ML060800731

Tech Spec for Susquehanna, Unit 1 - Issuance of Amendment Regarding Minimum Critical Power Ratio Safety Limit and Reference Changes

ML060800731
Person / Time
Site:	Susquehanna
Issue date:	03/20/2006
From:	Plant Licensing Branch III-2
To:
References
TAC MC9187
Download: ML060800731 (3)

Text

PPL Rev. 3 Safety Limits (SLs) 2.0 2.0 SAFETY LIMITS (SLs) 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 million Ibm/hr:

THERMAL POWER shall be < 25% RTP.

2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 2 10 million Ibm/hr:

MCPR shall be > 1.09 for two recirculation loop operation or 2 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 < 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

SUSQUEHANNA - UNIT 1 TS / 2.0-1 Amendment 1,< 24,. 22* 231

PPL Rev. 5 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

(102% of 3441 MWt), remains the initial power level for the bounding licensing analysis.

Future revisions of approved analytical methods listed in this Technical Specification that are currently referenced to 102% of rated thermal power (351 0 MWt) shall include reference that the licensed RTP is actually 3489 MWt. The revisions shall document that the licensing analysis performed at 3510 MWt bounds operation at the RTP of 3489 MWt so long as the LEFMVTM system is used as the feedwater flow measurement input into the core thermal power calculation.

The approved analytical methods are described in the following documents, the approved version(s) of which are specified in the COLR.

1. XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company.

2. XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet pump BWR Reload Fuel," Exxon Nuclear Company.

3. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Siemens Power Corporation.

4. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation.

5. XN-NF-80-19(P)(A), 'Exxon Nuclear Methodology for Boiling Water Reactors," Exxon Nuclear Company.

6. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-132," Siemens Power Corporation.

7. EMF-2361 (P)(A), "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP.

8. EMF-2292(P)(A), "ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation.

(continued)

SUSQUEHANNA - UNIT 1 TS / 5.0-22 Amendment tUa 1 , 2, 231

PPL Rev. 5 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

9. XN-NF-84-105(P)(A), "XCOBRA-T: A Computer.Code for BWR Transient Therrnal-Hydraulic Core Analysis," Exxon Nuclear Company.

10. ANF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors," Advanced Nuclear Fuels Corporation.

11. ANF-913(P)(A), "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation.

12. ANF-1 358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Advanced Nuclear Fuels Corporation.

13. EMF-2209(P)(A), "SPCB Critical Power Correlation," Siemens Power Corporation.

14. EMF-CC-074(P)(A), "BWR Stability Analysis - Assessment of STAIF with Input from MAICROBURN-B2," Siemens Power Corporation.

15. NE-092-OOlA, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company.

16. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety while Increasing Operating Power Level Using the LEFTM4TM System," Engineering Report - 80P.

17. Caldon, Inc., uSLIpplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMITm or LEFM CheckPlusTm System,"

Engineering Report ER-160P.

18. NEDO-32465-A "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications."

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

SUSQUEHANNA - UNIT 1 TS / 5.0-23 Amendment SUB 1i, I, 194, 209, 2M1-5 24-1, 2*17, 231