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
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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. l 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";
(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.