ML043200202

From kanterella
Jump to navigation Jump to search

Technical Specifications, Amendments 217 & 192, Revised Response to Generic Letter 94-02, Long-Term Stability Solution
ML043200202
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 11/09/2004
From:
NRC/NRR/DLPM/LPD1
To:
References
TAC MC1659, TAC MC1660
Download: ML043200202 (29)
v • d • e


Text

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................................................ 1.1-1 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) ..................................................TS/2.0-1 2.1 SLs ................................................ TS2.-1 2.2 SL Violations ................................................ TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ....................... TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ................................................ 3.1-1 3.1.1 Shutdown Margin (SDM) ................................................ 3.1-1 3.1.2 Reactivity Anomalies ................................................ 3.1-5 3.1.3 Control Rod OPERABILITY ................................................ 3.1-7 3.1.4 Control Rod Scram Times ................................................ 3.1-12 3.1.5 Control Rod Scram Accumulators ................................................ 3.1-15 3.1.6 Rod Pattern Control ................................................ 3.1-18 3.1.7 Standby Liquid Control (SLC) System ................................................ 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ................... 3.1-25 3.2 POWER DISTRIBUTION LIMITS ................................................ 3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ................. 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) .............................................. 3.2-3 3.2.3 Linear Heat Generation Rate (LHGR) ............................................... 3.2-5 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints ............. 3.2-7 3.3 INSTRUMENTATION ................................................ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.1.3 Oscillation Power Range Monitor (OPRM)

Instrumentation ......................... TS/3.3-15a 3.3.2.1 Control Rod Block Instrumentation ....................... 3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation .................................. 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation .............................. 3.3-23 3.3.3.2 Remote Shutdown System .................................. 3.3-26 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation .. 3.3-29 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .................................... 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation ............... 3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ................................... 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation ............................ TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation ............................ 3.3-63 (continued)

SUSQUEHANNA- UNIT 1 TS/TOC -1 Amendment 1%4, gXt 217

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation ...................................... 3.3-67 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation. 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring .3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS) . TS/3.4-1 3.4.1 Recirculation Loops Operating. TS13.4-1 3.4.2 Jet Pumps .3.4-6 3.4.3 Safety/Relief Valves (S/RVs) .3.4-8 3.4.4 RCS Operational LEAKAGE. 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage. 3.4-12 3.4.6 RCS Leakage Detection Instrumentation. 3.4-14 3.4.7 RCS Specific Activity.3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ............... 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .3.4-22 3.4.10 RCS Pressure and Temperature (P/T) Limits .3.4-24 3.4.11 Reactor Steam Dome Pressure. 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM .3.5-1 3.5.1 ECCS - Operating. 3.5-1 3.5.2 ECCS - Shutdown. 3.5-8 3.5.3 RCIC System .3.5-12 3.6 CONTAINMENT SYSTEMS .3.6-1 3.6.1.1 Primary Containment. 3.6-1 3.6.1.2 Primary Containment Air Lock .3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) . TS/3.6-8 3.6.1.4 Containment Pressure .3.6-17 3.6.1.5 Drywell Air Temperature. 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers. 3.6-19 3.6.2.1 Suppression Pool Average Temperature. 3.6-22 3.6.2.2 Suppression Pool Water Level .3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling . TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners .3.6-30 3.6.3.2 Drywell Air Flow System. 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration. 3.6-34 3.6.4.1 Secondary Containment .3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System .3.6-42 (continued)

