BYRON 2006-0027, Transmittal of Inservice Inspection Program Plan for Third Ten Year Inspection Interval
| ML063530333 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/14/2006 |
| From: | Hoots D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, BYRON 2006-0027 | |
| Download: ML063530333 (141) | |
Text
Exekn~.
Exelon Generation Company, LLC Byron Station www.exeloncorp.com N uciear 4450 t~1orthGerman Church Road Byron, IL 610109794 10 CFR 50.55a February 14, 2006 LTR: BYRON 2006-0027 p-file: 1.10.0101 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units I and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455
Subject:
Byron Station, Units 1 and 2, Transmittal of lnservice Inspection Program Plan for the Third Ten year Inspection Interval Enclosed is the Byron Station, Units I and 2 third ten-year inspection interval lnservice Inspection Program. The enclosed plan replaces the second ten-year inspection interval plan in its entirety. The third interval began January 16, 2006 and will end January 15, 2016.
Section 8 of the enclosed plan contains the third interval proposed alternatives to the American Society of Mechanical Engineers Code, Section Xl uRules for Inspection and Testing of Components of Light Water Cooled PlantsTM (ASME Code) 2001 Edition through 2003 Addenda.
In accordance with 10 CFR 50.55a, Codes and standards, paragraph 10 CFR 50.55a(a)(3)(i),
Exelon Generating Company, LLC (EGC), is requesting approval ofthese third interval proposed alternatives to the ASME OM Code.
EGC requests approval of these proposed alternatives prior to our Fall 2006 refuel outage for Unit I which is scheduled to begin September 11, 2006. Should you have any questions concerning this matter, please contact Mr. William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
~ully~~,
David M. Hoots Plant Manager Byron Nuclear Generating Station Attachment - Byron Station, Units 1 and 2 Inservice Inspection Program Plan for the Third Ten year Inspection Interval
ATTACHMENT Byron Station, Units I and 2 Inservice Inspection Program Plan for the Third Ten year Inspection Interval
BYRON NUCLEAR POWER STATION UNITS I & 2 xe.&!~n.
Nuclear ISI PROGRAM PLAN THIRD TEN-YEAR INSPECTION INTERVAL Commercial Service Dates:
Unit I 09/16/85 Unit 208/22/87 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, Illinois 61010 Exelon Generation Company, LLC (EGC) 200 Exelon Way KennettSquare,PA 19348 Prepared By:
Allon Science and Technology Corporation Engineering and Technical Programs Division Warrenville, lIllnoIs ALION SCIeNCE AN~ TECHNOLOCY
REVISION CONTROL SHEET TITLE: ISI Program Plan REVISION: 0 Major changes should be outlined within the table below. Minor editorial and formatting revisions are not required to be logged.
REVISION DATE REVIStON
SUMMARY
0 9/12/05 InItial issuance. This ISI Program Plan was prepared by Alion Science and Technology Corporation to support Byron Stations Third Inservice Inspection Interval and Second Containment Inservice inspection interval.
Prepared: S. Coleman RevIewed: T. Hadaway Approved: 0. Lamond Notes:
I. This lSI Program Plan (Sections 1 -9 inclusive) is controlled by the Byron Nuclear Power Station Engineering Programs Group.
- 2. Revision 0 of this document was issued as the Third Interval lSl Program Plan and was submitted to the NRC for review, including approval of the initial Third Interval Relief Requests. Future revisions of this document made within the Third Interval will be maintained and controlled at the station; however, they are not required to be and will not be submitted to the NRC for approval. The exception to this is that new or revised Relief Requests shall be submitted to the NRC for safety evaluation and approval.
Exelon Byron Station i Revision 0
IS! Program Plan Units I & 2, Third Interval REVISION
SUMMARY
SECTION EFFECTIVE PAGES REViSION DATE Preface i to iii 0 9/12/05 1.0 1-1 to 1-18 0 9/12/05 2.0 2-1 to 2-39 0 9/12/05 3.0 3-1 to 3-2 0
- 9/12/05 4.0 4-1 to 4-2
- 0 9/12/05 5.0 . 5-1 0 9/12/05 6.0 6-1 to 6-2 0 9/12/05 7.0 7-lto7-40 0 9/12/05 8.0 8-1 to 8-3 0 9/12/05 9.0 9-1 to 9-3 0 9112/05 Exelon Byron Station ii Revision 0
IS! Program Plan Units I & 2, Third Interval TABLE OF CONTENTS SECTION DESCRIPTION PAGE Preface Table of Contents and Revision Summary ito iii
1.0 INTRODUCTION AND BACKGROUND
1-1 to 1-18 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM 2-1 to 2-39 3.0 WELDS AND COMPONENTS IS1 PLAN 3-1 to 3-2 4.0 SUPPORT 1St PLAN 4-1 to 4-2 5.0 SYSTEM PRESSURE TESTING ISI PLAN 5-1 6.0 CONTAINMENT ISI PLAN 6-1 to 6-2 7.0 . COMPONENT
SUMMARY
TABLES 7-1 to 7-40 8.0 RELIEF REQUESTS FROM ASME SECTION Xl 8-1 to 8-3
9.0 REFERENCES
9-1 to 9-3 Exelon Byron Station iii Revision 0
IS! Program Plan Units 1 & 2, Third !nter.,al
1.0 INTRODUCTION AND BACKGROUND
1.1 INTRODUCTION
This Inservice Inspection (1St) Program Plan details the requirements for the examination and testing of lSl Class 1, 2, 3, MC, and CC pressure retaining components, supports, and containment structures at Byron Nuclear Power Station (Byron Station), Units I and 2. UnIt 0 (Common) components are included in the Unit 1 sections, reports, and tables. This ISI Program Plan also includes Containment Inservice Inspection (CISI), Risk-Informed Inservice Inspection (RISI),
augmented inservice inspections, and pressure testing requirements imposed on or committed to by Byron Station. At Byron Station, the Inservice Testing (1ST)
Program Is maintained and implemented separately from the ISI Program. The 1ST Basis Document and Program Plan contain all applicable inservice testing requirements.
The Steam Generator Inservice Inspection Plan is not included in this document except for applicable Code Cases and relief requests. A program addressing inspection requirements is maintained in separate documents and procedures.
Eddy current examination of steam generator tubing Is controlled and maintained under Byron Station Technical Specifications.
The ASME Section Xl Repair/Replacement Program is not included In this document except for referenced Code Cases and relief requests. The program addressing code and regulatory requirements are maintained in separate documents and procedures.
The Byron Station FAC Program is not included in this document except for referenced Code Cases and relief requests. The program addressing code and regulatory requirements are maintained in separate documents and procedures.
The Byron Station Turbine Disk and Rotor Integrity Program is not included in this document except for minor references. The program addressing regulatory requirements are maintained in separate documents and procedures.
The Third 151 Interval is effective from January 16, 2006 through January 15, 2016 for both Byron Station Units 1 and 2. This represents updating the Unit 2 program approximately one and one-half years early as proposed by Relief Request I3R-01.
With the update to the lSl Program for the Third Inspection Interval for Class 1, 2, and 3 components, including their supports, Exelon Generation Company, LLC (Exelon) has also elected to update the CISI Program to its Second Interval for Class MC and CC components at the same time (Relief Request 13R-01). This update will enable all of the ISI Program components/ elements to be based on the same effective Edition and Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI as well as share a common interval start and end date. The common ASME Code of Record for the Exelon Byron Station 1-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Third ISl Interval and the Second CISI Interval is the 2001 Edition through the 2003 Addenda.
Paragraph IWA-2430(d)(1) of ASME Section XI allows an Inspection Interval to be extended or decreased by as much as one year, and Paragraph IWA-2430(e) allows an inspection interval to be extended when a unit is out of service continuously for six months or more. The extension may be taken for a period of time not to exceed the duration of the outage. See Tables 1.1-1, 1.1-2, and 1.1-3 for intervals, periods, and extensions that apply to Byron Stations Third ISI Interval and Second CISI Interval.
The Third lSl interval and the Second CISI Interval are dMded into two or three inspection periods as determined by calendar years within the intervals. Tables 1.1-1, 1.1-2, and 1.1-3 identify the period dates for the Third lSl Interval and the Second CISI Interval as defined by Inspection Program B. In accordance with Paragraph IWA-2430(d)(3), the Inspection periods specified in these Tables may be decreased or extended by as much as 1 year to enable inspection to coincide with Byron Stations refueling outages.
Exelon Byron Station 1-2 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Table 1.1-1 Byron Station Unft 1 and Unft 21S1 Interval/Perlod(Outage Matrix (for lSl Class 1, 2, and 3 component examinations)
Unit 1 Period Interval PeIIOd Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Dat. to End Date Projected Outage Outage Number Start Date or End Date Start Date or Number Outage Duration Outage Duration B1R14 Fa112006 1~ 1~ Spring2007 B2R13 (3-1-1) (Start tnt) 1/16/06tol/15(09 1/16/06(0 1/15/09 (Start3~dInt) (3-1-1)
B1R15 SprIng 2008 3~(Unit 1) Fall 2008 B2R14 (3-1-2) 1/16/06 to 1/15/16 j~-1-2)
B1R16 Fall 2009 2~° ,~ 2~ Spring 2010 B2R15 (3-2-1) 1/l6Io9to 1/15/122 3 (UnIt 2) , 1/16/09 to 1/15/122 (3-2-1)
B1R17 Spring 2011 1/16/O6to 1/15/16 Fall 2011 B2R16 (3-2-2) (3-2-2)
B1R18 Fall 2012 3 m 3t0 Spring 2013 B2R17 (3-3-1) 1/16/l2tol/15/162 1/16/l2tol/1511& f3-3-1)
B1R19 SprIng 2014 Fall 2014 B2R18 (3-3-2) (End 3fC~lnt) (End 3~d Int) (3-3-2)
Note 1: A request to share a common intetvai start and end date between Byron Station Units 1 and 2 was submitted in accordance with Relief Request 13R-O1.
Note 2: The Byron Station Units 1 and 2 Second Period was reduced by one year and the Third Period was extended by one year as permitted by IWA-2430(d)(3) in order to coincide with the plant refueling outage schedule.
Exelon Byron Station 1-3 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Table 1.1-2 Byron Station Unit I and Unit 2151 IntervallPeriodlOutage Matrix (for ISI Class MC component examinations)
Unit 1 Period Interval Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Data to End Date Projected Outage Outage Number Start Data or End Date Start Date or Number Outage Duration Outage Duration B1R14 FaIl 2006 1~ 1~ SprIng 2007 B2R13 (2-1-1) (Start 2i~dtnt) 1/16106 to 1/15/09 1/16(06 to 1/15/09 (Start 2~tnt) (2-1-1)
B1A15 Sprlng200S 2~(Unit 1) Fall 2008 B2R14 (2-1-2) 1/16/O6to 1/15/161 (2-1-2)
Bi R16 Fall 2009 2~ 2t~a SprIng 2010 B2R1 5 (2-2-1) 1/16/O9tol/15/122 2~(Uflit2) 1/16/O9tol/15/122 (2-2-1)
B1R17 Spring2Oll 1/16/O6tol/15/16 FaIl2Oll B2R16 (2-2-2) (2-2-2)
B1R18 Fall 2012 3~a 3~ Spring 2013 - B2R17 (2-3-1) 1/16/12 to 1/15/162 1/16/12(0 1/15/162 (2-3-1)
B1R19 Spring 2014 Fall 2014 B2R18 (2-3-2) (End 2~Int) (End 2~tnt) (2-3-2)
Note 1: A request for use of subsequent ASME Section XI Code Edition and Addenda was submitted In accordance with Relief Request 13R-01 which Implements the 2001 EdItion through the 2003 Addenda of ASME Section Xl for the CISI Programs as well as to share a common Interval start and end date with the ISl Program.
Note2: TheByronStatlonUnitsi and2SecondPeriodwasreducedbyoneyearandtheThirdPerlodwasextendedbyoneyearaspermittedby IWA-2430(d)(3) In order to coincide with the plant refueling outage schedule.
Exelon Byron Station 1-4 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Table 1.1-3 Byron Station Unit 1 and Unit 2151 lntervallPeriodlOutage Matrix (for ISI Class CC component examinations)
UnIt 1 Period Interval Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Date to End Date Projected Outage Outage Number Start Date or End Date Start Date or Number Outage Duration Outage Duration B1R14 FaIl 2006 i~ 1~ Spring 2007 B2R13 (2-1-1) (Start2~tnt) 1/1~6to1/15/11 1/16/06 to 1/15/11 (Start2~Int) (2-1-1)
B1R15 Spring 2008 2~(Unit 1) Fall 2008 B2R14 (2-1 -2) 1/16/06 to 1/15/16 (2-1-2)
B1R16 Fall 2009 SprIng 2010 B2R15 (2-1-3) ~ 2~(Unit 2) (2-1-3) 1/16106 to 1/15/161 2~
B1R17 SprIng 2011 2~ FaIl 2011 B2R16 (2-2-1) 1/16/11 to 1/15/16 1/16/11(01/15/16 (2-2-1)
B1R1S Fall 2012 Spring 2013 B2R17 (2-2-2) (2-2-2)
B1R19 Spring 2014 FaIl 2014 B2R18 (2-2-3) (End 2~tnt) (End 2~~tnt) d (2-2-3)
Note 1: A request for use of subsequent ASME Section XI Code Edition and Addenda was submitted in accordance with Relief Request 13R-O1 which Iniptements the 2001 Edition through the 2003 Addenda of ASME Section Xl for the CISI Programs as well as to share a common Interval start and end date with the ISI Program.
Exelon Byron Station 1-5 Revision 0
IS! Program Plan Units 1 & 2, Third Interval
1.2 BACKGROUND
The Commonwealth Edison Company, now known commercially as Exelon Generation Company or Exelon, obtained Construction Permits to build Byron Station Units 1 and 2 on December 31, 1975, for Unit 1, CPPR-1 30, and for Unit 2, CPPR-1 31. The Docket Numbers assigned to Byron Station are 50-454 for Unit 1 and 50-455 for Unit 2. After satisfactory plant construction and pro-operational testing was completed, Exelon was granted a full-power operating license for Unit 1, NPF-37, and subsequently commenced commercial operation on September 16, 1985; the full-power operating license for Unit 2, NPF-66, was granted and cornmercial operation commenced on August 22, 1987.
Byron Stations piping systems and associated components were designed and fabricated to the examination requirements of ASME Section Xl. Although this plant was specifically designed to meet the requirements of ASME Section Xl, literal compliance may not be feasible or practical within the limits of the current plant design. Certain limItations are likely to occur due to conditions such as accessibility, geometric configuration, and/or metallurgical characteristics. For some inspection categories, an alternate component may be selected for examination and the code statistical and distribution requirements can still be maintained. If Code required examination selection criteria cannot be met, a relief request will be submitted in accordance with 10 CFR 50.55a.
1.3 SECOND INTERVAL ISI PROGRAM Pursuant to the Code Of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (10 CFR 50.55a), Paragraph (g), Inservice inspection requirements, licensees were required to update their ISI Programs to meet the requirements of ASME Section Xl once every ten years or inspection interval. The ISI Program was required to comply with the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a twelve (12) months prior to the start of the interval per 10 CFR 50.55a(g)(4)(ii).
The Byron Station Second Interval 1St Program Plan was initially developed In accordance with the requirements of 10 CFR 50.55a including alt published changes through June 30, 1995 and September 15, 1997 for Units 1 and 2 respectively, and the 1989 Edition, No Addenda of ASME Section Xl. This ISI Program Plan addressed Subsections IWA, IWB, IWC, IWD, IWF, and Mandatory Appendices of ASME Section Xl, approved ASME Code Cases, approved alternatives through relief requests and Safety Evaluation Reports (SEAs), and utilized inspection Program B as defined therein.
As an alternative to the full ten-year interval duration requirements of IWA-2430(b) and (d) and IWA-2432 for the Unit 2 Second IS1 Interval and for the Units 1 and 2 First CISI Intervals, Byron Station has proposed Relief Request l3R-01 to modify the interval dates of the Unit 2 Second ISI Interval and of the Units 1 and 2 First ClSl Intervals. This will permit the subsequent lSI and CISI Programs to share a common inspection interval and to implement common code editions for Class 1, 2, 3, MC, Exelon Byron Station 1-6 RevisIon 0
Exekn~.
Exelon Generation Company, LLC Byron Station www.exeloncorp.com N uciear 4450 t~1orthGerman Church Road Byron, IL 610109794 10 CFR 50.55a February 14, 2006 LTR: BYRON 2006-0027 p-file: 1.10.0101 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units I and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455
Subject:
Byron Station, Units 1 and 2, Transmittal of lnservice Inspection Program Plan for the Third Ten year Inspection Interval Enclosed is the Byron Station, Units I and 2 third ten-year inspection interval lnservice Inspection Program. The enclosed plan replaces the second ten-year inspection interval plan in its entirety. The third interval began January 16, 2006 and will end January 15, 2016.
