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{{#Wiki_filter:Apr. 15, 2010 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2010-17378 USER INFORMATION: | |||
GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION: | |||
TO: GERLACH*ROSE M 04/15/2010 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) | |||
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY | |||
This requirement applies to all ASME Code Class 1, 2, and 3 piping and components. | This requirement applies to all ASME Code Class 1, 2, and 3 piping and components. | ||
In addition to these piping and components, structural support components such as pipe hangers, vendor catalog items, supplementary steel, base plates, welds, bolts, etc are considered part of the scope of this TRO.Snubbers are not considered part of the scope of this TRO. They are part of the scope of TRO 3.7.8.The inservice inspection program for ASME Code Class 1, 2 and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by IOCFR Part 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CFR Part 50.55a(g)(6)(i). (Reference 1)ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. | In addition to these piping and components, structural support components such as pipe hangers, vendor catalog items, supplementary steel, base plates, welds, bolts, etc are considered part of the scope of this TRO. | ||
Snubbers are not considered part of the scope of this TRO. They are part of the scope of TRO 3.7.8. | |||
The inservice inspection program for ASME Code Class 1, 2 and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by IOCFR Part 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CFR Part 50.55a(g)(6)(i). (Reference 1) | |||
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. | |||
A.1 Upon finding an "indication," ISI personnel will conduct further investigation. | A.1 Upon finding an "indication," ISI personnel will conduct further investigation. | ||
During the time frame of these investigations, no Condition Reports (CR)are generated and no Technical Requirement is considered not met.At such time as the above examinations indicate that an "unevaluated indication" exists (i.e., an indication which fails to meet the acceptance criteria of the ASME or applicable code, the requirements of an endorsed ASME Code Case, or an NRC approved alternative), a CR will be written and forwarded for review. In addition, this TRO will be declared "not met" and Condition A will be entered. As stated in a Note for Condition A, an evaluation of all "unevaluated indications" must be completed. | During the time frame of these investigations, no Condition Reports (CR) are generated and no Technical Requirement is considered not met. | ||
If the"indication" is found to impact the structural integrity or OPERABILITY of the component, system, or structure, the appropriate TRO Condition shall be (continued) | At such time as the above examinations indicate that an "unevaluated indication" exists (i.e., an indication which fails to meet the acceptance criteria of the ASME or applicable code, the requirements of an endorsed ASME Code Case, or an NRC approved alternative), a CR will be written and forwarded for review. In addition, this TRO will be declared "not met" and Condition A will be entered. As stated in a Note for Condition A, an evaluation of all "unevaluated indications" must be completed. If the "indication" is found to impact the structural integrity or OPERABILITY of the component, system, or structure, the appropriate TRO Condition shall be (continued) | ||
SUSQUEHANNA | SUSQUEHANNA - UNIT 1 TRM / B 3.7-36 EFFECTIVE DATE 04/01/2009 | ||
-UNIT 1 TRM / B 3.7-36 EFFECTIVE DATE 04/01/2009 Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS A.1 (continued) entered. If the evaluation determines that the flaw does not impact the component, systems, or structure OPERABILITY or structural integrity, the"indication" becomes an "evaluated indication" and the TRO is considered met and the Actions Table is exited. The 72 hour Completion Time provides a reasonable amount of time to perform the necessary evaluations. | |||
In accordance with Title 10 of the Code of Federal Regulations (10 CFR)50.55a(g), structural integrity must be maintained in conformance with American Society of Mechanical Engineers (ASME) Code Section XI for those parts of a system that are subject to ASME Code requirements. | Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS A.1 (continued) entered. If the evaluation determines that the flaw does not impact the component, systems, or structure OPERABILITY or structural integrity, the "indication" becomes an "evaluated indication" and the TRO is considered met and the Actions Table is exited. The 72 hour Completion Time provides a reasonable amount of time to perform the necessary evaluations. | ||
'10 CFR 50.55a(g)(4) requires, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI..." ASME Section XI, Article IWA 3000 contains weld examination flaw acceptance standards. | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g), structural integrity must be maintained in conformance with American Society of Mechanical Engineers (ASME) Code Section XI for those parts of a system that are subject to ASME Code requirements. | ||
If flaws are found in components for which ASME Section XI has no acceptance standards, then the construction code is to be used to establish the acceptance standards. | '10 CFR 50.55a(g)(4) requires, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI..." | ||
This is supported by Sub-article IWA-3100(b) which states "if acceptance -standards for a particular component, Examination Category, or examination method are not specified in this Division [Division 1] then flaws that exceed the acceptance standards for materials and welds specified in the Section III Edition applicable to construction of the component shall be evaluated to determine disposition."-I'he ASME Code contains requirements describing acceptable means of performing preservice and inservice inspection of welds and certain other locations in piping, vessels, and other pressure boundary components. | ASME Section XI, Article IWA 3000 contains weld examination flaw acceptance standards. If flaws are found in components for which ASME Section XI has no acceptance standards, then the construction code is to be used to establish the acceptance standards. This is supported by Sub-article IWA-3100(b) which states "if acceptance -standards for a particular component, Examination Category, or examination method are not specified in this Division [Division 1] then flaws that exceed the acceptance standards for materials and welds specified in the Section III Edition applicable to construction of the component shall be evaluated to determine disposition." | ||
