PLA-5888, Proposed Amendment Nos. 274 and 243 to License Nos. NPF-14 and NPF-22, Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Monthly Operating Reports.

Proposed Amendment Nos. 274 and 243 to License Nos. NPF-14 and NPF-22, Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Monthly Operating Reports.

ML052850299
Person / Time
Site:	Susquehanna
Issue date:	10/05/2005
From:	Mckinney B Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5888
Download: ML052850299 (21)

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Bratn T. McKinney PPL Susquehanna, LLC I'I, &

W40, Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 O T.

Tel. 570.542.3149 Fax 570.542.1504 btmckinneypplweb.com OCT 0 5 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 274 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 243 TO LICENSE NPF-22:

APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO REVISE TECHNICAL SPECIFICATIONS TO ELIMINATE REQUIREMENTS FOR MONTHLY OPERATING REPORTS AND OCCUPATIONAL RADIATION EXPOSURE REPORTS USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS Docket Nos. 50-387 PLA-5888 and 50-388 In accordance with the provisions of 10 CFR 50.90, PPL Susquehanna, LLC is submitting a request for an amendment to the Technical Specifications (TS) for Susquehanna Units 1 and 2.

The proposed amendment would delete the TS requirements to submit monthly operating reports and occupational radiation exposure reports. The change is consistent with NRC-approved Revision 1 to Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report." The availability of this TS improvement was announced in the FederalRegister on June 23, 2004 (69 FR 35067) as part of the Consolidated Line Item Improvement Process (CLIIP).

These proposed changes have been reviewed by the Plant Operations Review Committee and by the Susquehanna Review Committee. provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications. Attachment 2 provides the existing Technical Specification pages marked-up to show the proposed changes. Attachment 3 provides the list of regulatory commitments.

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Document Control Desk PLA-5888 PPL Susquehanna, LLC requests approval of the proposed License Amendment by December 30, 2005, with the amendment and regulatory commitments being implemented within 60 days following approval.

In accordance with 10 CFR 50.91(b), PPL Susquehanna, LLC is providing the Commonwealth of Pennsylvania with a copy of this proposed License Amendment request.

If you have any questions regarding this submittal, please contact Mr. Duane L. Filchner at (610) 774-7819.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: to -0i;i CDw B. T. McKinney Attachments:

Attachment 1 - Description, Applicability, and Verification of the Proposed Change Attachment 2 - Proposed Technical Specification Changes Units 1 & 2, (Mark-ups)

Attachment 3 - List of Regulatory Commitments cc: NRC Region I Mr. B. A. Bickett, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP

Attachment 1 to PLA-5888 Description, Applicability, and Verification of the Proposed Changes

Attachment 1to PLA-5888 Page 1 of 3 DESCRIPTION AND ASSESSMENT

1.0 DESCRIPTION

The proposed License amendment deletes the requirements in Technical Specification (TS) 5.6.1 for an annual report on occupational radiation exposures and TS 5.6.4 for a monthly report of operating statistics and shutdown experience.

The changes are consistent with NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report," Revision 1.

The availability of this Technical Specification Improvement was announced in the FederalRegister on June 23, 2004 (69 FR 35067), as part of the Consolidated Line Item Improvement Process (CLIIP).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision 1 of TSTF-369, the proposed TS changes include:

> Delete TS 5.6.1, Occupational Radiation Exposure Report

> Delete TS 5.6.4, Monthly Operating Reports As addressed in the Safety Evaluation published in the Notice of Availability for TSTF-369, PPL Susquehanna, LLC is proposing to adopt a part of NRC-approved Revision 4 to TSTF-258, "Changes to Section 5.0, Administrative Controls."

Specifically, TS 5.6.4 includes a requirement to include in the monthly operating reports any challenges to safety/relief valves. The NRC model safety evaluation addressed the removal of requirements to submit monthly operating reports in those cases where the TS includes a requirement to address challenges to relief and safety valves (i.e., as in the case where Susquehanna Units 1 and 2 had not yet adopted the associated part of TSTF-258).

