ML20137K411

Proposed Tech Specs,Authorizing Operation at 2,775 Mwt W/Steam Generator Tube Plugging of Up to 7%

ML20137K411
Person / Time
Site:	North Anna
Issue date:	01/17/1986
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20137K386	List: ML20137K383 ML20137K404 ML20137K411
References
NUDOCS 8601240056
Download: ML20137K411 (7)

Text

,- -

ATTAC M NT 3 3

t PROPOSED TECHNICAL SPECIFICATION CHANGES t

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8601240056 860117 -

PDR ADOCK 05000338 P PDR 84R629NPW165 22

1-27-83 POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-F (Z)

LIMITING CONDITION FOR OPERATION 3.2.2 F9 (Z) shall be limited by the following relationships:

Fq (Z) s [ 2.15] [ K(Z)] for P> 0.5 P

Fq (Z) s [4.30] [K(Z)] for Ps 0.5 where P = 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 q(Z) exceeding its limit:

a. Comply with either of the following ACTIONS:

1. Reduce THERMAL POWER at least 1% for each 1% F (Z' exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% F (Z) 9 exceeds the limit. The Overpower AT Trip Setpoint reduction shell be performed with tha reactor in at least HOT STANDBY.

2. Reduce THERMAL POWER as necessary to meet the limits of Specification _ 3.2.6 using the APDMS with the latest fucore map and updated R.

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

demonstrated through incore mapping to be within its limit.

NORTH ANNA - UNIT 1 3/4 2-5 Amendment No.

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(10.97,0.938)

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I-27-83 POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBl' TION LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following relationship:

[F (Z)]g =

(E )(P )(1.03)(1 + a))(1.07)

Where:

a. F (Z) is the nomalized axial power distribution from thimble j at core evaluation 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. E) , for thimble j, is determined from at least n=6 incore flux maps covering the full configuration of permissible rod patterns above Pm

% of RATED THERMAL POWER in accordance with:

1 "j " n I i = 't R) g Where:

pMeas R)=

g

[F (Z)]g and [F (Z)}g,x is the maximum value of the nomalized axial distribution at elevation Z from thimble j in map i which had a measured peaking factor without uncertainties or densification allowance of Fq Meas ,

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

ATTACMENT 4 REVISED CORE SURVEILLANCE REPORT FOR NORTH ANNA 1 CYCLE 5 84R629NPW165 23

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l NORTH ANNA UNIT 1. CYCLE 6 CORE SURVEILLANCE LIMITS, FQ = 2.15  ;

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! I. The F-xy limits for RATED THERMAL POWER within specific core planes j shall be:

j 1. Fxy-RTP 5,1.71 for all core planes containing bank "D" control i rods, and

2. Fxy-RTP 5,1.65 for all unrodded core planes.

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

1. Pm = 100% of RATED THERMAL POWER.

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