ML061670221

Technical Specifications, Activation of the Trip-Outputs of the Oscillation Power Range Monitor System

ML061670221
Person / Time
Site:	LaSalle
Issue date:	06/13/2006
From:	Plant Licensing Branch III-2
To:
Sands, S, NRR/DLPM/PD3-2, 415-3154
Shared Package
ML060400603	List: ML060400599 ML061670221
References
TAC MC3033, TAC MC3034
Download: ML061670221 (10)

Text

TABLE OF CONTENTS 1.0 USE AND APPLICATION 1.1 Definitions .............................................. 1.1-1 1.2 Logical Connectors ....................................... 1.2-1 1.3 Completion Times ......................................... 1.3-1 1.4 Frequency ................................................ 1.4-1 2.0 SAFETY LIMITS (SLs) 2.1 SLs ...... ........................................... 2.0-1 2.2 SL Violations ............................................ 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................. 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) .................................... 3.1.1-1 3.1.2 Reactivity Anomalies ..................................... 3.1.2-1 3.1.3 Control Rod OPERABILITY .................................. 3.1.3-1 3.1.4 Control Rod Scram Times .................................. 3.1.4-1 3.1.5 Control Rod Scram Accumulators ........................... 3.1.5-1 3.1.6 Rod Pattern Control ...................................... 3.1.6-1 3.1.7 Standby Liquid Control (SLC) System ...................... 3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ....... 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ...... 3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) ...................... 3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) ...................... 3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation .......... 3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation ............... 3.3.1.2-1 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation.. .3.3.1.3-1 3.3.2.1 Control Rod Block Instrumentation ........................ 3.3.2.1-1 3.3.2.2 Feedwater System and Main Turbine High Water Level Trip Instrumentation .................... ......... 3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ........... 3.3.3.1-1 3.3.3.2 Remote Shutdown Monitoring System ........................ 3.3.3.2-1 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation ........................................ 3.3.4.1-1 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ................... 3.3.4.2-1 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation ..... 3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation 3.3.5.2-1

........

3.3.6.1 Primary Containment Isolation Instrumentation............ 3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation .......... 3.3.6.2-1 3.3.7.1 Control Room Area Filtration (CRAF) System Instrumentation ........................................ 3.3.7.1-1 (continued)

LaSalle 1 and 2 i Amendment No. 177/163

OPRM Instrumentation 3.3.1.3 3.3 INSTRUMENTATION 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation LCO 3.3.1.3 Four channels of the OPRM instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER > 25% RTP.

ACTIONS

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NOTE -------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 30 days inoperable, trip.

A.2 Place associated RPS 30 days trip system in trip.

OR A.3 Initiate alternate 30 days method to detect and suppress thermal hydraulic instability oscillations.

(continued)

LaSalle 1 and 2 3.3.1.3-1 Amendment No. 177/163

OPRM Instrumentation 3.3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. OPRM trip capability B.1 Initiate alternate 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> not maintained, method to detect and suppress thermal hydraulic instability oscillations.

AND B.2 Restore OPRM trip 120 days capability.

C. Required Action and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion < 25% RTP.

Time not met.

LaSalle 1 and 2 3.3.1.3-2 Amendment No. 177/163

OPRM Instrumentation 3.3.1.3 SURVEILLANCE REQUIREMENTS

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NOTE -------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the OPRM maintains trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.3.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.3.2 Calibrate the local power range monitors. 1000 effective full power hours SR 3.3.1.3.3 -------------------NOTE----------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. The setpoints 24 months for the trip function shall be as specified in the COLR.

SR 3.3.1.3.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.3.5 Verify OPRM is not bypassed when THERMAL 24 months POWER is : 28.6% RTP and recirculation drive flow is < 60% of rated recirculation drive flow.

SR 3.3.1.3.6 -------------------NOTE --------------------

Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within 24 months on a limits. STAGGERED TEST BASIS LaSalle 1 and 2 3.3.1.3-3 Amendment No. 177/163

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.

OR One recirculation loop shall be in operation with the following limits applied when the associated LCO is applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR;

c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," single loop operation limits specified in the COLR;

d. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power - Upscale),

Allowable Value of Table 3.3.1.1-1 is reset for single loop operation; and

e. LCO 3.3.2.1, "Control Rod Block Instrumentation,"

Function l.a (Rod Block Monitor - Upscale), Allowable Value of Table 3.3.2.1-1, specified in the COLR, is reset for single loop operation.

APPLICABILITY: MODES 1 and 2.

LaSalle I and 2 3.4.1-1 Amendment No. 177/163

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No recirculation A.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> loops in operation. I B. Recirculation loop B.1 Declare the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> flow mismatch not recirculation loop within limits, with lower flow to be "not in operation."

C. Requirements of the C.1 Satisfy the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO not met for requirements of the reasons other than LCO.

Condition A or B.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition C not met.

LaSalle 1 and 2 3.4.1-2 Amendment No. 177/163

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

• 1~

SR 3.4.1.1 NOTE --------- r----------

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Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops are in operation.

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Verify recirculation loop jet pump flow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mismatch with both recirculation loops in operation is:

a.

• 10% of rated core flow when operating at < 70% of rated core flow; and

b.

• 5% of rated core flow when operating at Ž 70% of rated core flow.

J ________________________________

I LaSalle I and 2 3.4.1-3 Amendment No. 1'77/163

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4

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. The Rod Block Monitor Upscale Instrumentation Setpoint for the Rod Block Monitor-Upscale Function Allowable Value for Specification 3.3.2.1.

5. The OPRM setpoints for the trip function for SR 3.3.1.3.3.

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 documents:

1. ANF-1125(P)(A), "ANFB Critical Power Correlation."

2. Letter, Ashok C. Thadani (NRC) to R.A. Copeland (SPC),

"Acceptance for Referencing of ULTRAFLOWr' Spacer on 9x9-IX/X BWR Design," July 28, 1993.

3. XN-NF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors."

4. ANF-913(P)(A), "COTRANSA 2: A Computer Program for Boiling Water Reactor Transient Analysis."

5. ANF-CC-33(P)(A), "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option."

6. XN-NF-80-19(P)(A), "Advanced Nuclear Fuel Methodology for Boiling Water Reactors."

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

8. ANF-89-014(P)(A), "ANF Corporation Generic Mechanical Design for ANF Corporation 9x9-IX and 9x9-9X BWR Reload Fuel."

9. EMF-CC-074(P)(A), Volume 4 - "BWR Stability Analysis:

Assessment of STAIF with input from MICROBURN-B2."

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

11. XN-NF-84-105(P)(A), "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis."

(continued)

LaSalle 1 and 2 5.6-3 Amendment No. 177/163

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

12. ANF-91-048(P)(A), "ANF Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model."

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

14. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs."

15. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel."

16. NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods."

17. EMF-1125(P)(A), "ANFB Critical Power Correlation Application for Co-Resident Fuel."

18. ANF-1125(P)(A), "ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties."

19. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."

20. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2."

21. NEDC-32981P(A), "GEXL96 Correlatibn for Atrium-9B Fuel."

22. NEDC-33106P, "GEXL97 Correlation for Atrium-10 Fuel."

23. EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel."

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

25. NEDO-32465-A, "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," August 1996.

(continued)

LaSalle I and 2 5.6-4 Amendment No. 177/163

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIM1IS REPORT (COLR) (continued)

The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

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.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

LaSalle I and 2 5.6-5 Amendment No. 177/163