For preservice and inservice inspections, the ASME Code also specifies acceptable flaw sizes based on material type, location, and service of the system within which the flaw is discovered. | -I'he ASME Code contains requirements describing acceptable means of performing preservice and inservice inspection of welds and certain other locations in piping, vessels, and other pressure boundary components. For preservice and inservice inspections, the ASME Code also specifies acceptable flaw sizes based on material type, location, and service of the system within which the flaw is discovered. If the flaw exceeds these specified acceptance flaw sizes, the ASME Code describes an alternate method by which a calculation may be performed to evaluate the acceptability of the flaw. While ASME Section XI does not specifically provide flaw acceptance standards for components other than those specified in Table IWX-2500-1, its methods and standards may be applied to other components when appropriate. | ||
If the flaw exceeds these specified acceptance flaw sizes, the ASME Code describes an alternate method by which a calculation may be performed to evaluate the acceptability of the flaw. While ASME Section XI does not specifically provide flaw acceptance standards for components other than those specified in Table IWX-2500-1, its methods and standards may be applied to other components when appropriate.(continued) | (continued) | ||
SUSQUEHANNA | SUSQUEHANNA - UNIT 1 TRM / B 3.7-37 EFFECTIVE DATE 04/01/2009 | ||
-UNIT 1 TRM / B 3.7-37 EFFECTIVE DATE 04/01/2009 Structural Integrity B 3.7.11 | |||
The table below summarizes the NRC accepted methods available for evaluating structural integrity of flaws in components (including supports)classified as ASME Code Class 1, Class 2, and Class 3 components. | Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS A.1 (continued) | ||
Pipe ASME Code NRC Approved Code Case GL 90-05 Class/Energy Section Xll Alternative e.g. N-513 (1)Construction RG approved Code Code Case Class 1/HE12) X X Class 2/HE X X Class 2/ME( | The table below summarizes the NRC accepted methods available for evaluating structural integrity of flaws in components (including supports) classified as ASME Code Class 1, Class 2, and Class 3 components. | ||
SUSQUEHANNA | Pipe ASME Code NRC Approved Code Case GL 90-05 Class/Energy Section Xll Alternative e.g. N-513 (1) | ||
-UNIT I TRM / B 3.7-38 EFFECTIVE DATE 04/01/2009 Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS C. 1 (continued) | Construction RG approved Code Code Case Class 1/HE12) X X Class 2/HE X X 3 | ||
When ASME Class 1 components do not meet ASME Code or construction code acceptance standards, the requirements of an NRC endorsed ASME Code Case, or an NRC approved alternative, then an immediate operability determination cannot conclude a reasonable expectation of operability exists and the components are inoperable. | Class 2/ME( ) X X X Class 3/HE X X X Class 3/ME X X X X (1) Refer to RG 1.147 for the latest revision acceptable to the NRC, and any conditions placed upon the code case. | ||
Satisfaction of Code acceptance standards is the minimum necessary for operability of Class 1 pressure boundary components because of the importance of the safety function being performed. | (2) HE - High Energy - Maximum operating temperature greater than 200° F or maximum operating pressure greater than 275 psig. | ||
(3) ME - Moderate Energy - Maximum operating temperature equal to or less than 200° F or maximum operating pressure equal to or less than 275 psig. | |||
B. 1 If the evaluation of operability can not be completed within the required Completion Time, the component shall be declared inoperable and the appropriate LCOs and TROs entered. | |||
(continued) | |||
SUSQUEHANNA - UNIT I TRM / B 3.7-38 EFFECTIVE DATE 04/01/2009 | |||
Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS C. 1 (continued) | |||
When ASME Class 1 components do not meet ASME Code or construction code acceptance standards, the requirements of an NRC endorsed ASME Code Case, or an NRC approved alternative, then an immediate operability determination cannot conclude a reasonable expectation of operability exists and the components are inoperable. Satisfaction of Code acceptance standards is the minimum necessary for operability of Class 1 pressure boundary components because of the importance of the safety function being performed. | |||
TS LCO 3.4.4, RCS Operational Leakage, does not permit any reactor coolant pressure boundary leakage. Upon discovery of leakage from a Class 1 pressure boundary component (pipe wall, valve body, pump casing, etc.) the component must be declared inoperable. | TS LCO 3.4.4, RCS Operational Leakage, does not permit any reactor coolant pressure boundary leakage. Upon discovery of leakage from a Class 1 pressure boundary component (pipe wall, valve body, pump casing, etc.) the component must be declared inoperable. | ||
