PLA-7644, Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644)
| ML17348B097 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/14/2017 |
| From: | Berryman B Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7644 | |
| Download: ML17348B097 (27) | |
Text
TALEN~
Brad Berryman Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1 504 ENERGY Brad.Berryman@TalenEnergy.com DE~ 1 4 2011 U.S. Nuclear Regulatory Commission 10CFR 50.90 Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENTS TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-551, REVISE SECONDARY CONTAINMENT SURVEILLANCE REQUIREMENTS Docket Nos. 50-387 PLA-7644 and 50-388 Pursuant to 10CFR 50.90, Susquehanna Nuclear, LLC (Susquehanna) hereby requests an amendment to the Technical Specifications (TS) for Susquehanna Steam Electric Station (SSES) Units 1 and 2, Operating Licenses NPF-14 and NPF-22.
The proposed revises TS 3.6.4.1, "Secondary Containment," Surveillance Requirement (SR) 3.6.4.1.1. The SR is revised to address conditions during which the secondary containment pressure may not meet the SR pressure requirements. provides a description and assessment of the changes along with Susquehanna's determination that the changes do not involve a significant hazard consideration. Attachment 2 provides the existing TS pages marked to show the proposed changes. Attachment 3 provides the existing TS Bases pages marked to show the changes that are for information only.
Both the Plant Operations Review Committee (PORC) and the Nuclear Safety Review Board (NSRB) have reviewed these proposed changes in accordance with the Susquehanna Quality Assurance Requirements.
Approval of the proposed amendments is requested by June 30, 2018. Once approved, these amendments shall be implemented within 60 days.
Pursuant to 10CFR 50.91, "Notice for public comment; State consultation, " paragraph (b), Susquehanna is notifying the Commonwealth of Pennsylvania of this application for license amendments by transmitting a copy of this letter and it's supporting attachments to the designated state official.
Document Control Desk PLA-7644 There are no new regulatory commitments contained in this submittal.
Should you have any questions regarding this submittal, please contact Mr. Jason Jennings, Manager- Nuclear Regulatory Affairs at (570) 542-3155.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: lz/4/;J B.Berr Attachments:
- 1. Description and Assessment
- 2. Marked-Up Technical Specification Pages- Units 1 and 2
- 3. Marked-Up Technical Specification Bases Changes Pages- Infmmation Only Copy: NRC Region I Ms. L. H. Micewski, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP
Attachment 1 to PLA-7644 Description and Assessment
1.0 DESCRIPTION
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation 2.2 Variations 2.3 Administrative Update
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination Analysis 3.2 Conclusion 4.0 ENVIRONMENTAL EVALUATION
Attachment 1 to PLA-7644 Page 1 of4 DESCRIPTION AND ASSESSMENT
1.0 DESCRIPTION
Susquehanna Nuclear, LLC (Susquehanna) proposes changes to the Technical Specifications (TS), Appendix A of Renewed Facility Operating License Nos. NPF-14 and NPF-22 for Susquehanna Steam Electric Station (SSES), Units 1 and 2, respectively.
The proposed change revises Technical Specification (TS) 3.6.4.1, "Secondary Containment,"
Surveillance Requirement (SR) 3.6.4.1.1. The SR is revised to allow conditions during which the secondary containment pressure may not meet the SR pressure requirements.
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation Susquehanna has assessed the safety evaluation for TSTF-551 provided to the Technical Specifications Task Force in a letter dated September 21, 2017. This assessment included a review of the NRC staffs evaluation, as well as the information provided in TSTF-551.
Susquehanna has concluded that the justifications presented in TSTF-551 and the safety evaluation prepared by the NRC staff are applicable to Susquehanna Steam Electric Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to Units 1 and 2 TS.
