PLA-5755, Proposed Amendment No. 265 to License NPF-14 & Proposed Amendment No. 230 to License NPF-22: Application for Technical Specification Improvement to Revise Technical Specification 3.1.8 Scram Discharge Volume.

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Proposed Amendment No. 265 to License NPF-14 & Proposed Amendment No. 230 to License NPF-22: Application for Technical Specification Improvement to Revise Technical Specification 3.1.8 Scram Discharge Volume.
ML042590557
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 09/08/2004
From: Mckinney B
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5755
Download: ML042590557 (44)
v • d • e


Text

I I j Britt T. McKlnney PPL Susquehanna, LLC a M-,-

Vice President-Nuclear Site Operations 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney pplweb.com PPP l4--

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  • a--

SEP 0 8 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 265 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 230 TO LICENSE NPF-22: APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO REVISE TECHNICAL SPECIFICATION 3.1.8 "SCRAM DISCHARGE VOLUME (SDV)

VENT AND DRAIN VALVES," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS Docket Nos. 50-387 PLA-5755 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 for Susquehanna Units 1 and 2.

The proposed changes would revise the required action within Technical Specification (TS) 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves." The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF)

Standard Technical Specification Change Traveler, TSTF-404, Revision 0. The availability of this technical specification improvement was announced in the Federal Register on April 15, 2003 as part of the consolidated line item improvement process (CLIIP).

These proposed changes have been reviewed by the Plant Operations Review Committee and approved 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 change. Attachment 3 provides revised "Camera Ready" TS pages. Attachment 4 provides the corresponding TS Bases "markup" pages. No new regulatory commitments are associated with this change.

Document Control Desk PLA-5755 We request approval of the proposed License Amendment by May 30, 2005, with the amendment 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. Michael H. Crowthers at (610) 774-7766.

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

Executed on: _____

B. T. Mc nney Attachments:

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

Attachment 3 - Proposed Technical Specification Pages Units 1 & 2 (Camera Ready)

Attachment 4 - Technical Specification Bases "Markup" Pages (Provided for Information) cc: NRC Region I Mr. A. J. Blamey, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP

Attachment 1 to PLA-5755 Description, Applicability, and Verification of the Proposed Change

Attachment 1 to PLA-5755 Page 1 of 2 DESCRIPTION AND ASSESSMENT l

1.0 DESCRIPTION

The proposed changes would revise the required action within TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves." These changes are based on Technical Specifications Task Force (TSTF) change traveler TSTF404-A, Revision 0, (hereafter TSTF-404) that has been approved generically for the BWR Boiling Water Reactor/4 Standard Technical Specifications (STS), NUREG-1433, Revision 2. The availability of this technical specification improvement was announced in the FederalRegister on April 15, 2003 as part of the consolidated line item improvement process (CLIIP).

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation PPL Susquehanna LLC has reviewed the safety evaluation published on April 15, 2003 (68 FR 18294) as part of the CLIIP. This verification included a review of the NRC staff's evaluation, as well as the supporting information provided to support TSTF-404.

PPL Susquehanna LLC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Susquehanna Steam Electric Station, Unit 1 (Unit 2) and justify this amendment for the incorporation of the changes to the Susquehanna Steam Electric Station, Unit 1 (Unit 2)

Technical Specifications.

2.2 Optional Changes and Variations PPL Susquehanna LLC is not proposing any variations or deviations from the technical specification changes described in TSTF-404 or the NRC staff's model safety evaluation published on April 15, 2003.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Determination PPL Susquehanna, LLC has reviewed the proposed no significant hazards consideration determination published on April 15, 2003 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 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

3.2 Verification and Commitments See the Attachment 3 for the applicable Regulatory Commitment.

Attachment 1 to PLA-5755 Page 2 of 2 4.0 ENVIRONMENTAL EVALUATION PPL Susquehanna, LLC has reviewed the environmental evaluation included in the model safety evaluation published on April 15, 2003 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.

