PLA-5882, Proposed Amendment No. 273 & 242 to License NPF-14 & NPF-22: Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using.

Proposed Amendment No. 273 & 242 to License NPF-14 & NPF-22: Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using.

ML052850297
Person / Time
Site:	Susquehanna
Issue date:	10/05/2005
From:	Mckinney B Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5882
Download: ML052850297 (25)

Text

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& 3a I* I P' I**el Britt T. McKlnney PPL Susquehanna, LLC Senior Vice President &Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 El Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com aft...

OCT 0 5 20G5 T.

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OPI-17 Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 273 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 242 TO LICENSE NPF-22:

APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO REVISE TECHNICAL SPECIFICATIONS TO ELIMINATE REQUIREMENTS FOR HYDROGEN RECOMBINERS AND HYDROGEN/OXYGEN MONITORS USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS D( )cket Nos. 50-387 PLA-5882 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 will delete the TS requirements related to hydrogen recombiners, containment hydrogen monitors and containment oxygen monitors. The proposed TS changes support implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on September 16, 2003 (68 FR 54141). The changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003 (68 FR 555416) as part of the consolidated line item improvement process (CLIIP). Also included are markups of the Table of Contents pages which convey editorial changes to TS page numbers.

These proposed changes have been reviewed by the Plant Operations Review Committee and by the Susquehanna Review Committee.

Document Control Desk PLA-5882 provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications and commitments. Attachment 2 provides the existing TS pages marked-up to show the proposed change. Attachment 3 provides the list of regulatory commitments. Implementation of TSTF-447 also involves various changes to the TS Bases. The TS Bases changes will be submitted with a future update in accordance with TS 5.5.10, "Technical Specifications (TS) Bases Control Program."

PPL Susquehanna, LLC requests approval of the proposed License Amendment by March 31, 2006 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: /ia -s 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-5882 Description, Applicability, and Verification of the Proposed Change

Attachment 1 to PLA-5882 Page 1 of 3 I -- DESCRIPTION AND ASSESSMENT I

1.0 INTRODUCTION

The proposed License amendment deletes Technical Specification (TS) 3.6.3.1, "Primary Containment Hydrogen Recombiners," and the requirements for the containment hydrogen analyzer and containment oxygen analyzer in TS 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation." The proposed TS changes support implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on September 16, 2003 (68 FR 54141). The deletion of the requirements for the hydrogen recombiner, hydrogen analyzers, and oxygen analyzers did not result in renumbering of the TS sections. The associated Specifications and related surveillance requirements are shown as "Not Used" such that the Specification numbering and subsequent page numbering were unaffected by this proposed amendment.

The changes are consistent with Revision 1 of NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the FederalRegister on September 25, 2003 (68 FR 55416) 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-447, the proposed TS changes include:

> Delete Table 3.3.3.1, Function 8, Containment H2 & 02 Analyzer

> Delete TS 3.6.3.1, Primary Containment Hydrogen Recombiners As described in NRC approved Revision 1 of TSTF-447, the changes to TS requirements result in changes to the associated TS Bases sections. The TS Bases changes will be submitted with a future update in accordance with TS 5.5.10, "Technical Specifications (TS) Bases Control Program."

3.0 BACKGROUND

The background for this application is adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking (68 FR 54141), and other related documents.

Attachment 1 to PLA-5882 Page 2 of 3 4.0 REGULATORY GUIDANCE AND REQUIREMENTS The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking (68 FR 54141), and other related documents.

5.0 TECHNICAL ANALYSIS

PPL Susquehanna, LLC has reviewed the safety evaluation (SE) published on September 25, 2003 (68 FR 55416) 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-447. 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 I 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 September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking (68 FR 54141), and other related documents.

6.1 Verifications And Commitments As discussed in the model SE published in the Federal Register on September 25, 2003 (68 FR 55416) for this TS improvement, PPL Susquehanna, LLC is making the following verifications and regulatory commitments:

1. PPL Susquehanna, LLC has verified that a hydrogen monitoring system capable of diagnosing beyond design-basis accidents is installed at Susquehanna Steam Electric Station, Unit 1 and Unit 2 and is making a regulatory commitment to maintain that capability. The hydrogen monitors will be included in the Technical Requirements Manual prior to implementation of the approved TS amendment.

2. Susquehanna Steam Electric Station, Unit 1 and Unit 2, has an inerted containment. PPL Susquehanna, LLC has verified that an oxygen monitoring system capable of verifying the status of the inerted containment is installed at Susquehanna Steam Electric Station, Unit 1 and Unit 2 and is making a

Attachment 1 to PLA-5882 Page 3 of 3 regulatory commitment to maintain that capability. The oxygen monitors will be included in the Technical Requirements Manual prior to implementation of the approved TS amendment.

