ML20211H928
| ML20211H928 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/26/1997 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20211H919 | List: |
| References | |
| NUDOCS 9710070200 | |
| Download: ML20211H928 (2) | |
Text
.
SLs 2.0 2.0 SAFETY LIMITS (SLs) 1 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
l
- 2.1.1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow MCPR shall be a 1.11 for two recirculation loop operation or a 1.12 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 1.2.2.2 Insert all insertable control rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Plant Manager and the Vice President-Peach Bottom Atomic Power Station.
(continued)
{ *MCPR values in TS 2.1.1.2 are applicable only for Cycle 12 operation 9710070200 970926 PDR ADOCK 05000270 P
PDR PBAPS UNIT 3 2.0-1 Amendment No.
Reporting Requirements
+
5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) a.
Core operating limits shall be established prior to each reload cycle, or ortor to any remaining portion of a reload cycle, and shall ae documented in the COLR for the following:
1.
The Average Planar Linear Heat Generation Rate for Specification 3.2.1; 2.
The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.1; 3.
The Linear Heat Generation Rate for Specification 3.2.3; and 4.
The Control Rod Block Instrumentation for Specification 3.3.2.1.
b.
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 I
documents:
1.
NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version as specified i
in the COLR);*
2.
NEDC-32162P, " Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Units 2 and 3," Revision 1. February, 1993; 3.-
PECo-FMS-0001-A, " Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code";
4.
PEco-FMS-0002-A, " Method for Calculating Transient critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPECo)";
5.
PEco-FMS-0003-A, " Steady-State Fuel Performance Methods Report";
6.
PEco-FMS-0004-A, " Methods for Performing BWR Systems Transient Analysis";
(continued)
- For Cycle 12, specific documents were approved in the Safety Evaluation dated
(
) to support License Amendment No. (
)
PBAPS UNIT 3 5.0-21 Amendment No.