Section 8 of the enclosed plan contains the third interval proposed alternatives to the American Society of Mechanical Engineers Code, Section Xl uRules for Inspection and Testing of Components of Light Water Cooled PlantsTM (ASME Code) 2001 Edition through 2003 Addenda.
In accordance with 10 CFR 50.55a, Codes and standards, paragraph 10 CFR 50.55a(a)(3)(i),
Exelon Generating Company, LLC (EGC), is requesting approval ofthese third interval proposed alternatives to the ASME OM Code.
EGC requests approval of these proposed alternatives prior to our Fall 2006 refuel outage for Unit I which is scheduled to begin September 11, 2006. Should you have any questions concerning this matter, please contact Mr. William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
~ully~~,
David M. Hoots Plant Manager Byron Nuclear Generating Station Attachment - Byron Station, Units 1 and 2 Inservice Inspection Program Plan for the Third Ten year Inspection Interval
ATTACHMENT Byron Station, Units I and 2 Inservice Inspection Program Plan for the Third Ten year Inspection Interval
BYRON NUCLEAR POWER STATION UNITS I & 2 xe.&!~n.
Nuclear ISI PROGRAM PLAN THIRD TEN-YEAR INSPECTION INTERVAL Commercial Service Dates:
Unit I 09/16/85 Unit 208/22/87 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, Illinois 61010 Exelon Generation Company, LLC (EGC) 200 Exelon Way KennettSquare,PA 19348 Prepared By:
Allon Science and Technology Corporation Engineering and Technical Programs Division Warrenville, lIllnoIs ALION SCIeNCE AN~ TECHNOLOCY
REVISION CONTROL SHEET TITLE: ISI Program Plan REVISION: 0 Major changes should be outlined within the table below. Minor editorial and formatting revisions are not required to be logged.
REVISION DATE REVIStON
SUMMARY
0 9/12/05 InItial issuance. This ISI Program Plan was prepared by Alion Science and Technology Corporation to support Byron Stations Third Inservice Inspection Interval and Second Containment Inservice inspection interval.
Prepared: S. Coleman RevIewed: T. Hadaway Approved: 0. Lamond Notes:
I. This lSI Program Plan (Sections 1 -9 inclusive) is controlled by the Byron Nuclear Power Station Engineering Programs Group.
- 2. Revision 0 of this document was issued as the Third Interval lSl Program Plan and was submitted to the NRC for review, including approval of the initial Third Interval Relief Requests. Future revisions of this document made within the Third Interval will be maintained and controlled at the station; however, they are not required to be and will not be submitted to the NRC for approval. The exception to this is that new or revised Relief Requests shall be submitted to the NRC for safety evaluation and approval.
Exelon Byron Station i Revision 0
IS! Program Plan Units I & 2, Third Interval REVISION
SUMMARY
SECTION EFFECTIVE PAGES REViSION DATE Preface i to iii 0 9/12/05 1.0 1-1 to 1-18 0 9/12/05 2.0 2-1 to 2-39 0 9/12/05 3.0 3-1 to 3-2 0
- 9/12/05 4.0 4-1 to 4-2
- 0 9/12/05 5.0 . 5-1 0 9/12/05 6.0 6-1 to 6-2 0 9/12/05 7.0 7-lto7-40 0 9/12/05 8.0 8-1 to 8-3 0 9/12/05 9.0 9-1 to 9-3 0 9112/05 Exelon Byron Station ii Revision 0
IS! Program Plan Units I & 2, Third Interval TABLE OF CONTENTS SECTION DESCRIPTION PAGE Preface Table of Contents and Revision Summary ito iii
1.0 INTRODUCTION AND BACKGROUND
1-1 to 1-18 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM 2-1 to 2-39 3.0 WELDS AND COMPONENTS IS1 PLAN 3-1 to 3-2 4.0 SUPPORT 1St PLAN 4-1 to 4-2 5.0 SYSTEM PRESSURE TESTING ISI PLAN 5-1 6.0 CONTAINMENT ISI PLAN 6-1 to 6-2 7.0 . COMPONENT
SUMMARY
TABLES 7-1 to 7-40 8.0 RELIEF REQUESTS FROM ASME SECTION Xl 8-1 to 8-3
9.0 REFERENCES
9-1 to 9-3 Exelon Byron Station iii Revision 0
IS! Program Plan Units 1 & 2, Third !nter.,al
1.0 INTRODUCTION AND BACKGROUND
1.1 INTRODUCTION
This Inservice Inspection (1St) Program Plan details the requirements for the examination and testing of lSl Class 1, 2, 3, MC, and CC pressure retaining components, supports, and containment structures at Byron Nuclear Power Station (Byron Station), Units I and 2. UnIt 0 (Common) components are included in the Unit 1 sections, reports, and tables. This ISI Program Plan also includes Containment Inservice Inspection (CISI), Risk-Informed Inservice Inspection (RISI),
augmented inservice inspections, and pressure testing requirements imposed on or committed to by Byron Station. At Byron Station, the Inservice Testing (1ST)
Program Is maintained and implemented separately from the ISI Program. The 1ST Basis Document and Program Plan contain all applicable inservice testing requirements.
The Steam Generator Inservice Inspection Plan is not included in this document except for applicable Code Cases and relief requests. A program addressing inspection requirements is maintained in separate documents and procedures.
Eddy current examination of steam generator tubing Is controlled and maintained under Byron Station Technical Specifications.
The ASME Section Xl Repair/Replacement Program is not included In this document except for referenced Code Cases and relief requests. The program addressing code and regulatory requirements are maintained in separate documents and procedures.
The Byron Station FAC Program is not included in this document except for referenced Code Cases and relief requests. The program addressing code and regulatory requirements are maintained in separate documents and procedures.
The Byron Station Turbine Disk and Rotor Integrity Program is not included in this document except for minor references. The program addressing regulatory requirements are maintained in separate documents and procedures.
The Third 151 Interval is effective from January 16, 2006 through January 15, 2016 for both Byron Station Units 1 and 2. This represents updating the Unit 2 program approximately one and one-half years early as proposed by Relief Request I3R-01.
With the update to the lSl Program for the Third Inspection Interval for Class 1, 2, and 3 components, including their supports, Exelon Generation Company, LLC (Exelon) has also elected to update the CISI Program to its Second Interval for Class MC and CC components at the same time (Relief Request 13R-01). This update will enable all of the ISI Program components/ elements to be based on the same effective Edition and Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI as well as share a common interval start and end date. The common ASME Code of Record for the Exelon Byron Station 1-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Third ISl Interval and the Second CISI Interval is the 2001 Edition through the 2003 Addenda.
Paragraph IWA-2430(d)(1) of ASME Section XI allows an Inspection Interval to be extended or decreased by as much as one year, and Paragraph IWA-2430(e) allows an inspection interval to be extended when a unit is out of service continuously for six months or more. The extension may be taken for a period of time not to exceed the duration of the outage. See Tables 1.1-1, 1.1-2, and 1.1-3 for intervals, periods, and extensions that apply to Byron Stations Third ISI Interval and Second CISI Interval.
The Third lSl interval and the Second CISI Interval are dMded into two or three inspection periods as determined by calendar years within the intervals. Tables 1.1-1, 1.1-2, and 1.1-3 identify the period dates for the Third lSl Interval and the Second CISI Interval as defined by Inspection Program B. In accordance with Paragraph IWA-2430(d)(3), the Inspection periods specified in these Tables may be decreased or extended by as much as 1 year to enable inspection to coincide with Byron Stations refueling outages.
Exelon Byron Station 1-2 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Table 1.1-1 Byron Station Unft 1 and Unft 21S1 Interval/Perlod(Outage Matrix (for lSl Class 1, 2, and 3 component examinations)
Unit 1 Period Interval PeIIOd Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Dat. to End Date Projected Outage Outage Number Start Date or End Date Start Date or Number Outage Duration Outage Duration B1R14 Fa112006 1~ 1~ Spring2007 B2R13 (3-1-1) (Start tnt) 1/16/06tol/15(09 1/16/06(0 1/15/09 (Start3~dInt) (3-1-1)
B1R15 SprIng 2008 3~(Unit 1) Fall 2008 B2R14 (3-1-2) 1/16/06 to 1/15/16 j~-1-2)
B1R16 Fall 2009 2~° ,~ 2~ Spring 2010 B2R15 (3-2-1) 1/l6Io9to 1/15/122 3 (UnIt 2) , 1/16/09 to 1/15/122 (3-2-1)
B1R17 Spring 2011 1/16/O6to 1/15/16 Fall 2011 B2R16 (3-2-2) (3-2-2)
B1R18 Fall 2012 3 m 3t0 Spring 2013 B2R17 (3-3-1) 1/16/l2tol/15/162 1/16/l2tol/1511& f3-3-1)
B1R19 SprIng 2014 Fall 2014 B2R18 (3-3-2) (End 3fC~lnt) (End 3~d Int) (3-3-2)
Note 1: A request to share a common intetvai start and end date between Byron Station Units 1 and 2 was submitted in accordance with Relief Request 13R-O1.
Note 2: The Byron Station Units 1 and 2 Second Period was reduced by one year and the Third Period was extended by one year as permitted by IWA-2430(d)(3) in order to coincide with the plant refueling outage schedule.
Exelon Byron Station 1-3 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Table 1.1-2 Byron Station Unit I and Unit 2151 IntervallPeriodlOutage Matrix (for ISI Class MC component examinations)
Unit 1 Period Interval Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Data to End Date Projected Outage Outage Number Start Data or End Date Start Date or Number Outage Duration Outage Duration B1R14 FaIl 2006 1~ 1~ SprIng 2007 B2R13 (2-1-1) (Start 2i~dtnt) 1/16106 to 1/15/09 1/16(06 to 1/15/09 (Start 2~tnt) (2-1-1)
B1A15 Sprlng200S 2~(Unit 1) Fall 2008 B2R14 (2-1-2) 1/16/O6to 1/15/161 (2-1-2)
Bi R16 Fall 2009 2~ 2t~a SprIng 2010 B2R1 5 (2-2-1) 1/16/O9tol/15/122 2~(Uflit2) 1/16/O9tol/15/122 (2-2-1)
B1R17 Spring2Oll 1/16/O6tol/15/16 FaIl2Oll B2R16 (2-2-2) (2-2-2)
B1R18 Fall 2012 3~a 3~ Spring 2013 - B2R17 (2-3-1) 1/16/12 to 1/15/162 1/16/12(0 1/15/162 (2-3-1)
B1R19 Spring 2014 Fall 2014 B2R18 (2-3-2) (End 2~Int) (End 2~tnt) (2-3-2)
Note 1: A request for use of subsequent ASME Section XI Code Edition and Addenda was submitted In accordance with Relief Request 13R-01 which Implements the 2001 EdItion through the 2003 Addenda of ASME Section Xl for the CISI Programs as well as to share a common Interval start and end date with the ISl Program.
Note2: TheByronStatlonUnitsi and2SecondPeriodwasreducedbyoneyearandtheThirdPerlodwasextendedbyoneyearaspermittedby IWA-2430(d)(3) In order to coincide with the plant refueling outage schedule.
Exelon Byron Station 1-4 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Table 1.1-3 Byron Station Unit 1 and Unit 2151 lntervallPeriodlOutage Matrix (for ISI Class CC component examinations)
UnIt 1 Period Interval Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Date to End Date Projected Outage Outage Number Start Date or End Date Start Date or Number Outage Duration Outage Duration B1R14 FaIl 2006 i~ 1~ Spring 2007 B2R13 (2-1-1) (Start2~tnt) 1/1~6to1/15/11 1/16/06 to 1/15/11 (Start2~Int) (2-1-1)
B1R15 Spring 2008 2~(Unit 1) Fall 2008 B2R14 (2-1 -2) 1/16/06 to 1/15/16 (2-1-2)
B1R16 Fall 2009 SprIng 2010 B2R15 (2-1-3) ~ 2~(Unit 2) (2-1-3) 1/16106 to 1/15/161 2~
B1R17 SprIng 2011 2~ FaIl 2011 B2R16 (2-2-1) 1/16/11 to 1/15/16 1/16/11(01/15/16 (2-2-1)
B1R1S Fall 2012 Spring 2013 B2R17 (2-2-2) (2-2-2)
B1R19 Spring 2014 FaIl 2014 B2R18 (2-2-3) (End 2~tnt) (End 2~~tnt) d (2-2-3)
Note 1: A request for use of subsequent ASME Section XI Code Edition and Addenda was submitted in accordance with Relief Request 13R-O1 which Iniptements the 2001 Edition through the 2003 Addenda of ASME Section Xl for the CISI Programs as well as to share a common Interval start and end date with the ISI Program.
Exelon Byron Station 1-5 Revision 0
IS! Program Plan Units 1 & 2, Third Interval
1.2 BACKGROUND
The Commonwealth Edison Company, now known commercially as Exelon Generation Company or Exelon, obtained Construction Permits to build Byron Station Units 1 and 2 on December 31, 1975, for Unit 1, CPPR-1 30, and for Unit 2, CPPR-1 31. The Docket Numbers assigned to Byron Station are 50-454 for Unit 1 and 50-455 for Unit 2. After satisfactory plant construction and pro-operational testing was completed, Exelon was granted a full-power operating license for Unit 1, NPF-37, and subsequently commenced commercial operation on September 16, 1985; the full-power operating license for Unit 2, NPF-66, was granted and cornmercial operation commenced on August 22, 1987.
Byron Stations piping systems and associated components were designed and fabricated to the examination requirements of ASME Section Xl. Although this plant was specifically designed to meet the requirements of ASME Section Xl, literal compliance may not be feasible or practical within the limits of the current plant design. Certain limItations are likely to occur due to conditions such as accessibility, geometric configuration, and/or metallurgical characteristics. For some inspection categories, an alternate component may be selected for examination and the code statistical and distribution requirements can still be maintained. If Code required examination selection criteria cannot be met, a relief request will be submitted in accordance with 10 CFR 50.55a.
1.3 SECOND INTERVAL ISI PROGRAM Pursuant to the Code Of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (10 CFR 50.55a), Paragraph (g), Inservice inspection requirements, licensees were required to update their ISI Programs to meet the requirements of ASME Section Xl once every ten years or inspection interval. The ISI Program was required to comply with the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a twelve (12) months prior to the start of the interval per 10 CFR 50.55a(g)(4)(ii).
The Byron Station Second Interval 1St Program Plan was initially developed In accordance with the requirements of 10 CFR 50.55a including alt published changes through June 30, 1995 and September 15, 1997 for Units 1 and 2 respectively, and the 1989 Edition, No Addenda of ASME Section Xl. This ISI Program Plan addressed Subsections IWA, IWB, IWC, IWD, IWF, and Mandatory Appendices of ASME Section Xl, approved ASME Code Cases, approved alternatives through relief requests and Safety Evaluation Reports (SEAs), and utilized inspection Program B as defined therein.
As an alternative to the full ten-year interval duration requirements of IWA-2430(b) and (d) and IWA-2432 for the Unit 2 Second IS1 Interval and for the Units 1 and 2 First CISI Intervals, Byron Station has proposed Relief Request l3R-01 to modify the interval dates of the Unit 2 Second ISI Interval and of the Units 1 and 2 First ClSl Intervals. This will permit the subsequent lSI and CISI Programs to share a common inspection interval and to implement common code editions for Class 1, 2, 3, MC, Exelon Byron Station 1-6 RevisIon 0
ISI Program Plan Units 1 & 2, Third Interval and CC components. As such, the Second Inservice Inspection Interval was effective from June 30, 1996 through January 15, 2006 for Byron Station Unit 1 and effective from August 16, 1998 through January 15, 2006 for Byron Station Unit 2.
Augmented ISI of Byron Station Unit 1 Reactor Vessel shell welds as mandated by 10 CFR 50.55a(g)(6)(ii)(A), was completed during the last period of First Ten-Year InspectIon interval. Volumetric examination of greater than 90% of the weld volume was completed, except as detailed In Relief Request NR-20 of the First Ten-Year Interval ISI Program Plan.
Augmented lSl of Byron Station Unit 2 Reactor Vessel shell welds as mandated by 10 CFR 50.55a(g)(6)(ii)(A), was completed during the last period of First Ten-Year Inspection Interval. Volumetric examination of greater than 90% of the weld volume was completed, except as detailed in Relief Request NA-27 of the First Ten-Year Interval 1St Program Plan.
1.4 THIRD INTERVAL 1St PROGRAM Per 10 CFR 50.55a(g), licensees are required to update their IS1 Programs to meet the requirements of ASME Section Xl once every ten years or inspection interval.
The ISI Program is required to comply with the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a twelve (12) months prior to the start of the interval per 10 CFR 50.55a(g)(4)(ii). As discussed in Section 1.3.1 above, the start of the Third ISI Interval will be on January 16, 2006 for Byron Station UnIts 1 and 2. Based on this date, the latest edition and addenda of the Cde referenced in 10 CFR 50.55a(b)(2) twelve months prior was the 2001 Edition through the 2003 Addenda.
