ML20058N590
| ML20058N590 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/08/1990 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20058N585 | List: |
| References | |
| NUDOCS 9008140216 | |
| Download: ML20058N590 (8) | |
Text
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'.4 ADMINISTRATIVE CONTROLS
, - CORE OPERATING LIMITS REPORT
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' 6.9.1 ~.7.a ' Core operating limhs shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle , ~
for the following:
- 1. Moderator Temperature Coefficient BOC and EOC limits, and 300 ppm and-60 ppm surveillance' limits for Specification 3/4.1.1.4, .
- 2. Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, i
- 3. Control Rod Insertion Limits for Specification 3/4.1.3.6,
- 4. Axial Flux Difference limits for Specification 3/4.2.1,
- 5. ' Heat Flux Hot Channel Facior, K(2), N(Z) for Specification 3/4.2.2, and t
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- 6. - Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier, for Specification 3/4.2.3.
- 7. Boron Concentration for Specification 3/4.9.1. ;
6.9.1.7.b' The analytical methods used to determine the core operating limits shall be those , previously reviewed and approved by the NRC as identified in 6.9.1.7.c. l< The core operating limits shall be determined so that all applicable limits (e.g., s
- fuel thermal. mechanical limits, core thermal. hydraulic limits, ECCS limits, ,
nuclear limits such as shutdown margin, and transient and accident analysis L limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, l,' ' including.any mid-cycle revisions or supplements thereto, shall be provided I, ' upon issuance, for.each reload cycle, to the NRC' Document Control Desk with > copies to the Regional Administrator and Resident inspector. 3 6.9,1.7.c. REFERENCES L 1. VEP FRD-42,- Rev.1 A, " Reload Nuclear Design Methodology',' September I" 1986. (Methodology for LCO 3.1.1.4 - Moderator Temperature Coefficient, LCO H ' 3.1.3.5 - Shutdown Bank Insertion Limit, LCO 3.1.3.6 - Control Bank ~ . K Insertion Limits, LCO 3.2.2 Heat Flux Hot Channel Factor, LCO 3.2.3 - l L Nuclear Enthalpy Rise Hot Channel Factor, and LCO 3.9.1 - Boron Concentration).
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h NORTH ANNA UNIT 1 6-17 Amendment No. ( 1' l i Z , _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
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.. 7 ADMINISTRATIVE CONYROLS (Conrd) :,
a 2a. .WCAP 9220 P A. Rev.1," WESTINGHOUSE ECCS EVALUATION MODEL- :
. 1981 VERSION", February 1982_ (E Preprietary).
(Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor);
, .2b; WCAP 9561 P A, ADD. 3, Rev.1,"BART A 1: A COMPUTER CODE FOR l
THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS SPECIAL .! REPORT: THIMBLE MODELING IN W ECCS EVALUATION MODEL", JULY, - 1986, (E Proprietary). - (Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor). l i 2c. WCAP 10266-P A, Rev. 2 "The 1981 Version of the Westinghouse ECCS ; Evaluation Model Using the BASH Code", March 1987 (E Proprietary), a (Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor). [ 2d. WCAP 10054 P-A, " Westinghouse Small Break ECCS Evaluation Model
. Using the NOTRUMP Code," August 1985 (E Proprietary). ,
l (Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor). - " i 2e. WCAP 10079 P-A, "NOTRUMP, A Nodal Transient Small Break and } General Network-Code", August 1985 (E Proprietary). 7 -, (Methodology for LCO 3.2.2 - Heat Flux Hot Channel Factor). f
' 3a. 'VEP NE 2-A, " Statistical DNBR Evaluation Methodology", June 1987.-
(Methodology for LCO 3.2.3, Nucle'ar Enthalpy Rise Hot Channel Factor.) l 3b. VEP-NE 3 A, "Qualificathn of the WRB 1 CHF Correlation in_the Virginia
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Power COBRA Code", July 1990. (Methodology for LCO 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor).- 1 6
- 4. VEP NE-1 A, "Vepco Relaxed Power Distribution-Control Methodology and Associated FO Surveillance Technical Specifications," . March 1986. '
(Methodology for LCO' 3.2.2 - Heat Flux Hot Channel Factor and LCO 3.2.1 - Axial Flux Difference.) l i NORTH ANNA UNIT 1 6-17a Amendt@ ( No. l 1 l l l
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g op 7u,, , i M- " ADMINISTRATIVE CONTROLS i [ CORE OPERATING LIMITS REPORT y 6.9,1.7.a Core operating limits shall be established and documented in the CORE' OPERATING - _1 ' i LIMITS REPORT before each reload cycle or any remaining part of a reload cycle 3 E for the following:
.e F 1. - Moderator Temperature Coefficient BOC and EOC limits, and 300 ppm and 60 ppm surveillance limits for Specification _3/4.1.1.4, l
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- 2. - Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, t
- 3. Control Rod Insertion Limits for Specification 3/4.1.3.6,.
