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| {{#Wiki_filter:November 9, 2006MEMORANDUM TO:Richard Laufer, ChiefSection I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor RegulationFROM:Timothy Kobetz, Chief /RA/Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation | | {{#Wiki_filter:November 9, 2006 MEMORANDUM TO: Richard Laufer, Chief Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Timothy Kobetz, Chief /RA/ |
| | Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1AND 2 AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.8.1 (TAC NOS. MD2142 AND MD2143)By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a requestfor changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical "AND" connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specifications 4.0.The Technical Specifications Branch (ITSB) has reviewed the Susquehanna TS submittal andsupporting documentation. Based on our review, the staff finds that the proposed revisions to the Susquehanna Technical Specifications are acceptable. Our safety evaluation is attached. | | REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.8.1 (TAC NOS. MD2142 AND MD2143) |
| This completes our efforts on TAC Numbers MD2142 and MD2143.Docket Nos. 50-387 and 50-388 | | By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical AND connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specifications 4.0. |
| | The Technical Specifications Branch (ITSB) has reviewed the Susquehanna TS submittal and supporting documentation. Based on our review, the staff finds that the proposed revisions to the Susquehanna Technical Specifications are acceptable. Our safety evaluation is attached. |
| | This completes our efforts on TAC Numbers MD2142 and MD2143. |
| | Docket Nos. 50-387 and 50-388 |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedContacts:R. Clark, NRR/DIRS301-415-2297 November 9, 2006MEMORANDUM TO:Richard Laufer, Chief,Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor RegulationFROM:Timothy Kobetz, Chief /RA/Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation | | |
| | As stated Contacts: R. Clark, NRR/DIRS 301-415-2297 |
| | |
| | November 9, 2006 MEMORANDUM TO: Richard Laufer, Chief, Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Timothy Kobetz, Chief /RA/ |
| | Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1AND 2 AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.8.1 (TAC NOS. MD2142 AND MD2143)By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a requestfor changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical "AND" connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specifications 4.0.The Technical Specifications Branch (ITSB) has reviewed the Susquehanna TS submittal andsupporting documentation. Based on our review, the staff finds that the proposed revisions to the Susquehanna Technical Specifications are acceptable. Our safety evaluation is attached. | | REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.8.1 (TAC NOS. MD2142 AND MD2143) |
| | By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical AND connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specifications 4.0. |
| | The Technical Specifications Branch (ITSB) has reviewed the Susquehanna TS submittal and supporting documentation. Based on our review, the staff finds that the proposed revisions to the Susquehanna Technical Specifications are acceptable. Our safety evaluation is attached. |
| This completes our efforts on TAC Numbers MD2142 and MD2143. | | This completes our efforts on TAC Numbers MD2142 and MD2143. |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedContacts:R. Clark, NRR/DIRS301-415-2297DISTRIBUTION:ITSB R/FDOCUMENT NAME: C:\FileNet\ML062910409.wpdOFFICEITSB\DIRSSC:ITSB\DIRS NAMERClarkTKobetzDATE10/27/0611/09/06OFFICIAL RECORD COPY EnclosureSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONSUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 AND UNIT 2DOCKET NO. 50-272 AND 50-31
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| ==11.0INTRODUCTION== | | As stated Contacts: R. Clark, NRR/DIRS 301-415-2297 DISTRIBUTION: |
| By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a requestfor changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical "AND" connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specification 4.0. | | ITSB R/F DOCUMENT NAME: C:\FileNet\ML062910409.wpd OFFICE ITSB\DIRS SC:ITSB\DIRS NAME RClark TKobetz DATE 10/27/06 11/09/06 OFFICIAL RECORD COPY |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 AND UNIT 2 DOCKET NO. 50-272 AND 50-311 |
| | |
| | ==1.0 INTRODUCTION== |
| | |
| | By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical AND connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specification 4.0. |
| | |
| | ==2.0 REGULATORY EVALUATION== |
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| | The regulatory requirements and guidance which the NRC staff considered in its review of the application are as follows: |
| | : 1. General Design Criterion (GDC) 17, Electrical power systems, in Appendix A to Part 50, General Design Criteria for Nuclear Power Plants, states, in part, that nuclear power plants must have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure. The offsite power system must be supplied by two physically independent circuits that are designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies. |
| | : 2. GDC-18, Inspection and testing of electric power systems, requires that electric power systems that are important to safety be designed to permit appropriate periodic inspection and testing. |
| | : 3. Section 50.36, Technical specifications, provides the regulatory requirements for the content required in a licensees TSs. Section 50.36 states, in part, that the TSs will include SRs to assure that the quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation (LCO) will be met. |
| | Specifically, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether an LCO is required to be included in the TSs. These criteria are as follows: |
| | (a) Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. |