The Byron Station Third Interval 151 Program Plan was developed in accordance with the requirements of 10 CFR 50.55a including all published changes through November 1, 2004 for Units 1 and 2 respectIvely, and the 2001 Edition through the 2003 Addenda of ASME Section Xl, subject to the limitations and modifications contained within Paragraph (b) of the regulation. The limitations and modifications are detailed in Table 1.7-1 of this section. This ISI Program Plan addresses Subsections IWA, IWB, IWC, IWD, IWF, Mandatory Appendices of ASME Section Xl, approved ASME Code Cases, approved alternatives through relief requests and SEAs, and utilizes Inspection Program B as defined therein.
Byron Station has adopted the EPRI Topical Report TA-i12657, Rev. B-A methodology, which is supplemented by Code Case N-578-1, for implementing risk-informed inservice inspections under Relief Request l3R-02. The RISI Program will be in effect for the entire Third Inspection Interval. This approach replaces the categorization, selection, and examination volume requirements of ASME Section Xl Categories B-F, B-J, C-F-i, and C-F-2 applicable to Byron Station with Category A-A as defined in Code Case N-578-i.
Byron StatiOn has also adopted the EPRI Topical Report TR-1 006937, Rev. 0-A, methodology for additional guidance for adaptation of the AISI evaluation process to Exelon Byron Station 1-7 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Break Exclusion Region (BER) piping, also referred to as the High Energy Line Break (HELB) region. This change to the BER program is made under 10 CFR 50.59 evaluation criteria. The BEA program will be in effect for the entire Third Inspection Interval.
1.5 First Interval CISI Program CISI examinations were originally invoked by amended regulations contained within a Final Rule issued by the Nuclear Regulatory Commission (NRC). The amended regulation incorporated the requirements of the 1992 Edition with the 1992 Addenda of the ASME Section XI, Subsections IWE and IWL, subject to specific modifications that were included in Paragraphs 10 CFR 50.55a(b)(2)(ix) and 10 CFR 50.55a(b)(2)(x). Relief from the examination requirements of Subsections IWE and IWL of the 1992 Edition through the 1992 Addenda of ASME Section XI was granted by the NRC to allow Byron Station to use the 1998 Edition of Subsections IWE and 1WL of ASME Section XI for inspection of containment components.
The final rulemaking was published in the Federal Register on August 8, 1996 and specified an effective date of September 9, 1996. Implementation of the Subsection IWE and IWL Program from a scheduling standpoint was driven by the five year expedited implementation period per 10 CFR 50.55a(g)(6)(ii)(B), which specified that the examinations required to be completed by the end of the First Period of the First Inspection Interval (per Table IWE-241 2-1) be completed by the effective date (by September 9, 2001).
ASME Section Xl Subsections IWE, IWL, Mandatory Appendices, approved ASME Code Cases, and approved alternatives through relief requests and SEAs were added to the ISI Program midway through the Second Inspection Interval to address CISI. The CISI Program Plan was developed and implemented prior to the required date, and examinations for the first and second periods were performed in accordance with the First Inspection interval schedule.
As an alternative to the full ten-year interval duration requirements of IWA-2430(b) and (d) and IWA-2432 for the Unit 2 Second ISI Interval and for the Units I and 2 First CISI Intervals, Byron Station has proposed Relief Request 13R-01 to modify the interval dates of the Unit 2 Second lSl Interval and of the Units 1 and 2 First ClSl Intervals. This will permit the subsequent 151 and CISI Programs to share a common inspection interval and to implement common code editions for Class 1, 2, 3, MC, and CC components. As such, the First CISI Interval occurred approximately three years early and was effective from September 9, 1996 through January 15, 2006 for Byron Station Units 1 and 2.
1.6 Second Interval CISI Proaram Per 10 CFR 50.55a(g), licensees are required to update their ClSl Programs to meet the requirements of ASME Section XI once every ten years or inspection interval.
The CISI Program is required to comply with the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a twelve (12) months prior to the Exelon Byron Station 1-8 Revision 0
ISI Program Plan Units 1 & 2, Third Interval start of the interval per 10 CFR 50.55a(g)(4)(il). As discussed in Section 1.5 above, the start of the Second CISI Interval will be on January 16, 2006 for Byron Station Units 1 and 2. Based on this date, the latest edition and addenda of the Code referenced in 10 CFA 50.55a(b)(2) twelve months prior was the 2001 EdItion through the 2003 Addenda.
The Byron Station Second Interval C1SI Program Plan was developed in accordance with the requirements of 10 CFR 50.55a including all published changes through November 1, 2004, and the 2001 EditIon through the 2003 Addenda of ASME Section XI, subject to the limitations and modifications contained within Paragraph (b) of the regulation. The limitations and modifications are detailed in Table 1.7-1 of this section.
This ClSl Program Plan addresses Subsections IWE, IWL, Mandatory Appendices, approved ASME Code Cases, approved alternatives through relief requests and SEAs, and utilizes Inspection Program B as defined therein.
1.7 Code of Federal Reaulations 10 CFR 50.55a Reauirements There are certain Paragraphs in 10 CFR 50.55a that list the limitations, modifications, and/or clarifications to the Implementation requirements of ASME Section XI. These Paragraphs in 10 CFR 50.55a, including all published changes through November 1, 2004, that are applicable to Byron Station are detailed in Table 1.7-1.
Exelon Byron Station 1-9 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATiONS 10 CFR 50.55A REQUIREMENTS Sheet I of 7 10 CFR 50.55a Paragraphs Limitations, Modifications, and Clarifications 10 CFR 50.55a(b)(2)(viii)(E) (CISI) Examination of concrete containments: For Class CC applications, the licensee shall evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result In degradation to such inaccessible areas. For each Inaccessible area identified, the licensee shall provide the following in the lSl Summary Report required by IWA-6000:
(1) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (2) An evaluation of each area, and the result of the evaluation, and; (3) A description of necessary corrective actions.
10 CFR 50.55a(b)(2)(viii)(F) (CISI) Examination ofconcrete containments: Personnel that examine containment concrete surfaces and tendon hardware, wires, or strands must meet the qualification provisions in IWA-2300. The owner-defined personnel qualification provisions in IWL-2310(d) are not approved for use.
10 CFR 50.55a(b)(2)(viii)(G) (CISI) Examination ofconcrete containments: Corrosion protection material must be restored following concrete containment post-tensioning system repair and replacement activities in accordance with the quality assurance program requirements specified in IWA-1 400.
10 CFR 50.55a(b)(2)(ix)(A) (CISI) Examination of metal containments and the liners of concrete containments: For Class MC applications, the licensee shall evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could Indicate the presence of or result in degradation to such inaccessible areas. For each inaccessible area identified, the licensee shall provide the following in the ISI Summary Report as required by IWA-6000:
(1) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (2) An evaluation of each area, and the result of the evaluation, and;
{3) A description of necessary corrective actions.
Exelon Byron Station 1-10 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATIONS 10 CFR 50.55A REQUiREMENTS Sheet 2 of 7 10 CFR 50.55a Paragraphs LimitatIons, Modifications, and Clarifications 10 CFR 50.55a(b)(2)(ix)(B) (CISI) Examination ofmetal containments and the !iners ofconcrete containments: When performing remotely the visual examinations required by Subsection IWE, the maximum direct examination distance specified in Table IWA-2210-1 may be extended and the minimum illumInation requirements specified in Table IWA-2210-1
- may be decreased provided that the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination.
10 CFR 50.55a(b)(2)(ix)(F) (CISI) Examination ofmetal containments arid the liners of concrete containments: VT-i and VT-3 examinations must be conducted In accordance with IWA-2200.
Personnel conducting examinations in accordance with the VT-i or VT-3 examination method shall be qualified in accordance with IWA-2300. The owner-defined personnel qualification provisions In IWE-2330(a) for personnel that conduct VT-i and VT-3 examinations are not approved for use.
10 CFR 50.55a(b)(2)(ix)(G) (CISI) Examination of metal containments and the liners ofconcrete containments: The VT-i examination method must be used to conduct the examination in Item E4.i 1 of Table 1WE-2500-1. An examination of the pressure-retaining bolted connections in Item El .11 of Table IWE-2500-i using the VT-3 examination method must be conducted once each interval. The owner-defined vIsual examination provisions in IWE-231 0(a) are not approved for use for VT-i and VT-3 examinations.
Exelon Byron Station 1-11 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATIONS 10 CFR 50.55A REQUIREMENTS Sheet 3o17 10 CFR 50.55a Paragraphs Umltatlons, Modifications, and Clarifications 10 CFR 50.55a(b)(2)(ix)(H) (CISI) Examination ofmetal containments and the liners ofconcrete containments: Containment bolted connections that are disassembled during the scheduled performance of the examinations in Item El .11 of Table IWE-2500-l must be examined using the VT-3 examination method. Flaws or degradation identified during the performance of a VT-3 examination must be examined in accordance with the VT-i examination method. The criteria in the material specification or IWB-3517.1 must be used to evaluate containment bolting flaws or degradation. As an alternative to performing VT-3 examinations of containment bolted connections that are disassembled during the scheduled performance of item El .11, VT-3 examinations of containment bolted connections may be conducted whenever containment bolted connections are disassembled for any reason.
10 CFR 50.55a(b)(2)(Ix)(l) (CISI) Examination of metal containments and the liners of concrete containments: The ultrasonic examination acceptance standard specified in IWE-351 1.3 for Class MC pressure-retaining components must also be applied to metallic liners of Class CC pressure-retaining components.
10 CFA 50.55a(b)(2)(xi) (lSI) Class 1 piping: Licensees may not apply IWB-i 220, Components Exempt from Examination, of Section Xl, 1989 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, and shall apply IWB-1220, 1989 Edition.
10 CFR 50.55a(b)(2)(xii) (ISI) Underwater Welding: The provisions in IWA-4660, Underwater Welding, of Section Xi, 1997 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, are not approved for use on irradiated material.
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IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATIONS 10 CFR 50.55A REQUIREMENTS Sheet 4 of 7 10 CFR 50.55a Paragraphs Umltatlons, ModIficatIons, and ClarifIcatIons 10 CFR 50.55a(b)(2)(xviii)(A) (ISI) Certification ofNDE personnel: Level I and Ii nondestructive examination personnel shall be recertified on a 3-year interval in lieu of the 5-year interval specified in the 1997 Addenda and 1998 Edition of IWA-2314, and IWA-2314(a) and IWA-2314(b) of the 1999 Addenda through the latest edition and addenda incorporated by reference In Para~aph(b)(2) of this section.
10 CFR 50.55a(b)(2)(xviii)(B) (ISI) Certification ofNDE personnel: Paragraph IWA-2316 of the 1998 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, may only be used to qualify personnel that observe for leakage during system leakage and hydrostatic tests conducted in accordance with IWA-5211(a) and (b), 1998 Edition through the latest edition and addenda incorporated by reference in Paragraph (bX2) of this section.
10 CFR 50.55a(b)(2)(xvili)(C) (ISI) Certification ofNDE personnel: When qualifying visual examination personnel for VT-3 visual examinations under Paragraph IWA-231 7 of the 1998 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, the proficiency of the training must be demonstrated by administering an Initial qualification examination and administering subsequent examinations on a 3-year interval.
Exelon Byron Station
- 1-13 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATIONS 10 CFR 50.55A REQUIREMENTS Sheet 5 of 7 10 CFR 50.55a Paragraphs LimitatIons, Modifications, and Clarifications 10 CFR 50.55a(b)(2)(xix) (151) Substitution ofalternative methods: The provisions for the substitution of alternative examination methods, a combination of methods, or newly developed techniques in the 1997 Addenda of IWA-2240 must be applied. The provisions in IWA-2240, 1998 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, are not approved for use.
The provisions in IWA-4520(c), 1997 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, allowing the substitution of alternative examination methods, a combination of methods, or newly developed techniques for the methods specified in the Construction Code are not approved for
. use.
10 CFR 50.55a(b)(2)(xxl)(A) (ISI) Table IWB-2500- 1 examination requirements: The provisions of Table IWB-2500-1, Examination Category B-
. D, Full Penetration Welded Nozzles in Vessels, Items B3.120 and B3.140 (Inspection Program B) in the 1998
- Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference In Paragraph (b)(2) of this section. A visual examination with enhanced magnification that has a resolution sensitivity to detect a 1 -mil width wire or crack, utilIzing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda Incorporated by reference in Paragraph (b)(2) of this section, may be performed in place of an ultrasonic examination.
Exelon Byron Station 1-14 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATIONS 10 CFR 50.55A REQUIREMENTS Sheet 6 of 7 10 CFR 50.55a Paragraphs LimitatIons, Modifications, and ClarIfications 10 CFR 50.55a(b)(2)(xxi)(C) (151) Table IWB-2500-1 examination requirements: The provisions of Table IWB-2500-1, Examination Category B-K, Item B10.10, of the 1995 Addenda must be applied
. when using the 1997 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section.
10 CFR 50.55a(b)(2)(xxil) (151) Surface Examination: The use of the provision in IWA-2220, Surface Examination, of Section Xl, 2001 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, that allow use of an ultrasonic examination method is prohibited.
10 CFR 50.55a(b)(2)(xxiii) (ISI) Evaluation of Thermally Cut Surfaces: The use of the provisions for eliminating mechanical processing of thermally cut surfaces In IWA-4461 .4.2 of Section Xl, 2001 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section are prohibited.
10 CFR 50.55a(b)(2)(xxiv) (PDI) Incorporation of the Performance Demonstration Initiative and Addition of Ultrasonic Examination Criteria:
The use of Appendix VIII and the supplements to Appendix VIII and Article 1-3000 of Section XI of the ASME BPV Code, 2002 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section, is prohibited.
10 CFR 50.55a(b)(2)(xxv) (151) Mitigation ofDefects by Modification: The use of the provisions in IWA-4340, Mitigation of Defects by Modification,Section XI, 2001 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section are prohibited.
10 CFR 50.55a(b)(2)(xxvi) (SPT) Pressure Testing Class 1, 2, and 3 Mechanical Joints: The repair and replacement actMty provisions in IWA-4540(c) of the 1998 Edition of Section XI for pressure testing Class 1, 2, and 3 mechanical joints must be applied when using the 2001 Edition through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section.
Exelon Byron Station 1-15 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 1.7-1 CODE OF FEDERAL REGULATIONS 10 CFR 50.55A REQUIREMENTS Sheet 7 of 7 10 CFR 50.55a Paragraphs Umitatlons, Modifications, and Clarifications 10 CFR 50.55a(b)(2)(xxvii) (SPT) Removal ofInsulation: When performing visual examinations in accordance with IWA-5242 of Section Xl, 2003 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of the section, insulation must be removed from 17-4 PH or 410 stainless steel studs or bolts aged at a temperature below 1100°For having a Rockwell Method C hardness value above 30, and from A-286 stainless steel studs or bolts preloaded to 100,000 pounds per square Inch or higher.
Exelon Byron Station 1-16 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 1.8 Code Cases Per 10 CFR 50.55a(b)(5) and (b)(6), ASME Code Cases that have been determined to be suitable for use In ISI Program Plans by the NRC are listed in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1. The approved Code Cases in Regulatory GuIde 1.147, which are being utilized by Byron Station, are included in Section 2.1.2. The most recent version of a given Code Case incorporated in the revision of Regulatory GuIde 1.147 referenced in 10 CFR 50.55a(b)(5)(I) at the time it is applied within the ISI Program shall be used. The latest version of Regulatory Guide 1.147 incorporated into this document is Revision 14. As this guide is revised, newly approved Code Cases should be assessed for plan implementation at Byron Station.
The use of other Code Cases (than those listed In Regulatory GuIde 1.147) may be authorized by the Director of the office of Nuclear Reactor Regulation upon request pursuant to 10 CFR 50.55a(a)(3). Code Cases not approved for use in Regulatory Guide 1.147, which are being utilized by Byron Station through associated relief requests, are included in Section 8.0.
This lSl Program Plan will initially utilize the Draft Regulatory Guide DG-1 125 (Proposed Revision 14 of Regulatory Guide 1.147) with the anticipation that the Final Revision 14 of Regulatory Guide 1 .147 will be approved prior to the start of the Third Inspection Interval. Byron Station will review the Final Revision 14 of Regulatory Guide 1.147 for ISI Program Impact at which time It is published.
This ISI Program Plan will also utilize Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code. The approved Code Case in Regulatory Guide 1.192, which Is being utilized by Byron Station, is included in Section 2.1.3. The latest version of Regulatory Guide 1.192 incorporated into this document is Revision 0. As this guide is revised, newly approved Code Cases should be assessed for plan implementation at Byron Station.
1.9 REUEF REQUESTS In accordance with 10 CFR 50.55a, when a licensee either proposes alternatives to ASME Section Xl requirements, which provide an acceptable level of quality and safety, determines compliance with ASME Section Xl requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, or determines that specific ASME Section Xl requirements for inservice inspection are impractical, the licensee shall notify the NRC and submit information to support the determination.
