control bank "D" more than an accumulated total of 5 steps in any one direction.

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

at least 2 thimbles shall be monitored and an F (Z) accuracy equivalent to that obtained from the APDMS shall be maintained.

NORTH ANNA - UNIT 1 3/4 2-18 1 _

POWER DISTRIBUTION LIMITS BASES Although it is intended that the plant will be operated with the AXIAL FLUX DIFFERENCE within the 15% target band about the target. flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels.

j This deviation will not affect the xenon redistribution sufficiently to change 7

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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumulative 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 i outside of 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% and 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 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 OPERABLE excore channels are outside the. target band and the THERMAL POWER is greater than P % of RATED THERMAL POWER. During operation at THERMAL POWER ,

f levels between 50% and P %f and 15% and 50% RATED THERMAL POWER, the computer

outputs an alarm message when the . penalty deviation accumulates beyond the

{ limits of I hour 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.

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

u..___....._._n . _. ,.,.....m_-._.

. _,;. a._._ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____

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 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.

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 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.

3/4.2.6 AXIAL POWER DISTRIBUTION The limit on axial power distribution ensures that F will be controlled q

and monitored on a more exact basis through use of the APDMS when operating above P,% of RATED THERMAL POWER. This additional limitation on Fq is necessary in order to provide assurance that peak clad temperatures will remain below the ECCS acceptance criteria limit of 2200 F in the event of'a LOCA. The value for P is based on the cycle dependent potential violation of the FgxK(Z) limit, whEre K(Z) is i.he graph shown in Figure 3.2-2. The amount of pocential violation is determined by subtracting 1 from the maximum ratio of the predicted F n(Z) analysis (flyspeck) results for a particular fuel cycle to the Fg xK(Z) ISit. This amount of potential violation, in percent, is subtracted from 100% to determine the value for P . If P is equal to 100%,

no axial power distribution surveillance is required. [ "will not exceed I 100%.

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

s *

  • ADMINISTRATIVE CONTROLS 2

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.

THIRTY-DAY WRITIEN REPORT t

6.9.1.9 The types of events listed below shall be the subject of written reports of to the Director of the Regional Office within 30 days of occurrence the event.

i copy of the licenseeThe written event report report shall form.include, as a minimum, a completed Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material event. to provide complete explanation of the circumstances surrounding the a.

Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which it 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 required by a limiting condition for operation.

c. Observed inadequacies in the implementation of administrative 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 material resulting from the fission process.

l CORE SURVEILLANCE REPORT 6.9.1.10 The Fxy limit for Rated Thermal Power (F xy ) in all core 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 Fq f"yspeck basis shall be provided to the Director of the Regional Office of Inspection and Enforcement, with a copy to;

! Director, Office of Nuclear Reactor Regulation

Attention
Chief of Core Performance Branch

' L. S. Nuclear Regulatory Commission l

Washington, D. C. 20555 l

I NORTH ANNA - UNIT 1 6-18 i

7_..._..-...--..------ -... ~ ~~- .-~ ~ - ~ ~ ~~ - - ~ ~ ~

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 exempted

-by the Commission.

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

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Regulatory Operations Regional Office within the time period specified for each report.

These reports shall be submitted covering 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.

l l

f NORTH ANNA - UNIT 1 6-18a

a * *.

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

LIMITING CONDITION FOR OPEU TION 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% RATED THERMAL POWER

  • ACTION:

a.

With the indicated AXIAL FLUX DIFFERENCE outside of the 15%

target band about the target flux difference and with THERMAL POWER:

{ 1. Above P % of RATED THERMAL POWER, within 15 minutes, where Pf =(0.9xP,); the value for P, is established in the Core Surveillance Report per Technical Specification 6.9.1.10.

4 a) Either restore the indicated AFD to within the target band limits, or b) Reduce THERMAL POWER to less than P f% of RATED THERMAL POWER.

2. Between 50% and P %g of RATED THERMAL POWER:

a) POWER OPERATION may continue provided:

1) The indicated AFD has not been outside of the 15% target band for more than I 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 indicated 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 .o 55%

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 testing 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 total 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 2 3/4 2-1 J

_ , , - * ~ * * ' ~ * ' *' *

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

1 s  ! .