Attachment 2 to PLA-5755 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 (SLs). 2.0-1 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 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 . . 1-25 3.2 POWER DISTRIBUTION LIMITS .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 3.3.2.1 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 .. 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 1 i Amendment 104, 2/5

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) .................................. 3.4-1 3.4.1 Recirculation Loops Operating ................................... 3.4-1 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) ................................. 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 ................ 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)

Amendment I $4, ?1 5 SUSQUEHANNA -UNIT SUSQUEHANNA - UNIT 1I iiii Amendment 104, ?i5

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS ................................ 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) . 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 ... 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 Maih Turbine Bypass System ... 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 ....................................... 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 Amendment 1 5 iii

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 TS1 text TOC.doc SUSQUEHANNA - UNIT 1 iv Amendment 1 , 2i5

PPL Rev. 0 em E ~.tV.ŽJi'vt com-pdl -4o ' I/C.- d'c'-1--s / SDVVen itand Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE and open.

APPLICABILITY: MODES 1 and 2.

ACTIONS

/earae C n entdorthe-------------a . _ ___ _

L ....)Separate Condition entry is allowed for the SDV vent line and drain line.

(E - A.V4SDV vent or drain line with one valve inoperable B. SDV vent or drain line with both valves inoperable.

SUSQUEHANNA - UNIT I I S/3.1-25 Amendment 17f'

PPL Rev. 0 SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 ---- NOTE- E- -

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully 92 days closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in *30 seconds after receipt of an actual or simulated scram signal; and
b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT I T5/3.1-26 Amendment4s8

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS)

- 1.0 USE AND APPLICATION ............................ 1.1-1

. Definitions ............ 1.1-1

  • 12 Logical Connectors .... 1.2-1 1.3 Completion Times . 1.3-1 1.4 Frequency ................. 1.4-1 2.0 SAFETY LIMITS (SLs) . 2.0-1 2.1 2.1 SLs .. ................................................................................................

S~s..... 2.0-1 2o 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 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 ................... j.1.2 5 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 0 2.3 Linear Heat Generation Rate (LHGR) ......................... . 3.2-5 b3.2.4 Average Power Range Monitor (APRM)...Gain and Setpoints ............ 3.2-7 3.3 INSTRUMENTATION .3.3............... .3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation ........................ ..- 10 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 ............... 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 ................................. 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)

Amendment 1'1, 18, 120 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 2 2 i Amendment 1!1, 1X8, 1,

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) ..................................3.4-1 3.4.1 Recirculation Loops Operating. 3.4-1 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 (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.-1 3.5.2 ECCS - Shutdown. 3.5-8 3.5.3 RCIC System .3.5-12 W 3.6 CONTAINMENT SYSTEMS ..................... 3.6-1 3.6.1.1 Primary Containment........3..........................................3..................63.-1 3.6.1.2 Primary Containment Air Lock..................... 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ................................ 3.6-3.6.1.4 Containment Pressure.......................................................................3.17 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 Coling .3.6-26. . . - - . . - -I . . . r :

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

Amendment i1, 158, SUSQUEHANNA-- UNIT SUSQUEHANNA UNIT 22 iiii Amendment 1i, 1T8, 17

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS ..................................... 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) Systemn and the Ultimate Heat Sink (UHS) . . 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.................................................................... 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 .................... 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 ................ . 3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . .. 3.8-23 3.8.4 DC Sources - Operating ....................... 3.8-26 3.8.5 DC Sources - Shutdown .. . . 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 WaterLevel . ............. 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 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 Contrpl 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........................................................................................4.01 4.2 Reactor Core........................................................................................4.01 4.3 Fuel Storage.........................................................................................4. -1 (continued)

SUSQUEH LANNA - UNIT 2 iii Amendment i1g, 108, 1)'

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 5.-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 . 5.0-24 NFM TS2 Texd TOC.doc SUSQUEHANNA - UNIT 2 is Amendment ii1, 1A,1?6

,-Am i< j5cic,4e.I /; ye gnaw (e.th,CA1I'C \

/ .1t.^ 3t'oi.cjE+/- Cc...i.'l A. <

csJv 2 PPL Rev. 0

. cdojSB\w dy(}c ^ .,e.s45 SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS

.3.1.8 Scram Discharge Volume (SDV) Vent ar id Drain Valves LCO 3.1. 8 Each SDV vent and drain valve shall Ibe OPERABLE and open.