The implementation of alternative radiological source term (AST) was evaluated by the NRC for issuance of Units 1 and 2 Amendments 239 and 216, respectively_Cl) A more recent revision of the radiological consequence analysis was evaluated by the NRC in the safety evaluation dated March 18, 2009.(2) The LOCA offsite and control room dose consequence analysis is documented in FSAR Section 15.6. Susquehanna has confirmed that the brief, inadvertent, simultaneous opening of both an inner and outer personnel access door during normal entry and exit conditions, and their prompt closure by normal means, is bounded by the radiological dose consequence analysis. The NRC recently evaluated and approved this condition in a safety evaluation, dated March 27, 2017.0) In the unlikely event that an accident would occur when both personnel access doors are open for entry or exit, the brief time required to close one of the doors is small compared to the 10 minutes assumed in the accident analysis for reducing the post-accident secondary containment pressure to 0.25 inch of vacuum water gauge, and will not (I)
NRC Safety Evaluation, "Issuance of Amendment [Nos. 239 and 216] re: Implementation of Alternative Radiological Source Term (TAC Nos. MC8730 and MC8731 )," dated January 31, 2007, with correction in letter May 10, 2007, (Accession ML070080301 and ML071270053).
(2)
NRC Safety Evaluation, "Issuance of Amendment re: Technical Specification Change to Technical Specification 3.6.1.3 to Increase the Maximum Allowable Secondary Containment Bypass Leakage Limit," dated March 18, 2009 (Accession ML090500233).
(3)
NRC Safety Evaluation, "Issuance of Amendments [267 and 249] re: Secondary Containment Access Openings," dated March 27, 2017 (Accession ML17067A444).
Attachment 1 to PLA-7644 Page 2 of4 result in an increase in any onsite or offsite dose. Although, the Standby Gas Treatment (SGT)
System is not required to draw down secondary containment until the time stated in the Bases for SR 3.6.4.1.4, the typical time it takes SGT System to draw down secondary containment at Susquehanna, Units 1 and 2, when tested for SR 3.6.4.1.4 is 75 seconds.
2.2 Variations Susquehanna is proposing the following variations from the TS changes described in the TSTF-551 or the applicable parts of the NRC staffs safety evaluation. These variations do not affect the applicability ofTSTF-551 or the NRC staffs safety evaluation to the proposed license amendment.
- 1. The TS already contains an allowance, similar to that made to SR 3.6.4.1.3.
Therefore, the proposed change does not contain this portion ofTSTF-551.
- 2. The existing Note for SR 3.6.4.1.3 describes that single door access openings may be opened for entry and exit. The Note is not in the NUREG-1433 and is unnecessary. The Note is redundant to the SR itself that already contains an allowance for an access opening used for entry and exit purposes. Therefore, the proposed change removes the Note. This does not change the intent of the existing SR.
2.3 Administrative Update Changes in the TOC are administrative, in that they correct spelling and a section title.
- 1. In Unit 1 Table of Contents (TOC), the misspelled word 'INSTURMENTATION' on page TOC-2 will change to 'INSTRUMENTATION'.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination Analysis Susquehanna requests adoption ofTSTF-551, "Revise Secondary Containment Surveillance Requirements," which is an approved change to the standard technical specifications (STS), into the Susquehanna Steam Electric Station, Units 1 and 2, Technical Specifications (TS). The proposed change revises Technical Specification (TS) Surveillance Requirement (SR) 3 .6.4.1.1 .
The SR is revised to permit conditions during which the secondary containment may not meet the SR acceptance criterion for a period of up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if an analysis demonstrates that one standby gas treatment (SGT) subsystem remains capable of establishing the required secondary containment vacuum. Editorial changes are also included to remove the Note of SR 3.6.4.1.3 that is no longer necessary and redundant to the SR itself, and to edit the Table of Contents.
Attachment 1 to PLA-7644 Page 3 of4 Susquehanna has evaluated the proposed change against the criteria of 10CFR 50.92(c) to determine if the proposed change results in any significant hazards. The following is the evaluation of each ofthe 10CFR 50.92(c) criteria:
- 1. Does the proposed change involve a significant increase in the probability or consequence of an accident previously evaluated?
Response: No The proposed change addresses conditions during which the secondary containment SR is not met. The secondary containment is not an initiator of any accident previously evaluated. As a result, the probability of any accident previously evaluated is not increased. The consequences of an accident previously evaluated while utilizing the proposed changes are no different than the consequences of an accident while utilizing the existing four hour Completion Time for an inoperable secondary containment. In addition, the proposed Note for SR 3.6.4.1.1 provides an alternative means to ensure the secondary containment safety function is met. Additionally, the Note removed from SR 3 .6.4.1.3 is editorial because it is redundant to the SR itself and does not alter the requirement. As a result, the consequences of an accident previously evaluated are not significantly increased.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed change does not alter the protection system design, create new failure modes, or change any modes of operation. The proposed change does not involve a physical alteration of the plant; and no new or different kind of equipment will be installed.
