ML20062L475
| ML20062L475 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/16/1982 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20062L470 | List: |
| References | |
| NUDOCS 8208190122 | |
| Download: ML20062L475 (15) | |
Text
{{#Wiki_filter:Attachment 2 Proposed Technical Specification Changes 8208190122 820816 PDR ADOCK 05000338 P PDR
POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-F (Z) LIMITING CONDITION FOR OPERATION 3.2.2 Fq (Z) shall be limited by the following relationships: Fq (Z) 3 [2.20] P [K(Z)]for P > 0.5 Fq (Z) $ [4.40] [K(Z)]for P $ 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 (Z) exceeding its limit: 9
- a. Comply with either of the following ACTIONS:
- 1. Reduce THERMAL POWER at least 1% for each 1% qF (Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours; POWER OPERATION may proceed for up to a total of 72 hours; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% F (Z) q exceeds the limit. The Overpower AT Trip Setpoint reduction shall be performed with the 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 incore map and updated R.
- b. Identify and correct the cause of the out of limit condition prior to increasing TFERMAL POWER above the reduced limit required by a, above; THERMAL .OWER may then be increased providedqF (Z) is demonstrated through incore mapping to be within its limit.
NORTH ANNA - UNIT 1 3/4 2-5
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0 2 4 6 8 10 12 CORE HEIGHT (FI) 1 i Figure 3.2-2 K(Z) - Normalized Fq(Z) as a Function of Core Height NORTH ANNA - UNIT 1 3/4 2-8 I l l i I
+ - - . . _ . . _ . .
POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following , relationship: [2.20) (K(Z)) [F (Z)]g = (I )(P )(1.03)(1 + cr )(1.07) 3 g ; 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 from at least n=6 inc;re flux maps covering the full configuration of permissible rod patterns above P % of RATED THERMAL POWER in accordance with:
j ij t Where: pMeas R = ij [F (Z)]Ma and [P)(Z)]g,x 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 eas or densification allowance of F , q NORTH ANNA - UNIT 1 3/4 2-16
3/4.2 POWER DISTRIBUTION LIMITS 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 11.30 during normal operation and in 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 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 9 heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for man-ufacturing tolerances on fuel pellets and rods. F Nuclear Enthalpy Rise Hot Chanael 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. F Radial Peaking Factor, is defirad as the ratio of peak power
*7(Z) 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 Fq (Z) upper bound envelope, as given in Specification 3.2.2, is not exceeded during either normal operation or in the event of xenon redistribution following power 4 changes. Target flux difference is determined at equilibrium xenon 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 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 conditions. Target flux differences for other 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. 4 i NORTH ANNA - UNIT 1 B 3/4 2-1
POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-F (Z) LIMITING CONDITION FOR OPERATION 3.2.2 Fq (Z) shall be limited by the following relationships: F (Z) 1 [2.20] [K(Z)] for P > 0.5 P Fq (Z) 1 [4.40} [K(Z))for P 10.5 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 (Z) exceeding its limit: q
- 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 hours; POWER OPERATION may proceed for up to a total of 72 hours; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for cach 1% F (Z) q exceeds the limit. The Overpower AT Trip Setpoint reduction shall be performed with the 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 incore map and updated R.
- b. Identify and correct the cause of the out of limit condition prior to increasing TEERMAL 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 2 3/4 2-5
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( 2. 2 . ..p :. , 0 2 4 6 8 10 12 CORE HEIGHT (FI) Figure 3.2-2 K(Z) - Normalized Fq(Z) as a Function of Core Height l l i 1 1 i NORTH ANNA - UNIT 2 3/4 2-8
POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION 3.2.6 - The axial power distribution shall be limited by the following relationship:
= [2.20) IK(Z)]
[F(Z)]3 3 (I )(P g)(1.03)(1 + o-3 )(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 _ from at. least n=6 incore flux maps covering the: full configuration of permissible
-rod patterns above P % of RATED THERMAL POWER in accordance with:
j 13 1 Where: , Qi ij
~[F)(ZdMax g
, and[F (Z)] g is the maximum value of the normalized l axial distribution at elevation Z from thimble j in map i 1 i l NORTH ANNA - UNIT 2 3/4 2-17 i l
h 3/4.2 POWER DISTRIBUTION LIMITS BASES i 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 in 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 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 i these specifications are as follows: I 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 by the average fuel rod heat flux, allowing for man-ufacturing tolerances on fuel pellets and rods. !