D.1 and D.2 When ASME Class 2 or Class 3 components do not meet ASME Code or construction code acceptance standards, the requirements of an NRC endorsed ASME Code Case, or an NRC approved alternative, then a determination of whether the degraded or nonconforming condition results in a TS/TRM-required SSC or a TSJTRM-required support SCC being inoperable must be made. In order to determine the component is OPERABLE under an immediate operability determination, the degradation mechanism must be readily apparent. | D.1 and D.2 When ASME Class 2 or Class 3 components do not meet ASME Code or construction code acceptance standards, the requirements of an NRC endorsed ASME Code Case, or an NRC approved alternative, then a determination of whether the degraded or nonconforming condition results in a TS/TRM-required SSC or a TSJTRM-required support SCC being inoperable must be made. In order to determine the component is OPERABLE under an immediate operability determination, the degradation mechanism must be readily apparent. To be readily apparent, the degradation mechanism must be discernable from visual examination (such as external corrosion or wear), or there must be substantial operating experience with the identified degradation mechanism in the affected system. In addition, detailed non-destructive examination data may be necessary to determine that a component is OPERABLE under an immediate operability determination. If detailed non-destructive examination is necessary and the examination cannot be completed within 24 hours, the component should be declared inoperable and the appropriate TS/TRM action statement entered. There is no indeterminate state of operability. | ||
To be readily apparent, the degradation mechanism must be discernable from visual examination (such as external corrosion or wear), or there must be substantial operating experience with the identified degradation mechanism in the affected system. In addition, detailed non-destructive examination data may be necessary to determine that a component is OPERABLE under an immediate operability determination. | The time frame for flaw characterization and engineering analysis should be no longer than a reasonable time frame for completing the actions. NRC views that 24 hours is a reasonable maximum time frame for this assessment. | ||
If detailed non-destructive examination is necessary and the examination cannot be completed within 24 hours, the component should be declared inoperable and the appropriate TS/TRM action statement entered. There is no indeterminate state of operability. | (continued) | ||
The time frame for flaw characterization and engineering analysis should be no longer than a reasonable time frame for completing the actions. NRC views that 24 hours is a reasonable maximum time frame for this assessment.(continued) | SUSQUEHANNA - UNIT 1 TRM /B 3.7-39 EFFECTIVE DATE 04/01/2009 | ||
SUSQUEHANNA | |||
-UNIT 1 TRM /B 3.7-39 EFFECTIVE DATE 04/01/2009 Structural Integrity B 3.7.11 | Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS E.1 and E.2 (continued) | ||
E.1 and E.2 Structural support components are required to be OPERABLE by the TS or TRM, since they are related support functions for SCCs in the TS or TRM.Examples of structural degradation are concrete cracking and spalling, excessive deflection or deformation, water leakage, rebar corrosion, missing or bent anchor bolts, and degradation of door and penetration sealing. If the support structure is degraded, the support structure's capability of performing its specified function shall be assessed. | Structural support components are required to be OPERABLE by the TS or TRM, since they are related support functions for SCCs in the TS or TRM. | ||
As long as the identified degradation does not result in exceeding acceptance limits specified in applicable design codes and standards referenced in the design basis documents, the affected structure is either operable or functional. | Examples of structural degradation are concrete cracking and spalling, excessive deflection or deformation, water leakage, rebar corrosion, missing or bent anchor bolts, and degradation of door and penetration sealing. If the support structure is degraded, the support structure's capability of performing its specified function shall be assessed. As long as the identified degradation does not result in exceeding acceptance limits specified in applicable design codes and standards referenced in the design basis documents, the affected structure is either operable or functional. | ||
The time frame for an engineering analysis should be no longer than a reasonable time frame for completing the actions. NRC views that 24 hours is a reasonable maximum time frame for this assessment. | The time frame for an engineering analysis should be no longer than a reasonable time frame for completing the actions. NRC views that 24 hours is a reasonable maximum time frame for this assessment. | ||
F. 1 Once a component is evaluated for structural integrity using criteria acceptable to the NRC staff and determined to be unacceptable, the component has to be declared inoperable and the TRO or LCO action statements for the applicable system must be followed.TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Structural Integrity requirements are maintained. | F. 1 Once a component is evaluated for structural integrity using criteria acceptable to the NRC staff and determined to be unacceptable, the component has to be declared inoperable and the TRO or LCO action statements for the applicable system must be followed. | ||
The Frequency for the TRS is defined by the Inservice Inspection (ISI)Program.REFERENCES | TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Structural Integrity requirements are maintained. | ||
The Frequency for the TRS is defined by the Inservice Inspection (ISI) | |||
SUSQUEHANNA | Program. | ||
-UNIT 1 TRM /B 3.7-40 EFFECTIVE DATE 04/08/2010}} | REFERENCES 1. 10 CFR Part 50. | ||
: 2. Regulatory Issue Summary 2005-20, Rev. 1, "Revision to Guidance Formerly Contained in NRC Generic Letter 91-18, 'Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability."' | |||
SUSQUEHANNA - UNIT 1 TRM /B 3.7-40 EFFECTIVE DATE 04/08/2010}} |
Revision as of 20:36, 13 November 2019
ML101130040 | |
Person / Time | |
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Site: | Susquehanna ![]() |
Issue date: | 04/15/2010 |
From: | Susquehanna |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML101130040 (31) | |
Text
Apr. 15, 2010 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2010-17378 USER INFORMATION:
GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 04/15/2010 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON
.
THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRMI - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 04/05/2010 ADD MANUAL TABLE OF CONTENTS DATE: 04/14/2010 CATEGORY: DOCUMENTS TYPE: TRMI kiQ~
Apr. 15, 2010 Page 2 of 2 ID: TEXT B3.7.11 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT LOES ADD: REV: 58 REMOVE: REV:57 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
'SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 04/14 /2010 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 58 04/14/2010 Title: LIST OF EFFECT:IVE SECTIONS TEXT TOC 17 04/05/2010 Title: TABLE OF CONTENTS /j TEXT 1.1 0 11/18/2002 Title: USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005, Title: PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 8 02/12/2010 Title: PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE LDCN 4414 TEXT 3.0 / 4 05/23/2008 Title: TECHNICAL REQUIREMENT\FOR OPERATION (TRO) APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY TEXT 3.1.1 1 11/09/2007 Title: REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS7-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 5 04/16/2009 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION &
CHECK VALVE TEXT 3.2.1 11 03/16/2010 Title: CORE OPERATING LIMITS REPORT (COLR)
Report Date: 04/14/10 Page 1 1 of of 15
.15 Report Date: 04/14/10
SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002 Title: INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 2 11/09/2007 Title: INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007 Title: INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 5 05/23/2008 Title: INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/18/2002 Title: INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 10/19/2005 Title: INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 1 11/09/2007 Title: INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003 Title: INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3. 3.9 3 04/17/2008 Title: OPRM INSTRUMENTATION CONFIGURATION TEXT 3.3.10 1 12/14/2004 Title: INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003 Title: INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 0 04/16/2009 Title: WATER MONITORING INSTRUMENTATION Report Date: 04/14/10 Page 22. of of 15 15 Report Date: 04/14/10
SSES MANUAL
- Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 1 04/26/2006 Title: REACTOR COOLANT SYSTEM REACTOR-COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009 Title: REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 1 11/09/2007 Title: REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2 04/17/2008 Title: REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006 I Title: REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.5.1 1 02/04/2005 Title: EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007 Title: EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002 Title: EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002 Title: CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/18/2002 Title: CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002 Title: CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/18/2002 Title: CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES Page .1 of 15 Report Date: 04/14/10
SSES M.ANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.1 0 11/18/2002 Title: PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/18/2002 Title: PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 2 04/16/2009 Title: PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009 Title: PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 3 04/16/2009 Title: PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 2 04/16/2009 Title: PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2 04/16/2009 Title: PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2 04/16/2009 Title: PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1 04/26/2006 Title: PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 7 01/20/2010 Title: PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION LDCN 3503 TEXT 3.7.4 1 04/26/2006 Title: PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 0 11/18/2002 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR Report Date: 04/14/10 Page 4 4 of of 15
.15 Report Date: 04/14/10
SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.2 0 11/18/2002 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1 04/26/2006 Title: PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 2 06/27/2008 Title: PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 4 06/21/2007 Title: PLANT SYSTEMS SNUBBERS TEXT 3. 7.9 1 08/28/2006 Title: PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004 Title: PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7.11 0 04/16/2009 Title: STRUCTURAL INTEGRITY TEXT 3.8.1 2 04/05/2010 Title: ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LDCN 4760 TEXT 3.8.2.1 2 11/09/2007 Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT 3.8.2.2 2 12/14/2004 Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT 3.8.3 1 04/05/2010 Title: ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES Page 5 of 15 Report Date: 04/14/10
SSES MANUJAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.4 0 11/18/2002 Title: ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 0 11/18/2002 Title: ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 0 11/18/2002 Title: ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 1 06/15/2009 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/18/2002 Title: REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002 Title: REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002 Title: REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006 Title: MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006 Title: MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 1 04/26/2006 Title: MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 2 04/17/2008 Title: MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
TEXT 3.11.1.1 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION Page 6 of 15 Report Date: 04/14/10
SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.2 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 1 12/14/2004 Title: RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 2 05/02/2007 Title: RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006 Title: RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2..2 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/18/2002 Title: RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 3 11/14/2006 Title: RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 4 09/16/2009 Title: RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 4 08/08/2006 Title: RADIOACTIVE EFFLUENTS MONITORING PROGRAM Report Date: 04/14/10 Page i~
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SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.4.2 2 04/26/2006 Title: RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002 Title: LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL STORAGE POOL TEXT 3.12.2 4 04/17/2008 Title: LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12 0 11/19/2002 Title: DADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT 4.1 0 08/31/1998 Title: ADMINISTRATIVE CONTROL S ORGANIZATION TEXT 4.2 0 08/31/1998 Title: ADMINISTRATIVE CONTROL S REPORTABLE EVENT ACTION TEXT 4.3 0 08/31/1998 Title: ADMINISTRATIVE CONTROL S SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008 Title: ADMINISTRATIVE CONTROL S PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998 Title: ADMINISTRATIVE CONTROL S REPORTING REQUIREMENTS TEXT 4.6 0 08/31/1998 Title: ADMINISTRATIVE CONTROL S RADIATION PROTECTION PROGRAM S. TEXT 4.7 0 08/31/1998 Title: ADMINISTRATIVE CONTROLS TRAINING Report Date: 04/14/10 Page .~.