The proposed change is consistent with the option described in the Notice of Availability published on June 23, 2004 (69 FR 35067) and the related documentation for both TSTF-369 and the limited portion of TSTF-258 included in this application.

The deletion of these reporting requirements does not result in renumbering of the TS sections. The associated Specifications are shown as "Not Used" such that the following Specification numbering and associated page numbering of subsequent pages were unaffected by this proposed amendment.

Attachment 1 to PLA-5888 Page 2 of 3

3.0 BACKGROUND

The background for this application is adequately addressed by the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369.

4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable Regulatory Requirements and Guidance associated with this application are adequately addressed by the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369.

5.0 TECHNICAL ANALYSIS

PPL Susquehanna, LLC has reviewed the Safety Evaluation (SE) published on June 23, 2004 (69 FR 35067) as part of the CLIIP Notice of Availability. This verification included a review of the NRC staff's SE, as well as the supporting information provided to support TSTF-369. PPL Susquehanna, LLC has concluded that the justifications presented in the TSTF proposal and the SE prepared by the NRC staff are applicable to Susquehanna Steam Electric Station, Unit 1 and Unit 2, and justify this amendment for the incorporation of the changes to the Susquehanna Steam Electric Station, Unit 1 and Unit 2 TS.

6.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369.

6.1 Verifications And Commitments As discussed in the model SE published in the FederalRegister on June 23, 2004 (69 FR 35067) for this TS improvement, PPL Susquehanna, LLC is making the following regulatory commitments:

PPL Susquehanna, LLC is making a regulatory commitment to provide to the NRC using an industry database, the operating data (for each calendar month) that is described in Generic Letter 97-02 "Revised Contents of the Monthly Operating Report," by the last day of the month following the end of each calendar quarter. The regulatory commitment will be based on use of an industry database (e.g., the industry's Consolidated Data Entry (CDE) program, developed and maintained by the Institute of Nuclear Power Operations). This regulatory commitment will be implemented to prevent any gaps in the monthly operating statistics and shutdown experience provided to the NRC (i.e., data for

Attachment 1 to PLA-5888 Page 3 of 3 all months will be provided using one or both systems (monthly operating reports and CDE).

A regulatory commitment for Susquehanna Steam Electric Station, Unit I and Unit 2, to provide information to the NRC annually to support the apportionment of station doses to each type of reactor or to differentiate between operating and shutdown units, is not required since they are not of differing reactor types (i.e., both are BWR-type reactors) and neither unit has ceased operation.

7.0 NO SIGNIFICANT HAZARDS DETERMINATION PPL Susquehanna, LLC has reviewed the proposed "No Significant Hazards Determination" published on June 23, 2004 (69 FR 35067) as part of the CLIIP.

PPL Susquehanna, LLC has concluded that the proposed determination presented in the notice is applicable to Susquehanna Steam Electric Station Unit 1 and Unit 2 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

8.0 ENVIRONMENTAL EVALUATION PPL Susquehanna, LLC has reviewed the environmental evaluation included in the model Safety Evaluation published on June 23, 2004 (69 FR 35067) as part of the CLIIP.

PPL Susquehanna, LLC has concluded that the NRC staff's findings presented in that evaluation are applicable to Susquehanna Steam Electric Station, and the evaluation is hereby incorporated by reference for this application.

9.0 PRECEDENT This application is being made in accordance with the CLIIP. PPL Susquehanna, LLC is not proposing variations or deviations from the TS changes described in TSTF-369 or the NRC staff's model SE published on June 23, 2004 (69 FR 35067).

10.0 REFERENCES

Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specifications Improvement To Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process, published June 23, 2004 (69 FR 35067).