APPLICABILITY: MODES 1 and 2.

a ACTIONS ( Ie

/ -NOTE-/

lSeparate Condition entry is allowed for the SDV vent Iiline and drain line.

__ A.

I I

SUSQUEHANNA - UNIT 2 T/3.1 -25 Amendment 161

PPL Rev. 0 SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 -- -NOTE Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully 92 days closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in c 30 seconds after receipt of an actual or simulated scram signal; and
b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT 2 - 13.1-26 Amendment +1

Attachment 3 to PLA-5755 Proposed Technical Specification Pages Units 1 & 2

("Camera Ready")

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) ................................................ 2.0-1 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 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 ............... TS/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 3.3.2.1 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 ................................. 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 1 i Amendment 1g4, t1 5

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). 3.4-1 3.4.1 Recirculation Loops Operating .3.4-1 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) ................................. 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 .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) iiii Amendment 104, 2/15 SUSQUEHANNA - UNIT 1 SUSQUEHANNA -

1 Amendment 1g4, 2215

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS .................................. 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ............................. 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 .................................. 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 .................................. 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. 3.81 3.8.2 AC Sources - Shutdown. 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .3.8-20 3.8.4 DC Sources - Operating .3.8-23 3.8.5 . DC Sources - Shutdown .3.8 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 UNIT 11 iii Amendment 1?4, gAS SUSQUEHANNA -

iii Amendment 1?4, 2,15

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 TS1 text TOC.doc 5/3104 SUSQUEHANNA - UNIT 1 iv Amendment 19 2t5

PPL Rev. 1 SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE and open.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTES-----------------------------------------------------

1. Separate Condition entry is allowed for the SDV vent line and drain line.
2. An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent or A.1 Isolate the associated line. 7 days drain lines with one valve inoperable.

B. One or more SDV vent or B.1 Isolate the associated line. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> drain lines with both valves inoperable. I1 C. Required Action and 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 /> associated Completion Time not met.

SUSQUEHANNA - UNIT 1 TS /3.1-25 Amendment 17yE

PPL Rev. 1 SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 ---------------------------- NOTE---------------------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully 92 days closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in *30 seconds after receipt of an actual or simulated scram signal; and
b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT 1 TS /3.1-26 Amendment 17j6

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) ................................ 2.0-1 2.1 SLs... ....................... 2.0-1 2.2 SL Vidlations ....... 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 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 ............... TS/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 3.3.2.1 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 ............... 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 ................................. 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)

Amendment 1, 18, 1,0 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 22 i Amendment 1F1, 1%8, 1,io

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) .................................................. 3.4-1 3.4.1 Recirculation Loops Operating .................................................. 3.4-1 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) ................................. 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 ................ 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 2 ii Amendment 1i%, 1 8, 1}05

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS ................................ 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ............................. 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 ............................... 3.7-6 3.7.4 Control Room Floor Cooling System ............................... 3.7-10 3.7.5 Main Condenser Off gas ............................... 3.7-13 3.7.6 Main Turbine Bypass System ................................ 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 ............................... 3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ............................... 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 399................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) 2 SUSQUHANNA- UNT ii Amndmen 151 1.8 .~

SUSQUEHANNA - UNIT 2 Amendment 151, 198, t§°0 iii

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ....................... 5.0-1 5.1 Responsibility..............................................................5......................... 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 ....................... 5.0-24 TS2 Text TOC.doc 513104 SUSQUEHANNA - UNIT 2 IV Amendment 1/51, I A8 1wA

PPL Rev. 0 SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1. 8 Each SDV vent and drain valve shall be OPERABLE and open.