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SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.0 4 05/23/2008 Title: APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 1 11/09/2007 Title: REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 03/31/2006 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002 Title: CORE OPERATING L IMITS BASES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.1 0 11/19/2002 Title: INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 1 11/09/2007 Title: INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008 Title: INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 3 11/09/2007 Title: INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007 Title: INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3 10/19/2005 Title: INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION Report Date: 04/14/10 Page ~
Page2 of 15 15 Report Date: 04/14/10
SSES MANUAL Manual Name.- TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.7 1 11/09/2007 Title:-INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003 Title: INSTRUMENTATION BASES TRM REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT B3.3.9 3 04/17/2008 Title: OPRM INSTRUMENTATION TEXT B3.3.10 2 04/05/2010 Title: INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS LDCN 4709 TEXT B3.3.11 1 10/22/2003 Title: INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 0 04/16/2009 Title: WATER MONITORING INSTRUMENTATION TEXT B3.4.1 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1 04/16/2009 Title: REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 1 11/09/2007 Title: REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS TEXT B3.5.1 0 11/19/2002 Title: ECCS AND RCIC BASES ADS MANUAL INHIBIT Report Date: 04/14/10 Page 1Q Page 10 of of ~
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SSES MANUAL Manual Name: TRI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.5.2 1 11/09/2007 Title: ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007 Title: ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002 Title: CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002 Title: CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 2 04/17/2008 Title: CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION LDCN 3933 TEXT B3.6.4 1 12/14/2004 Title: CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002 Title: PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)
TEXT B3.7.2 0 11/19/2002 Title: PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 2 01/07/2008 Title: PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006 Title: PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 0 11/19/2002 Title: PLANT SYSTEMS BASES C02 SYSTEMS TEXT B3.7.3.4 1 04/26/2006 Title: PLANT SYSTEMS BASES HALON SYSTEMS Report Date: 04/14/10 Page ii11 Page of of 15
.15 Report Date: 04/14/10
SSES MANIUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.5 1 04/26/2006 Title: PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006 Title: PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0 11/19/2002 Title: PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 1 01/12/2004 Title: PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002 Title: PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0 11/19/2002 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0 11/19/2002 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002 Title: PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 2 06/27/2008 Title: PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2 01/31/2008 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 3 06/21/2007 Title: PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 1 12/14/2004 Title: PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC Report Date: 04/14/10 Page .i2~
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SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.10 1 12/14/2004 Title: PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 1 04/14/2010 Title: STRUCTURAL INTEGRI' PY TEXT B3.8.1 2 03/10/2010 Title: ELECTRICAL POWER BIASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0 11/19/2002 Title: ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT B3.8.2.2 1 09/17/2004 Title: ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT B3.8.3 0 11/19/2002 Title: ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002 Title: ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 0 11/19/2002 Title: ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 1 02/04/2005 Title: ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 1 06/15/2009 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT B3.9.1 0 11/19/2002 Title: REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002 Title: REFUELING OPERATIONS BASES COMMUNICATIONS Report Date: 04/14/10 Page j3 13 of of 15 15 Report Date: 04/14/10
SSES MANlUAL~
Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.9.3 0 11/19/2002 Title: REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0 11/19/2002 Title: MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 03/31/2006 Title: MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002 Title: MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3.10.4 1 04/17/2008 Title: MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.11.1.1 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION.
TEXT B3.11.1.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID. RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004 Title: RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES Report Date: 04/14/10 Page 24 14 of of 15
.15 Report Date: 04/14/10
SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 4 11/14/2006 Title: RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27/2004 Title: RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 2 01/06/2006 Title: RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11.4.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 1 10/04/2007 Title: LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 0 11/19/2002 Title: LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002 Title: LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 04/14/10