7.0 NO SIGNIFICANT HAZARDS DETERMINATION PPL Susquehanna, LLC has reviewed the proposed no significant hazards consideration determination published on September 25, 2003 (68 FR 55416) 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 September 25, 2003 (68 FR 55416) 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-447 or the NRC staff's model SE published on September 25, 2003 (68 FR 55416).

10.0 REFERENCES

Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specifications Improvement To Eliminate Hydrogen Recombiner Requirement, and Relax the Hydrogen and Oxygen Monitor Requirements for Light Water Reactors Using the Consolidated Line Item Improvement Process, published September 25, 2003 (68 FR 55416).

Attachment 2 to PLA-5882 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) ................................................ TS/2.0-1 2.1 SLs ................................................ TS/2.0-1 2.2 SL Violations ................................................ TSt2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ......... 13.0-1 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 ............... 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). 32-5 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 ...................... 13 3.3-23 3.3.3.2 Remote Shutdown System........................................................ 7 1/ . 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)

TSITOC- 1 Amendment 1Z4, 2*, 2.*7, 2g2 SUSQUEHANNA -

UNIT 1 SUSQUEHANNA - UNIT 1 TS / TOC - 1 Amendment 104, MS, RV7, 2;Z2

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 .TS/3.4-1 3.4.2 Jet Pumps . 3.4-6 3.4.3 Safety/Relief Valves (SRVs)..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 ... . .. . rsf- 3-123.5-1........--

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 (PCI-Vs). TS/3.6-8 3.6.1.4 Containment Pressure ............ ............................. 4.. 3.6-17 3.6.1.5 Drywell Air Temperature ............. ........................I...... 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 CntainmORt Hydrgen flocombirc .......................-

r/3.6-30 3.6.3.2 Drywell Air Flow System ... ............................................ rff. 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration .................................... 3.6-34 3.6.4.1 Secondary Containment ............................................ 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ............................................ 3.6-42 (continued)

SUSQUEHANNA - UNIT 1 TS / TOC - 2 Amendment 1,$, Z5, 2F7, ?2t

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 ............................................ TSt3.7-6 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............................................. TS13.7-15 3.7.7 Spent Fuel Storage Pool Water Level ............................................ 3.7-17 3.8 ELECTRICAL POWER SYSTEMS ...............................................-W;.3.8-1 3.8.1 AC Sources - Operating .n/.3.8-1 3.8.2 AC Sources - Shutdown ................. TS./3.8-17 1 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 ................ TS/3.8-37 3.8.8 Distribution Systems - Shutdown ................ TS/3.8-41 3.9 REFUELING OPERATIONS ................ 3.9-1 3.9.1 Refueling Equipment Interlocks ................ 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock ................ 3.9-3 3.9.3 Control Rod Position ................ 3.9-5 3.9.4 Control Rod Position Indication ................ 3.9-6 3.9.5 Control Rod OPERABILITY - Refueling ................ 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level ................ 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level ................ 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level ................. 3.9-13 3.10 SPECIAL OPERATIONS .................. 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ............ .... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ................ 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ................ 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown ................ 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................ 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling ................ 3.10-16 3.10.7 Control Rod Testing-Operating ................ 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ................ 3.10-20 4.0 DESIGN FEATURES ................ 4.0-1 4.1 Site Location ................ 4.0-1 4.2 Reactor Core ................ 4.0-1 4.3 Fuel Storage ................ 4.0-1 (continued)

SUSQUEHANNA - UNIT 1 TS/ TOC - 3 Amendment 1,$4, 2*5, ?7, 2t2

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........................................... 5.0-7 5.6 Reporting Requirements ...... 5.0-19 5.7 High Radiation Area ...... 5.0-27 G:AGoadmIn\LUC\Typing\TS1 text TOC TSTF16.doc 7129/05 SUSQUEHANNA - UNIT 1 TS/I TOC - 4 Amendment 1$4, t25, 2y1, g2

PPL RevX PAM Instrumentation 3.3.3.1.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition referenced Immediately associated in Table 3.3.3.1-1 for the Completion Time of channel.

Condition C not met E. As required by E.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 /> Required Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by F.1 Initiate action in accordance Immediately Required with Specification 5.6.7.

Action D.1 and referenced in Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS, These SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK 31 days SR 3.3.3.1.2 Perfermn CGI AWNMEL CABURATION of theePimar'f .Q2 dey Gentari. enl l l. and OEAnalycr.

