ML20058F381
| ML20058F381 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/30/1990 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20058F379 | List: |
| References | |
| NUDOCS 9011080247 | |
| Download: ML20058F381 (3) | |
Text
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Proposed Technical Specifications Changes North Anna Unit 1 & 2 Virginia Electric and Power-Company 1
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! ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT 6.9.1.7.a Core operating limits 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 Bank Insertion Limit for Specification 3/4.1.3.5, l
3.
Control Bank Insettlon Limits for Specification 3/4.1.3.6, l
4.
Axlal 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 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 l-previously reviewed and approved by the NRC as identified in 6.9.1.7,0.
6.9.1.7.c The core operating limits shall be determined so that all applicable limits (e.g.,
l-fuel thermal mechanical limits, core. thermal hydraulic Ilmits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis
. limits) of the safety analysis are met.-
6.9.1.7.d.
The CORE OPERATING LIMITS REPORT, including any mid cycle revisions or l
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.
6.9.1.7.ef REFERENCES 1.
VEP FRD-42, Rev.1 A, " Reload Nuclear Design Methodology," September 1986.
H (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 l-Insertion Limits. LCO 3.2.2 Heat Flux Hot Channel Factor, LCO 3.2.3.
Nuclear Enthalpy Rise Hot Channel Factor, and LCO 3.9.1 - Boron
- Concentration).
l I
l NORTH ANNA - UNIT 1 6 17 Amendment No.
m e
ADM!NISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT 6.9.1.7.a Core operating limits 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 lirnits for Specification 3/4.1.1.4, 2.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, l
)
3.
Control Bank Insertion Limits for Specification 3/4.1.3.6, l
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 6.
Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier, for Specification 3/4.2.3.
ll 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 l
previously reviewed and approved by the NRC as identified in 6.9.1.7,0.
6.9.1.7.c The core operating limits shall be determined so that all applicable limits (e.g.,
l fuel thermal mechanical limits, core thermai. hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are. met.
6.9.1.7.d The CORE OPERATING LIM!TS REPORT, including any mid-cycle revisions or l
supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and e
Resident inspector.
- 6.9.1.7,e REFERENCES l
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 Insertion Limits, LCO 3.2.2 Heat Flux Hot Channet Factor, LCO 3.2.3 -
i Nuclear Enthalpy Rise Hot Channel Factor, and LCO 3.9.1 Boron
- Concentration).
NORTH ANNA - UNIT 2 6 17 Amendment No.
s a
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.