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SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 03125/2010 1.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM / 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 04/02/1999 Page TRM / 2.0-6 03/27/2008 Page TRM / 2.0-7 05/15/2008 Page TRM / 2.0-8 03/27/2008 Page TRM / 2.0-9 11/15/2004 Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM /2.0-12 03/27/2008 Pages TRM / 2.0-13 and TRM / 2.0-14 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Page TRM / 3.0-1 04/14/2008 Page TRM / 3.0-2 04/12/2007 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Page TRM / 3.1-1 10/31/2007 Pages TRM / 3.1-2 through TRM / 3.1-5 08/31/1998 Page TRM / 3.1-6 03/22/2006 Page TRM / 3.1-7 04/07/2009 Page TRM / 3.1-8 03/27/2008 Pages TRM / 3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-54 03/11/2010 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM / 3.3-6 08/31/1998 Page TRM / 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 Page TRM / 3.3-9 04/12/2007 SUSQUEHANNA - UNIT 1 TRM / LOES-1 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-9a 12/17/1998 Page TRM / 3.3-10 10/31/2007 Page TRM / 3.3-11 06/02/2005 Page TRM /3.3-11a 04/14/2008 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 Page TRM / 3.3-16 06/27/2001 Page TRM / 3.3-17 06/14/2002 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 Page TRM / 3.3-22 03/27/2008 Page TRM / 3.3-22a 11/15/2004 Pages TRM / 3.3-22b through TRM / 3.3-22d 03/22/2006 Page TRM / 3.3-23 12/03/2004 Pages TRM / 3.3-24 and TRM / 3.3-25 05/16/2003 Page TRM / 3.3-26 10/22/2003 Pages TRM / 3.3-27 and TRM / 3.3-28 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page TRM / 3.4-9 08/31/1998 Page TRM / 3.4-10 10/31/2007 Page TRM / 3.4-11 08/31/1998 Page TRM / 3.4-12 03/27/2008 Page TRM / 3.4-13 03/31/2006 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Pages TRM / 3.5-4 and TRM / 3.5-5 10/31/2007 Pages 3.5-6 and 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 SUSQUEHANNA - UNIT 1 TRM / LOES-2 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / 3.7-5 04/07/2009 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Pages TRM / 3.7-9 and TRM / 3.7-10 04/07/2009 Page TRM / 3.7-11 12/29/1999 Page TRM / 3.7-12 08/02/1999 Page TRM / 3.7.13 04/07/2009 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 04/07/2009 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 04/07/2009 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Page TRM / 3.7-23 04/07/2009 Page TRM / 3.7-24 03/31/2006 Pages TRM / 3.7-25 and TRM 3.7-26 08/02/1999 Page TRM 3.7-27 10/31/2007 Page TRM / 3.7-28 11/29/2006 Page TRM / 3.7-29 08/09/2005 Page TRM / 3.7-30 01/13/2010 Pages TRM / 3.7-31 and TRM / 3.7-32 11/16/2001 Page TRM / 3.7-33 01/09/2004 Page TRM / 3.7-34 11/16/2001 Page TRM / 3.7-34a 10/05/2002 Page TRM / 3.7-35 03/31/2006 Pages TRM / 3.7-36 and TRM / 3.7-37 02/01/1999 Pages 3.7-38 and 3.7-39 08/31/1998 Page TRM / 3.7-40 03/31/2006 Page TRM / 3.7-41 02/14/2005 Page TRM / 3.7-41a 06/20/2008 Page TRM / 3.7-42 09/04/2008 Page TRM / 3.7-43 08/31/1998 Pages TRM / 3.7-44 through TRM / 3.7-46 10/05/2006 Page TRM / 3.7-47 06/07/2007 Page TRM / 3.7-48 10/05/2006 Page TRM / 3.7-49 06/07/2007 Page TRM / 3.7-50 03/09/2001 Page TRM / 3.7-51 08/16/2006 Page TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 Pages TRM / 3.7-55 through TRM / 3.7-57 04/01/2009 TRM / LOES-3 EFFECTIVE DATE 04/08/2010 SUSQUEHANNA - UNIT
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UNIT I1 TRM / LOES-3 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM /3.8-4 03/25/2010 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Page TRM / 3.8-7 10/31/2007 Pages TRM / 3.8-8 through TRM / 3.8-10 12/03/2004 Page TRM / 3.8-11 09/03/2004 Page TRM / 3.8-12 12/03/2004 Page TRM / 3.8-13 03/25/2010 Page TRM / 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Pages TRM / 3.8-28 and TRM / 3.8-29 05/28/2009 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 and 3.10-3 08/31/1998 Pages 3.10-2 and 3.10-3 08/31/1998 Page TRM / 3.10-4 08/01/2006 Pages TRM / 3.10-5 and TRM / 3.10-6 03/22/2006 Page TRM / 3.10-7 03/31/2006 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 and 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM /3.11-6 03/31/2006 Pages TRM / 3.11-7 through TRM / 3.11-9 08/31/1998 Page TRM / 3.11-10 12/03/2004 Pages 3.11-11 and 3.11-12 08/31/1998 Page TRM /3.11-13 04/12/2007 TRM / LOES-4 EFFECTIVE DATE 04/08/2010 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT I1 TRM / LOES-4 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.11-14 12/03/2004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM / 3.11-17 03/31/2006 Page 3.11-18 08/31/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 05/13/2005 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM / 3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM / 3.11.30 through TRM / 3.11.32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-43 08/31/1998 Page TRM / 3.11-44 08/01/2006 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 03/14/2008 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages TRM / 4.0-5 through TRM / 4.0-8 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-5 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 08/31/1998 Page TRM / B 3.0-4 01/10/2007 Page TRM / B 3.0-5 04/14/2008 Page TRM / B 3.0-6 08/31/1998 Page TRM / B 3.0-7 04/12/2007 Pages TRM / B 3.0-8 through TRM / B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 and TRM / B 3.0-14 11/30/2005 Page TRM / B 3.0-15 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Pages TRM / B 3.1-2 and TRM / B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Page TRM / B 3.1-5 11/15/2005 Pages TRM / B 3.1-6 and TRM / B 3.1-7 03/22/2006 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 04/07/2000 Pages TRM / B 3.3-2 and TRM / B 3.3-2a 10/31/2007 Page TRM / B 3.3-3 12/11/2008 Page TRM / B 3.3-3a 10/31/2007 Pages TRM / B 3.3-4 and TRM / B 3.3-5 05/30/2006 Pages TRM / B 3.3-6 through TRM / B 3.3-9 10/31/2007 Page B 3.3-10 08/31/1998 Pages TRM / B 3.3-11 and TRM / B 3.3-12 09/13/2005 Page TRM / B 3.3-13 12/03/2004 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 10/31/2007 Page TRM / B 3.3-14b 10/31/2007 Pages TRM / B 3.3-15 and TRM / B 3.3-16 10/22/2003 Page TRM / B 3.3-17 03/22/2006 Pages TRM / B 3.3-17a through TRM / B 3.3-17c 03/22/2006 Page TRM / B 3.3-17d 03/27/2008 Pages TRM / B 3.3-17e and TRM / B 3.3-17f 03/22/2006 Page TRM / B 3.3-18 03/25/2010 Page TRM / B 3.3-19 05/16/2008 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 Pages TRM / B 3.3-22 and TRM / B 3.3-23 04/07/2009 TRM I LOES-6 EFFECTIVE DATE 04/08/2010 SUSQUEHANNA - UNIT