The submittal of this information will be referred to in this document as a Relief Request or Request for Relief. Relief Requests for the Third Inspection Interval are included in Section 8.0 of this document. The text of the Relief Requests contained in Section 8.0 will demonstrate one of the following: the proposed alternatives provide an acceptable level of quality and safety per 10 CFR 50.55a(a)(3)(i); or compliance with the specified requirements would result in Exelon Byron Station 1-17 Revision 0
IS! Program Plan Units 1 & 2, Third Interval hardship or unusual difficulty without a compensating increase in the level of quality and safety per 10 CFR 50.55a(a)(3)(ii), or the code requirements are considered impractical per 10 CFR 50.55a(g)(5)(iii).
Per 10 CFR 50.55a Paragraphs (a)(3) and (g)(6)(i), the Director of the Office of Nuclear Reactor Regulation will evaluate relief requests and may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Exelon Byron Station 1-18 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM 2.1 ASME SEcTIoN Xl EXAMINATION REQUIREMENTS 2.1.1 Welds and Components, Supports, and Pressure Tests As required by the Code Of Federal Regulations, Title 10, Part 50, Section 55a, (10 CFR 50.55a), this Program was developed in accordance with the requirements detailed in the 2001 Edition through the 2003 Addenda, of the ASME Boiler and Pressure Vessel Code,Section XI, Division 1, Subsections IWA, IWB, IWC, IWD, IWE, IWF, IWL, Mandatory Appendices, and Inspection Program B of IWA-2432, approved ASME Code Cases, and approved alternatives through relief requests and SERs.
The lSl Program implements Appendix VIII Performance Demonstration for Ultrasonic Examination Systems, ASME Section Xi 2001 EditIon, No Addenda as required by 10 CFR 50.55a(b)(2) and modified by 10 CFR 50.55a(b)(2)(xxiv).
Appendix VIII requires qualification of the procedures, personnel, and equipment used to detect and size flaws in piping, bolting, and the reactor pressure vessel (RPV). Each organization (e.g., owner or vendor) will be required to have a written program to Insure compliance with the requirements. These requirements were Initially implemented through the Performance Demonstration Initiative (PDI) Program according to the schedule defined in 10 CFR 50.55a(g)(6)(ii)(C).
For the Third Inspection Interval, Byron Stations inspection program for ASME Section Xl Categories B-F, B-J, C-F-i, and C-F-2 will be governed by risk-informed regulations. The RISI Program methodology is described in the EPRI Topical Report TR-1 12657, Rev. B-A. To supplement the EPRI Topical Report, Code Case N-578-1 (as applicable per Relief Request 13R-02) is also being used for the classification of piping structural elements under the RISI Program. The RISI Program scope will be implemented as an alternative to the 2001 Edition through the 2003 Addenda ASME Section Xl Code examination program for Class 1 B-F and B-J welds and Class 2 C-F-1 and C-F-2 welds in accordance with 10 CFR 50.55a(a)(3)(I). The basis for the resulting Risk Categorizations of the non-exempt Class 1 and 2 piping systems at Byron Station is defined and maintained in the Final Report Risk Informed lnservice inspection Evaluation as referenced in Section 9.0 of this document.
For the Third Inspection Interval, the RlSl Program scope has been expanded to include welds in the BER piping, also referred to as the HELB region, which includes several non-class welds that fall within the BER augmented inspection program. The BER program methodology is described in EPRI Topical Report TR-1 006937, Rev.
0-A, which will be used to define the inspection scope in lieu of the 100% examination of all piping welds in the previous BER augmented program. Therefore, all welds in the original augmented program for BER will be evaluated under the RISI Program using an integrated risk-informed approach.
Exelon Byron Station 2-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 2.1.2 ASME Section Xl Code Cases As referenced by 10 CFR 50.55a(b)(5) and allowed by NRC Regulatory Guide 1.147, Revision 14, the following Code Cases are being Incorporated into the Byron Station ISi Program.
N-432-1 Repair Welding UsingAutomatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique,Section XI, Division 1.
N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1.
N-51 7-1 Quality Assurance Program Requirements for Owners,Section XI, Division 1.
Code Case N-51 7-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14.
The Owners Quality Assurance (QA) Program that is approved under Appendix B to 10 CFR Part 50 must address the use of this Code Case and any unique QA requirements identified by the Code Case that are not contained in the owners QA Program description. This would include the actMties performed in accordance with this Code Case that are subject to monitoring by the Authorized Nuclear inspector.
N-526 Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels,Section XI, DIvision 1.
N-528-1 Purchase, Exchange, or Transfer ofMaterial Between Nuclear Plant Sites, Section Xl, Division 1.
Code Case N-528-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14.
The requirements of 10 CFR Part 21 are to be applied to the nuclear plant site supplying the material as well as to the nuclear plant site receMng the material that has been purchased, exchanged, or transferred between sites.
N-532-1 Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and !WA-6000, Section Xl, Division 1.
Code Case N-532-i is acceptable subject to the following conditions specified In Regulatory Guide 1.147, RevisIon 14.
Code Case N-532-1 requires an Owners Activity Report Form OAR-i to be prepared and certified upon completion of each refueling outage. The OAR-i forms must be submitted to the NRC within 90 days of the completion of the refueling outage.
Exelon Byron Station 2-2 Revision 0
IS! Program Plan Units 1 & 2, Third Interval N-566-2 Corrective Action for Leakage Identifiedat Bolted Connections, Section Xl, Division 1.
N-576-1 Repair of Class 1 and 2 SB-i63, UNS N06600 Steam Generator Tubing,Section XI, Division 1.
Code Case N-576-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14.
NOTES: Steam Generator tube repair methods require prior NRC approval through the Technical Specifications. This Code Case does not address certain aspects of this repair, e.g., the qualification of inspection and plugging criteria necessary for staff approval of the repair method. In addItion, it the user plans to reconcile, as described in the footnote, the reconciliation is to be performed in accordance with IWA-4200 in the 1995 Edition through the 1996 Addenda of ASME Section Xl.
N-586 Alternative Additional Examination Requirements for Class 1, 2, and 3 Piping, Components, and Supports, Section Xl, Division 1.
N-597-1 Requirements for Analytical Evaluation of Pipe Wall Thinning, Section Xl, Division 1.
Code Case N-597-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, RevisIon 14.
(1) Code Case must be supplemented by the provisions of EPRI Nuclear Safety Analysis Center Report 202L-R2, April 1999, Recommendations for an Effective Flow Accelerated Corrosion Program, for developing the inspection requirements, the method of predicting the rate of wall thickness loss, and the value of the predicted remaining wall thickness. As used in NSAC-202L-R2, the terms should and shall have the same expectation of being completed.
(2) Components affected by flow-accelerated corrosion to which this Code Case are applied must be repaired or replaced in accordance with the construction code of record and Owners requirements or a later NRC approved edition of Section III of the ASME Code prior to the value of t~,
reaching the allowable minimum wall thickness, tmlfl, as specified Ifl
-3622.1(a)(1) of this Code Case. Alternatively, use of the Code Case is subject to NRC review and approval.
(3) For Class 1 piping not meeting the criteria of -3221, the use of evaluation methods and criteria is subject to NRC review and approval.
(4) For those components that do not require immediate repair or replacement, the rate of wall thickness loss is to be used to determine a suitable Inspection frequency so that repair or replacement occurs prior to reaching allowable minimum wall thickness, t~.
(5) For corrosion phenomenon other than flow accelerated corrosion, use of the Code Case is subject to NRC review and approval. Inspection plans Exelon Byron Station 2-3 Revision 0
IS! Program Plan Units 1 & 2, Third Interval and wall thinning rates may be difficult to justify for certain degradation mechanisms such as MIC and pitting.
N-600 Transfer of Welder, Welding Operator, Brazer, and Brazing Operator Qualffications Between Owners, Section Xl, Division 1.
N-61 3-1 Ultrasonic Examination of Penetration Nozzles in Vessels, Examination Category B-D, Item Nos. 83.10 and B3.90, Reactor Nozzle-to-Vessel Welds, Figs. lWB-2500-7(a), (b), and (c), Section Xl, Division 1.
N-624 Successive Inspections,Section XI, Division 1.
N-638-1 Similararid DissimilarMetal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique, Section Xl, Division 1.
Code Case N-638-1 is acceptable subject to the following conditIons specified in Regulatory Guide 1.147, Revision 14.
UT volumetric examinations shall be performed with personnel and procedures qualified for the repaired volume and qualified by demonstration using representative samples which contain construction type flaws. The acceptance criteria of NB-5330 in the 1998 Edition through the 2000 Addenda of Section lIt apply to all flaws IdentifIed within the repaired volume.
N-639 Alternative Calibration Block Material, Section Xl, Division 1.
Code Case N-639 is acceptable subject to the following conditions specified In Regulatory Guide 1.147, Revision 14.
Chemical ranges of the calibration block may vary from the materials specification if: (1) it is within the chemical range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.
N-641 Alternative Pressure-Temperature Relationship and Low Temperature Overpressure Protection System Requirements, Section Xl, Division 1.
N-643 Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water Environment, Section Xl, DMsion 1.
N-648-1 Alternative Requirements for Inner Radius Examinations ofClass 1 Reactor Vessel Nozzles, Section Xl, Division 1.
Code Case N-648-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14.
In place of a UT examination, licensees may perform a visual examination with enhanced magnification that has a resolution sensitMty to detect a 1-Exelon Byron Station 2-4 Revision 0
IS! Program Plan Units 1 & 2, Third Interval mit width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table.
N-651 Ferritic and DissimilarMetal Welding Using SMAW Temper Bead Technique Without Removing the Weld Bead Crown for the First Layer, Section Xl, Division 1.
N-661 Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service, Section Xl, Division 1.
Code Case N-661 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14.
(a) If the root cause of the degradation has not been determined, the repair Is only acceptable for one cycle.
(b) Weld overlay repair of an area can only be performed once in the same location (c) When through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair is only acceptable until the next refueling outage.
N-695 Qualification Requirements for DissimilarMetal Piping Welds, SectionXl, Division 1.
Additional Code Cases may be invoked in the future based on new ISI Program Plan requirements or revisions to Regulatory Guide 1.147. Any Code Cases invoked in the future shall be in accordance with those approved for use in the latest published revision of Regulatory Guide 1.147 at that time.
2.1.3 OM Code Cases As referenced by 10 CFR 50.55a(b)(6) and allowed by NRC Regulatory Guide 1.192, Revision 0, the following Code Case is being incorporated into the Byron Station ISI Program.
OMN-1 3, Rev. 0 Requirements for Extending Snubber Inservice Visual Examination Intervalat LWR Power Plants, OM Code.
Additional Code Cases may be invoked in the future based on new 151 Program Plan requirements or revisions to Regulatory Guide 1.192. Any Code Cases invoked in the future shall be in accordance with those approved for use In the latest published revision of Regulatory Guide 1.192 at that time.
Exelon Byron Station 2-5 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 2.2 AUGMENTED EXAMINATiON REQUIREMENTS Augmented examination requirements are those examinations that are performed above and beyond the requirements of ASME Section XI. Below is a summary of those examinations performed by Byron Station that are not specifically addressed by ASME Section XI, or the examinations that will be performed in addition to the requirements of the Code on a routine basis during the Third Inspection Interval.
2.2.1 NRC Branch Technical Position MEB 3-1, High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment, dated November 24, 1975.
UFSAR Sections 3.6.1 and 3.6.2 detail Byron Station compliance with NRC Branch Technical Position MEB 3-1, which includes requirements for licensees to perform a 100% volumetric examination each interval of circumferential and longitudinal pipe welds within the pipe break exclusion regions associated with high energy piping in containment penetration areas.
Implementation of the examination commitments is included In SectIon 7.0 of this ISI Program Plan and the associated ISI database.
Note: This commitment was previously maintained in accordance with UFSAR Section 3.6.1 and 3.6.2. With the Implementation of the RISI-BER Program, all BER augmented welds were evaluated underthe RISI methodology and were integrated into the RlSl Program. The RISI Program will also Include several non-class welds that fall within the BER augmented inspection program. Additional guidance for adaptation of the RISI evaluation process to BER piping is given in EPRI TR-1006937 Rev. 0-A.
2.2.2 NRC Regulatory Guide 1.14, Reactor Coolant Pump Flywheel Integrity This Regulatory Guide includes inspection requirements for Reactor Coolant Pump Flywheels in Section 4. Exelon has committed to these inspections per UFSAR Appendix A and Technical Specifications Section 5.5.7.
Implementation of the examination commitments is included in Section 7.0 of this ISI Program Plan and the associated lSI database.
2.2.3 Byron Station UFSAR Section 10.2.3, Turbine Disk and Rotor Integrity This details Byron Stations commitment to perform visual and magnetic particle examination of the accessible areas of the high-pressure turbine rotor, low-pressure turbine blades, and low-pressure disks. In addition, visual examinations of the turbine coupling and coupling bolts are performed.
This program has been removed from the Engineering Group and is maintained by the Turbine Maintenance organization.
2.2.4 NRC Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant Systems, including supplements 1, 2, and 3.
Exelon Byron Station 2-6 Revision 0
IS! Program Plan Units 1 & 2, Third Interval With the implementation of the RlSl Program, the Bulletin 88-08 augmented inspection commitment will no longer be required at Byron Station. The RISI Program completely subsumes this requirement based on the fact that the Degradation Mechanism assessment and Risk Categorization involve full assessment for Thermal Transients and Thermal Stratification, Cycling, and Striping.
Thus, these piping structural elements will be categorized and selected for examination in accordance with the EPRI Topical Report TA-i 12657, Rev. B-A and Code Case N-578-1 in lieu of the original commitment to Bulletin 88-08.
2.2.5 Information Notice 79-19, Pipe Cracks in Stagnant Borated Water Systems at PWR Plants.
Volumetric examinations will be performed on Class 2 ECCS systems (or portions of systems) that are currently not subject to evaluation under the RISI Program. The inspections include 7.5% sampling of the total population of circumferential piping welds (greater than 4 inches nominal pipe size) that contain stagnant berated water.
For the current inspection interval, the areas subject to augmented examination are limited to the 10 Safely Injection piping from the SI Accumulators (1/2SIO4TA, B, C, and D) to the class boundary second check valve (1/2S18956A, B, C, and D). These lines are exempted from ASME Section Xl examination by Paragraph IWC-1 221(c).
The components selected for these examinations are to be examined before the end of the inspection interval.
2.2.6 NRC NUREG 0737, Section Ill.D.1.1, dated November 1980.
Requires applicants to implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids or gases during a serious transient or accident to as low as practical levels. In response to this NUREG commitment, Section E.77, Primary Coolant Sources Outside Containment, was included in the Byron/Braidwood Station UFSAR. This UFSAR Section along with Technical Specifications Section 5.5.2 require performance of integrated leak tests at refueling cycle intervals or less on each system or portions of systems, which could potentially contain highly radioactive liquids or gases.
Implementation of the Byron Station program addressing these requirements is included In site procedure BVP 200-7.
2.2.7 Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants The Nuclear Regulatory Commission issued Generic Letter (GL) 88-05 to all licensees of operating Pressurized Water Reactors (PWR) in March, 1988. This Generic Letter deals with boric acid corrosion of carbon steel reactor coolant pressure boundary components in PWR plants. Specifically, GL 88-05 requested information to assess safe operation of PWRs when reactor coolant leaks below Tech Spec limits develop and the coolant containing Boric Acid comes in contact with and degrades low alloy carbon steel components. Byron Stations response to Exelon Byron Station 2-7 Revision 0
IS! Program Plan Units I & 2, Third Interval GL 88-05 requirements are incorporated through the completion of normal station operator walkdowns, heightened Maintenance and Tech Staff (now System Engineering) training, the normal Inservice Inspection Program, and the ASME Section XI System Pressure Testing Program.
To ensure compliance with this augmented commitment, the Reactor Coolant Pressure Boundary (RCPB), as defined by UFSAR Section 5.2, shall have a system inspection performed by certified VT-2 examiners every refueling outage consisting of a pre-outage visual examination as well as a visual examination conducted prior to startup. These examinations shall be conducted to identify evidence of boric acid crystallization and residue accumulations.
Implementation of the Byron Station program addressing these requirements is included In site procedure BVP-200-7.
2.3 SYSTEM CLASSIF1CAT~ONSAND P&lD BOUNDARY DRAWINGS The lSl Classification Basis Document details those systems that are ISI Class 1, 2, 3, or MC that fall within the ISI scope of examinations. The concrete containment structure is ISI Class CC and is shown on the containment roll-out drawings. Below is a summary of the classification criteria used within the ISI Classification Basis Document.