SUSQUEHANNA - UNIT 1 TS / TOC - 2 Amendment UW4 217

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS ........................................... TS13.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) TS/3.7-1 3.7.2 Emergency Service Water (ESW) System. 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ........................................... TS/3.7-6 3.7.4 Control Room Floor Cooling System ........................................... 3.7-10 3.7.5 Main Condenser Offgas ........................................... 3.7-13 3.7.6 Main Turbine Bypass System ............................................ TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level ........................................... 3.7-17 3.8 ELECTRICAL POWER SYSTEMS ............................................ 3.8-1 3.8.1 AC Sources - Operating ........................................... 3.8-1 3.8.2 AC Sources - Shutdown ........................................... 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .................................... TS/3.8-20 3.8.4 DC Sources - Operating ........................................... 3.8-23 3.8.5 DC Sources - Shutdown ........................................... 3.8-29 3.8.6 Battery Cell Parameters ............................................ 3.8-32 3.8.7 Distribution Systems - Operating ............................................ 3.8-37 3.8.8 Distribution Systems - Shutdown ........................................... 3.8-41 3.9 REFUELING OPERATIONS ........................................... 3.9-1 3.9.1 Refueling Equipment Interlocks ............................................ 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock ........................................... 3.9-3 3.9.3 Control Rod Position ............................................ 3.9-5 3.9.4 Control Rod Position Indication ........................................... 3.9-6 3.9.5 Control Rod OPERABILITY - Refueling ........................................... 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level .................................... 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level .......................... 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level ........................... 3.9-13 3.10 SPECIAL OPERATIONS ............................................ 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ............................ 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ........................................... 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ............................... 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown .............................. 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ...................... 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling .................................... 3.10-16 3.10.7 Control Rod Testing-Operating ........................................... 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ................................ 3.10-20 4.0 DESIGN FEATURES ........................................... 4.0-1 4.1 Site Location ........................................... 4.0-1 4.2 Reactor Core ........................................... 4.0-1 4.3 Fuel Storage ........................................... 4.0-1 (continued)

SUSQUEHANNA - UNIT 1 TS / TOC - 3 Amendment 1,4 217

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ..................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization ..................... 5.0-2 5.3 Unit Staff Qualifications........................................................................ 5.0-5 5.4 Procedures ..................... 5.0-6 5.5 Programs and Manuals ..................... 5.0-7 5.6 Reporting Requirements ..................... 5.0-19 5.7 High Radiation Area ..................... 5.0-27 NFM T IS ta4 TX TS dxc SUSQUEHANNA - UNIT 1 TS/TOC-4 Amendment 1 / l 217

PPL Rev. 0 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 within the limits as specified In the COLR.

APPLICABILITY: THERMAL POWER 2 25% RTP.

ACTIONS NOTE-- -

Separate Condition entry is allowed for each channel.

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

OR A.2 Place associated RPS trip 30 days system in trip OR A.3 Initiate alternate method to 30 days detect and suppress thermal hydraulic instability oscillations.

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

AND B.2 Restore OPRM trip capability 120 days (continued)

SUSQUEHANNA- UNIT 1 TS / 3.3-15a Amendment 217

PPL Rev. 0 OPRM Instrumentation 3.3.1.3 SURVEILLANCE REQUIREMENTS (continued) .-

SURVEILLANCE FREQUENCY SR 3.3.1.3.5 Verify OPRM is not bypassed when THERMAL POWER 24 months is 2 30% RTP and core flow s 65 MLb/Hr. I SR 3.3.1.3.6 - ------ NOTE--

Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS SUSQUEHANNA - UNIT 1 TS /3.3-1 Sc Amendmnent 217

PPL Rev.

Recirculating 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 Inoperation. I OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable: I

a. LCO 3.2.1, -AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR),o single loop operation limits specified Inthe 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 Inthe COLR, and

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

Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 Is reset for single loop operation.

e. Recirculation pump speed IsS 80%.

Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY: M(:)DES 1 and 2.

SUSQUEHANNA - UNIT 1 TS /3.4-1 ArT4endnent 1.8, J4, 2,f5, 2 17

PPL Rev.

Recirculating Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No recirculation loops A.1 Place reactor mode Immediately operating while in switch In the shutdown MODE 1. position.

B. Recirculation loop flow 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 /> mismatch not within recirculation loop with limits. lower flow to be "not In operation."

C. No recirculation loops CA Be InMODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Inoperation while In MODE 2.

OR Single Recirculation Loop required limits and setpoints not established within required time.

SUSQUEHANNA - UNIT 1 TS / 3.4-2 Argend nent t18, j4, 2>, 21IL7

PPL Rev.

Recirculating Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1*

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

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.

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 million Ibm/hr when operating at

< 75 million Ibrn/hr total core flow; and

b. s 5 million Ibrn/hr when operating at 2 75 million Ibm/hr total core flow.

SR 3.4.1.2 ------ -NOTE--

Only required to be met during single loop operations.

Verify recirculation pump speed is within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit specified in the LCO.

SUSQUEHANNA - UNIT 1 TS / 3.4-3 184.2,15, 217

PPL Rev.