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;. 4. Axial Flux Difference limits for Specification 3/4.2.1,
- 5. Heat Flux Hot Channel Factor, K(Z), N(Z) for Specification 3/4.2.2, and 4'" 6. Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier, gy ' - for Specification 3/4.2.3.
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-7. Boron Concentration. for Specification 3/4.9.1.
W 6.9.1.7.b The analytical methods used to datermine the core operating limits shall be those previously reviewed and approved by the NRC as identified in 6.9.1.7.c. ; The core operating lim.its shall be determined so that all applicable limits (e.g., '
- fuel thermal mechanical limits, core thermal h';draulic limits, EC_CS limits, nuclear limits such as shutdown margin, and transient and ac ident analysis limits) of the safety analysis are met. The CORE OPERATING L ..!!TS REPORT, including any mid cycle revisions or. supplements thereto, shall be provided -
upon issuance, for each reload cycle, to the NRC Document Control Desk with , copies to the Regional Administrator and Resident Inspector. 1 6.9.1.7.c BEEERENCES
- 1. 'VEP FRD 42, Rev.1-A,_" Reload Nuclear Design Methodology", September 1986.
(Methodology for LCO 3.1.1.4 Moderator Temperature Coefficient, LCO 3.1.3.5 - Shutdown Bank Insertion Limit,-LCO 3.1.3.6 - Control Bank o y insertion Limits. LCO 3.2.2 Heat Flux Hot Channel Factor, LCO 3.2.3 - 1 Nuclear Enthalpy Rise Hot Channel Factor, and LCO 3.9.1 Boron Concentration). NORTH ANNA - UNIT 2 6-17 Amendment No. +
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1 ADMINISTRATIVE CONTROLS (Cont'd)- q I 2a. WCAP 9220 P-A. Rev.1," WESTINGHOUSE ECCS EVALUATION MODEL - -{ 1981 VERSION", February 1982 (E Proprietary). ! (Methodology for' LCO 3.2.2 - Heat Flux Hot Channel Factor), .,
, 2b. WCAP 9561 P-A, ADD. 3, Rev.1,"BART A 1: A COMPUTER CODE FOR -{
THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS - SPECIAL } W 1 REPORT: THIMBLE MODELING IN W ECCS EVALUATION MODEL", JULY, . 4 1986, (W. Proprietary). - i (Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor).- [ 2c. WCAP 10266 P A, Rev. 2, "The 1981 Version of the Westinghouse ECCS ? i Evaluation Model Using the BASH Code", March 1987 (E Proprietary). q (Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor). '[
- l. i 2d. WCAP 10054 P-A, " Westinghouse Small Broak ECCS Evaluation Model Using the NOTRUMP Code," August 1985 (E Proprietary).
. (Methodology for LCO 3.2.2 - Heat Flux Hot Channel Factor).
- 2e. WCAP-10079-P A, "NOTRUMP, A Noda! Transient Small Break and a General Network Code", August 1985 (E Proprietary), j (Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor).
i L , L 3a. -VEP NE 2 A,'" Statistical DNBR Evaluation. Methodology", June-1987, i _( Methodology for.LCO 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor.) 3b. VEP-NE 3-A, " Qualification of the WRB 1 CHF Correlation In the Virginia
. Power COBRA Code", July 1990.-
(Methodology for LCO 3.2.3 Nuclear Enthalpy Riso Hot Channel Factor).
'4- . VEP NE 1-A, "Vepco Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications," March.1986.
(Methodology for LCO 3.2.2 - Heat Flux Hot Channel Factor and LCO 3.2.1 - Axlal Flux Difference.) l p . 4 NORTH ANNA UNIT 2 6 17a Amendment No. l l- ,_. 1L. l ;i (
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