Each safety related, fluid system containing water, steam, air, oil, etc. included in the Byron Station UFSAR was reviewed to determine which safety functions they perform during all modes of system and plant operation. Based on these safety functions, the systems and components were evaluated per classification documents. The systems were then designated as ISI Class 1, 2, 3, MC, CC, or non-classed accordingly. This evaluation followed the guidelines of UFSAR Section 5.2.4 for lSl Class 1 and 6.6 for ISI Classes 2 and 3. Safety related portions of systems are defined on the Piping and Instrument Diagrams (P&IDs) and Control and instrumentation Diagrams (C&IDs).
When a particular group of components is identified as performing a ISI Class 1, 2, or 3 safety function, the components are further reviewed to assure the interfaces (boundary valves and boundary barriers) meet the criteria set by 1 OCFR5O.2, 10CFR5O.55a(c)(1), 10CFR5O.55a(c)(2), Regulatory Guide 1.26, and ANSI N18.2-1973. Although Byron Station is not committed to or licensed in accordance with these documents, Standard Review Plan (SAP) 3.2.2 System Quality Group Classification, and other American National Standards Institute/American Nuclear Society (ANSI/ANS) standards were also used for guidance in determining the classification boundaries when 1 OCFR and Regulatory Guide 1.26 dId not address a given situation. The valve positions shown on the system flow diagrams are assumed to be the normal positions during system operation unless otherwise noted.
lSl classification boundaries are defined by the Inservice Inspection ISI Code Boundary Drawings (ISI CBDs) with classification line codes. A summary of the line coding system used on the lSl CBDs to identify safely related systems or portions of Exelon Byron Station 2-8 Revision 0
IS! Program Plan Units 1 & 2, Third Interval systems subject to examination is included on drawing ISl-CBD-LEGEND. Typically, unhatched, solid coding (blue, yellow and green, Coding Designators 1A, 2A, and 3A, respectively) was used for nonexempt ASME Section Xl components. Some hatched codings, (Coding Designators 2HPSI, 2F, and 3C) were also used to identify nonexempt ASME Section Xl components. The remaining codings shown on lSl-CBD-LEGEND (Coding Designators 1B, 1C, 10, 2B, 2C, 2D, 2E, 3B, and 3D) were used to identify exempt ASME Section Xl components.
The systems and components (piping, pumps, valves, vessels, etc.), which are subject to the examinations of Articles IWB-2000, IWC-2000, IWD-2000, and IWF-2000 are identified on the ISI CBDs as detailed in Table 2.3-1 and 2.3-2.
Containment components subject to examination of Articles IWE-2000 and IWL-2000 are identified on the ClSl Drawings shown in Table 2.4-3 and 2.4-4.
Exelon Byron Station 2-9 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.31 .
BYRON STATION COLOR CODED ISI P&ID BOUNDARY DRAWINGS UNIT1&O UNIT2 TITLE M-34-1, 2, 3, 4, 5 M-34-1, 2, 3, 4, 5 P&lD Index & Symbols M-35-1, 2 M-120-1, 2A, 2B Main Steam (MS)
M-36-1A, 1B, 1C, 1D M-121-1A, lB. 1C, 1D Feedwater (FW)
M-152-45 M-152-45 M-37 M-122 Auxiliary Feedwater (AF)
M-42-IA, 18, 2A, 2B, 3, M42-1A, 18, 2A, 28 EssentIal Service Water (SX) 4,5A,5B,6,7 M-126-1,2,3 M-46-1A, IB, 1C M-129-1A, lB. 1C Containment Spray (CS)
M-47-2 M-150-2 Off Gas Hydrogen Recombiners (OG)
M-48-5A M-48-5B Waste Disposal Steam Generator BIOWdOWn (SD)
M-48-6A, 6B M-48-6A, 6B Waste Disposal Aux. Building Floor Drains (RF)
M-48-18 Waste Disposal Resin Removal (WX)
M-49-IA M-49-1B Make-Up Demineralizer (WM)
M-50-1A, 18, 1C, 1D,3 M-130-1A, lB. 2 Diesel Fuel Oil (DO)
M-52-1 Fire Protection (FP)
M-54-2, 4A M-54-2, 48 Service Air (SA)
M-55-4, 9 M-55-5, 7D Instrument Air (IA)
M-59-1A,1B M-149 Nltrogen(NT)
M-60-1A, 1B, 2, 3,4, 5, M-135-1A, 1,2, ~ ~
Reactor Coolant (RC 6,8 6,8 ~ & RY)
M-61 -1 A, 1B, 2, 3, 4, 5, M-136-l, 2, 3, 4, 5, 6 Safety Injection (SI) 6 M-62 M-137 Residual Heat Removal (RH)
M-63-1A, lB. 1C M-63-IA, lB. 1C Fuel Pool Cooling and Clean-Up (FC)
M-64-1, 2, 3A, 3B, 4A, M-138-1, 2, 3A, 3B, ~,
Chemical and Volume Control (CV) 4B,5 5A,5B Chemical and Volume Control I Boron Thermal M-64-6, 7 M-138-6, 7 Regeneration (CV & BR)
M-65-1 B, 2A, 3, 5A, 5B M-65-l B, 5A, 5B Boric Acid (AB)
M-66-3A, 38,48, M-66-1A, 18,2, 3A, 3B, 4C, 4D, Component Cooling (CC) 4A,4C,4D M-139-1,2 M-68-1A, lB. 6, 7, 8 M-140-1, 5, 6 Process Sampling (PS)
M-69-1, 2,3 - Radioactive Waste Gas (GW)
M-70-1, 2 M-1 41-1, 2 Reactor Building Equipment Drains & Vents to Radwaste (RE)
Exelon Byron Station 2-10 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.3-1 BYRON STATION COLOR CODED ISI P&ID BOUNDARY DRAWINGS (Continued)
UNIT1&O UN1T2 TITLE M-78-6, 10 Process Radiation Monitoring (PR)
AuxIliary Building & Containment Equipment Drains M-82-l 2 3 5 15 M-82-l 2 3 5 6
~ ~?JE M 105 1 M-105-1 Containment Purge / Pressure & Vacuum Relief Systems (VO & VP)
M-105-3 M-105-3 Integrated Leak Rate System (VQ)
M-1l8-l, 5, 14 M-118-7 Control Room Chilled Water (WO)
M-152-9 M-152-9, 10 Diesel Generator Lube Oil (DG & DO)
M-152-14 M-152-14 Diesel Generator Jacket Water (DG)
M-152-19 M-152-19 Diesel Generator Cooling Water (DG)
TABLE 2.3-2 BYRON STATION COLOR CODED ISI C&ID BOUNDARY DRAWINGS UNIT1&O UNIT2 TITLE I M~2060-6,7, 8, 17, 18 M-2135-6, 7, 8, 17, 18 C&lD Reactor Coolant System (RC) I Exelon Byron Station 2-11 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 2.4 IS) ISOMETR1C AND COMPONENT DRAWiNGS FOR NONEXEMPT ISI Ct~ssCOMPONENTS AND SUPPORTS lSl Isometric and Component drawings were developed to detail the ISI Code Class 1, 2, 3, MC, and CC components (welds, bolting, etc.) and support locations at Byron Station. These component and support locations are identified on the ISl Isometric and Component drawings listed in Tables 2.4-1, 2.4-2, 2.4-3, and 2.4-4.
Byron Stations ISI Program, including the ISI Database, iSl Classification Basis Document, and 151 Selection Document, addresses the non-exempt components, which require examination and testing.
A summary of Byron Station Unit 1 and 2 ASME Section Xl nonexempt components and supports is included in Section 7.0.
Exelon Byron Station 2-12 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-1 BYRON STATION UNiT 1ISI ISOMETRIC AND COMPONENT DRAWINGS DRAWING SHEET DRAWING TITLE NUMBER NUMBER AUXIUARYFEEDWATER SYSTEM (AF) 1AF-12-B-T --- Auxiliary Feedwater Lines 1AFO2DB-4, 1AFO2DF-4, and 1AFO2EB-4 1AF-12-C-T - Auxiliary Feedwater Lines 1AFO2DC-4~,1AFO2DG-4, and 1AFO2EC~4H IAF-13-A-T --- Auxiliary Feedwater Lines 1AFO2DA-4M, 1AFO2DE-4. and 1AFO2EA-4 1AF-13-D-T Auxiliary Feedwater Lines 1AFO2DD-4, 1AFO2DH-4M, and 1AFO2ED-40 1FW-39-T - Auxiliary Feedwater Lines 1FWO6AB-4 and IFW87BB-3 1 FW-40-T - Auxiliary Feedwater Lines I FW06AC~4Nand 1 FW87BC-3 1 FW-51 -T Auxiliary Feedwater Lines 1 FWO6AA-4 and 1 FW87BA-3 1 FW-52-T Auxiliary Feedwater LInes 1 FWO6AD-4 and 1 FW87BD-30 CONTAINMENT SPRAY SYSTEM (CS) 1CS-l-151 1 Containment Spray Line 1CS02AA-10~
1CS-1 -ISI 2 Containment Spray Line 1CS10AA~6N 1CS-l-ISI 3 ContaInment Spray Lines 1CSO1AA-16, 1CS23AA-14, and 1CSO6AA-6 1CS-l-ISI 4 ContaInment Spray Lines lCS01AB-16~,1CS23AB-14, and 1CSO6AB-6 1CS-l-ISI 5 Containment Spray Line 1CSO2AB-10 1CS-1 -151 6 Containment Spray Lines 1CSO2AB-10 and 1CS10AB-8~
1CS-l -lSl 7 ContaInment Spray Line ICSO2AA-10 1VCT-1-ISl Containment Spray Pumps 1CS-01-PA-1 and 1CS-01-PB-2 CHEMICAL & VOLUME CONTROL SYSTEM (CV)
ICV-l-ISI 1 Chemical & Volume Control Line lCVB7A-3~
1CV-1-lSI 2 ChemIcal & Volume Control Lines 1 RY18A-2M and 1CV45B-2~
ICy-i-lSl 3 ChemIcal & Volume Control Lines 1CV14FB-2 and 1CV14GB-1W 1CV-1 -151 4 ChemIcal & Volume Control Lines 1CVA5AB-2 and lCVA6AB-2~
iCy-i -151 5 Chemical & Volume Control Line lCVA3B-2~
1CV-1-lSl 6 ChemIcal & Volume Control Lines 1CVi4FA-2~and 1CV14FD-2~
1CV-l-ISI 7 Chemical & Volume Control Line 1CVA3B-2 iCy-i-ISI 8 Chemical & Volume Control Line 1CVA5AA-2~
icy-I -ISI 9 Chemical & Volume Control Lines ICVA3B.2N, 1CVA3AB-2, and ICVA7AB-2 1CV-1 -ISI 10 Chemical & Volume Control Line 1CVA3AB-2 1CV-i-lSl 11 ChemIcal & Volume Control Lines 1CVA3B-21 and 1CVA6AA-2 1CV-1 -lSl 12 Chemical & Volume Control Line 1CV45B-2~
1CV-1 -ISI 13 Chemical & Volume Control Line 1CVA3B-2 1CV-1-lSl 14 Chemical & Volume Control Line 1CVA3B-2 1CV-1-ISl 15 ChemIcal & Volume Control Line 1CVA3B-2 1CV-1-ISI 16 Chemical & Volume Control Lines 1CVI4FC-2 and 1CV14GC-1W Exelon Byron Station 2-13 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-1 BYRON STATION UNIT 1ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER CHEMICAL & VOLUME CONTROL SYSTEM (CV) [Continued]
1CV-i-ISI 17 Chemical & Volume Control Lines 1CV99A-8, 1CVO5B-8, and 1CVAIA-6 iCV-1-ISI i8 Chemical & Volume Control Unes 1CVO5B-8, ICVO5CA-6, 1CV9BBA-8, ICV98BB-8, and ICV9SBC-r 1CV-1 -151 19 Chemical & Volume Control Line 1CVO5CB-6 1CV-i-ISI 20 Chemical & Volume Control Lines 1CVO8AB-4, ICV12AA-3, and 1CV42AA-2 ICV-1-ISl 21 Chemical & Volume Control Lines 1CVJ4A-4, 1CVO9A-4, and 1CVOBBA-4 FEEDWATER SYSTEM (FW) 1FW-i-ISI 1 Feedwater Lines 1FWO3DD-16 and 1FW86AD-16 1FW-I-ISI 2 Feedwater Lines 1FWO3DA-16 and 1FW86AA-I6° 1FW-i-ISl 3 Feedwater Lines IFW86AB-16 and 1FWO3DB-16 1FW-1-lSl 4 Feedwater Lines 1FWO3DC-16 and 1FW86AC-16 1FW-1-lSl 5 Feedwater Lines 1FW81AB-6, 1FW81BB-6, and IFW87CB-6 1 FW-1 -ISI 10 Feedwater LInes 1 FW81 AC-6, 1 FW81 BC-6, and 1 FW87CC-6 1FW-1-lSl 11 Feedwater Lines 1FW81AA-6, 1FW8IBA-6, and 1FW87CA-6 1FW-1-lSl 12 Feedwater Lines 1FW81AD-6, 1FW8IBD-6, and 1FW87CD-6 MAIN STEAM SYSTEM (MS) 1MS-i-ISI 1 MaIn Steam Line 1MSO1AD-30 1/4 (Loop 4) 1MS-1-ISI 2 MaIn Steam Unes IMSOISD-30 1/4, 1MSO7AD-28, 1MS13AD-8, 1MSO7BD-28, and 1MS143AD-12 (Loop 4) 1MS-l-ISl 3 MaIn Steam Line 1MSO1AA-30 1/4 (Loop 1) 1MS-1-ISl 4 Main Steam Lines 1MSO1BA-30 1/4, 1MSO7AA-28, 1MS13AA-8, 1MSO7BA-28, and 1MSi43AA-i2 (Loop 1)
IMS-1-ISI 5 MaIn Steam Line 1MS01AB-32 3/4 (Loop 2) 1MS-i-lSl 6 MaIn Steam Lines 1MSOIBB-32 3/4, 1MSO7AB-28, IMS13AB-8, 1MSO7BB-28, and IMS143AB-12 (Loop 2) 1 MS-i -lSl 7 Main Steam Line 1 MSO1 AC-32 3/4 (Loop 3) 1 MS-i -151 8 MaIn Steam Lines 1 MSOI BC-32 3/4, 1 MSO7AC-28, 1 MSI 3AC-r, 1MS143AC-i2, and 1MSO7BC-28 (Loop 3)
REACTOR COOLANT SYSTEM (RC & RY) 1 AC-i -151 1 PrImary Coolant System Loop 1 To Steam Gen. No. 1 RC-01 -BA 1RC-1-lSl 2 PrImary Coolant System Loop 2 To Steam Gen. No. 1RC-01-BB 1 AC-i -ISI 3 PrImary Coolant System Loop 3 To Steam Gen. No. 1 RC-01 -SC 1 RC-1 -ISI 4 Primary Coolant System Loop 4 To Steam Can. No. 1 RC-0I -BD 1RC-i-ISI 5 Reactor Coolant Surge Line 1RY11A-14 1 RC-1 -lSl 6 Reactor Coolant Lines 1 RC21 AA-8 and 1 RC21 BA-8 Exelon Byron Station 2-14 Revision 0
IS! Program Plan Units 1 & 2, Third Interval
.TABLE 2.4-1 BYRON STATION UNIT 1 ISV iSOMETRiC AND COMPONENT DRAWiNGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER REACTOR COOLANT SYSTEM (AC & flY) [Continued]
iRC-1-ISI 7 Reactor Coolant Lines 1RC28A-3, 1CV1ODA-3, 1RC37A-3, iCV1ODB-3, and 1 RC36A-3 1RC-1 -lSl 9 Reactor Coolant Line 1RC21AB-8 1RC-1-ISl ii Reactor Coolant Lines 1RCO4AB-12 and 1RCO5AB-6; Residual Heat Removal Line 1RHO1AB-12 IRC-1 -ISI 12 Reactor Coolant Lines IRC21AC-8 and IRC21BC-8 1RC-1 -ISI 14 Reactor Coolant Lines 1RC24AB-4 and 1RYO1AB-4 1RC-1-lSl 15 Reactor Coolant Lines 1RC21AD-8 and iRC21BD-8 1 AC-i-ISI 16 Reactor Coolant Lines 1 RYO1 B-6 and 1 RYOI C-4 1RC-i-ISl 17 Reactor Coolant Lines 1RC24AA-4 1RYO1AA-4, iRYOIAB-4, and 1RYO1B-6 IRC-1-ISI 19 Reactor Coolant Lines 1RC22AB-11/2and 1RC46AB-3 1 AC-I -ISI 20 Reactor Coolant Lines 1 RC22AD-i1/2 and 1 RC46AD-3 1RC-1-lSl 21 Reactor Coolant Line IRC22AB-iW 1 AC-i -ISI 22 Reactor Coolant LInes 1 RCO5M-6 (Loop 2) and 1RC35AB-6 (Lqop 4) 1 AC-i -ISI 23 Reactor Coolant Lines 1 RC22AA-1 1/2 and 1 RC46AA-3 1RC-1-ISI 24 Reactor Coolant Lines iRC22AC-i1/2 and IRC46AC-3 1RC-1-lSl 27 Reactor Coolant Lines 1RC22AA-1W and 1RC22AC-1W 1RC-1-lSl 29 Reactor Coolant Lines 1RC16AC-2 (Loop 3) and 1RC16AD-2 (Loop 4) 1RC-i-lSl 30 Reactor Coolant Lines IRC13AA-2, 1RC13AB-2,1RC13AC-2, and 1 RC13AD-2 1RC-1-ISI 31 Reactor Coolant Lines 1RC14AB-2 (Loop 2) and 1RC26A-2 (Loop 4)