Recirculating Loops Operating 3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 1 TS / 3.4-4 Arirendnent V8, K4, 2,5, 217

PPL Rev.

Recirculating Loops Operating 3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 1 TS / 3.4-5 ArTjendroent VS, jf4, PS, 21 7

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam safety/relief valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be 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 Specification 3.2.2;
3. The Linear Heat Generation Rate for Specification 3.2.3;
4. The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and
5. The Shutdown Margin for Specification 3.1.1.
6. The OPRM setpoints for Specification 3.3.1.3.
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an Initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MVWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as Input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM/Tu) as described In the LEFMW7 Topical Report and supplement referenced below. When feedwater flow measurements from the LEFM/Tm system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (continued)

SUSQUEHANNA - UNIT 1 TS /5.0-21 Amendment1O*; 194, f1e; 217

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

7. ANF-91-048(P)(A), 'Advanced Nuclear Fuels Corporation Methodology for.Boiling Water Reactors EXEM BWR, Evaluation Model."
8. XN-NF-79-71 (P)(A), 'Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors.'
9. EMF-1997(P)(A), 'ANFB-10 Critical Power Correlation."
10. Caldon, Inc., TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMV'h System," Engineering Report - 80P.
11. Caldon, Inc., 'Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM/Tu or LEFM CheckPlustu System,", Engineering Report ER -160P.
12. EMF-85-74(P)(A), -RODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."
13. EMF-C074 (P)(A), Volume 4, "BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2."
14. EMF-2158(P)(A), 'Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2."
15. NEDO-32465-A, uBWROG 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 Apendpent 8 1 A6, lb 6, 217

PPL Rev. 0 OPRM Instrumentation 3.3.1.3 ACTIONS (continued)

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

Completion Time not met.

SURVEILLANCE REQUIREMENTS

, ----- NOTED---~------~-~-

When a channel Isplaced Inan 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 System 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 MWD / MT average core exposure SR 3.3.1.3.3 ------------- -NOTE-----

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.3.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months (continued)

SUSQUEHANNA- UNIT 1 TS/3.3-15b Amendment 217

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................................................ 1.1-1 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) .................................................. TS 12.0-1 2.1 SLs ................................................ TS/2.0-1 2.2 SL Violations ................................................ TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ....................... TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ................................................ 3.1-1 3.1.1 Shutdown Margin (SDM) ................................................ 3.1-1 3.1.2 Reactivity Anomalies ................................................ 3.1-5 3.1.3 Control Rod OPERABILITY ........................ ........................ 3.1-7 3.1.4 Control Rod Scram Times ................................................ 3.1-12 3.1.5 Control Rod Scram Accumulators ................................................ 3.1-15 3.1.6 Rod Pattern Control ................................................ 3.1-18 3.1.7 Standby Liquid Control (SLC) System ............................................... 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ................... 3.1-25 3.2 POWER DISTRIBUTION LIMITS ................................................ 3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) .......... ....... 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) .............................................. 3.2-3 3.2.3 Linear Heat Generation Rate (LHGR) ............................................... 3.2-5 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints ............. 3.2-7 3.3 INSTRUMENTATION ................................................ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.1.3 Oscillation Power Range Monitor (OPRM)

Instrumentation ......................... TS/3.3-1 5a 3.3.2.1 Control Rod Block Instrumentation ....................... 3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation .................................. 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation .............................. 3.3-23 3.3.3.2 Remote Shutdown System .................................. 3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation .. 3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .................................... 3.3-34 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .......... TS/3.3-37 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ................................... 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation ............................ TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation ............................ 3.3-63 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation .. 3.3-67 (continued)