| | Enclosure |
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| | (b) A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. |
| | (c) A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. |
| | (d) A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. |
| | Existing LCOs and related surveillances included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs, while those requirements that do not fall within or satisfy these criteria may be relocated to licensee-controlled documents. |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
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| ==2.0REGULATORY EVALUATION==
| | 3.1 Background In 1998 during the conversion of the Technical Specifications to the Improved Technical Specifications (ITS), a required AND logical connector was inadvertently left out of Condition B of LCO 3.8.1 in Unit 1 only. The Unit 2 Technical Specifications correctly reflect the AND logical operator and do not need to be revised. During the ITS conversion, Figure 4.1-2 was also drawn incorrectly for both units. |
| The regulatory requirements and guidance which the NRC staff considered in its review of theapplication are as follows: 1.General Design Criterion (GDC) 17, "Electrical power systems," in Appendix A to Part50, "General Design Criteria for Nuclear Power Plants," states, in part, that nuclear power plants must have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure. The offsite power system must be supplied by two physically independent circuits that are designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies.2. GDC-18, "Inspection and testing of electric power systems," requires that electric powersystems that are important to safety be designed to permit appropriate periodic inspection and testing.3. Section 50.36, "Technical specifications," provides the regulatory requirements for thecontent required in a licensee's TSs. Section 50.36 states, in part, that the TSs will include SRs to assure that the quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation (LCO) will be met. Specifically, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determiningwhether an LCO is required to be included in the TSs. These criteria are as follows:(a)Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. (b)A process variable, design feature, or operating restriction that is an initialcondition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.(c)A structure, system, or component that is part of the primary success pathand which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.(d)A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.Existing LCOs and related surveillances included as TS requirements which satisfy anyof the criteria stated above must be retained in the TSs, while those requirements that do not fall within or satisfy these criteria may be relocated to licensee-controlled documents.
| | 3.2 PPLs Proposed Changes Changes to Technical Specifications LCO 3.8.1 The proposed TS change adds a logical AND connector to Condition B, in LCO 3.8.1, between REQUIRED ACTIONS B.3.2 and B.4. The addition of the logical connector is in accordance with ITS Section 1.2. |
| | Changes to Figure 4.1-2 The proposed TS change deletes the connection between Interstate Route I-80 and Interstate Route I-81. |
| | 3.3 NRC Staff Evaluation Changes to Technical Specifications LCO 3.8.1 The proposed changes to LCO 3.8.1 correct administrative errors in the ITS. The logical AND connector is needed to ensure that all REQUIRED ACTIONS are completed consistent with |
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| ==3.0TECHNICAL EVALUATION==
| | NUREG-1433. With one required DG inoperable, the operator must: |
| | : 1. Perform SR 3.8.1.1, and |
| | : 2. Declare required feature(s) supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable, and |
| | : 3. Determine operable DGs are not inoperable due to common cause failures or perform SR 3.8.1.7 for operable DGs, and |
| | : 4. Restore required DG to OPERABLE status in 72 hours. |
| | The NRC staff reviewed the administrative changes proposed by the licensee and find them acceptable because they are compatible with the Standard Technical Specifications, do not result in any change in operating requirements, and are consistent with the Commissions regulations. |
| | Changes to Figure 4.1-2 Figure 4.1-2 is a map of the Low Population Zone. The map incorrectly shows I-80 intersecting with I-81 and becoming part of I-81. Figure 4.1-2 is redrawn to show correct routing of I-80. |
| | The proposed changes to Figure 4.1-2 is acceptable because the changes correctly indicate the routes by which state and local police departments can direct traffic in the event of an emergency. Inaccurate maps could cause unnecessary delays, confusion and needless radiation exposure to the local population if the surrounding areas is to be evacuated. |
| | Based on the review of the above changes, the NRC staff concludes that the proposed changes to SR 3.8.1 do not affect the safe and reliable operation of the plant, maintains compliance with requirements governing the design and operation of the Electrical Power System and, therefore, are acceptable. The proposed changes to Figure 4.1-2 are acceptable because they will ensure proper implementation of the Emergency Preparedness Plan if necessary. |
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| ===3.1Background=== | | ==4.0 CONCLUSION== |
| In 1998 during the conversion of the Technical Specifications to the Improved TechnicalSpecifications (ITS), a required "AND" logical connector was inadvertently left out of Condition B of LCO 3.8.1 in Unit 1 only. The Unit 2 Technical Specifications correctly reflect the "AND" logical operator and do not need to be revised. During the ITS conversion, Figure 4.1-2 was also drawn incorrectly for both units.3.2PPL's Proposed Changes Changes to Technical Specifications LCO 3.8.1 The proposed TS change adds a logical "AND" connector to Condition B, in LCO 3.8.1,between REQUIRED ACTIONS B.3.2 and B.4. The addition of the logical connector is in accordance with ITS Section 1.2.