Attachment 2 to PLA-5888 Proposed Technical Specification Changes Units 1 & 2 (Mark-ups)

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 TST (SLs)............................................................................ 12.0-1 2.1 SLs ................................................ T512.0-1 2.2 SL Violations.................................................................................. .TS12.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ j 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ............ .......... Ts3.-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 OPERABIIY............................................................... 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 ................................................... .....32-1 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 ........................ TS/3.3-23 3.3.3.2 Remote Shutdown System .................................. TS/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)

TS/TOC- 1 Amendment 14, 2ZS, *7, *'9 SUSQUEHANNA -

UNIT 1 SUSQUEHANNA - UNIT 1 TS/ TOC - 1 Amendment 10g4, 2t5 t,. 2J7,

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 . TS/3.4-14 3.4.7 RCS Specific Activity .TS/3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ............... TSL3.4-19 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 .TS/3.5-1 3.5.1 ECCS - Operating ... I3.151 3.5.2 ECCS - Shutdown. 3.5-8 3.5.3 RCIC System .TS/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 . TS/3.6-30 3.6.3.2 Drywell Air Flow System .TS/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)

TS/TOC-2 Amendment 1$, ZI'S, 2y7, SUSQUEHANNA -

UNIT 11 SUSQUEHANNA - UNIT TS / TOC - 2 Amendment 1,04, V5,2r,,ZA

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) ............................. TS13.7-1 3.7.2 Emergency Service Water (ESW) System ............................. 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System..................................................................TS13.7-6 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 .. ............................................ TS/3.8-1 3.8.1 AC Sources - Operating .............................................. T/S3.8-1 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)

UNIT 11 TS/TOC-3 Amendment 1,84,2)1'S, ?J1'7,?*

SUSQUEHANNA SUSQUEHANNA - UNIT

- TS/ TOC - 3 Amendment 1X84, X5,V(7,3,

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 ...... . -.V.5.0-199................-

5.7 High Radiation Area ............... 5.0-27 TS1 TOC 3/8s2005 SUSQUEHANNA - UNIT 1 TS /TOC -4 Amendment 1$4, 225, 2y,, 3

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)..................................................T......................... TS/2.0-1 2.1 SLs ............... TS/2.0-1 2.2 SL Violations................................................:T................................. 2.0-1

/TS 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ TS/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 ........................ S/3.3-23 3.3.3.2 Remote Shutdown System .................................. TS/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 - I Amendment )1, 1%8, 10, ',W, ix

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/3.4-1 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 .................................. TS13.4-14 3.4.7 RCS Specific Activity.................................. TS13.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..... TS/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 (PT) 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 ............................... TS/3.5-1 3.5.1 ECCS - Operating ............................................ TS13.5-1 3.5.2 ECCS - Shutdown .......... .................................. 3.5-8 3.5.3 RCIC System.............................................................................. TS 13.5-12 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 .................. .......... TS/3.6-30 3.6.3.2 Drywell Air Flow System ............................................ TS/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 11, 1,8, 1fO, 1182, Jo

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 ELECTRICAL POWER SYSTEMS ............................ TS/3.8-1 3.8.1 AC Sources - Operating ............................ TS/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................................................................................. TS/4.0-1 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)

Amendment 1A1 1$8, 1,0, 1,O2,)6S SUSQUEHANNA -UNIT SUSQUEHANNA - UNIT 22 TS/TOC --33 TS/TOC Amendment 1j61, 1, 1,100, 1)02,>,S

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 0-1 9

S.

.5............................................................-----

5.7 High Radiation Area ................. TS/5.0-24 TS2 TOC I 3118/2005 I

SU SQUERHA NN.A - UNIT 2 TS/TOC - 4 Amendment 1/1, 1i8, 1JO, 1I2, ;ST

PPL Rev.2 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CkR 50.4.

5.6.1 ec>

(.kcupmi

- ------- NTD-----NOE - -

A single subm may be made or both SSES its. The a mittal shou combine secti s common to units at the tion.