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) i- b.- THERMAL POWER shall not be increased above P % of RATED THERMAL f

i POWER unless the indicated AFD is within the 15% 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 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 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 />.

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

a. Monitoring the indicated AFD for each OPERABLE excore channel:

4

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hour for the first 24 i

hours and at least once per 30 minutes thereaf ter, when the AXIAL i

FLUX DIFFERENCE Monitor Alarm is inoperable. The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during i

J the interval preceding each logging.

4.2.1.2 The indicated AFD shall be considered outside of its 15% target band

! when at least 2 OPERABLE excore channels are indicating the AFD to be outside the-target band. Penalty deviation outside of the 15% target band shall be accumulated on a time basis of:

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

1 4

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

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t FLUX DIFFERENCE (All".

l Figure 3.2-1 Axial Flux Difference Limits as a Function of Rated Thermal Powc-I NORTH ANNA - UNIT 2 3/4 2-4

e POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

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

2. When the F is less than or equal to the F limit for the appropriate measured core plane, additional power distribution maps shall be taken and F compared to F and F at least once per 31 EFPD.
e. The F limits for Rated Thermal Power (F RTP) shall be provided 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 core plane regions as measured in percent of core height from the bottom of the fuel:
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 !2%, 32.1 12%, 46.412%,

60.612% and 74.9!2%, inclusive (17 x 17 fuel elements).

4. Core plane regions within 12% of core height (!2.88 inches) about the bank demand position of the bank "D" control rods.

C exceedingFxk

g. With F
1. The effects of F on F (Z) shall be evaluated to determine if F
2. T3e(Z)iswithinIlslim9t,and F (Z) limit shall be reduced at least 1% for each 1%

q F exceeds F 4.2.2.3 When qF (Z) is measured for other than F determination, an overall measured F (Z) shall be obtained from a power distribution map and increased 9

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

NORTH ANNA-UNIT 2 3/4 2-7

t - .

POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION 3.2.6 _ The axial power distribution shall be limited by the following relationship:

l l

t

=

F$ (Z) 8 (R )(P )(1.03)(1 + a )(1.07)

Where:

a. F)(Z) is the normalized axial power distribution from thimble j at core elevation Z.
b. P is the fraction of RATED THERMAL POWER.
c. K(Z) is the function obtained from Figure 3.2-2 for a given core height location,
d. R , for thimble j, is determined f rom at least n=6 incore flux maps covering the full configuration of permissible rod patterns above P %"of RATED THERMAL POWER in accordance with:

1 R

3

=

,E R gj i=1 Where: , ,,

R =

ij F (Z) and F (Z) is the maximum value of the normalized axial distribution at elevation Z from thimble j in map i NORTH ANNA - UNIT 2 3/4 2-17

. o .

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) which had a measured peaking factor without uncertainties or densification allowance of eas ,

e. c) is the standard deviation associated with thimble j, expressed 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.

n

~1 1/2 j .n-1 i=1(RZ 3

-Rg3)2 R

j

f. 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 Fqusing the movable detector system, respectively.
g. The factor 1.03 is the engineering uncertainty factor.

APPLICAEILITY: MODE 1 ABOVE P,% OF RATED THERMAL POWER *, where the value for P, is established in the Core Surveillance Report per Technical Specification 6.9.1.10.

ACTION:

a.

With a F)(Z) factor exceeding F)(Z) g by less than or equal to 4 percetit, reduce THERMAL POWER one percent for every percent by which

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

NORTH ANNA - UNIT 2 3/4 2-18

, .. . .,  : -- .=. =: : : - - - -

N r .

POWER DISTRIBUTION LIMITS ACTION (Continued) l the F (Z) factor exceeds its limit wit bin 15 minutes and within the next two hours either reduce the F (Z) factor to within its limit 4

or reduce THERMAL POWER to P,% or less of RATED THERMAL POWER.

f

b. With a F (Z) factor exceeding F (Z) g by greater than 4 percent, reduce THERMAL POWER to P,% or less of RATED THERMAL POWER within 15 minutes.