IRC-1-ISI 32 Reactor Coolant Lines IRYO3AA-6, 1RYO3AB-6. 1RYO3AC-6, 1RYO3BA-6, 1RYO3BB-6, and 1RYO3BC-6 1RC-i-lSl 35 Reactor Coolant Lines 1RYO2A-6, 1RYO6A-3, and 1RYO2B-3 1RC-1-lSl 36 Reactor Coolant Lines 1RC14AA-2 and 1CVA3AA-2 1RC-1 -ISI 37 Reactor Coolant Lines 1RCI4AD-2 and 1CVA7M-2 1RC-1-ISI 4i Reactor Coolant Lines 1RC16AA-2 (Loop i) and 1RC16AB-2 (Loop 2) 1 RC-i-151 42 Reactor Coolant Line 1 RC14AC-2 1 PZR-i -lSl --- Pressurizer No. 1 RY-Ol -S 1 RCP-i -lSl --- Reactor Coolant Pumps 1 RC-01 -PA, 1 RC-01 -PB, iRC-01 -PC, and 1 RC-01 -PD 1 RPV-i-ISl Reactor Pressure Vessel No. 1 RC-01 -R 1SG-i -ISI 5 Replacement Steam Generator No. 1RC-0i-BA 1SG-1 -lSl 6 Replacement Steam Generator No. 1RC-01-BB 1SG-i-ISI 7 Replacement Steam Generator No. iRC-Oi-BC 1SG-i-ISI 8 Replacement Steam Generator No. 1RC-0l-BD Exelon Byron Station 2-15 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-1 BYRON STATION UNIT 1ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER RESIDUAL HEAT REMOVAL SYSTEM (RH) 1RH-1-lSl 1 Residual Heat Removal Line 1RHO1AB-i2 1RH-i-lSl 2 Residual Heat Removal Line IRHOIAA-i2 1RH-1-ISl 3 Residual Heat Removal Lines 1RHO3AA-8 and 1RH12A-8 1RH-1-lSl 4 Residual Heat Removal Lines 1RHO1BA-i2 and 1RHO1CA-16 1 RH-i-lSl 5 Residual Heat Removal Lines 1 RHO2AA-8 and 1 RHO9AA-8 1 RH-I -ISI 6 Residual Heat Removal Lines 1 RHO2AB-8, 1 RHO3AB-8, and 1 RHO9AB-8 1RH-i-lSl 7 Residual Heat Removal Lines iRHO3AB-8, iRH14A-8, and IRHO3AA-8 IRH-i-ISI 8 Residual Heat Removal Lines 1RHO1BB-12, 1RHO1CB-i6, and 1SI82BB-12 1 RH-i-151 9 ResIdual Heat Removal Line I RHO2AB-8 1RHP-i-lSl --- Residual Heat Removal Pumps 1RH-0I-PA-1-iA and 1RH-Oi-PB-2-iB 1 RHX-i -lSI Residual Heat Exchanger Nos. 1 RH-02-AA and 1 RH-02-AB STEAM GENERATOR BLOWDOWN (SD) 1SD-1-ISI 1 Inservlce Inspection Isometric Cant. Bldg. & Safety Valve Rm. Loop I 1SD-i -ISI 2 Inservice Inspection Isometric Cant. Bldg. & Safety Valve Am. - Loop 2 iSO-i-ISI 3 Inservlce Inspection Isometric Cont. Bldg. & Safety Valve Am. Loop 3 I SD-i -ISI 4 Inservice Inspection Isometric Cont. Bldg. & Safety Valve Rm. Loop 4 SAFETY INJECTION SYSTEM (SI) 1SI-i-lSl 1 Safety Injection Lines 1RC29AA-iO and 1SIO9BA-1O 1SI-i-lSl 2 Safety Injection Lines 1SIA4B-r, 1SIO3FA-2, 1RCO4AA-12, and 1RC35AA-6 lSl-i-ISl 3 Safety Injection Line 1SIO5DA-6 lSl-i-ISI 4 Safety Injection Lines 1SIO5BA-8, 1SIO5CA-8, and 1SIO5CD-8 1SI-i -ISI 5 Safety Injection Lines 1RC29AB-10 and 1SIO9BB-iO 1SI-i-ISI 6 Safety Injection Lines 1SIO5DB-6 and iSI18FB-2 1SI-1-lSl 7 Safety Injection Lines 1SIO8FA-3, 1SIOBFB-3, and 1SIO8E-3 lSl-1-lSl 8 Safety Injection Line 1SIO8FA-3 1SI-1-ISI 9 Safety Injection Lines 1RC29AC-10 and iSl09BC-i0~
lSl-1-ISI 10 Safety Injection Lines 1SIO5DC-6 and 1SI18FC-2 lSl-1-ISI Ii Safety Injection Lines 1SIO4O-8 and 1 SIO3DB-2 iSl-1-ISi 12 Safety Injection Lines 1SIO4A-12, 1SIO4B-i2, 1SIO4C-8, and 1SIA4A-8 lSl-1-ISI 13 Safety Injection Lines 1RC29AD-10 and 1510980-10 iSl-i -lSl 14 Safety Injection Line 1SIO5DD-6 1SI-i -ISI 15 Safety Injection Lines 1 SIO8JC-1 W 1 RC45AC-3, and i RC3OAC-1 1/2 Exelon Byron Station 2-16 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-1 BYRON STATION UNIT 1ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER SAFETY INJECTION SYSTEM (SI) (Continued) 1SI-1-ISI 16 Safety Injection Lines 1SIO8JD-1W, 1RC45AD-3, and 1RC3OAD-11/2 lSl-i-ISI 17 Safety Injection Lines 1SIO8JB-i1/2, 1RC45AB-3, and 1RC3OAB-11/2 lSl-I-ISI 18 Safety Injection Lines 1SIO8HB-2, 1SIO8GB-11/2, and ISIO8JB-iW 151-1-151 19 Safety Injection Lines 1SIO8GA-iW, 1SIO8HA-2, and 1SIO8JA-iW 1SI-i-lSI 20 Safety Injection Lines 1SIO8GC-iW, 1SIOSHC-2, 1SIOBJC-1 1/2, iSI08GD-i1/2, 1SIO8HD-2, and 1SIO8JD-i1/2 1SI-1-ISI 21 Safety Injection Line 1SIO3DA-2 151-I-ISI 22 Safety Injection Line 1SIO3FB-2 iSl-1-ISl 23 Safety Injection Lines 1SI18FA-2 and 1SI18FD-2, and Reactor Coolant Line 1 RV76A-2 1 SI-i-ISI 24 Safety Injection Lines I SIO6BA-24 and I SIO6BB-24 1SI-i -lSl 25 Safety Injection Line 1 SIO5AA-8 iSt-1-ISI 26 Safety Injection Lines 1SIO5BB-8, 1SIO5CB-8, and 15105CC-S1 1SI-i -ISI 27 Safety Injection Line 1SIO8JD-11/2 1 SI-I -151 29 Safety Injection Line 1 SIO8JC-1 W iSI-1-ISI 31 Safety Injection Lines 151081JA-11/2,1RC3OAA-11/2,and 1RC45AA-3 151-i -ISl 32 Safety Injection Line 1SIO5AB-8 iSl-1 -151 33 Safety Injection Line i SI34A-8 lSl-1-lSl 34 Safety Injection Lines 1SIO2A-8, 1SIO1B-24, and 1SI82AB-12 1SI-1-ISI 35 Safety Injection Lines 1SI82AA-12, iSlOiA-8, 1SI53AA-14, and 1SIO1B-24 1SI-l -ISI 36 Safety Injection Lines 1SIO2BB-6, 1SIF9A-8, and 1SIO2BA-6 151-i -ISI 37 Safety Injection Lines iSll3A-6, 1SI13BA-6, and 1SI13BB-6 151-i -ISI 38 Safety Injection Lines 1SIO8D-3, 1SIO8B-4, 1SIO8CA-4, and 1SIO8CB-4 Exelon Byron Station 2-17 Revision 0
IS! Program Plan Units 1 & 2, Third !nte,va!
TABLE 2.4-1 BYRON STATION UNIT 1ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER ESSENTIAL. SERVICE WATER SYSTEM (SX) 1SX-1-lSI 1 Essential Service Water Lines 1SXO6EA-i01, iSXO6CA-14, and ISXO6BA-16 1SX-1-ISl 2 Essential Service Water Lines 1SXO6DC-i01, 1SXO6EC-I01, 1SXO8AC-101, and 1SXO8BC-10 1SX-i-lSl 3 Essential Service Water Lines 1SXO6EA-10, 1SXO6FA-101, 1SXO8AA-i01, and i SXO8BA-1 ON 1SX-l-lSl 4 Essential Service Water Lines iSXO6EB-101, iSXO6CB-i4, and 1SXO6BB-16 1SX-i-ISI 5 EssentIal Service Water Lines 1SXO6DD-101, 1SXO6ED-iO, 1SXO8AD-iO, and 1 SXO8BD-1 0 1SX-i-ISI 6 Essential Service Water Lines 1SXO6EB-10, 1SXO6FB-i0, 1SXO8AB-10°,and I SXO8BB-1 0 1SX-1-ISI 7 Essential Service Water Lines 1SXO7CB-10, ISXO7EB-14, and 1SXO7FB-i6 1SX-1-ISI 8 EssentIal Service Water Lines 1SXO7BB-10, 1SXO7CB-iO, 1SXO9CB-10, and 1 SXO9BB-1 O~
1SX-I -151 9 Essential Service Water Lines 1SXO7BD-10, 1SXO7CD-10, 1SXO9BD-l0, and 1 SXO9CD-i 0 1SX-i-ISI 10 Essential Service Water Lines 1SXO7CA-iO, 1SXO7EA-14, and 1SXO7FA-16 iSX-i-ISI 11 EssentIal Service Water Unes 1SXO7BA-10, 1SXO7CA-10, 1SXO9CA-iO, and 1 SXO9BA-i0 iSX-l-ISI 12 EssentIal Service Water Lines 1SXO7CC-1O, 1SXO7BC-i0, 1SXO9CC-iO, and 1 SXO9BC-10 PRIMARY CONTAINMENT PURGE (VO) 1/Q-i*lSI 1 Primary Containment Purge Lines 1VQO3A-8, IVQO4A-8, 1VOO5A-8, 1VOO1A-48, and 1VOO2A-48 Exelon Byron Station 2-18 Revision 0
IS! Program Plan Units 1 & 2, Third Interial TABLE 2.4-2 BYRON STATION UNIT 21S1 ISOMETRIC AND COMPONENT DRAWINGS DRAWING SHEET DRAWING TITLE NUMBER NUMBER AUXIUARY FEEDWATER SYSTEM (AF) 2AF-27-B-T --- Auxiliary Feedwater Lines 2AFO2DB-4, 2AFO2DF-4, and 2AFO2EB-4 2AF-27-C-T Auxiliary Feedwater Lines 2AFO2DC-4, 2AFO2DG-4, and 2AFO2EC-4 2AF-28-A-T --- Auxiliary Feedwater Lines 2AFO2DA-4, 2AFO2DE-4, and 2AFO2EA-4 2AF-28-D-T --- Auxiliary Feedwater Lines 2AFO2DD-4, 2AFO2DH-4, and 2AFO2ED-4 2FW-70-T - Auxiliary Feedwater Lines 2FWO6AB-4 and 2FW87BB-3 2FW-73-T --- Auxiliary Feedwater Lines 2FWO6AA-4 and 2FW87BA-3 2FW-74-T --- Auxiliary Feedwater Lines 2FWO6AD-4 and 2FW87BD-3 2FW-77-T *-- Auxiliary Feedwater Lines 2FWO6AC-4 and 2FW87BC-3 CONTAINMENT SPRAY SYSTEM (CS) 2CS-1 -ISI 1 Containment Spray Line 2CSO2AA-l0 2CS-1 -151 2 Containment Spray Line 2CS1OAA-6 2CS-1 -151 3 ContaInment Spray Lines 2CSOiAA-I6 and 2CS23AA-14 2CS-1-ISI 4 Containment Spray Lines 2CSOiAB-16 and 2CS23AB-14 2CS-1-ISI 5 Containment Spray Line 2CSO2AB-10 2CS-l -151 6 Containment Spray Lines 2CSO2AB-10 and 2CSIOAB-8 2CS-1-ISl 7 ContaInment Spray Line 2CSO2AA-10 2CS-1-ISI 8 Containment Spray Lines 2CSO6AA-6 and 2CSO6AB-6 2VCT-l-ISI Containment Spray Pumps 2CS-Oi -PA-i and 2CS-Oi-PB-2 CHEMICAL & VOLUME CONTROL SYSTEM (CV) 2CV-1-ISI I Chemical & Volume Control Line 2CVB7A-3 2CV-1-ISI 2 Chemical & Volume Control Lines 2RV18A-2 and 2CV45B-2 2CV-l-ISI 3 Chemical & Volume Control Lines 2CV14FB-2 and 2CV14GB-1W 2CV-l-ISI 4 Chemical & Volume Control Lines 2CVA5AB-2 and 2CVA6AB-2 2CV-1-lSl 5 Chemical & Volume Control Line 2CVA3B-2 2CV-1-ISI 6 Chemical & Volume Control Lines 2CV14FA-2, 2CV14FD-2, and 2CVi4GB-11/2 2CV-1-lSI 7 Chemical & Volume Control Line 2CVA3B-2 2CV-l-ISI 8 Chemical & Volume Control Line 2CVA5AA-2 2CV-1-lSl 9 Chemical & Volume Control Lines 2CVA3B-2, 2CVA3AB-2, and 2CVA7AB-2 2CV-1 -ISI 10 Chemical & Volume Control Line 2CVA3AB-2 2CV-i-ISI 11 Chemical & Volume Control Lines 2CVA3B-2 and 2CVA6AA-2 2CV-1-ISI 12 Chemical & Volume Control Line 2CV45B-2 2CV-1-ISI 13 Chemical & Volume Control Line 2CVA3B-2 2CV-i-ISI 14 Chemical & Volume Control Line 2CVA3B-2 2CV-1-lSl 15 Chemical & Volume Control Line 2CVA3B-2 Exelon Byron Station 2-19 Revision 0
ISI Program Plan Units 1 & 2, Third Interval TABLE 2.4-2 BYRON STATION UNIT 2 ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER CH EMICAL & VOLUME CONTROL SYSTEM (CV) [Continued]
2CV-i -IS) 16 Chemical & Volume Control Lines 2CV14FC-2 and 2CV14GC-i1/2 2CV-1-ISI 17 Chemical & Volume Control Lines 2CV99A-8, 2CVO5B-8, and 2CVA1A-6 2CV-i-ISI 18 Chemical & Volume Control Lines 2CVO5B-8, 2CVO5CA-60, 2CV988A-8, 2CV98BB-8, and 2CV98BC-8 2CV-l-lSl 19 Chemical & Volume Control Line 2CVO5CB-6 2CV-i-ISI 20 Chemical & Volume Control Lines 2CVO8AB-4, 2CV12AA-3, and 2CV42AA-2 2CV-i-ISI 21 Chemical & Volume Control Lines 2CVJ4A-4, 2CVO9A-4°,and 2CVO8BA-4 FEEDWATER SYSTEM (FW) 2FW-i -ISI I Feedwater Lines 2FWO3DD-16 and 2FW86AD-16 2FW-l-lSI 2 Feedwater Lines 2FWO3DA-i6 and 2FW86AA-16 2FW-1-151 3 Feedwater Lines 2FW86AB-16 and 2FWO3DB-16 2FW-I-ISI 4 Feedwater Lines 2FWO3DC-16 and 2FW86AC-16 2FW-l-ISI 5 Feedwater Lines 2FW81AB-6, 2FW81BB-6, and 2FW87CB-6 2FW-1-lSl 6 Feedwater Line 2FW87CB-6 2FW-1 -151 7 Feedwater Line 2FW87CC-6 2FW-1-ISI S Feedwater Line 2FWS7CD-6 2FW-1-ISl 9 Feedwater Line 2FW87CA-6 2FW-i-ISI 10 Feedwater Lines 2FW8iAC-6, 2FW81BC-6, and 2FW87CC-6 2FW-1-lSl 11 Feedwater Lines 2FW8IAA-6, 2FW81BA-6°,and 2FW87CA-6 2FW-i-ISI 12 Feedwater Lines 2FW81AD-6, 2FW8iBD-6, and 2FW87CD-6 MAIN STEAM SYSTEM (MS) 2MS-1-lSl 1 Main Steam Line 2MSO1AD-30 1/4 (Loop 4) 2MS-i-ISI 2 Main Steam Lines 2MSO1BD-30 1/4, 2MSO7AD-28, 2M513A0-8, 2MSO7BD-28, and 2MS143AD-12 (Loop 4) 2MS-i-lSl 3 Main Steam Line 2MSO1AA-30 1/4 (Loop 1) 2MS-1 -ISI 4 Main Steam Lines 2MSO1BA-30 i/4, 2MSO7AA-28, 2MS13AA-8, 2MSO7BA-28, and 2MS143AA-12 (Loop 1) 2MS-i-ISl 5 Main Steam Line 2MSOIAB-32 3/40 (Loop 2) 2MS-1-ISI 6 Main Steam Lines 2MSO1BB-32 3/4, 2MSO7AB-28, 2MS13AB-8, and 2MS143A8-12 (Loop 2) 2MS-1 -151 7 MaIn Steam Line 2MSO1AC-32 3/4 (Loop 3) 2MS-1 -IS) 8 Main Steam Lines 2MSO1 BC-32 3/4, 2MSO7AC-28, 2MS1 3AC-8, and 2MS143AC-12 REACTOR COOLANT SYSTEM (RC & RY) 2RC-1-lSl 1 PrImary Coolant System Loop 1 To Steam Gen. No. 2RC-0l-BA 2RC-i -151 2 PrImary Coolant System Loop 2 To Steam Gen. No. 2RC-Oi-BB Exelon Byron Station 2-20 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-2 BYRON STATION UNIT 2ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER REACTOR COOLANT SYSTEM (RC & RY) [Continued]