SUSQUEHANNA - UNIT 2 TS/TOC -1 Amendment lo', 1%8, 19, 192

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation ........................................... 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring......................................................................................... 3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS) ................................... TS/3.4-1l 3.4.1 Recirculation Loops Operating ................................... TS/3.4-1 3.4.2 Jet Pumps ................................... 3.4-6 3.4.3 Safety/Relief Valves (SIRVs) ................................... 3.4-8 3.4.4 RCS Operational LEAKAGE ................................... 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ................................... 3.4-14 3.4.7 RCS Specific Activity ................................... 3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown .. 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ............................... 3.4-22 3.4.10 RCS Pressure and Temperature (PIT) Limits ............................... 3.4-24 3.4.11 Reactor Steam Dome Pressure ............................... 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ..................................... 3.5-1 3.5.1 ECCS - Operating .............................................. 3.5-1 3.5.2 ECCS - Shutdown ........................................... 3.5-8 3.5.3 RCIC System ............................................ 3.5-12 3.6 CONTAINMENT SYSTEMS ............................................ 3.6-1 3.6.1.1 Primary Containment ........................................... 3.6-1 3.6.1.2 Primary Containment Air Lock ........................................... 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............................ TS/3.6-8 3.6.1.4 Containment Pressure ........................................... 3.6-17 3.6.1.5 Drywell Air Temperature ............................................ 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers ........................ 3.6-19 3.6.2.1 Suppression Pool Average Temperature .......................................... 3.6-22 3.6.2.2 Suppression Pool Water Level ........................................... 3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ........... TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................... 3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners .................................. 3.6-30 3.6.3.2 Drywell Air Row System ........................................... 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration .................................... 3.6-34 3.6.4.1 Secondary Containment ........................................... 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ........................................... 3.6-42 (continued)

SUSQUEHANNA - UNIT 2 TS/TOC - 2 Amendment 1%1, Ue8 192

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS ........................................... TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) .. ............................. TS/3.7-1 3.7.2 Emergency Service Water (ESW) System ............................. 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ........................................... TS/3.7-6 3.7.4 Control Room Floor Cooling System ............................................ 3.7-10 3.7.5 Main Condenser Offgas ........................................... 3.7-13 3.7.6 Main Turbine Bypass System ........................................... TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level ........................................... 3.7-17 3.8 __E LECTRICAL PQ0WERSYSTEMS ........................................... 3.8-1 3.8.1 AC Sources - Operating ........................................... 3.8-1 3.8.2 AC Sources - Shutdown ............................................ 3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .................................... TS/3.8-23 3.8.4 DC Sources - Operating ........................................... 3.8-26 3.8.5 DC Sources - Shutdown ........................................... 3.8-34 3.8.6 Battery Cell Parameters ........................................... 3.8-39 3.8.7 Distribution Systems - Operating......................................................3.8-44 3.8.8 Distribution Systems - Shutdown ............................................ 3.8-50 3.9 REFUELING OPERATIONS ........................................... 3.9-1 3.9.1 Refueling Equipment Interlocks ........................................... 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock ............................................ 3.9-3 3.9.3 Control Rod Position ............................................ 3.9-5 3.9.4 Control Rod Position Indication ........................................... 3.9-6 3.9.5 Control Rod OPERABILITY - Refueling........................................... 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level .................................... 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level .......................... 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level ........................... 3.9-13 3.10 SPECIAL OPERATIONS ........................................... 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ............................ 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ........................................... 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ............................... 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown .............................. 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ...................... 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling .................................... 3.10-16 3.10.7 Control Rod Testing - Operating ........................................... 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling ................................ 3.10-20 4.0 DESIGN FEATURES ........................................... TS14.0-1 4.1 Site Location ........................................... TS/4.0-1 4.2 Reactor Core ............................................. TS/4.0-1 4.3 Fuel Storage ............................................. TS/4.0-1 (continued)

SUSQUEHANNA - UNIT 2 TSITOC - 3 Amendment 1 i, t&8 l 192

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ..................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization ..................... 5.0-2 5.3 Unit Staff Qualifications..................... 5.0-5 5.4 Procedures ..................... 5.0-6 5.5 Programs and Manuals........................................................................ 5.0-7 5.6 Reporting Requirements ..................... 5.0-19 5.7 High Radiation Area ..................... TSI5.0-24 I NFM TS2 Text TOC TS doc SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 1 1, tZ4 I 192

PPL Rev. 0 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 within the limits as specified in the COLR.

APPLICABILITY: THERMAL POWER > 25% R1 ACTIONS

-- NOT Separate Condition entry is allowed for each chann CONDITION REQUIRED ACTION COMPLElION TIME A. One or more required A.1 Place channel in trip. 30 days channels Inoperable.

OR A.2 Place associated RPS trip 30 days system in trip OR A.3 Initiate alternate method to 30 days detect and suppress thermal hydraulic instability oscillations.

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

AND B.2 Restore OPRM trip capablity 120 days (continued)

SUSQUEHANNA - UNIT 2 TS / 3.3-15a Amendment 192

PPL Rev. 0 OPRM Instrumentation 3.3.1.3 ACTIONS (continued) '

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

Completion Time not met.

