ML20058N590

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Proposed Tech Specs Re Core Operating Limits Rept
ML20058N590
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 08/08/1990
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20058N585 List:
References
NUDOCS 9008140216
Download: ML20058N590 (8)
v • d • e


Text

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1 .--T ii.- .i! + .~ 3 '.4 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT _l ' 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 ti
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). c 1: h NORTH ANNA UNIT 1 6-17 Amendment No. ( 1' l i Z

l p. f j 'I u.. o ,= i 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 THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS SPECIAL l 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 l . Using the NOTRUMP Code," August 1985 (E Proprietary). (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 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.) i NORTH ANNA UNIT 1 6-17a Amendt@ ( No. 1l

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iSQ + i g 7 op u,, M- " ADMINISTRATIVE CONTROLS i [ CORE OPERATING LIMITS REPORT 6.9,1.7.a Core operating limits shall be established and documented in the CORE' OPERATING - y _1 i LIMITS REPORT before each reload cycle or any remaining part of a reload cycle E for the following: 3 .e F

1. - Moderator Temperature Coefficient BOC and EOC limits, and 300 ppm and l

60 ppm surveillance limits for Specification _3/4.1.1.4, J l>

2. - Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, t

.g 3. Control Rod Insertion Limits for Specification 3/4.1.3.6,. uun 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. q -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 insertion Limits. LCO 3.2.2 Heat Flux Hot Channel Factor, LCO 3.2.3 - y 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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-7 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 } REPORT: THIMBLE MODELING IN W ECCS EVALUATION MODEL", JULY,. 4 W 1 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). L i 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 ( \\ l .h 1 4

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