APPLICABILITY: MODES 1 and 2.

ACTIONS

___ a__ i______________________ r_'IT~e_______________ _

M, I CO - ------ - . --

1. Separate Condition entry is allowed for the SDV vent line and drain line.
2. An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent or A.1 Isolate the associated line. 7 days drain lines with one valve inoperable.

B. One or more SDV vent or B.1 Isolate the associated line. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> drain lines with both valves inoperable.

C. Required Action and 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 /> associated Completion Time not met.

SUSQUEHANNA - UNIT 2 TS / 3.1-25 Amendment 1VI

w PPL Rev. 0 SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 -- ----- --- NOTE-------------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully 92 days closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in < 30 seconds after receipt of an actual or simulated scram signal; and
b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT 2 TS /3.1-26 Amendment 1VII

Attachment 4 to PLA-5755 Technical Specification Bases 'Markup" Pages (Provided for Information)

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves BASES BACKGROUN ID. The SDV vent and drain valves are normally open and discharge any accumulated water in the SDV to ensure that sufficient volume is available at all times to allow a complete scram. During a scram, the SDV vent and drain valves close to contain reactor water. The SDV is a volume of header piping that connects to each hydraulic control unit (HCU) and drains into an instrument volume. There are two SDVs (headers) and two instrument

- volumes, each receiving approximately onet half of t; ic control rod drive (CRD) discharges. The two instrument volumes are connected to a cowim6n drain line with two valves in series. Each header is connected to a common vent line with two valves in series. The header piping is sized to receive and contain all the water discharged by the CRDs during a scram. The design and functions of the SDV are described in Reference 1.

APPLICABLE The Design Basis Accident and transient analyses assume all of the control SAFETY rods are capable of scramming. The acceptance criteria for the SDV vent ANALYSES and drain valves are that they operate automatically to:

a. Close during scram to limit the amount of reactor coolant discharged so that adequate core cooling is maintained and offsite doses remain within the limits of 10 CFR 100 (Ref. 2); and
b. Open on scram reset to maintain the SDV vent and drain path open so that there is sufficient volume to accept the reactor coolant discharged during a scram.

Isolation of the SDV can also be accomplished by manual closure of the SDV valves. Additionally, the discharge of reactor coolant to the SDV can be terminated by scram reset or closure of the HCU manual isolation valves. For a bounding leakage case, the offsite doses are well within the limits of 10 CFR 100 (Ref. 2), and adequate core cooling is maintained (Ref. 3). The SDV vent and drain valves allow continuous drainage of the SDV during normal plant operation (continued)

SUSQUEHANNA- UNIT I B 3.1-47 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES APPLICABLE to ensure that the SDV has sufficient capacity to contain the reactor coolant SAFETY discharge during a full core scram. To automatically ensure this capacity, a ANALYSES reactor scram (LCO 3.3.1.1, "Reactor Protection System (RPS)

(continued) Instrumentation") is initiated if the SDV water level in the instrument volume exceeds a specified setpoint. The setpoint is chosen so that all control rods are inserted before the SDV has insufficient volume to accept a full scram; SDV vent and drain valves satisfy Criterion 3 of the NRC Policy Statement (Ref. 4).

LCO The OPERABILITY of all SDV vent and drain valves ensures that the SDV vent and drain valves will close during a scram to contain reactor water discharged to the SDV piping. The SDV vent and drain valves are required to be open to ensure the SDV is drained. Since the vent and drain lines are.

provided with two valves in series, the single failure of one valve in the open position will not impair the isolation function of the system. Additionally, the valves are required to open on scram reset to ensure that a path is available for the SDV piping to drain freely at other times.