SURVEILLANCE REQUIREMENTS

_-NOTE -

When a channel Isplaced Inan 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 System 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 MWD / MT average core exposure SR 3.3.1.3.3 -- NOTE--

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.3.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months (continued)

SUSQUEHANNA - UNIT 2 TS / 3.3-15b Amendment 192

PPL Rev. 0 OPRM Instrumentation 3.3.1.3 SURVEILLANCE REOUIREMENTS (continued).

SURVEILLANCE FREQUENCY SR 3.3.1.3.5 Verify OPRM is not bypassed when THERMAL POWER 24 months is a 30% RTP and core flow < 65 MLb/Hr.

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

Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within limits. 24 months orn a STAGGERED TEST BASIS SUSQUEHANNA - UNIT 2 TS /3.3-15c Amendment 192

PPL Rev.

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. I OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable: I

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, and

d. LCO 3.3.1.1, 'Reactor Protection System (RPS) Instrumentation,w Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 Is reset for single loop operation.
e. Recirculation pump speed Is S80%.

-a ~~~----Note ------ a-Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY: MC )DES 1 and 2.

SUSQUEHANNA - UNIT 2 TS / 3.4-1 Amendment 15t

-i5, "y, 192

PPL Rev.

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No recirculation loops A.1 Place reactor mode Immediately operating while in switch in the shutdown MODE 1. position.

B. Recirculation loop flow 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 /> mismatch not within recirculation loop with limits. lower flow to be "not In operation."

C. No recirculation loops C.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 /> In operation while in MODE 2.

OR Single Recirculation Loop required limits and setpoints not established within required time.

SUSQUEHANNA - UNIT 2 TS/3.4-2 Amendmentl151

-i, t96, 192

PPL Rev.

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 -A- ------ E-- -NOTE---

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.

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. s 10 million Ibmn/hr when operating at

< 75 million Ibm/hr total core flow; and

b. S 5 million Ibrn'hr when operating at 2 75 million Ibm/hr total core flow.

SR 3.4.1.2 --- -- NOTE----

Only required to be met during single loop operations.

Verify recirculation pump speed is within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit specified in the LCO.

SUSQUEHANNA - UNIT 2 TS I 3.4-3 Amendment 1t;

-th, 1M, 192

PPL Rev.

Recirculation Loops Operating 3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS / 3.4-4 Amendment tSt

-1 t,1-0 192

PPL Rev.

Recirculation Loops Operating 3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS / 3.4-5 Amendment-1St 5S,;46 19 2

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, Including documentation of all challenges to the main steam safety/relief valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be 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 Specification 3.2.2;
3. The Linear Heat Generation Rate for Specification 3.2.3; 4 The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and
5. The Shutdown Margin for Specification 3.1.1.
6. The OPRM setpoints for Specification 3.3.1.3.
b. The analytical methods used to determine the core operating limits shall be those previously reviewed.and approved by the NRC.

When an Initial assumed power level of 102 percent of rated power Is specified In a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is 1ovided by the Leading Edge Flow Meter (LEFMv) as described In the LEFMV Topical Report and supplement referenced below.

When feedwater flow measurements from the LEFMVTm system are not available, the (continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 469-1t, l92

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

11. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMV'or LEFM CheckPlusTm System." Engineering Report ER-160P.
12. EMF-85-74(P)(A), "RODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."
13. EMF-21 58(P)(A), 'Siemens Power Corporation Methodology for Boiling.

Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2,"

Siemens Power Corporation.

14. EMF-CC-074(P)(A), Volume 4, "BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN B2."
15. NEDO-32465-A, -BWROG Reactor Core Stability Detect and Suppress Solutions Ucensing 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.

5.6.6 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures In the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days.

Reports on EDG failures shall include the information recommended In Regulatory Guide 1.9, Revision 3, Regulatory Position C.4.

(continued)

SUSQUEHANNA - UNIT 2 TS /5.0-23 Amnrnment,1 1,my4, 19O, 192

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 PAM 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.

SUSQUEHANNA - UNIT 2 TS / 5.0-23a Ampnoment 109 aid 4, 196, 192

Retrieved from "https://kanterella.com/w/index.php?title=ML043200202&oldid=2604137"