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UNIT I1 TRM / LOES-6 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.4 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B 3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 08/31/1998 Pages TRM / B 3.5-3 through TRM / B 3.5-5 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/27/2008 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages B.3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Pages TRM / B 3.7-3 and TRM / B 3.7-3a 12/27/2007 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Page TRM / B 3.7-6 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 08/02/1999 Page TRM / B 3.7-9 03/31/2006 Page TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-10a 03/31/2006 Page TRM / B 3.7-11 08/02/1999 Page TRM / B 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 through TRM / B 3.7-14 08/02/1999 Page TRM / B 3.7-14a 08/02/1999 Page TRM / B 3.7-14b 01/09/2004 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 02/14/2005 Page TRM / B 3.7-21a 06/20/2008 Page TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Pages TRM / B 3.7-24 through TRM / B 3.7-28 10/05/2006 Pages TRM / B 3.7-29 and TRM / B 3.7-30 06/07/2007 Pages TRM / B 3.7-30a and TRM / B 3.7-30b 10/05/2006 Page TRM / B 3.7-31 12/03/2004 Page TRM / B 3.7-32 03/09/2001 SUSQUEHANNA - UNIT I TRM / LOES-7 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-33 04/15/2003 Page TRM /B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 Pages TRM / B 3.7-36 through TRM / B 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 08/10/2004 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-16 04/02/2002 Page TRM / B 3.8-17 01/28/2005 Pages TRM / B 3.8-18 through TRM / B 3.8-20 11/29/2006 Pages TRM / B 3.8-21 through TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 08/31/1998 B 3.10 MISCELLANEOUS BASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/22/2006 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-11a 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11.23 11/14/2006 Page TRM / B 3.11.23a 05/13/2005 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Page TRM / B 3.11-30 12/03/2004 Pages B 3.7-31 through B 3.7-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 TRM / LOES-8 EFFECTIVE DATE 04/08/2010 SUSQUEHANNA - UNIT
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UNIT I1 TRM / LOES-8 EFFECTIVE DATE 04/08/2010
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 58 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 09/19/2007 Pages TRM / B 3.12-2 and TRM / B 3.12-3 02/05/1999 TRM1 text LOES 4/8/2010 SUSQUEHANNA - UNIT 1 TRM / LOES-9 EFFECTIVE DATE 04/08/2010
Structural Integrity PPL Rev. I B 3.7.11 B 3.7.11 Structural Integrity BASES TRO The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. This requirement identifies appropriate actions to be taken upon discovery of indications or flaws in components that affect the structural integrity in piping and components.
This requirement applies to all ASME Code Class 1, 2, and 3 piping and components.
In addition to these piping and components, structural support components such as pipe hangers, vendor catalog items, supplementary steel, base plates, welds, bolts, etc are considered part of the scope of this TRO.
Snubbers are not considered part of the scope of this TRO. They are part of the scope of TRO 3.7.8.
The inservice inspection program for ASME Code Class 1, 2 and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by IOCFR Part 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CFR Part 50.55a(g)(6)(i). (Reference 1)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
A.1 Upon finding an "indication," ISI personnel will conduct further investigation.
During the time frame of these investigations, no Condition Reports (CR) are generated and no Technical Requirement is considered not met.
At such time as the above examinations indicate that an "unevaluated indication" exists (i.e., an indication which fails to meet the acceptance criteria of the ASME or applicable code, the requirements of an endorsed ASME Code Case, or an NRC approved alternative), a CR will be written and forwarded for review. In addition, this TRO will be declared "not met" and Condition A will be entered. As stated in a Note for Condition A, an evaluation of all "unevaluated indications" must be completed. If the "indication" is found to impact the structural integrity or OPERABILITY of the component, system, or structure, the appropriate TRO Condition shall be (continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-36 EFFECTIVE DATE 04/01/2009
Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS A.1 (continued) entered. If the evaluation determines that the flaw does not impact the component, systems, or structure OPERABILITY or structural integrity, the "indication" becomes an "evaluated indication" and the TRO is considered met and the Actions Table is exited. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time provides a reasonable amount of time to perform the necessary evaluations.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g), structural integrity must be maintained in conformance with American Society of Mechanical Engineers (ASME) Code Section XI for those parts of a system that are subject to ASME Code requirements.
'10 CFR 50.55a(g)(4) requires, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI..."
ASME Section XI, Article IWA 3000 contains weld examination flaw acceptance standards. If flaws are found in components for which ASME Section XI has no acceptance standards, then the construction code is to be used to establish the acceptance standards. This is supported by Sub-article IWA-3100(b) which states "if acceptance -standards for a particular component, Examination Category, or examination method are not specified in this Division [Division 1] then flaws that exceed the acceptance standards for materials and welds specified in the Section III Edition applicable to construction of the component shall be evaluated to determine disposition."