Consequently, there are no new initiators that could result in a new or different kind of accident.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Attachment 1 to PLA-7644 Page 4 of4
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change addresses conditions during which the secondary containment SR is not met. Conditions in which the secondary containment vacuum is less than the required vacuum are acceptable provided the conditions do not affect the ability of the SGT System to establish the required secondary containment vacuum under post-accident conditions within the time assumed in the accident analysis. This condition is incorporated in the proposed change by requiring an analysis of actual environmental and secondary containment pressure conditions to confirm the capability of the SGT System is maintained within the assumptions of the accident analysis. Therefore, the safety function of the secondary containment is not affected.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Susquehanna concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
3.2 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
4.0 ENVIRONMENTALEVALUATION The proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10CFR 51.22( c)(9). Therefore, pursuant to 10CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
Attachment 2 ofPLA-7644 Marked-Up Technical Specification Pages Unit 1 TS Pages TOC-1 thru TOC-4 3.6-35 (No Changes),
3.6-36, and 3.6-37 Unit 2 TS Pages TOC-1 tlnu TOC-4 3.6-35 (No Changes),
3.6-36, and 3.6-37
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. 8 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 ................................. ...... ...... ...... ........... .. ................... TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .. ....... TS/3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ........ .... .. .. .... .. TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS .. ...... ........ .. .................................... 3.1-1 3.1 .1 Shutdown Margin (SDM) .............................. ........ .. ...... .. .... .... ...... ..... 3.1-1 3.1.2 Reactivity Anomalies ....... .. ........ .......... .. .. .......................................... 3.1-5 3.1.3 Control Rod OPERABILITY ...... .... .... ...... ............ ..... ... ......... .... ......... . 3.1-7 3.1.4 Control Rod Scram Times ........................ .. .... ........ .. .. .... .. ...... .. ......... 3.1-12 3.1 .5 Control Rod Scram Accumulators .............. .. ...... .. .. ...... ..................... 3.1-15 3.1.6 Rod Pattern Control ............ .. .. ........ ... ............................ .. .. .... ....... ... . 3.1-18 3.1.7 Standby Liquid Control (SLC) System .... .. .... .. .... .. .. .. ......................... 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ............... 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 3.3 INSTRUMENTATION ............ ...... .. .... ....... ... ... .... ......... ................... ...... .. 3.3-1 3.3.1.1 Reactor Protection System (RPS) lnstrumentation .. ........ .. ...... .. ...TS/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 ............ .. .. ......... TS /3.3-23 3.3.3.2 Remote Shutdown System ... ......... ................ .................... .. ....... .. TS /3.3-26 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation ................. .. .. ...... ... ..... ..... .... ... ... ......... ................ 3.3-29 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ...... .. ............................ 3.3-33 3.3 .5.1 Emergency Core Cooling System (ECCS) Instrumentation .......... TS/3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation .. ... .... ... .. ........... .. ... ............ ..... .............. .. .... .... .... 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation ...... .. .... .......... .. .... TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation ............ .... ............ 3.3-63 (continued)
SUSQUEHANNA- UNIT 1 TS I TOG- 1 Amendment 1..84, 2'1-5, 24-1, m,
~.23'4,
- TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. 8 3.3 INSTURMENTATION INSTRUMENTATION (continued) 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)
System Instrumentation ......... ....... ...... .................. ............ ........... 3.3-67 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 (S/RVs) .. ....... .. ... .. ...... ... .............. ... .... ......... .... .. 3.4-8 3.4.4 RCS Operational LEAKAGE ..... ... ..... .. .. ...... ...... ................................ 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ..... ...... .......... .. ..... ....... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ..... .......... ... .................... TS/3.4-14 3.4.7 RCS Specific Activity .. .................................................. ................ . TS/3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System- Hot Shutdown .... ..... ................... .... .. ...... ......... ... ... ... TS/3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .... .... ............................................. ...... . 3.4-22 3.4.10 RCS Pressure and Temperature (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 ..... .. ............ ... .. ... ....... TS/3.5-1 3.5.1 ECCS- Operating ....... ....... ....... ..... .... ... .......................... ... .... .... ... TS/3.5-1 3.5.2 ECCS - Shutdown ..... ...... .. ....... ................................. .... ... ................ 3.5-8 3.5.3 RCIC System ........ ..... ...................... ...... ....... .. ...... ....... ... ..... ... ..... .. TS/3 .5-12 3.6 CONTAINMENT SYSTEMS ... .... ... .. .. .. ........ ....... .. ...... ...... ................... .... 3.6-1 3.6.1.1 Primary Containment ................... .... ............. .... ..... ........... .. ... ..... ...... 3.6-1 3.6.1 .2 Primary Containment Air Lock .. .... .... .... ..... ...................... ................ .. 3.6-4 3.6.1 .3 Primary Containment Isolation Valves (PCIVs) ............................. TS/3.6-8 3.6.1.4 Containment Pressure .... .......................... ......... ..... .. .... .... .... ..... ... .... 3.6-17 3.6.1.5 Drywell Air Temperature ..... .... ................................... ..... ......... ......... 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers .. ........ ........... ... 3.6-19 3.6.2.1 Suppression Pool Average Temperature ......... .... ...... .... ...... .... .... .. .... 3.6-22 3.6.2.2 Suppression Pool Water Level .............. .......... ........... ....... ....... .... ..... 3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .... .... .... TS/3 .6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ..... .............. 3.6-28 3.6.3.1 Not Used .. ... ... ....... ...... ........ ... .. .............................. ... .. .. .... ... ... ..... . TS/3.6-30 3.6.3.2 Drywell Air Flow System ... .. ... .................................. ........ .. .... ... ..... TS/3.6-32 3.6 .3.3 Primary Containment Oxygen Concentration .. ...... ... ... .... .......... ........ 3.6-34 3.6.4.1 Secondary Containment. .... ... .... .............. .................... ......... ....... ...... 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .... ... .. ........ .... ..... .. . 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ... ... ... .... ......... ... ..... .. .. .... ....... 3.6-42 (continued)
SUSQUEHANNA- UNIT 1 TS I TOC- 2 Amendment 'LM, ill, ~
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. 8 3.7 PLANT SYSTEMS ... .. .... ..... ....... ........................ .. ................ .... ..... ..... TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ................... ... ........... ......... TS/3.7-1 3.7.2 Emergency Service Water (ESW) System .... ....... .... ...... .... .... .. ... .. .... 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ... ... ...... ...... .... ... .......................... ... ...... ..... TS/3 .7-6 3.7.4 Control Room Floor Cooling System ...... .... ... ....... ...... ..... ....... ..... ...... 3. 7-10 3.7.5 Main Condenser Offgas ................ ..... ... .......................... ............. ..... 3.7-13 3.7.6 Main Turbine Bypass System .................... .... ........... ...... .... ... ....... TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level .... ... .. ...... .. ...... ... ...... .... ..... ..... . 3.7-17 3.7.8 Main Turbine Pressure Regulation System ....................................... 3. 7-18 3.8 ELECTRICAL POWER SYSTEMS .......................... ....................... .... TS/3.8-1 3.8.1 AC Sources- Operating .... ..... ........... ... ...... ...... ................... .TS/3.8-1 3.8 .2 AC Sources- Shutdown ........ .................... .... .. ...... .. .. ... ..... ....... .... TS/3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ... ... .... ...... ... .. ..... ... ........ TS/3.8-20 3.8.4 DC Sources - Operating .. ........ ........ ..... .................... .... ........... ......... 3.8-23 3.8.5 DC Sources - Shutdown .. ... ..... ...... ..... ... .. ......... ............... ......... ........ 3.8-29 3.8.6 Battery Parameters ..... ......... ...... .............. ............. ..... ...... ....... .. ... ..... TS/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 .. ..... .. ....... .... ..................... ........... ..... ...... ..... TS/3.10-1 3.10.1 lnservice Leak and Hydrostatic Testing Operation ...... ..... ..... ........ .. .. TS/3.1 0-1 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 ... .......... ... ...... ... ..... .. .. .. 3.1 0-16 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..84, W, 225, 2-8"4, ~
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. 8 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 ..... .. .... .... .. .. ..... .. ....................................... TS/5.0-19 5.7 High Radiation Area ............ ........................ .... ... ........ .... .. ..... ... ....... ... .. 5.0-27 SUSQUEHANNA- UNIT 1 TS/TOC - 4 Amendment 124, 2-t'r, ~
For Information Secondary Containment 3.6.4.1 No Changes This Page 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable in MODE 1, 2, containment to OPERABLE or 3. status.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for a one-time outage for replacement of the Reactor Building Recirculating Fan Damper Motors, to be completed by December 31, 2005.