A tabul on on an annu basis of number of tion, utility, a other pe nel (including fr whom mon ring was perf Otractors) , recel g an an at deep dose ivalent> mrem and e associated Ilective dee dose uivalent (reporte in perso em) accordin o work and j functions e.g., reactor op ations an surveillance, i ervice insp on, routine maintenance, ial ma tenance (desc' maintenan ), waste prcssing, a d refueling). s tabulatfn supplements e requireme of 10 CFR .2206. he dose assig nts to arious duty fun ons may b e imated ba on poc t ionization amber hermoluminesc nce dosimeter LD), electr ic dosi ter, or film bad e meas ements. Small sures totali < 20 perce of the i ividua total dqre needot be account or. In the aggr gate, at lea 80 perc t of th total d do equivalent rece ed from extemr sources sh d be a -igned specific maj work functions. he report cove* g the previ s calendr year hall be submftt by April 30 of e ch year.

5.6.2 Annual Radiological Environmental Onerating Report

--- NOTE--

A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued)

SUSQUEHANNA - UNIT 1 I5 / 5.0-1 9 Amendment U~

PPL Rev.,

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 = T Lt" Routine ports of Oerating stat ics am hutdown e erience, incIing docu ntation all challen s to the am steamr ety/relief v s, sh be submed on nthly b is no athan theeW of each mth folowjrig the calendar month cover 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 inthe 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 provided by the Leading Edge Flow Meter (LEFMVTm) as described in the LEFMVTm Topical Report and supplement referenced below. When feedwater flow measurements from the LEFMVTM 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 Amendment tf6 1-94; ,,W

PPL Rev.K Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Goupa2opaPi Radiat1io P e eI

__-4 -__----------NOTE-----7----L-------a--~---

A s gte submi may be m e for both S ES units. Tesubmittahould co me s ctions cornon to all uni at the stati .

/A tabuta o on an ar uat basis of ge number o sation, utV , and othe personnel (includj g contract r) for whom ionitoring wK performed, receiving Kannual dsp dose Eulvalent>>00 mrem aw the associ ed coltectiy deep dos equivalent/

(reported in per on-rem) acc ding to wor and job fu ~ions (e.g. eactor ope tions ah surveillan, inservice spection, r ne maint ance, spe at mainten

( escribe mai tenance), ste proces ng, and ref eling). Th' tabulation leme s e requirem nts 0110 R 20.2206The dose ssignment to various functins ay be esti ated bas on pocke onization c amber, th molumines nce dos eter (TLD), ele ronic dosi eter, or fil badge me urements Small expZ ures tot ing

< 20 perc t of the idividual to I dose nee not be a unted for. An the ag egate, at least 80 percent o he total de p dose equi lent recei ed from exemal sou a should be assigned to s ecific majo ork functionl. The report covering the previo s calendar year shall be submitted bypril 30 of each year.

5.6.2 Annual Radiological Environmental Operatinq Report

-- I--- --------- NOTE ---- - ---------------- ---------

A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued)

SUSQUEHANNA - UNIT 2 -TS / 5.0-19 Amendment IS<

PPL Rev./r Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Vonf ted z2&

Routin epo of operatstatistic and shutdowexperie includi ocumentton of allJhalle es to thriain stea safety/reliealves, sf be subrd on a mgnfhly b no ter than )We 15th of 'ch month flowing th~calendar rnnth coverdbyt 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 povided by the Leading Edge Flow Meter (LEFMVT) as described in the LEFMI( Topical Report and supplement referenced below.

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

SUSQUEHANNA - UNIT 2 TS 1 5.0-21 Amendment 169 19, 1w

Attachment 3 to PLA-5888 List of Regulatory Commitments

Attachment 3 to PLA-5888 Page 1 of 1 I LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by PPL Susquehanna in this document. Any other statements in this submittal are provided for informational purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Mr. Duane L. Filchner.

REGULATORY COMMITMENTS Due Date/Event

1. PPL Susquehanna, LLC is making a regulatory Upon implementation of approved commitment to provide to the NRC using an Technical Specification industry database, the operating data (for each amendment, reporting will be calendar month) that is described in Generic made by the last day of the month Letter 97-02 "Revised Contents of the Monthly following the end of each calendar Operating Report." quarter.