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

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

I 1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 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 i

THERMAL POWER, or b) Movement of control bank "D" more than an accumulated total of 5 steps in any one direction.

b. Or using the movable incore detectors at the following fre-l quencies when the APDMS is inoperable:

j 1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and

2. At intervals of 30, 60, 90,120, 240 and 480 minutes i following:

9 NORTH ANNA - UNIT 2 3/4 2-19

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

.~. , ,

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Contic*ted) f a) Increasing the THERMAL POWER above P % of RATED THERMAL POWER, or

  • b) Movement of control bank "D" more than an accumulated total of 5 steps 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 equiet1.ent to that obtained from the APDMS shall be maintained.

4

)

NORTH ANNA - UNIT 2 3/4 2-20

._....=...

  • d ,

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 value is necessary to_ reflect core burnup considerations.

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, 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumulative 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 the target band but within the limits of Figure 3.2-1 while at THERMAL POWER levels between 50% and P % g of RATED THERMAL POWER. For THERMAL l

POWER levels between 15% and 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 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 inanediately if the AFD for at least 2 OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than P %fof RATED THERMAL POWER. During operation at THERMAL POWER levels between 50% and P %f and 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of I hour 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.

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

e .

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 accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimtra DNBR of 1.30 throughout each analyzed transient. 1 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 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.

3/4.2.6 AXIAL POWER DISTRIBUTION The limit on axial power distribution ensures that F will be controlled q

and monitored on a more exact basis through use of the APDMS when operating above P,% of RATED THERMAL POWER. This additional limitation on Fq is necessary in order to provide assurance that peak clad temperatures will remain below the ECCS acceptance criteria limit of 2200 F in the event of a LOCA. The value for P is based on the cycle dependent potential violation of the F0xK(Z) limit, whEre K(Z) is the graph shown in Figure 3.2-2. The amount of potential violation is determined by subtracting i from the maximum ratio of the predicted Fn (Z) analysis (flyspeck) results for a particular fuel cycle to the F gxK(Z) liihit. This amount of potential violation, in percent, is subtractea from 100% to determine the value for P . If P is equal to 100%,

no axial power distribution surveillance is requTred. P M will not exceed 100%.

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

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

, r .

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 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.

a. Reactor protection system or engineered safety' feature instru-ment settings which are found to be less conservative than 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 required by a limiting condition for operation.
c. Observed inadequacies in the implementation of administrative 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 material resulting from the fission process.

CORE SURVEILLANCE REPORT 6.9.1.10 The F xy limit for Rated Thermal Power (Fxy ) in all core 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 FqfTyspeck basis l shall be provided to the Director of the Regional Office of Inspection and Enforcement, with a copy to; Director, Office of Nuclear Reactor Regulation Attention: Chief of Core Performance Branch U. S. Nuclear Regulatory Commission 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 limits would become effective unless otherwise exempted by the Commission.

NORTH ANNA - UNIT 2 6-18

ADMINISTRATIVE CONTROLS (Continued)

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

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement, Regional Office within the time period specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of ' Federal Regulations, the following records shall be retained 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.
b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

1 J

NORTH ANNA - UNIT 2 6-18a

9 4 e' ATTACHMENT 3 CORE SURVEILLANCE REPORTS FOR CURRENT NORTH ANNA CYCLES FOR Fq = 2.1 1

(

l i

7 .

MORTH ANNA UNIT 1, CYCLE 3 CORE SURVEILLANCE REPORT FOR F9 = 2.1 t

b

MORTH .;NNA UNIT 1, CYCLE 3 CORE SURVEILLANCE LIMITS, F2 = 2.10 I. The F-XY limits for RATED THERMAL POWER within specific core planes shall bei

1. Txy-RTP < 1.71 for all core planes containing bank "D" control rods,
2. Fxy-RTP < 1.60 for all unrodded core-planes from 0 to 28%

of core height,

3. Txy-RTP < 1.57 for all unrodded core planes from 28% to 65% of coFe height, and
4. Fxy-RTP < 1.62 for all unrodded core planes above 65%

, of core height.