2RC-i-ISI 3 PrImary Coolant System Loop 3 To Steam Gen. No. 2RC-01-BC 2RC-i -151 4 PrImary Coolant System Loop 4 To Steam Gen. No. 2RC-O1 -BD 2RC-i-ISI 5 Reactor Coolant Surge Line 2RY1 1A-14 2RC-1 -lSl 6 Reactor Coolant Lines 2RC21AA-8 and 2RC21 BA-S 2RC-i-ISI 7 Reactor Coolant Lines 2RC28A-3, 2CV1ODA-3, 2RC37A-3, 2CViODB-3, and 2RC36A-3 2RC-1-ISI 9 Reactor Coolant Lines 2RC2iAB-8 and 2RC21BB-8 2RC-i-lSl ii Reactor Coolant Lines 2RCO4AB-12 and 2RCO5AB-6; Residual Heat Removal Line 2RHOIAB-12 2RC-i -151 12 Reactor Coolant Lines 2RC21 AC-S and 2RC2iBC-8 2RC-i-ISI 14 Reactor Coolant Lines 2RC24AB-4 and 2RYO1AB-4 2RC-i-lSl 15 Reactor Coolant Lines 2RC21AD-8 and 2RC21BD-8 2RC-1-ISI 16 Reactor Coolant Lines 2RYO1B-6 and 2RYO1C-4 2RC-1-ISI 17 Reactor Coolant Lines 2RC24AA-4 2RYO1AA-4, 2RYO1AB-4, and 2RYO1B-6 2RC-i-ISI 19 Reactor Coolant Lines 2RC22A8-1W and 2AC46AB-3 2RC-i-ISI 20 Reactor Coolant Lines 2RC22AD-iW and 2RC46AD-3 2RC-i-lSI 21 Reactor Coolant Line 2RC22AB-1W 2RC-i-ISI 22 Reactor Coolant Lines 2RCO5M-6 (Loop 2) and 2RC35A8-6 (Loop 4) 2RC-i-ISI 23 Reactor Coolant Lines 2RC22AA-iW and 2RC46AA-3 2RC-1-lSI 24 Reactor Coolant Lines 2RC22AC-i1/2 and 2RC46AC-3 2RC-1 -ISI 27 Reactor Coolant Unes 2RC22AA-l 1/2 and 2RC22AC-11/2 2RC-1 -ISI 29 Reactor Coolant Lines 2RCi6AC~2(Loop 3) and 2RC16AD-2 (Loop 4) 2RC-1-ISI 30 Reactor Coolant Lines 2RC13AA-2, 2RC13AB-2, 2RC13AC-2, and 2RC1 3AD-2 2RC-i -151 31 Reactor Coolant Lines 2RC14AB-2 (Loop 2) and 2RC26A-2 (Loop 4) 2RC-l -1St 32 Reactor Coolant Lines 2RVO3AA-6~,2RYO3AB-6, 2RYO3AC-6, 2RYO3BA-6, 2RVO3BB-6, and 2RYO3BC-6 2RC-i -ISI 35 Reactor Coolant Lines 2RYO2A-6, 2RYO6A-3, and 2RYO2B-3 2RC-1-lSl 36 Reactor Coolant Lines 2RC14AA-2 and 2CVA3AA-211 2RC-l-lSl 37 Reactor Coolant Lines 2RC14AD-2 and 2CVA7AA-2 2RC-1-ISI 41 Reactor Coolant Lines 2RC16AA-2 (Loop i) and 2RC16AB-2 (Loop 2) 2RC-1-ISI 42 Reactor Coolant Line 2RC14AC-2 2PZR-1 -ISI --- Pressurizer No. 2RY-Ol-S 2RCP-1 -151 Reactor Coolant Pumps 2RC-0l-PA, 2RC-O1-PB, 2RC-O1-PC, and 2RC-0l-PD 2RPV-i-lSl --- Reactor Pressure Vessel No. 2RC-O1-R EXe1On Byron Station 2-21 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-2 BYRON STATION UNIT 2 ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER REACTOR COOLANT SYSTEM (RC & RY) [ContInued]
2SG-i -151 1 Steam Generator No. 2RC-01-BA 2SG-1-ISl 2 Steam Generator No. 2RC-Oi-BB 2SG-1 -151 3 Steam Generator No. 2RC-0i-BC 2SG-i~lSl 4 Steam Generator No. 2RC-01-BD RESIDUAL HEAT REMOVAL SYSTEM (RH) 2RH-l -ISI I Residual Heat Removal Line 2RHO1AB-i2 2RH-i -IS) 2 Residual Heat Removal Line 2RHO1AA-12° 2RH-1-ISI 3 Residual Heat Removal Line 2RHO3AA-8 2RH-i-ISI 4 Residual Heat Removal Line 2RHO1 CA-i 6 2RH-1 -151 5 Residual Heat Removal Lines 2RHO2AA-8 and 2RHO9AA-8 2RH-1 -ISI 6 Residual Heat Removal Line 2RHO3AB-8 2RH-1-lSl 7 Residual Heat Removal Lines 2RHO3AB-8, 2RH14A-8, and 2RHO3AA-8 2RH-1-lSl 8 Residual Heat Removal Line 2RHOICB-i6 2RH-1-lSl 9 Residual Heat Removal Line 2RHO2AB-8 2RH-1 -151 10 Residual Heat Removal Lines 2RHO3AA-8 and 2RH12A-8 2RH-i-lSl Ii Residual Heat Removal Line 2RHOIBC-i2 and 2SI82BB-i2 2RH-1 -ISI 12 Residual Heat Removal Line 2RHO1BA-12 2RH-1 -151 13 Residual Heat Removal Line 2RHO2AB-8 and 2RHO9AB-8 2RHP-i-ISI --- Residual Heat Removal Pumps 2RHOiPA-1-1A and 2RHO1 PB-2-iB 2RHX-1-IS) --- Residual Heat Exchanger Nos. 2RHO2AA and 2RHO2AB SAFETY INJECTION SYSTEM (SI) 251-1-ISI 1 Safety Injection Lines 2RC29AA-10 and 2SIO9BA-10 25)-i -lSI 2 Safety Injection Lines 2SIA4B-8, 2SIO3FA-2, 2RCO4AA-12°,and 2RC35AA-6 25)-I-151 3 Safety Injection Line 2SIO5DA-60 2Sf-i -lSI 4 Safety Injection Lines 2SIO5BA-8, 2SIO5CA-8, and 2SIO5CD-80 2Sl-1 -ISI 5 Safety Injection Lines 2RC29AB-iO and 2SIO9BB-l0 251-1-lSl 6 Safety Injection Lines 25)0508-6 and 2SI18FB-2° 251-i-IS) 7 Safety Injection Lines 2SIO8FA-3, 2SIO8FB-3, and 2SIO8E-3 251-1-ISI 8 Safety Injection Line 2SIO8FA-3° 251-1 -ISI 9 Safety Injection Lines 2RC29AC-100 and 2SIO9BC-10 2Sl-1-ISI 10 Safety Injection Lines 2SIO5DC-6 and 25118FC-2 2SI-i -ISI 11 Safety Injection Lines 2SIO4D-8 and 2SIO3DB-2 2S1-1-ISI 12 Safety Injection Lines 2S104A-i2, 2S104B-12, 2SIO4C-811, and 2SIA4A-8 2Sl-i -151 13 Safety Injection Lines 2RC29AD-l0 and 2510980-10 Exelon Byron Station 2-22 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-2 BYRON STATION UNIT 2 ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER SAFETY INJECTION SYSTEM (SI) [ContInued]
251-1 -151 14 Safety Injection Line 2SIO5DD-60 2SI-1-ISl 15 Safety Injection Lines 2SIO8JC-11/2 2RC45AC-3, and 2RC3OAC-1W 251-1-ISI 16 Safety Injection Lines 2SIO8JD-i1/2, 2RC45AD-r, and 2RC3OAD-1W 2Sl-1-lSl 17 Safety Injection Lines 2S108J8-11/2,2RC45AB-30, and 2AC3OAB-11/2 2Sl-i -ISI 18 Safety Injection Lines 2SIO8HB-2, 25108GB-lW, and 2SIO8JB-1W 251-1-151 19 Safety Injection Lines 2S)O8GA-11/2, 2SIO8HA-2, and 2SIO8JA-11/2 2SI-i-ISI 20 Safety Injection Lines 2S1083C-11/2, 2SIOSHC-2, 2SIO8JC-11/2, 2SIO8GD-1W, 2SIO8HD-2, and 2SIO8JD-1W 2Sl-l -ISI 21 Safety Injection Line 2SIO3DA-2 2S1-1 -151 22 Safety Injection Line 2SIO3FB-2 251-1 -151 23 Safety Injection Lines 2SIi8FA-2 and 2SI1SFD-2, and Reactor Coolant Line 2RV76A-2 2S1-i -151 24 Safety Injection Lines 2SIO6BA-24 and 2SIO6BB-24 2Sl-i -151 25 Safety Injection Line 2SIO5AA-8 28I-1-lS1 26 Safety Injection Lines 25I05B8-8, 2SIO5CB-8, and 2SIO5CC-r 251-1-ISI 27 Safety Injection Line 2SIO8JD-1W 251-1-151 29 Safety Injection Line 2SIO8JC-iW 2SI-1 -151 31 Safety Injection Lines 2SIO8JA-11/2,2RCOAA-11/2, and 2RC45AA-3 2SI-1-ISI 32 Safety Injection Line 2SIO5AB-8 2Sl-1-ISl 33 Safety Injection Line 2SI34A-8 251-1-ISI 34 Safety Injection Line 2SIO5CB-8 Exelon Byron Station 2-23 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-2 BYRON STATION UNIT 2 ISI ISOMETRIC AND COMPONENT DRAWINGS (Continued)
DRAWING SHEET DRAWING TITLE NUMBER NUMBER ESSENTIAL SERVICE WATER SYSTEM 2SX-1-)Sl 1 Essential Service Water Lines 2SXO6BA-16, 2SXO6CA-i4 11, 2SXO6DC-10, 2SXO6EA-I0, 2SXO8AA-l0, and 2SXO8AC-10 0 2SX-1-151 2 EssentIal Service Water Lines 2SXO6DC-i00, 2SXO6EC-10, 2SXO8AC-10, and 2SXOSBC-iO 2SX-l -IS) 3 Essential Service Water Lines 2SXO6EA-l0, 2SXO6FA-10, 2SXO8AA-iD, and 2SXO8BA-l0 2SX-1-lSl 4 EssentIal Service Water Lines 2SXO6BB-16, 2SXO6CB-14, 2SXO6EB-l0, 2SXO8AB-10, and 2SXO8AD-10 2SX-1-)SI 5 EssentIal Service Water Lines 2SXO6DD-10, 2SXO6ED-10, 2SXO8AD-10, and 2SXO8BD-10 2SX-1-ISI 6 EssentIal Service Water Lines 2SXO6EB-iO, 2SXO6FB-10, 2SXO8AB-10, and 2SXO8BB-l0 2SX-i-ISl 7 Essential Service Water Lines 2SXO7CB-10, 2SXO7EB-i4, 2SXO7FB-16, 2SXO9CB-10, and 2SXO9CD-l0 2SX-l -151 8 Essential Service Water Lines 2SXO7BB-l0, 2SXO7CB-10, 2SXO9BB-10°,and 2SXO9CB-i0 2SX-i-lSI 9 EssentIal Service Water Lines 2SXO7BD-i00, 2SXO7CD-1 011, 2SXO9BD-10, and 2SXO9CD-i0 2SX-1-%S) 10 EssentIal Service Water Lines 2SXO7CA-1O, 2SXO7EA-14, and 2SXO7FA-16 2SX-l-ISI ii Essential Service Water Lines 2SXO7BA-10, 2SXO7CA-i0, 2SXO9BA-l0, and 2SXO9CA-iO 2SX-1-I5l 12 Essential Service Water Lines 2SXO7BC-i0, 2SXO7CC-10, 2SXO9BC-10, and 2SXO9CC-iO PRIMARY CONTAINMENT PURGE (VO) 2VQ-1-lSl 1 Primary Containment Purge Lines 2VQO3A-8, 2V004A-8, 2V005A-8, 2VQO1A-48, and 2VQO2A-48 Exelon Byron Station
- 2-24 - Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-3 BYRON STATION UNIT 1 CONTAINMENT ISI DRAWINGS cisi DWG. NO. CISI DRAWING TITLE IWE COMPONENT ROLLOUT INSIDE CONTAINMENT LINER VIEW LOOKING OUT i-CISI-i000 SH.1 0°T0180° AZIMUTH 1-CISI-1 000 SH.2 IWE0COMPONENT ROLLOUT INSIDE CONTAINMENT LINER VIEW LOOKING OUT j5~ TO 360°AZIMUTH IWE COMPONENT DRAWING INSIDE CONTAINMENT MAT PLAN VIEW EL. 377 1-CISI-1000 SH. 3 ON 1-CISI-1000 SH. 4 IWE COMPONENT DRAWING CONTAINMENT DOME LINER VIEW LOOKING UP IWE COMPONENT DETAIL RECIRC. SUMP A & B GUARD PIPE & BELLOWS 1-CISI-1000 SH. 5 ASSEMBLY IWE COMPONENT DETAIL VALVE CONTAINMENT ASSEMBLY 1 RHOI SA &
l-CISI-1000 SH. 6A 1RHO1SB IWE COMPONENT DETAIL VALVE CONTAINMENTASSEMBLY 1 RHO1 SA &
i-CISI-i000 SH 6B 1 RHO1SB IWE COMPONENT DETAIL FUEL TRANSFER TUBE PENENTRATION (P-98) 1-CISI-i000 SH. 7A REACTOR POOL AREA 1-CISI-i000 5)1.78 IWE COMPONENT SECTIONS FUEL TRANSFER TUBE PENENTRATION (P-98)
REACTOR POOL AREA 1-CISI-1000 SH. 9A IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK 1-C)SI-1000 SH. 98 IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK 1-CISI-1 000 SH. 9C IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK i-CISI-1000 SH. 9D IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK i-CISI-i000 SH. iOA (WE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK i-CISI-1 000 SH. lOB IWE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK i-CISI-1000 SH. 1OC IWE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK 1-CISI-1 000 SH. 1OD IWE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK Exelon Byron Station 2-25 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-3 BYRON STATION UNIT 1 CONTAINMENT ISI DRAWINGS (Continued)
CISI OWO. NO. CISI DRAWING TITLE 1-CISI-i000 SH. 11 TYPICAL (WE COMPONENT SURFACE AND ATTACHMENT DETAILS TYPICAL PENETRATION DETAILS INSIDE CONTAINMENT CONFIGURATION No.s i-CISI-l 000 SH. 12 1,2&3 1-CISI-1000 SH. 13 TYPICAL PENETRATION DETAILS INSIDE CONTAINMENT CONFIGURATION No.s 4&5 1 -CISI-1 001, SH. Al ISI IDENTIFIER FORMAT AND EXPLANATION i-CISI-1001 SH. 1A IWE COMPONENT INFORMATION TABLE PIPING PENETRATIONS THRU iF l-CISI-i001 SH. 13 (WE COMPONENT INFORMATION TABLE ELECTRICAL PENETRATIONS THRU 1J 1 -CISI-lOOl SH. 1K IWE COMPONENT INFORMATION TABLE INSTRUMENT PENETRATIONS i-CISI-iOOl SH. 1L IWE COMPONENT INFORMATION TABLE MISCELLANEOUS COMPONENTS THRU 1R 1 -CISI-1 001 SH 2A ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION No. 1 i-CISI-iOOl SH 28 ELECTRICAL PENETRATION SECTION OUTSIDE CONTAINMENT CONFIGURATION No. i i-CISI-i0O1 SH 3A ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION No.2 ELECTRICAL PENETRATION SECTIONS OUTSIDE CONTAINMENT i-CISI-iOOl SH 3B CONFIGURATION No.2 1-CISI-lOOi SH 4A ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION No.3 ELECTRICAL PENETRATION SECTIONS OUTSIDE CONTAINMENT i-CISI-lOOi SH 48 CONFIGURATION No. 3 l-CISI-iOOl SH 5A ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION No.4 ELECTRICAL PENETRATION SECTION OUTSIDE CONTAINMENT i-ClSl-lOOi SH 5B CONFIGURATION No.4 ELECTRICAL PENETRATION DETAILS PERSONNEL AIR LOCKS i-CISI-iOOi SH 6A ~ CONFIGURATION No.5 i-CISI-iOOi SH 6B ELECTRICAL PENETRATION SECTION OUTSIDE CONTAINMENT CONFIGURAT1ON No.5 INSTRUMENT PENETRATION DETAILS OUTSIDE CONTAINMENT 1-CIS)-1 001 SH. 7 CONFIGURATION Nos 1,2 & 3 Exelon Byron Station 2-26 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-3 BYRON STATION UNIT 1 CONTAINMENT ISI DRAWINGS (Continued)
CISI OWO. NO. . CISI DRAWING TITLE PIPING PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION Nos 1~CISI -1001 SH .8 1&2 PIPING PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION Nos 1 CISI 1001 SH 9*
3&4 1-CISI-lOOl SH. 10 PIPING PENETRATION DETAIL OUTSIDE CONTAINMENT CONFIGURATION No.5 1-CISI-100l SH. 11 PIPING PENETRATION DETAIL OUTSIDE CONTAINMENT CONFIGURATION No.6 1-CISI-lOOl SH. 12 PIPING PENETRATION DETAIL OUTSIDE CONTAINMENT CONFIGURATION No.7 l-CISI-2000 SH.1 IWL/1WE COMPONENT ROLLOUT OUTSIDE CONTAINMENT0°TO 180°AZIMUTH IWLJIWE COMPONENT ROLLOUT OUTSIDE CONTAINMENT 180°TO 360° 1 CISI 2000 SH 2
- - AZIMUTH 1-CISI-2000 SH. 3 IWL COMPONENT DRAWING CONTAINMENT DOME EXTERIOR PLAN VIEW 1-CISI-2000 SH. 4 IWL COMPONENT DRAWING TENDON GALLERY PLAN VIEW 1 -CISI-2000 SH. 5 IWL COMPONENT DETAIL TENDON ANCHORAGE ASSEMBLY 1-CISI-2000 SH. 6 IWL COMPONENT DRAWING DOME TENDON LAYOUT Exelon Byron Station 2-27 Revision 0
IS! Program Plan Units I & 2, Third Interval TABLE 2.4-4 BYRON STATION UNIT 2 CONTAINMENT ISI DRAWINGS CISI DWG. NO. CISI DRAWING T~ItE IWE COMPONENT ROLLOUT INSIDE CONTAINMENT LINER VIEW LOOKING OUT 2-CISI-1000 SH.1 0010 180°AZIMUTh IWE COMPONENT ROLLOUT INSIDE CONTAINMENT LINER VIEW LOOKING OUT 2-CISI-1000 SH.2 180°TO 3600 AZIMUTH IWE COMPONENT DRAWING INSIDE CONTAINMENT MAT PLAN VIEW EL 377 2-CISI-1000 SH. 3 - -