APPLICABILITY In MODES I and 2, scram may be required; therefore, the SDV vent and drain valves must be OPERABLE. In MODES 3 and 4, control rods are not able to be withdrawn (except as permitted by LCO 3.10.3 and LCO 3.10.4) since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate controls to ensure that only a single control rod can be withdrawn. Also, during MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies. Therefore, the SDV vent and drain valves are not required to be OPERABLE in these MODES since the reactor is subcritical and only one rod may be withdrawn and subject to scram.

ACTIONS The ACTIONS table is modified bye Notdiindicating that a separate Condition entry is allowed for the SDV vent line and the SDV drain line.

This is acceptable, since the (continued)

SUSQUEHANNA - UNIT 1 B 3.1-48 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES ACTIONS

  • Required Actions for each Condition provide appropriate compensatory (continued) actions for each inoperable SDV line. Complying with the Required Actions may allow for continued operation, and subsequent inoperable SDV lines are
  • governed by subsequent Condition entry and application of associated Required Actions.

When one SDV vent or drain valve srPstorBo ALE Bsttus~-wth

'5b1Tiy to contai eactor coolduring a scra ost. If one or b valves in ent line or d e is closed, potential for an iTertent scra ue to high level is increase. Therefore, bo enting and draining capa and isolatiorucsabilitv must be re. red.

The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time to r e s1tig and dCAi it ('

nutemeti

%1 t LA is based on the low probability of a scram occurring while the line is not isolated and unlikelihood of significant CRD

. 4 Pamcc'4 .. w Ca ,; seal leakage.

t4 ypci ~4- C Je C.1

&kyr5Cj 5 CVCAtV1.

If any Required Action and associated Completion Time is not met, the plant must be brought to a MODE in which the LCO (continued)

SUSQUEHANNA- UNITI B B 3.1-49 Revision 0-

LCO 3.1.8 BASES INSERT:

The ACTIONS table is modified by a second note stating that a isolated line may be unisolated under administrative control to allow draining and venting of the SDV. When a line is isolated, the potential for an inadvertent scram due to high SDV level is increased. During these periods, the line may be unisolated under administrative control. This allows any accumulated water in the line to be drained, to preclude a reactor scram on high SDV level. This is acceptable since the administrative controls ensure the valve can be closed quickly, if a scram occurs with the valve open.

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES ACTIONS C.1 (continued) does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12.hours. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.1.8.1 REQUIREMENTS During normal operation, the SDV vent and drain valves should be in the open position (except when performing SR 3.1.8.2) to allow for drainage of the SDV piping. Verifying that each valve is in the open position ensures that the SDV vent and drain valves will perform their intended functions during normal operation. This SR does not require any testing or valve manipulation; rather, it involves verification that the valves are in the correct position.

The 31 day Frequency is based on engineering judgment and is consistent with the procedural controls governing valve operation, which ensure correct valve positions.

SR 3.1.8.2 During a scram, the SDV vent and drain valves should close to contain the reactor water discharged to the SDV piping. Cycling each valve through its complete range of motion (closed and open) ensures that the valve will function properly during a scram. The 92 day Frequency is based on operating experience and takes into account the level of redundancy in the system design.

SR 3.1.8.3 SR 3.1.8.3 is an integrated test of the SDV vent and drain valves to verify total system performance. After receipt of a simulated or actual scram signal, the closure of the SDV vent and drain valves is verified.

The closure time of (continued)

SUSQUEHANNA - UNIT 1 B 3.1-50 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES SURVEILLANCE SR 3.1.8.3 (continued)

REQUIREMENT 30 seconds after receipt of a scram signal is based on the bounding leakage case evaluated in the accident analysis based on the requirements of Reference 2. Similarly, after receipt of a simulated or actual scram reset signal, the opening of the SDV vent and drain valves is verified. The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.1.1 and the scram time testing of control rods in LCO 3.1.3 overlap this Surveillance to provide complete testing of the assumed safety function; The 24 month Frequency is based on the need to perform portions d. this Surveillance under the conditions that apply during a plant outage and the potential tor an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at the 24 month Frequency; therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

REFERENCES 1. FSAR, Section 4.6.