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for all Functions 24 months except&44fa-GAiRRFA__l rp

,ed. PCIV Position.

.__ tD .~

SUSQUEHANNA - UNIT 1 -r / 3.3-24 Amendmnent ;-_

PPL Rev. K' PAM Instrumentation 3.3.3.1 Table 33.1-1 (page 1 of 1)

Pos Accident Monitorng Iimela n CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1

1. Reactor Steam Dome Pressue 2 E

2. Reactor Vessel Water Level

a. Wide Range 2 E

b. Extended Range 2 E

c. Fuel Zone Range 2 E I1 Suppression Chamber Water Level 2 E.

3.

4. Prlmary Containment P essure

a. Accident Range 2 E

b. LOCA Range 2 E

5. Pnmary Containment High Radiation 2 F

6. PCIV Positon 2 per penetration flow pathi E

7. Neutron Fh.x 2 E

8. Drywel Atmnophere Tempeniture 2 E

10. Suppresson Chamber Water Temperatue 2 E (a) Nd feouwed for isolaon valves whose associated penetration flow path is Isolated by at least ne closed and deactived automatic Valve, c d manual valve, blind flange, or check valve with flow through te valve sectxed.

(b) Only one positon hdication channel Is required for penetration flow paths with only one installed contrl rom idication channel No 4- L le l SUSQUEHANNA - UNIT 1 - / 3.3-25 Amendment PC

PPL Rev.r 3.6 4CONTAINMENT SYSTEMS 3.6.3.1 -4 LG9 3.6.4.4 -Twdd"well and tWm supf lM9asicn chamber hy'drogon rFcombincrs chll be

-GPERAS6E-

-,PPICeA5Ib9P.' mODEG 1 and 2.

SUSQUEHANNA- UNIT 1 TS / 3.4530 Amendmrent 1 o,2,>

PPL Rev.k Prra~contairmcn Hdr ,gemtReerab 3.6.3.1 ACTIONS 4rntinued) / . /

/CONDION 7/UIRED ACTION// COMPON TIME

/

C. equired Action an C.1 e in MODE 3. 12 h ra associated Compl on Time not met.

I.

/

SURVLANCEREQ EMENTS //C

//URVEILLANC FEUENCY SR 3.6.3.1.1 erform a system ctional test for eVIhdrywell 2/months

/and suppression camber hydrogencombiner.

SR 3.6 .1.2 Visually examj e each drwell dsuppressio 24 months chamber hy ogen recombine enjiosure an verify thers no evidence o abnormal condition SR 3.6.3.1.3 Perf a resistance ground testf each 24 nts he er phase.

( '/

SUSQUEHANNA - UNIT 1 -r /3.6-31 Amendment '--"

IYX

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........................OTS2.0-1 2.1 SLs ....... TS/2.0-1 2.2 SL Violations ....... TS /2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY . ....... :NJ3.0-1 i

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 ............... 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 3.3.1.3 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 ..................... s.. 3.3-23 3.3.3.2 Remote Shutdown System..........................---........................ 3-3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

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

System Instrumentation .. 3.3-67 (continued)

Amendment .51, 1%8, 191), 12, 499 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 22 TS/TOC --1I TS/TOC Amendment )61, 108, 10D, 1,92, A9

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 3A.1 Recirculatlon Loops Operating .. ............................................ TS3.4-1 3.4.2 Jet Pumps .......................................... 3.4-6 3A.3 Safety/Relief Valves .(SIRVs).................................. 3.4-8 3.4.4 RCS Operational LEAKAGE ................................... 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage .................................. 3:4-12 3.4.6 RCS Leakage Detection Instrumentation ................................... 3.4-14 3.4.7 RCS Specific Activity ..................................... n .l3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling I System - Hot Shutdown .................................... . ... 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ....... ............................ 3A-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 ............................ a1

-.3s1 3.5.1 ECCS - Operating .................................. / .. 3.5-1 3.5.2 ECCS - Shutdown ... .5-8 3.5.3 RCIC System ............................................. J. 3.5-12 3.6 CONTAINMENT SYSTEMS ............................................ 3.. 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) ............................ TS13.6"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 y Hydrap/ R ooo ..... 3.6-30 3.6.3.2 Drywell Air Flow System F.

............................................... 13.6-32 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 I

~ A~

L4V (continued)

U~f SUSQ 2 NA EHA S/T C - A me dme t ~~ i, 8, i 0, ~2 ).