II. The anici power distribution surveillance threshold power level shall be:

1. Pm = 92% of RATED THERMAL POWER.

i S

l

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t k

l l

r 1

t

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

o . .

t NORTil ANNA UNIT 1. CYC1.E 3 MAXIMUM (F P Q Rel) vs. AXIAL CORE HEICHT DURING NORMAL CORE OPERATION

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1.968 9 11.015 ft. -_ _ .. _

s . .. _. . . . .. .. .. .. .. .. .... _ .... .... : . . . .. . ... :. .. .. . .. ..._,_. ._.

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4 2 4 6 8 10 12 Core Height (feet) .

8 .

L O

NORTH ANNA UNIT 2, CYCLE 1 4

CORE SURVEILLANCE REPORT FOR F9 = 2.1 1

l I

)

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t l

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-s e

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l NORTH AMMA UNIT 2, CYCLE 1 CORE SURVEILLANCE LIMITS, FS = 2.10

.I. The F-XY limits for RATED THERMAL POWER within specific core planes shall bc

1. Txy-RTP $, 1.71 for all core planes containing bank "D" control rods,
2. Txy-RTP 3, 1.55 for all unrodded core planes.

II. The axial power distribution surveillance threshold power level shall ben

1. Pm = 90!; of RATED THERMAL POWER.

1 y.

s "M

,ORUt ANNA UNIT 2, CYCLE 1 N

7

  • e . HAXIMUM (F 'PRal) vs. AXIAL C!RE HEICHT q

~

..DURING NORMAL C0'RE

  • 9PERATION 2.4

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  • Core Height (feet)

N

I & d ,

ATTACHMENT 4 CORE SURVEILLANCE REPORTS FOR CURRENT NORTH ANNA CYCLES FOR FQ = 2.14 I

t

NORTH ANNA UNIT 1, CYCLE 3 CORE SURVEILLANCE REPORT FOT. FQ = 2.14 e

=. - .

.. 4, I

NORTH ANNA UNIT 1, CYCLE 3 CORE SURVEILLANCE LIMITS. TS = 2.14 I. The T-XY limits for RATED THERMAL POWER within specific core planes

.shall her

1. Txy-RTP jL 1.71 for all core planes containing bank "D" control rods,
2. Txy-RTP jL .1.60 for all unrodded core planes from 0 to 28%

of core height,

3. Tny-RTP jL 1.57 for all unrodded core planas from 28% to 65% of core height, and
4. Txy-RTP jL 1.62 for all unrodded core planes above 65%

of core height.

II. The axial power distribution surveillance threshold power level shall be:

1. Pn = 94% of RATED THERMAL POWER.

l l

i 6

I

NORTl! ANNA UNIT 1, CYCI.E 3 -

HAXIMUM (F F Q Re1) vs. AXIAI. CORE HEICT

. DURING NORMAL CORE OPERATION

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Core Height Uect)

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  • D 4 ,

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i NORTH ANNA UNIT 2, CYCLE 1 CORE SURVEILLANCE REPORT FOR FC = 2.14 i

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MORTH ANNA UNIT 2. CYCLE 1 CORE SURVEILLANCE LIMITS, FS = 2.14 I. The F-XY limits for RATED THERMAL POWER within specific core planes shall her 1

1. Fxy-RTP 1 1.71 for all core planes containing bank "D" control rods,
2. Fxy-RTP 1 1.55 for all unrodded core planes.

II. The axial power distribution surveillance threshold power level shall bei

1. Pm = 91% of RATED THERMAL POWER.

1 0

1 4

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

- ~ .- . . - _ . .._;. -

NOltill ANNA UNIT 2 CYCLE 1 HAXIMUll (F Q 'PRei) vs. AXIAL CORE llEICllT DURING NOR>lAL CORE OPERATION i t E.N . . .. . .. . , ...

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