B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
B.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
SUSQUEHANNA- UNIT 1 TS I 3.6-35 Amendment 4-78, 226
Secondary Containment 3.6.4.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment C.1 -----------------NOTE----------------
inoperable during movement LCO 3.0.3 is not applicable.
of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.
C.2 Suspend CORE Immediately ALTERATIONS.
AND C.3 Initiate action to suspend Immediately OPDRVs.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 ----------------------------NOTE--------------------------- In accordance with the Not required to be met for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if analysis Surveillance Frequency demonstrates one standby gas treatment (SGT) Control Program subsystem is capable of establishing the required secondary containment vacuum.
Verify secondary containment vacuum is
~ 0.25 inch of vacuum water gauge.
SR 3.6.4.1.2 Verify all required secondary containment In accordance with the removable walls and equipment hatches required Surveillance Frequency to be closed are closed and sealed . Control Program (continued)
SUSQUEHANNA- UNIT 1 TS I 3.6-36 Amendment ..t+g, ~ ~. 2~
Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY NOTE Single door access openings between required zones 'Nithin the secondary containment boundary may be opened for entry and exit.
SR 3.6.4.1.3 Verify one secondary containment access door in In accordance with the each access opening is closed, except when the Surveillance Frequency access opening is being used for entry and exit. Control Program S R 3. 6.4 .1 .4 -----------------------------NOTE----------------------------- ---------------NOTE----------------
The maximum time allowed for secondary Test each configuration at containment draw down is dependent on the least one time every 60 secondary containment configuration. months.
Verify each standby gas treatment ( SGT~ In accordance with the subsystem will draw down the secondary Surveillance Frequency containment to;::: 0.25 inch of vacuum water gauge Control Program in less than or equal to the maximum time allowed for the secondary containment configuration that is OPERABLE.
S R 3. 6 .4. 1.5 -----------------------------N 0 T E---------------------------- ---------------NOTE----------------
The maximum flow allowed for maintaining Test each configuration at secondary containment vacuum is dependent on least one time every 60 the secondary containment configuration. months.
Verify each SGT subsystem can maintain In accordance with the
- 0.25 inch of vacuum water gauge in the Surveillance Frequency secondary containment for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at a flow Control Program rate less than or equal to the maximum flow rate permitted for the secondary containment configuration that is OPERABLE.
SUSQUEHANNA- UNIT 1 TS I 3.6-37 Amendment -t-7S, ~. ~ 2W, /s7
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. Q 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 ....... ....... ... ... ....... .. .. ..... ..... .. ....... ..... ..... .............. ......... TS /2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ... ... ... TS/3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .. ..... ............... .TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS .... .............. .... .......... .. .... .. .. ...... .. .... 3.1 -1 3.1 .1 Shutdown Margin (SDM) .. ..... ...... ... ....... .. .. ... ..... ................. ............ ... 3.1-1 3.1 .2 Reactivity Anomalies ...... ....... ... ......... .. ........ ......... ...... .... .. .......... ....... 3.1-5 3.1.3 Control Rod OPERABILITY ................. ..... ... .... .. ........ ............ ... ..... .... 3.1 -7 3.1.4 Control Rod Scram Times .. .. .. ..... ... .................... .. ... ... .. ......... ........... .TS/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 3.3 INSTRUMENTATION .... ........ ... ...... ... .... .... ..... ................. ...... ..... ............ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ..... ... ... ... ..... .... . TS/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 ...... .. ... .. ........ .... TS/3.3-23 3.3.3.2 Remote Shutdown System ................... ........ .... .. ...... ........... .. ....... TS/3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation ....... .. ... ................ .... .. ....... ............ .. ................... . 3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .... .... ........ ..... .. ...... ... ... . 3.3-34 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .......... TS/3.3-37 3.3 .5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation .. .... ........ ...... ...... .................. ............. ............... ... 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation .. ... ........... .......... ... TS/3.3-52 3.3 .6.2 Secondary Containment Isolation Instrumentation ..... .. ........ ..... ........ 3.3-63 3.3.7.1 Control Room Emergency Outside Ai r Supply (CREOAS)