SUSQUEHANNA - UNIT 2 TS/TOC - 2 Amendment 01 1fi8, 1%2, Aq

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS.............................................................................TS13.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ............................. TS/3.7-1 3.7.2 Emergency Service Water (ESW) System ............................. 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System.................................................................TS/3.7-6 3.7.4 Control Room Floor Cooling System .................................. 3.7-10 3.7.5 Main Condenser Offgas .................................. 3.7-13 3.7.6 Main Turbine Bypass System.................................. TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level .................................. 3.7-17 3.8 ELECTRICAL POWER SYSTEMS ............................ :.,/.... 3.8-1 3.8.1 AC Sources - Operating .......................... X ., ..3.8-1 3.8.2 AC Sources - Shutdown .. T.........................

TS /3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ........................ TS/3.823 3.8.4 DC Sources - Operating ...... .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 ........................ TS/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 ........................................... t.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 icontinued)

SUSQUEHANNA -UNIT 2 TS/T0C - 3 Amendment Il,1E18,1,00, 02, A9

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 ............... TS/5.0-24 G:\GoaadinW\LC\typlng\TS2 Texd TOC TSTF16.doc 7/29/05 SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 1,P1, 1f 8, 1#0, 1 2, 19

PPL Rev. I PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.3.1.2 Pedoman C;i4NEL CAUDR4TON Of th PrmarY Cont~inrnent H2 and Ca Anatl,'Or; SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for all Functions 24 months except..-'%. r'- th: Piim~ry CnnmentiH ad-Og Anawer&

.. Vd PCIV-'mmp u-Position.

i '

SUSQUEHANNA - UNIT 2 -J-5,1 3.3-25 Amendmentwr

PPL Rev. X I PAM Instrumentation 3.3.3.1 Table 3.31-1 (page 1 of 1)

Post Accident Monitoring Instruertafon~ Pi lN

-CONDITIONS REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION D.1

1. Reactor Steam Dome Pressure 2 E

2. Reactor Vessel Water Level L Wide Range 2 E b Edended Range 2 E

c. Fuel Zone Range 2 E

3. Suppesslon Chamber Water Level 2 E

4. Pdnmary Contalnent Pressure a Acckdent Range E

b. LOCA Range 2 E

.2 S. Primary Cortalnret High Radlation 2 F

6. PCIV Posltion 2 per penetration flow aWth E

7. Neulwn Fbutc 2 E

_. Cerhahwen! IL _.0. MAP4.ty

.Dywefl Atmosphere Temperature 2 E

10. Supprssion Chamnber.Water Temperature 2 E (a) Not required for Isolation valves whose asso clated penetration flow path Is Isolated by at least one dosed and deactivated suomatik valve. cosed manual valve, b&d flange, r check valve wIth flow trough the valve secured.

(b) Only one posffion idication channel is requi red for penetrat flow paths wIth only one ihstaled control rom kdxicaton channel.

ULC SUSQUEHANNA - UNIT 2 TS/3.3-26 Amendment p<

t PPL Rev. ;t 3.6 CONTAINMENT SYSTEMS 3.6.3.1 -Rimar; Gontainmont 4ydrOgOn r19omDT'

-LCC.6 Tw* drwelI and We_ suppressio4i i hl e I iyduiun 18M i ibinaefs-shaiibe 012r,4Blg

~PuITYH -M99E6+qand-2-~

I SUSQUEHANNA - UNIT 2 TS / 3.6-30 Amendment lpll, pl-'

PPL Rev. '

. %-- ^..ro .talmmet . .ydfegen R~ecom..b. sei &

ted 3.6.3.1 SUSQUEHANNA - UNIT 2 -9/ 3.6-31 Amendment,1,51

M Attachment 3 to PLA-5882 List of Regulatory Commitments

Attachment 3 to PLA-5882 Page 1 of I I __ LIST OF REGULATORY COMMITMENTS l The following table identifies those actions committed to by PPL Susquehanna in this document. Any other statements in this submittal are provided for information 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 has verified that a Prior to implementation of hydrogen monitoring system capable of diagnosing approved Technical beyond design-basis accidents is installed at Specification amendment Susquehanna Steam Electric Station, Unit 1 and Unit 2 and is making a regulatory commitment to maintain that capability. The hydrogen monitors will be included in the Technical Requirements Manual.

+

2. Susquehanna Steam Electric Station, Unit 1 and Prior to implementation of Unit 2, has an inerted containment. PPL approved Technical Susquehanna, LLC has verified that an oxygen Specification amendment monitoring system capable of verifying the status of the inerted containment is installed at Susquehanna Steam Electric Station, Unit 1 and Unit 2 and is making a regulatory commitment to maintain that capability. The oxygen monitors will be included in the Technical Requirements Manual.