l F Nuclear Enthalpy Rise Hot Channel Factor, is defined as the [ H " ratio of the integral of linear power along the rod with the highest integrated power to the average rod power. [ , F Radial Peaking Factor, is defined as the ratio of peak power
*7(Z) density to average power density in the horizontal plane at i
, core elevation Z. . 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) i The limits on A(IAL FLUX DIFFERENCE assure that the Fq(Z) upper bound l J 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. . Target flux difference is determined at equilibrium xenon 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 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 conditions. Target flux differences for other
. i f ,
1 b
- i NORTH ANNA - UNIT 2 B 3/4 2-1 i
i
Attachment 3 ~ Core Surveillance Reports for North Anna 1 Cycle 4 and North Anna 2 Cycle 2 1 I .
l TABLE 1 NORTH ANNA UNIT 1, CYCLE 4 CORE SURVEILLANCE LIMITS, TS = 2.20 ) I. The'T-XY limits for RATED THERMAL POWER within specific core planes shall be
- 1. Txy-RTP s 1.71 for all core planes containing bank "D" control rods, and
- 2. Txy-RTP < 1.65 for all unrodded core planes between 15 % and 25 % of core height, or i
- 3. Txy-RTP :s 1.70 for all unrodded core planes between 25 % and 55 % of core height, or i
- 4. Txy-RTP :s 1.65 for all unrodded core planes between 55 % and !
85 % of core height. , II. The axial power distribution surveillance threshold power level shall has ( 1. Pm = 100% of RATED THERMAL POWER. i l 1
NORTH ANNA UNIT 1 CYCLE 4 MAXIMUM FQ-TOTALaP VS. AXIRL CORE HEIGHT DURING NORMAL CORE OPERATION x XDN
. .x>. .
. x> %x .. w XX X g <' "X 2.0 ' ,
x x < XX 1.8 , A : X I - n . U 1.6 - M F ' 0 : \ T 1. 4 ' 0 : . T ' A ~ L m X P 1.2 1.0 , X 0.8 a . 0 2 4 6 8 10 12 CORE HEIGHT (FEET) TECHNICAL SPECIFICATIONS LIMIT X CALCULATED DATA .
i TABLE 1 , NORTH AMMA UNIT 2, CYCLE 2 CORE SURVEILLAMCE LIMITS, TS = 2.20 I. The F-XY limits for RATED THERMAL POWER within specific core' planes shall be:
- 1. Txy-RTP g 1.71 for all core planes'containing bank "D" control rods, an'd i
- 2. Fxy-RTP s 1.65 for all unrodded core planes between 15 % and 25 % of core height, or
- 3. Fxy-RTP sr 1.70 for all unrodded core planes between 25 % and 55 % of core height, or
- 4. Txy-RTP s 1.65 for all unrodded core planes between 55 % and 85 % of core height. !
II. The axial power distribution surveillance threshold power level , shall bei
- 1. Pm = 100% of RATED THERMAL POWER. ,
[ i r 4 i L h l
NORnl ANNA UNIT 2 CYCLE 2 NRXINUM FO-TOTAL =P VS. RXIRL CORE HEIGHT DURING NORNRL CORE OPERATION 2.2
>: N x N w xx x x 2.0
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COMMONWEALTH OF VIRGINIA )
)
CITY OF RICHMOND ) The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by R. H. Leasburg, who is Vice President-Nuclear Operations, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. Acknowledged before me this /S day of 8 , 19 PA . My Commission expires: > 6 , 19 P( . O . N #h Notary Public l l l l (SEAL) i . . _ _ _ .}}