| |
| Changes to Figure 4.1-2 The proposed TS change deletes the connection between Interstate Route I-80 and InterstateRoute I-81.3.3NRC Staff EvaluationChanges to Technical Specifications LCO 3.8.1 The proposed changes to LCO 3.8.1 correct administrative errors in the ITS. The logical "AND"connector is needed to ensure that all REQUIRED ACTIONS are completed consistent with NUREG-1433. With one required DG inoperable, the operator must:1.Perform SR 3.8.1.1, and2.Declare required feature(s) supported by the inoperable DG, inoperable when theredundant required feature(s) are inoperable, and 3.Determine operable DGs are not inoperable due to common cause failures orperform SR 3.8.1.7 for operable DGs, and4.Restore required DG to OPERABLE status in 72 hours.The NRC staff reviewed the administrative changes proposed by the licensee and find themacceptable because they are compatible with the Standard Technical Specifications, do not result in any change in operating requirements, and are consistent with the Commission's regulations.Changes to Figure 4.1-2 Figure 4.1-2 is a map of the Low Population Zone. The map incorrectly shows I-80 intersectingwith I-81 and becoming part of I-81. Figure 4.1-2 is redrawn to show correct routing of I-80. The proposed changes to Figure 4.1-2 is acceptable because the changes correctly indicate theroutes by which state and local police departments can direct traffic in the event of an emergency. Inaccurate maps could cause unnecessary delays, confusion and needless radiation exposure to the local population if the surrounding areas is to be evacuated. Based on the review of the above changes, the NRC staff concludes that the proposedchanges to SR 3.8.1 do not affect the safe and reliable operation of the plant, maintains compliance with requirements governing the design and operation of the Electrical Power System and, therefore, are acceptable. The proposed changes to Figure 4.1-2 are acceptable because they will ensure proper implementation of the Emergency Preparedness Plan if necessary.