-I'he ASME Code contains requirements describing acceptable means of performing preservice and inservice inspection of welds and certain other locations in piping, vessels, and other pressure boundary components. For preservice and inservice inspections, the ASME Code also specifies acceptable flaw sizes based on material type, location, and service of the system within which the flaw is discovered. If the flaw exceeds these specified acceptance flaw sizes, the ASME Code describes an alternate method by which a calculation may be performed to evaluate the acceptability of the flaw. While ASME Section XI does not specifically provide flaw acceptance standards for components other than those specified in Table IWX-2500-1, its methods and standards may be applied to other components when appropriate.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-37 EFFECTIVE DATE 04/01/2009
Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS A.1 (continued)
The table below summarizes the NRC accepted methods available for evaluating structural integrity of flaws in components (including supports) classified as ASME Code Class 1, Class 2, and Class 3 components.
Pipe ASME Code NRC Approved Code Case GL 90-05 Class/Energy Section Xll Alternative e.g. N-513 (1)
Construction RG approved Code Code Case Class 1/HE12) X X Class 2/HE X X 3
Class 2/ME( ) X X X Class 3/HE X X X Class 3/ME X X X X (1) Refer to RG 1.147 for the latest revision acceptable to the NRC, and any conditions placed upon the code case.
(2) HE - High Energy - Maximum operating temperature greater than 200° F or maximum operating pressure greater than 275 psig.
(3) ME - Moderate Energy - Maximum operating temperature equal to or less than 200° F or maximum operating pressure equal to or less than 275 psig.
B. 1 If the evaluation of operability can not be completed within the required Completion Time, the component shall be declared inoperable and the appropriate LCOs and TROs entered.
(continued)
SUSQUEHANNA - UNIT I TRM / B 3.7-38 EFFECTIVE DATE 04/01/2009
Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS C. 1 (continued)
When ASME Class 1 components do not meet ASME Code or construction code acceptance standards, the requirements of an NRC endorsed ASME Code Case, or an NRC approved alternative, then an immediate operability determination cannot conclude a reasonable expectation of operability exists and the components are inoperable. Satisfaction of Code acceptance standards is the minimum necessary for operability of Class 1 pressure boundary components because of the importance of the safety function being performed.
TS LCO 3.4.4, RCS Operational Leakage, does not permit any reactor coolant pressure boundary leakage. Upon discovery of leakage from a Class 1 pressure boundary component (pipe wall, valve body, pump casing, etc.) the component must be declared inoperable.
D.1 and D.2 When ASME Class 2 or Class 3 components do not meet ASME Code or construction code acceptance standards, the requirements of an NRC endorsed ASME Code Case, or an NRC approved alternative, then a determination of whether the degraded or nonconforming condition results in a TS/TRM-required SSC or a TSJTRM-required support SCC being inoperable must be made. In order to determine the component is OPERABLE under an immediate operability determination, the degradation mechanism must be readily apparent. To be readily apparent, the degradation mechanism must be discernable from visual examination (such as external corrosion or wear), or there must be substantial operating experience with the identified degradation mechanism in the affected system. In addition, detailed non-destructive examination data may be necessary to determine that a component is OPERABLE under an immediate operability determination. If detailed non-destructive examination is necessary and the examination cannot be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the component should be declared inoperable and the appropriate TS/TRM action statement entered. There is no indeterminate state of operability.
The time frame for flaw characterization and engineering analysis should be no longer than a reasonable time frame for completing the actions. NRC views that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is a reasonable maximum time frame for this assessment.
(continued)
SUSQUEHANNA - UNIT 1 TRM /B 3.7-39 EFFECTIVE DATE 04/01/2009
Structural Integrity PPL Rev. 1 B 3.7.11 B 3.7.11 Structural Integrity BASES ACTIONS E.1 and E.2 (continued)
Structural support components are required to be OPERABLE by the TS or TRM, since they are related support functions for SCCs in the TS or TRM.
Examples of structural degradation are concrete cracking and spalling, excessive deflection or deformation, water leakage, rebar corrosion, missing or bent anchor bolts, and degradation of door and penetration sealing. If the support structure is degraded, the support structure's capability of performing its specified function shall be assessed. As long as the identified degradation does not result in exceeding acceptance limits specified in applicable design codes and standards referenced in the design basis documents, the affected structure is either operable or functional.
The time frame for an engineering analysis should be no longer than a reasonable time frame for completing the actions. NRC views that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is a reasonable maximum time frame for this assessment.
F. 1 Once a component is evaluated for structural integrity using criteria acceptable to the NRC staff and determined to be unacceptable, the component has to be declared inoperable and the TRO or LCO action statements for the applicable system must be followed.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Structural Integrity requirements are maintained.
The Frequency for the TRS is defined by the Inservice Inspection (ISI)
Program.
REFERENCES 1. 10 CFR Part 50.
- 2. Regulatory Issue Summary 2005-20, Rev. 1, "Revision to Guidance Formerly Contained in NRC Generic Letter 91-18, 'Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability."'
SUSQUEHANNA - UNIT 1 TRM /B 3.7-40 EFFECTIVE DATE 04/08/2010