System Instrumentation ... ....... .. .......... ........ ..... ......... .... ...... .... ...... .. 3.3-67 (continued)
SUSQUEHANNA- UNIT 2 TS I TOC- 1 Amendment 1J'1 , 1~,;t~ . 1~ , 1_g9, 2~, 2Vf, 42'0, ?23
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. 9 I 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 (S/RVs) ... .... .... .. ... ..... ........... ...................... ... .... 3.4-8 3.4.4 RCS Operational LEAKAGE .... ... ..... ... .... ..... ...... ............ ................... 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ............................ ....... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ............. ... .... ......... ...... .. TS/3.4-14 3.4.7 RCS Specific Activity ... ....... .... ... .. ... ................. ..... ......... ... .......... ..TS/3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System- Hot Shutdown ................ ......... .......... ....... ..... .... .... ..TS/3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ................. ..... ....... ... .. ... ...... ....... ..... .... . 3.4-22 3.4.10 RCS Pressure and Temperature (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 ............................. .... TS/3 .5-1 3.5.1 ECCS- Operating ............ ................ .... .................. ... .. ..... ...... ... ... TS/3.5-1 3.5.2 ECCS- Shutdown ......................................... .............. ............ ......... 3.5-8 3.5.3 RCIC System .... ............................ .... ...... ... ......... ......... ................. TS/3 .5-12 3.6 CONTAINMENT SYSTEMS .. ... .. ... ................. ................... .............. ... ..... 3.6-1 3.6.1.1 Primary Containment ........................... ......... ................ ..... ............... 3.6-1 3.6.1.2 Primary Containment Air Lock ..................................... .. .. ...... ...... .... .. 3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ... .. ...... .... ...... ... ....TS/3.6-8 3.6.1.4 Containment Pressure .... ......................... ..... .................... ................ 3.6-17 3.6.1.5 Drywell Air Temperature ......................... .. ... .. .. .......... ....... ........... .... . 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers ................. .... ... 3.6-19 3.6.2.1 Suppression Pool Average Temperature ........ .......... ........... .............. 3.6-22 3.6.2.2 Suppression Pool Water Level ........... ....... ..... .. .. .. ...... ....................... 3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ........... TS/3 .6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ....... ........ .. .. 3.6-28 3.6.3.1 Not Used ..................... ................. ........... .... ....... .. .. ... .... ................ TS/3.6-30 3.6.3.2 Drywell Air Flow System ....... ..... ... ..... ............ ............................... TS/3.6-32 3.6.3.3 Primary Containment Oxygen Concentration ..... ..... ...................... .. .. 3.6-34 3.6.4.1 Secondary Containment. ......... ........ ............ .... .. .. .... .. .. .... ...... ... ......... 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ..... ..... ...... .. ... ........ 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ......................................... .... 3.6-42 (continued)
SUSQUEHANNA- UNIT 2 TS/TOC-2 Amendment 1.5'1, 1$8. 1¢, 2,Yf
TABLE OF CONTENTS (T ECHNICAL SPECIFICATIONS) PPL Rev. 9 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 Ai r Supply (CREOAS) System ....... .... ...... .... .... ... ..... ...... ..... ... .. .. .... ... ... .. .. TS/3.7-6 3.7.4 Control Room Floor Cooling System .... ...... ............. ... .... .... .. .. ... ... .. ... 3.7-1 0 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 3:7.8 Main Turbine Pressure Regulation System ...... ..................... ............ 3.7-18 3.8 ELECTRICAL POW ER SYSTEMS ........ ...... .......................... ......... ... TS/3.8-1 3.8.1 AC Sources- Operating ...... ........... ....... ............. ....... ............... ... TS/3.8-1 3.8.2 AC Sources- Shutdown ..... ............ .................... ........... .. ........ .... TS/3 .8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .. .... ...... ....... .. ....... ....... .TS/3 .8-23 3.8.4 DC Sources - Operating ....... ................ ... .. ..... .... .. ... .... .. .. ...... ... ...... .. 3.8-26 3.8.5 DC Sources- Shutdown ..... ...... ........... ... .............................. ............ 3.8-34 3.8.6 Battery Parameters ...... ...... .. ...... ............... .. ......... .................. ...... TS/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 ............ ............. ..... ....... ........ 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 .... ... .... .. ... ........ ... .... ..... .. ... ........ ......... ......... .TS/3.10-1 3.10.1 lnservice Leak and Hydrostatic Testing Operation ......... ......... ... .... ... TS/3.1 0-1 3.10.2 Reactor Mode Switch Interlock Testing ..... ............ .... .. ...... .. .... ....... ... 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ...... .... ......... ..... ..... .. 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown .. ........ .... ................ 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal- Refueling .... .. ...... .. ..... .. . 3.10-13 3.10 .6 Multiple Control Rod Withdrawal- Refueling ......... ........................... 3.10-16 3.10.7 Control Rod Testing- Operating ..... ... .. ...... ....... ..... ....... .. ................ .. 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling ... .... .......... ......... .. .... 3.10-20 4.0 DESIGN FEATURES .... ...... .... ... ........ ....... ...... .. ........... ...... ... ........ .. ..... ...... TS/4.0-1 4.1 Site Location .. ... ... ... .. .... ....... ........... ............. ............ ........ ........... ...... TS/4.0-1 4.2 Reactor Core ............. ..... ..... ..... .......... .... ... .. ... ........... ...... ........ ..... .. .. TS/4 .0-1 4.3 Fuel Storage .... ... .... ............... ......... .. ..... .. ..... .... ......... ....... .......... ...... TS/4.0-1 (continued)
SUSQUEHANNA- UNIT 2 TS I TOC - 3 Amendment 1!Y1, 1yB. 19'f, 212. 2j1, 221
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev. 9 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 ......................... ............. .. ........ ... ........ ...... TS/5.0-19 5.7 High Radiation Area .. ........... ..... ...... ... ..... ..... ....... ... .... .... .... .. .... ....... TS/5.0-24 SUSQUEHANNA- UNIT 2 TS/TOC-4 Amendment 15/1 , 1js. 1~2 . .7;<1 I
For Information Secondary Containment 3.6.4.1 No Changes This Page 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable in MODE 1, 2, containment to OPERABLE or 3. status. OR 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for a one-time outage for replacement of the Reactor Building Recirculating Fan Damper Motors, to be completed by December 31, 2005.
B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
AND B.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
{continued}
SUSQUEHANNA- UNIT 2 TS I 3.6-35 Amendment 4-M, 203
Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment C.1 -----------------NOTE----------------
inoperable during movement LCO 3.0.3 is not applicable.
of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.
C.2 Suspend CORE Immediately ALTERATIONS.
C.3 Initiate action to suspend Immediately OPDRVs.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 -----------------------------NOTE---------------------------- In accordance with the Not required to be met for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if analysis Surveillance Frequency demonstrates one standby gas treatment (SGT) Control Program subsystem is capable of establishing the required secondary containment vacuum.
Verify secondary containment vacuum is
~ 0.25 inch of vacuum water gauge.
SR 3.6.4.1.2 Verify all required secondary containment In accordance with the removable walls and equipment hatches required Surveillance Frequency to be closed are closed and sealed. Control Program (continued)
SUSQUEHANNA- UNIT 2 TS I 3.6-36 Amendment 4-M, ~. ~. 2/7
Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY NOTE Single door access openings betv;een required zones within the secondary containment boundary may be opened for entry and exit.
SR 3.6.4.1.3 Verify one secondary containment access door in In accordance with the each access opening is closed, except when the Surveillance Frequency access opening is being used for entry and exit. Control Program S R 3. 6 .4 .1 .4 -----------------------------N0 T E----------------------------- ---------------NOTE---------------
The maximum time allowed for secondary Test each configuration at containment draw down is dependent on the least one time every 60 secondary containment configuration. months.
Verify each standby gas treatment (SGTj In accordance with the subsystem will draw down the secondary Surveillance Frequency containment to ~ 0.25 inch of vacuum water gauge Control Program in less than or equal to the maximum time allowed for the secondary containment configuration that is OPERABLE.
SR 3. 6. 4. 1.5 -----------------------------N0 T E---------------------------- ---------------NOTE---------------
The maximum flow allowed for maintaining Test each configuration at secondary containment vacuum is dependent on least one time every 60 the secondary containment configuration . months.