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| ==4.0CONCLUSION==
| | The staff has reviewed the licensees submittals and supporting documentation. Based on the above evaluation the staff has concluded that: (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 Commissions 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. |
| The staff has reviewed the licensee's submittals and supporting documentation. Based on theabove evaluation the staff has concluded that: (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.Contributor:R. Clark}} | | Contributor: R. Clark |
| | }} |
Letter Sequence Approval |
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MONTHYEARML0629104092006-11-0909 November 2006
Review of Susquehanna Steam Electric Station Units 1 and 2 Amendment Request to Revise Technical Specifications 3.8.1
Project stage: Approval
ML0714103332007-04-26026 April 2007
Technical Specifications, Issuance of Amendment Technical Specification 3.8.1 and Figure 4.1-2 (TAC Nos. MD2142 and MD2143)
Project stage: Approval
ML0712102952007-04-26026 April 2007
Units 1 & 2, Technical Specifications, Correct Administrative Errors in in Condition B of Limiting Condition for Operation (LCO) 3.8.1 & Correct the Routing of Interstate 80 (I-80) on Figure 4.1-2 in the SSES 1 and 2 TSs Section 4.0
Project stage: Acceptance Review
ML0710702172007-04-26026 April 2007
License Amendment, Issuance of Amendment Technical Specification 3.8.1 and Figure 4.1-2 (TAC Nos. MD2142 and MD2143)
Project stage: Approval
2006-11-09
[Table View] |
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[Table view]
Category:Safety Evaluation
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Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes
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Relief Request - RR02
ML24067A2512024-03-19019 March 2024
Authorized Alternative to Requirements of the ASME Code
ML24039A1882024-02-27027 February 2024
Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods
ML23257A1222023-09-19019 September 2023
Authorization and Safety Evaluation for Alternative Request for Valve 251130
ML23207A1762023-08-0101 August 2023
Authorization and Safety Evaluation for Relief Request 4RR-10
ML23073A1072023-03-30030 March 2023
Enclosure 4 - Safety Evaluation Nonproprietary Susquehanna Steam Electric Station,Units 1,2 & Associated Independent Spent Fuel Storage Installation-Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L-
ML23073A0822023-03-30030 March 2023
Enclosure 2 - Draft Conforming Amendments - Susquehanna Steam Electric Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation- Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L
ML23010A1082023-01-15015 January 2023
Issuance of Amendment No. 268 Change to Control Rod Technical Specifications
ML22294A1502022-11-17017 November 2022
Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program
ML22256A0542022-10-28028 October 2022
Issuance of Amendment Nos. 283 and 266 Change to Reactor Steam Dome Pressure--Low Instrument Function Allowable Value in Technical Specifications
ML22200A0622022-08-30030 August 2022
Issuance of Amendment Nos. 282 and 265 Regarding Risk-Informed Completion Times in Technical Specifications
ML22146A2072022-07-15015 July 2022
Issuance of Amendment Nos. 281 and 264 Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR - NON-PROPRIETARY -
ML21229A1572021-11-0404 November 2021
Issuance of Amendment No. 263 Temporary Change to Unit 2 Technical Specification 3.8.7 to Allow Replacement of Unit 1 480 Volt Load Center Transformers
ML21095A3042021-04-19019 April 2021
Relief Request 4RR-02 Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML20317A3142021-03-10010 March 2021
Issuance of Amendment Nos. 280 and 262 Revise Technical Specification 3.8.1, AC Sources-Operating, to Create a New Condition for an Inoperable Manual Synchronization Circuit
ML20342A2372021-02-18018 February 2021
Issuance of Amendment Nos. 279 and 261 Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements
ML20168B0042021-01-21021 January 2021
Issuance of Amendment Nos. 278 and 260 to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2019-LLA-0153) (Redacted)
ML20297A5642020-12-22022 December 2020
Issuance of Amendment Nos. 277 and 259 Revise Technical Specifications to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules
ML20199G7492020-10-0808 October 2020
Issuance of Amendment Nos. 276 and 258 Revise Technical Specification 5.5.2 to Modify the Design-Basis Loss-of-Coolant Accident Analysis
ML20028E8842020-02-10010 February 2020
Correction to Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of the Emergency Service Water System Piping
ML19248A8442020-01-17017 January 2020
Issuance of Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of Emergency Service Water System Piping
ML19336D0642020-01-13013 January 2020
Issuance of Amendment Nos. 274 and 256 to Revise Shutdown Margin Definition to Address Advanced Fuel (TSTF-535, Revision 0)
ML19155A2642019-07-16016 July 2019
Issuance of Amendment Nos. 273 and 255 Adoption of TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
ML19154A0602019-06-24024 June 2019
