ML20028H748
| ML20028H748 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/22/1991 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20028H747 | List: |
| References | |
| NUDOCS 9101290356 | |
| Download: ML20028H748 (3) | |
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Unit 2 PBAPS 6.9.1 Routine Reports (Cont'd)
(2) PECo-FMS-0002-A, " Method for Calculating Transient Critical Po.er Ratios for Boiling Water Reactors (RETRAN-TCPPECo)"
(3) PECo-FMS-0003-A, " Steady-State Fuel Performance Methods Report" (4) PECo-FMS-0004-A, " Methods for Performing BWR Systems Transient Analysis" (5) PECo-FMS-0005-A, " Methods for Performing BWR Steady-State Reactor Physics Analysis" (6) PEco-FMS-0006-A, "Metnods for Performing BWR Reload 4
Safety Evaluations" (3) The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.
(4) The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be submitted upon issuance for each Operating Cycle to the NRC Document Control Desk with copies to the Regional Acministrator and Resident Inspector.
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. s Unit 3 PEAPS i
2.1 BASES
FUEL CLADDING INTEGRITY i.
The_ abnormal operational transients applicable to operation of the Peach Bottom Atomic Power Station Units have been analyzed throughout the spectrum of planned operating conditions up to or above the thermal power. condition required by Regulatory Guide 1.49.
The analyses were based upon plant operation in accordance with the operating map given in Figure 3.7.1 of the PSAR.
In addition, 3293 MWt is the licensed maximum power level of each Peach Bottom Atomic Power Station Unit, and this represents the maximum steady state-power which shall not knowingly be exceeded.
Conservatism is incorporated in the transient analyses in estimating the controlling factors, such as void reactivity coefficient, control. rod scram worth, scram delay time, peaking factors, and axial power ~ shapes.
These factors are selected conservatively with respect to their effect en the applicable transient results as determined by the current analysis model.
Conservatism incorporated inte the transient analyses is documented in Ref erences 4 and S.
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g Unit 3 PBAPS 6.9.1 hutine Reports (Cont'd)
(2) PECo-FMf-0002-A, " Method for Calculating Transient Critical Power hatios for Boiling Water Reactors (RETRAN-TCFPECo)"
(3) PECo-FMS-0003-A, " Steady-State Fuel Performance Methods Report" (4) PECo-FMS-0004-A, " Methods for Performing BWR Systems Transient Analysis" (5) PEco-FMS-0005-A, " Methods for Performing BWR Steady-State Reactor Pbysics Analysic" (6) PECo-FMS-0006-A, " Methods for Performing BWrt Reload Safety Evaluatiors d (3) The core operating limits shall be determined such that til applicable limits (e.g., fuel tnermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as I
shutdown margin, transient analysis limits, and 1ccident analysis limits) of the safety analysis are met.
(4) The CORE OPERATING LIMITS REPORT, including any mic-cycle revisions or supplements, shall be submitted upon issuance for each Ocerating Cycle to the NRC Document Centrol Desk with copies to the Regional Administrator and Resident Inspector, s
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