ML20217K529
| ML20217K529 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/24/1998 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20217K526 | List: |
| References | |
| NUDOCS 9805040002 | |
| Download: ML20217K529 (2) | |
Text
1 ATTACHMENT LIMERICK GENERATING STATION UNIT 1 l
DOCKET NO. 50-352 LICENSE NO. NPF-39 TECHNICAL SPECIFICATIONS CHANGE REQUEST j
NO. 97-03-1 Technical Specifications Page No. 6-18a 9805040002 990424 PDR ADOCK 05000352 P
'. ADMINISTRATIVE CONTROLS CORE 0,PERAT(NG LIMITS REPORT l
)
6.9.1.9 Core Operating Limits shall be established prior to each reload l
cycle, or prior to any remaining portion of a reload cycle, and shall be j
documented in the CORE OPERATING LIMITS REPORT for the following:
a.
The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1, I
b.
MAPFAC(P) and MAPFAC(F) factors for Specification 3.2.1, c.
The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.3, d.
The MCPR(P) and MCPR(F) adjustment factors for specification 3.2.3, e.
The LINEAR HEAT GENERATION RATE (LHGR) for Specification 3.2.4, f.
The power biased Rod Bleck Monitor setpoints and the Rod Block Monitor MCPR OPERABILITY limits of Specification 3.3.6, g.
The Reactor Coolant System Recirculation Flow upscale trip setpoint and allowable value for Specification 3.3.6, h.
The Recirculation MG set mechanical and electrical overspeed stop setpoints for Specification 4.4.1.1.2.
6.9.1.10 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
a.
NEDE-240ll-P-A " General Electric Standard Application for Reactor Fuel" (Latest approved revision).
l 6.9.1.11 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.
i 6.9.1.12 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPGRTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
For Cycle 8, specific documents were approved in the Safety Evaluation dated
(
) to support License Amendment No. (
).
LIMERICK - UNIT 1 6-18a