Issuance of Amendment Nos. 272 and 254 Technical Specifications to Adopt TSTF-501, Revision 1, Relocated Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML18302A3032019-01-0303 January 2019
SE Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order Ea-13-109 (CAC Nos. MF4364 and MF4365; EPID No. L-2014-JLD-0055
ML18284A4552018-11-0707 November 2018
Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML18222A2032018-09-26026 September 2018
Issuance of Amendment Nos. 271 and 253 Revising Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MG0269 and MG0270; EPID L-2017-LLA-0306)
ML17187A2972017-07-28028 July 2017
Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendments Revising Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF9154 and MF9155)
ML17067A4442017-03-27027 March 2017
Issuance of Amendments Secondary Containment Access Openings
ML16320A0802016-11-30030 November 2016
NON-PROPRIETARY - Safety Evaluation by NRR Related to Indirect Transfer of Renewed Operating Licenses from Talen Energy Corporation to Riverstone Holdings, LLC for the Susquehanna Steam Electric Station, Units 1 and 2
ML16005A2342016-05-20020 May 2016
Issuance of Amendments Adoption of TSTF-425
ML16069A1992016-05-10010 May 2016
Relief Requests for the Third 10-Year Inservice Inspection Interval (CAC Nos. MF6302 Through MF6307)
ML16062A2162016-03-28028 March 2016
Issuance of Amendments Emergency Action Level Scheme Change
ML15267A3812015-11-0202 November 2015
Issuance of Amendments Approval of Cyber Security Plan Milestone 8
ML15243A1402015-09-30030 September 2015
Issuance of Amendments Revisions to Technical Specification 3.4.10, Reactor Coolant System Pressure and Temperature (P/T) Limits
ML15098A4782015-04-28028 April 2015
Relief Requests 4RR-01: Use of a Risk-Informed Inservice Inspection Alternative for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF5097 and MF5098)
ML15054A0582015-04-10010 April 2015
Letter Forwarding Order Approving Transfer of Licenses and Conforming Amendments Related to Susquehanna Steam Electric Station, Units 1 and 2 (TAC MF4426 and MF4427)
ML14141A0732014-06-0909 June 2014
Relief Requests for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF2705 Through MF2714)
ML14122A1972014-05-22022 May 2014
Relief Requests for the Fourth 10-Year Inservice Testing Interval (TAC Nos. MF2905 Through MF2912 and MF2915)
ML14111A0522014-05-14014 May 2014
Issuance of Amendments Regarding Change to Technical Specification Surveillance Requirement 3.5.1.12
ML14028A3952014-03-12012 March 2014
Request for Relief 3RR-20 from the Requirements of the American Society of Mechanical Engineers Section XI
ML14036A2572014-02-26026 February 2014
Issuance of Amendment Change to Allow Only One Manual Trip System to Be Operable for the Residual Heat Removal Shutdown Cooling System in Modes 4 and 5
ML12160A1942012-06-11011 June 2012
Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident
ML1211701292012-04-27027 April 2012
Correction to Issuance of Amendment
ML12096A1582012-04-19019 April 2012
Issuance of Amendment Temporary Change to Unit 2 Technical Specifications 3.8.7 and 3.7.1 to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1, 4160 V Buses
ML12062A1332012-03-0606 March 2012
ME7902 & ME7903-Approval of RR-2012-001 Use of Later Edition of the ASME OM Code for Check Valve Condition Monitoring Program
ML12046A0462012-02-23023 February 2012
Relief Request No. 3RR-18, Regarding Relief from the Requirements of the ASME Code for Successive Inspections
2024-09-03
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Text
November 9, 2006 MEMORANDUM TO: Richard Laufer, Chief Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Timothy Kobetz, Chief /RA/
Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
SUBJECT:
REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.8.1 (TAC NOS. MD2142 AND MD2143)
By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical AND connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specifications 4.0.
The Technical Specifications Branch (ITSB) has reviewed the Susquehanna TS submittal and supporting documentation. Based on our review, the staff finds that the proposed revisions to the Susquehanna Technical Specifications are acceptable. Our safety evaluation is attached.
This completes our efforts on TAC Numbers MD2142 and MD2143.
Docket Nos. 50-387 and 50-388
Enclosure:
As stated Contacts: R. Clark, NRR/DIRS 301-415-2297
November 9, 2006 MEMORANDUM TO: Richard Laufer, Chief,Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Timothy Kobetz, Chief /RA/
Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
SUBJECT:
REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.8.1 (TAC NOS. MD2142 AND MD2143)
By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical AND connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specifications 4.0.
The Technical Specifications Branch (ITSB) has reviewed the Susquehanna TS submittal and supporting documentation. Based on our review, the staff finds that the proposed revisions to the Susquehanna Technical Specifications are acceptable. Our safety evaluation is attached.
This completes our efforts on TAC Numbers MD2142 and MD2143.