2. 10 CFR 100.
3. NUREG-0803, "Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping," August 1981.
4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

SUSQUEHANNA- UNIT I B 3.1-51 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves BASES BACKGROUND The SDV vent and drain valves are normally open and discharge any accumulated water in the SDV to ensure that sufficient volume is available at all times to allow a complete scram. During a scram, the SDV vent and drain' valves close to contain reactor water. The SDV is a volume of header piping that connects to each hydraulic control unit (HCU) and drains into an instrument volume. There are two SDVs (headers) and two instrument volumes, each receiving approximately one half of the control rod drive (CRD) discharges. The two instrument volumes are connected to a common drain line with two valves in series. Each header is connected to a common vent line with two valves in series. The header piping is sized to receive and contain all the water discharged by the CRDs during a scram. The design and functions of the SDV are described in Reference 1.

APPLICABLE The Design Basis Accident and transient analyses assume all of the control SAFETY rods are capable of scramming. The acceptance criteria for the SDV vent ANALYSES and drain valves are that they operate automatically to:

a. Close during scram to limit the amount of reactor coolant discharged so that adequate core cooling is maintained and offsite doses remain within the limits of 10 CFR 100 (Ref. 2); and
b. Open on scram reset to maintain the SDV vent and drain path open so that there is sufficient volume to accept the reactor coolant discharged during a scram.

Isolation of the SDV can also be accomplished by manual closure of the SDV valves. Additionally, the discharge of reactor coolant to the SDV can be terminated by scram reset or closure of the HCU manual isolation valves.

For a bounding leakage case, the offsite doses are well within the limits of 10 CFR 100 (Ref. 2), and adequate core cooling is maintained (Ref. 3). The SDV vent and drain valves allow continuous drainage of the SDV during normal plant operation (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.1-47 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES APPLICABLE to ensure that the SDV has sufficient capacity to contain the reactor coolant SAFETY discharge during a full core scram. To automatically ensure this capacity, a ANALYSES reactor scram (LCO 3.3.1.1, "Reactor Protection System (RPS)

(continued) Instrumentation") is initiated if the SDV water level in the instrument volume exceeds a specified setpoint. The setpoint is chosen so that all control rods are inserted before the SDV has insufficient volume to accept a full scram.

SDV vent and drain valves satisfy Criterion 3 of the NRC Policy Statement (Ref. 4).

LCO The OPERABILITY of all SDV vent and drain valves ensures that the SDV vent and drain valves will close during a scram to contain reactor water discharged to the SDV piping. The SDV vent and drain valves are required to be open to ensure the SDV is drained. Since the vent and drain lines are provided with two valves in series, the single failure of one valve in the open position will not impair the isolation function of the system. Additionally, the valves are required to open on scram reset to ensure that a path is available for the SDV piping to drain freely at other times.

APPLICABILITY In MODES 1 and 2, scram may be required; therefore, the SDV vent and drain valves must be OPERABLE. In MODES 3 and 4, control rods are not able to be withdrawn (except as permitted by LCO 3.10.3 and LCO 3.10.4) since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate controls to ensure that only a single control rod can be withdrawn. Also, during MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies. Therefore, the SDV vent and drain valves are not required to be OPERABLE in these MODES since the reactor is subcritical and only one rod may be withdrawn and subject to scram.

ACTIONS The ACTIONS table is modified byoNote indicating that a separate Condition entry is allowed for the SDV vent line and the SDV drain line. This is acceptable, since the (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.1-48 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES ACTIONS Required Actions for each Condition provide appropriate compensatory (continued) actions for each inoperable SDV line. Complying with the Required Actions may allow for continued operation, and subsequent inoperable SDV lines are governed by subsequent Condition entry and application of associated Required Actions.