Verify each SGT subsystem can maintain In accordance with the
~ 0.25 inch of vacuum water gauge in the Surveillance Frequency secondary containment for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at a flow Control Program rate less than or equal to the maximum flow rate permitted for the secondary containment configuration that is OPERABLE.
SUSQUEHANNA- UNIT 2 TS I 3.6-37 Amendment M, ~. ~. 24-7, 2~
Attachment 3 ofPLA-7644 Marked-Up Technical Specification Bases Pages (For Information Only)
Units 1 and 2, Section for SR 3.6.4.1.1
Secondary Containment B 3.6.4.1 BASES ACTIONS C.1. C.2. and C.3 (continued)
Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.
Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position . Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until OPDRVs are suspended.
Required Action C.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.
SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude exfiltration under expected wind conditions.
The SR is modified by a Note which states the SR is not required to be met for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if an analysis demonstrates that one SGT subsystem remains capable of establishing the required secondary containment vacuum. Use of the Note is expected to be infrequent but may be necessitated by situations in which secondary containment vacuum may be less than the required containment vacuum. such as. but not limited to. wind gusts or failure or change of operating normal ventilation subsystems. These conditions do not indicate any change in the leak tightness of the secondary containment boundary. The analysis should consider the actual conditions (equipment configuration.
temperature. atmospheric pressure. wind conditions. measured secondary containment vacuum. etc.) to determine whether. if an accident requiring secondary containment to be OPERABLE were to occur. one train of SGT could establish the assumed secondary (continued)
SUSQUEHANNA - UNIT 1 TS I B 3.6-87 Revision 2
Secondary Containment B 3.6.4.1 containment vacuum within the time assumed in the accident analysis. If so. the SR may be considered met for a period up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The* 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit is based on the expected short duration of the situations when the Note would be applied .
Expected wind conditions are defined as sustained wind speeds of less than or equal to 16 mph at the 60m meteorological tower or less than or equal to 11 mph at the 1Om meteorological tmver if the 60m tower wind speed is not available. Changes in indicated reactor building differential pressure observed during periods of short term Vt'ind speed gusts above these sustained speeds do not by themselves impact secondary containment integrity. However, if secondary containment integrity is known to be compromised, the LCO must be entered regardless of wind speed .
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. *
(continued)
SUSQUEHANNA- UNIT 1 TS I B 3.6-88 Revision 2
Rev. 14 Secondary Containment B 3.6.4.1 BASES ACTIONS C.1. C.2. and C.3 (continued)
Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.
Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until OPDRVs are suspended.
Required Action C.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.
SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude exfiltration under expected wind conditions.
The SR is modified by a Note which states the SR is not required to be met for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if an analysis demonstrates that one SGT subsystem remains capable of establishing the required secondary containment vacuum . Use of the Note is expected to be infrequent but may be necessitated by situations in which secondary containment vacuum may be less than the required containment vacuum. such as. but not limited to. wind gusts or failure or change of operating normal ventilation subsystems. These conditions do not indicate any change in the leak tightness of the secondary containment boundary. The analysis should consider the actual conditions (equipment configuration. temperature. atmospheric pressure. wind conditions. measured secondary containment vacuum. etc.) to determine whether. if an accident requiring secondary containment to be OPERABLE were to occur. one train of SGT could establish the assumed secondary containment vacuum within the time assumed in the accident analysis. If so.
the SR may be considered met for a period up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit is based on the expected short duration of the situations when the Note would (continued)
SUSQUEHANNA- UNIT 2 TS I B 3.6-86 Revision 2
Rev. 14 Secondary Containment B 3.6.4.1 be applied.
Expected wind conditions are defined as sustained 'Nind speeds of less than or equal to 16 mph at the 60m meteorological to*Ner or less than or equal to 11 mph at the 1Om meteorological tower if the 60m tower 'Nind speed is not available. Changes in indicated reactor building differential pressure observed during periods of short term wind speed gusts above these sustained speeds do not by themselves impact secondary containment integrity. However, if secondary containment integrity is known to be compromised , the LCO must be entered regardless of wind speed .
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
SUSQUEHANNA- UNIT 2 TS I B 3.6-87 Revision 2