Enclosure:
As stated Contacts: R. Clark, NRR/DIRS 301-415-2297 DISTRIBUTION:
ITSB R/F DOCUMENT NAME: C:\FileNet\ML062910409.wpd OFFICE ITSB\DIRS SC:ITSB\DIRS NAME RClark TKobetz DATE 10/27/06 11/09/06 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 AND UNIT 2 DOCKET NO. 50-272 AND 50-311
1.0 INTRODUCTION
By application dated May 31, 2006, PPL Susquehanna, LLC (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Unit Nos. 1 and 2, Technical Specifications. The proposed changes correct administrative errors in the Technical Specifications. The amendments add a logical AND connector in Condition B of LCO 3.8.1 (Unit 1 only) and correct the routing of I-80 on Figure 4.1-2 in Technical Specification 4.0.
2.0 REGULATORY EVALUATION
The regulatory requirements and guidance which the NRC staff considered in its review of the application are as follows:
- 1. General Design Criterion (GDC) 17, Electrical power systems, in Appendix A to Part 50, General Design Criteria for Nuclear Power Plants, states, in part, that nuclear power plants must have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure. The offsite power system must be supplied by two physically independent circuits that are designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies.
- 2. GDC-18, Inspection and testing of electric power systems, requires that electric power systems that are important to safety be designed to permit appropriate periodic inspection and testing.
- 3. Section 50.36, Technical specifications, provides the regulatory requirements for the content required in a licensees TSs. Section 50.36 states, in part, that the TSs will include SRs to assure that the quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation (LCO) will be met.
Specifically, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether an LCO is required to be included in the TSs. These criteria are as follows:
(a) Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
Enclosure
(b) A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
(c) A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
(d) A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Existing LCOs and related surveillances included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs, while those requirements that do not fall within or satisfy these criteria may be relocated to licensee-controlled documents.
3.0 TECHNICAL EVALUATION
3.1 Background In 1998 during the conversion of the Technical Specifications to the Improved Technical Specifications (ITS), a required AND logical connector was inadvertently left out of Condition B of LCO 3.8.1 in Unit 1 only. The Unit 2 Technical Specifications correctly reflect the AND logical operator and do not need to be revised. During the ITS conversion, Figure 4.1-2 was also drawn incorrectly for both units.
3.2 PPLs Proposed Changes Changes to Technical Specifications LCO 3.8.1 The proposed TS change adds a logical AND connector to Condition B, in LCO 3.8.1, between REQUIRED ACTIONS B.3.2 and B.4. The addition of the logical connector is in accordance with ITS Section 1.2.
Changes to Figure 4.1-2 The proposed TS change deletes the connection between Interstate Route I-80 and Interstate Route I-81.
3.3 NRC Staff Evaluation Changes to Technical Specifications LCO 3.8.1 The proposed changes to LCO 3.8.1 correct administrative errors in the ITS. The logical AND connector is needed to ensure that all REQUIRED ACTIONS are completed consistent with
NUREG-1433. With one required DG inoperable, the operator must:
- 1. Perform SR 3.8.1.1, and
- 2. Declare required feature(s) supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable, and
- 3. Determine operable DGs are not inoperable due to common cause failures or perform SR 3.8.1.7 for operable DGs, and
- 4. Restore required DG to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The NRC staff reviewed the administrative changes proposed by the licensee and find them acceptable because they are compatible with the Standard Technical Specifications, do not result in any change in operating requirements, and are consistent with the Commissions regulations.
Changes to Figure 4.1-2 Figure 4.1-2 is a map of the Low Population Zone. The map incorrectly shows I-80 intersecting with I-81 and becoming part of I-81. Figure 4.1-2 is redrawn to show correct routing of I-80.
The proposed changes to Figure 4.1-2 is acceptable because the changes correctly indicate the routes by which state and local police departments can direct traffic in the event of an emergency. Inaccurate maps could cause unnecessary delays, confusion and needless radiation exposure to the local population if the surrounding areas is to be evacuated.
Based on the review of the above changes, the NRC staff concludes that the proposed changes to SR 3.8.1 do not affect the safe and reliable operation of the plant, maintains compliance with requirements governing the design and operation of the Electrical Power System and, therefore, are acceptable. The proposed changes to Figure 4.1-2 are acceptable because they will ensure proper implementation of the Emergency Preparedness Plan if necessary.
4.0 CONCLUSION
The staff has reviewed the licensees submittals and supporting documentation. Based on the above evaluation the staff has concluded that: (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 Commissions 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.
Contributor: R. Clark