OrdalPC,g t /e~1 Lseeby 2 9 A.1 When one SDV vent or drain valve is inoperableC o the

- e The Completion Timeis-k ~dai tpreasonatle pa AS~Ci<stA' IlA U5' > is maiiainediisAhows aIo probailitystascma

/ II * .. ,, occumng while the valve(s) are inoperab1e. The SDV isstill isolable since ( f

'the redundant valve in the affectedline is OPERABLE. Duringthese t r t LlIlt I' / iperiods, the single failure criterion is not preserved, and a higher risk exists

/ / ~to allow reactor water out of the primary system during a scram.

,) B.1 qd He l;- 4A S Vj ) If,abF both Xto valves in athe contan linereare or inoperable automati during acram If one orandththe is loscapability solation valvls in a v nt line drain lin closede potentia or an inadrtent/

s am duiyto high V level' increase Therefor ,both ye g andv/

~rainn capabilit and isolation capabili must be rstored.

/ >The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time to f'zOrS venting and dra~ining sap~iW arid rA ho a"t4tomcti cip0bfityis based on the low probability of a scram

- ioccurring while the line is not isolated and unlikelihood of significant CRD 15s,5.l C444} 4 c3 'a'"-( -- s6el leakage; -

i c Scttcv t -. C.1 If any Required Action and associated Completion Time is not met, the plant must be brought to a MODE in which the LCO (continued)

SUSQUEHANNA - UNIT 2 TS / B3.1-49 Revision 0

LCO 3.1.8 BASES INSERT:

The ACTIONS table is modified by a second note stating that an isolated line may be unisolated under administrative control to allow draining and venting of the SDV. When a line is isolated, the potential for an inadvertent scram due to high SDV level is increased. During these periods, the line may be unisolated under administrative control. This allows any accumulated water in the line to be drained, to preclude a reactor scram on high SDV level. This is acceptable since the administrative controls ensure the valve can be closed quickly, if a scram occurs with the valve open.

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES ACTIONS . CA (continued) does not apply. To achieve this status, the plant must be brought to at least

  • . MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.1.8.1 REQUIREMENTS During normal operation, the SDV vent and drain valves should be in the open position (except when performing SR 3.1.8.2) to allow for drainage of the SDV piping. Verifying that each valve is in the open position ensures that the SDV vent and drain valves will perform their intended functions during normal operation. This SR does not require any testing or valve manipulation; rather, it involves verification that the valves are in the correct position.

The 31 day Frequency is based on engineering judgment and is consistent with the procedural controls governing valve operation, which ensure correct valve positions.

SR 3.1.8.2 During a scram, the SDV vent and drain valves should close to contain the reactor water discharged to the SDV piping. Cycling each valve through its complete range of motion (closed and open) ensures that the valve will function properly during a scram. The 92 day Frequency is based on -

operating experience and takes into account the level of redundancy in the system design.

SR 3.1.8.3 SR 3.1.8.3 is an integrated test of the SDV vent and drain valves to verify total system performance. After receipt of a simulated or actual scram signal, the closure of the SDV vent and drain valves is verified. The closure time of (continued)

SUSQUEHANNA - UNIT 2 TS I B 3.1-50 Revision 0

PPL Rev. 0 SDV Vent and Drain Valves B 3.1.8 BASES SURVEILLANCE SR 3.1.8.3 (continued)

REQUIREMENTS 30 seconds after receipt of a scram signal is based on the bounding leakage case evaluated in the accident analysis based on the requirements of Reference 2. Similarly, after receipt of a simulated or actual scram reset.

signal, the opening of the SDV vent and drain valves is verified. The LOGIC' SYSTEM FUNCTIONAL TEST in LCO 3.3.1.1 and the scram time testing of control rods in LCO 3.1.3 overlap this Surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform portions of this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at the 24 month Frequency; therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

REFERENCES 1. FSAR, Section 4.6.

2. 10 CFR 100.
3. NUREG-0803, "Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping," August 1981.
4. Final Policy Statement on Technical Specifications Improvements,

, July 22, 1993 (58 FR 39132).

SUSQUEHANNA - UNIT 2 TS / B 3.1-51 Revision 0

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