0 2-CISI-1000 SH. 4 IWE COMPONENT DRAWING CONTAINMENT DOME LINER VIEW LOOKING UP IWE COMPONENT DETAIL RECIRC. SUMP A & B GUARD PIPE & BELLOWS 2-CISI-1 000 SH. 5 ASSEMBLY 2-CISI-1000 SH. 6A (WE COMPONENT DETAIL VALVE CONTAINMENT ASSEMBLY 2RHO1 SA &
2RHOISB IWE COMPONENT DETAIL VALVE CONTAINMENT ASSEMBLY 2RHO1SA &
2-CISI-1 000 SH 6B. 2RHO1 SB 2-CISI-1000 SH. 7A IWE COMPONENT DETAIL FUEL TRANSFER TUBE PENENTRATION (P-98)
REACTOR POOL AREA (WE COMPONENT SECTIONS FUEL TRANSFER TUBE PENENTRATION (P-98) 2-CISI-1000 SH. 7B REACTOR POOL AREA 2-CISI-1000 SH. 9A IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK 2-CISI-1 000 SH.9B IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK 2-CISI-1 000 SH. 9C IWE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK 2-CISI-1 000 SH. 9D (WE COMPONENT DETAIL EQUIPMENT HATCH/PERSONNEL AIR LOCK 2-CISI-1000 SH. 1OA IWE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK 2-CISI-i000 SH. lOB (WE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK 2-CISI-1 0005)1. 100 IWE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK 2-CISI-1 000 SH. 100 IWE COMPONENT DETAIL EMERGENCY PERSONNEL AIR LOCK 2-CISI-1000 SH. 11 TYPICAL (WE COMPONENT SURFACE AND ATTACHMENT DETAILS TYPICAL PENETRATION DETAILS INSIDE CONTAINMENTCONFIGURATION No.s 2-0151-i 000 SH. 12 l,2&3 TYPICAL PENETRATION DETAILS INSIDE CONTAINMENT CONFIGURATION No.s 2-C1SI-l000 SH. 13 4&5 2-CISI-1 001, SH. Al ISI IDENTIFIER FORMAT AND EXPLANATION 2-CISI-lOOl SH. 1A IWE COMPONENT INFORMATION TABLE PIPING PENETRATIONS THRU iF 2-CISI-lOOl SH. 1G (WE COMPONENT INFORMATION TABLE ELECTRICAL PENETRATIONS THRU IP Exelon Byron Station 2-28 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.4-4 BYRON STATION UNIT 2 CONTAINMENT ISI DRAWINGS (Continued)
CISi DWG. NO. CISI DRAWING TITLE 2-CISI-lOOl SH. 10 IWE COMPONENT INFORMATION TABLE INSTRUMENT PENETRATIONS 2-CISI-lOOl SH. 1R (WE COMPONENT INFORMATION TABLE MISCELLANEOUS COMPONENTS THRU 1W ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT 2-CISI-lOOl SH 2A CONFIGURATION No. 1 2-CISI-lOOl SH 2B ELECT. PENETRATION SECTIONS OUTSIDE CONTAINMENT CONFIGURATION No. I 2-CISI-lOOl SH 3A ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION No.2 2-CISI-lOOl SH 3B ELECT. PENETRATION SECTIONS OUTSIDE CONTAINMENT CONFIGURATION No.2 2-CISI-lOOl SH 4 ELECTRICAL PENETRATION DETAILS PERSONNEL AIR LOCKS CONFIGURATION No.3 ELECTRICAL PENETRATION DETAILS OUTSIDE CONTAINMENT 2-CISI-lOOl SH 5A CONFIGURATION No.4 2-CISI-lOOl SH 5B ELECT. PENETRATION SECTIONS OUTSIDE CONTAINMENT CONFIGURATION No.4 INSTRUMENT PENETRATION DETAILS OUTSIDE CONTAINMENT 2-CISI-lOOl SH. 6 CONFIGURATION Nos 1,2 & 3 PIPING PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION 2-CISI-1001 SH.7 Nos 1 & 2 2-CISI-1001 SH.8 PIPING PENETRATION DETAILS OUTSIDE CONTAINMENT CONFIGURATION Nos 3 & 4 PIPING PENETRATION DETAIL OUTSIDE CONTAINMENT CONFIGURATION No.
2-CISI-1001 SF19 5 PIPING PENETRATION DETAIL OUTSIDE CONTAINMENT CONFIGURATION No.
2-CISI-lOOl SH. 10 6 PIPING PENETRATION DETAIL OUTSIDE CONTAINMENT CONFIGURATION No.
2-CISI-lOOl SH. 11 7 2-CISI-2000 SH. 1 IWL/IWE COMPONENT ROLLOUT OUTSIDE CONTAINMENT 0°TO 180° AZIMUTH IWL/IWE COMPONENT ROLLOUT OUTSIDE CONTAINMENT 180°TO 360° 2-CISI-2000
~ SH.2 AZIMUTH 2-CISI-2000 SH. 3 IWL COMPONENT DRAWING CONTAINMENT DOME EXTERIOR PLAN VIEW 2-0151-2000 SH.4 IWL COMPONENT DRAWING TENDON GALLERY PLAN VIEW 2-CISI-2000 SH. 5 IWL COMPONENT DETAIL TENDON ANCHORAGE ASSEMBLY 2-CISI-2000 SH. 6 IWL COMPONENT DRAWING DOME TENDON LAYOUT Exelon Byron Station 2-29 - Revision 0
IS! Program Plan Units 1 & 2, Third Interval 2.5 TECHNICAL APPROACH AND PosmoNs When the requirements of ASME Section XI are not easdy Interpreted, Byron Station has reviewed general licensing/regulatory requirements and industry practice to determine a practical method of implementing the Code requirements. The technical approach and position (TA&P) documents contained In this section have been provided to clarify Byron Stations implementation of ASME Section XI requirements.
An index which summarizes each technical approach and position is included in Table 2.5-1. This section is reserved for Site Specific issues. Corporate Policy statements will be tracked and maintained by the Corporate Staff.
Exelon Byron Station 2-30 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TABLE 2.5-1 TECHNICAL APPROACH AND POS~ONSINDEX POSITiON REVISIONI STATUS DESCRIPTION OF TECHNICAL APPROACH NUMBER DATE I3T-O1 ActIve (1St) RISI examination volumes and methods.
I3T-02 9/1V05 Active ((SI) Determination of additional examinations per Code Case N-578-1 Paragraph 2430.
I3T-03 0 (SPT) Hydrostatic and operational pressure testing of open Active ended piping.
9/12/05 I3T-04 0 Activ (SPT) Valve seats as pressurization boundaries.
9/12/05 Note 1: TechnIcal Approach and Position Status Options: Active Current (SI Program Technical Approach Is being utilized at Byron Station; Deleted Technical Approach is no longer being utilized at Byron Station Exelon Byron Station 2-31 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: 13T-O1 REVISION 0 (Page 1 of 3)
COMPONENT IDENTIFICATION CodeClass: land2
Reference:
Byron Station Request for Relief I3R-02, Afternative to the ASME Section XI Requirements for Class 1 and Class 2 Piping Welds Executive Summary, Risk Informed Inservice Inspection Program Plan Byron Nuclear Power Station Units 1 and 2 ASME Code Case N-578-i: Risk-Informed Requirements for Class 1,2, or 3 Piping, Method B Section XI, DMsion 1 Electric Power Research Institute (EPRI) Topical Report (TA) 112657 Rev. B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure ExamInation Category: Previously B-F, B-J, C-F-i, and C-F-2 now incorporated into R-A
==
Description:==
RISI examination volumes and methods CODE REQUIREMENT The requirements for examination methods and areas/volumes are assembled from several sources other than the stations base edition of the ASME Code.
Relief Request I3R-02:
For this application, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1.
Executive Summary, SectIon 3.5 Inspection Location Selection and NDE Selectiorr~
Code Case N-578-1 Table 1, ExaminatIon Category A-A, Risk-Informed Piping Examinatlonsa will also be used in conjunction with Table 4-i of EPRI TA-i 12657 to categorize the parts examined under the RISI Program. Code Case N-578-i Table 1 provides examination requirements, examination method, acceptance standards, examination extent and frequency for piping structural elements not subject to a damage mechanism.
Code Case N-578-i, Section 1-5.2 Examination Volumes and Methods Examination programs developed In accordance with this Case shall use NDE techniques suitable for specific degradation mechanisms and examination locations. The examination volumes and methods that are appropriate for each degradation mechanism are provided in Table 1 of this Case. The methods and procedures used for the examinations shall be qualified to reliably detect and size the relevant degradation mechanisms identified for each elements.
TA-i 12657, Section 4 Mechanism Specific Examination Volumes and Methods:
Application of RISI uses NDE techniques that are designed to be effective for specific degradation mechanisms and examination locations. This inspection for cause approach involves identification of specific damage mechanisms that are likely to be operative, the location where they may be operative, and the appropriate examination methods and volumes specific to address the damage mechanism.
Exelon Byron Station 2-32 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: I3T-01 REVISION 0 (Page 2 of 3)
POS~ON Table 131-01-1: Degradation Mechanisms with Examination Methods and Volumes DEGRADATION MECHAN$SM (DM) N.678-1 TABLE I TR-1 12657 TABLE 4-1 COMMENTS OR COMPONENT TYPE EXAM METhOD EXAM VOLUME OR AREA Thermal Fatigue Volumetric Figure 4-1 thru 4-~ volume High Cycle Mechanical Fatigue Visual, VT-2 Not Applicable, Note1 None currently Identified at station.
Erosion Cavitation Volumetric FIgure 4-16 thru 4-22 In accordance w/ FAC Program Crevice Corrosion Cracking Volumetric FIgure 4-6 and 4-7 None currently Identified at station.
Primary Water Stress See Note2 Corrosion Cracking See Note2 See Note2
. Effected components not subject lntergranular or Transgranular Volumetric ~ure 4-10 thru 4-14 to an additional DM. Only SCC Stress Corrosion Cracking ~ type examinations required for components.
Microblologically Corrosion Volumetric Figure 4-15 See Note3 Flow Accelerated Corrosion Volumetric FIgure 4-16 thru 4-22 In accordance WI FAC Program External Chloride Stress Surface Affected Surface None currently kientifled at station.
Figure 4-1 IWB-2500-8(c) Includes e~ ~~ xam volume No Damage Mechanism Volumetric IWB-2500-9, 10, Ii ~ ,.~ . r r~ae 458 IWC-2500-7(a) or 1 1 ~ png.
~
See Notes45~8 Socket Welds (All DM) Visual, VT-2 Not Applicable, Note1 See Note1 Note 1: VT-2 examinations are performed during each refueling cycle. VT-2 examination area is not identified in Code Case N-578-1 or TA-i 12657 (TR-RISI). Socket welds are not specifically addressed In TR-RISI with the exception of FAC exams. N-578-i Table 1 Note 12 specifies that socket welds require only a VT-2 exam.
Note 2: N-578-1 requires a VT-2 examination for this DM while TA-i12657 requires a volumetric or visual method. Recent industry events necessitated the change to volumetric examination techniques (where qualified examination techniques are available) for detection prior to through-wall leakage. TR-RlSl Identifies Figures 4-8 and 4-9 for the required examination volumes based on component configuration. Figure 4-8 would not be applicable to components incorporated into RISI. At Byron Station, all components subject to PWSCC (12 in each unit) are classified as High-Risk Group, Risk Category 2. Joint configuration may result in obtained examination coverage of less than the percentage required by adopted Code Case N-460. Due to the significance of these components, credit for these examinations will be taken and a Request for Relief will be submitted as described in TR-RISI Section 6.4.
Exelon Byron Station 2-33 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: 131-01 REVISION 0 (Page 3 of 3)
Note 3: DM currently limited to SX system components. These components have been removed from the RISI inspection population and default by Incorporation into the Service Water Inspection program.
Note 4: ExamInation of components without an Identified DM is not addressed in TR-RISI. Code Case N-578-1 requires that these components receive the same examination as components subject to thermal fatigue. For no DM components, the examination requirements of N-578-1 will be used.
Note 5: For piping butt welds with no DM, the length for the examination volume shall be increased to include 1/2 beyond each side of the detectable base metal thickness transition or counterbore. For components without a detectable base metal thickness transition or counterbore, the basic examination volume specified in TR-RISI Figure 4-1 shall be used.
The figure applicable for use shall be based on the detectable presence of a counterbore regardless of the pipe size.
Note 6: For branch connection piping without a DM, the examination volume shall be determined using the figures specified in N-578-1 (IWB-2500-9, 10, 11 of the 1989 Edition).
Exelon Byron Station 2-34 Revision 0
ISI Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: 131-02 REVISION 0 (Page 1 of 3)
COMPONENT IDENTIFICATION Code Class: 1,2, and 3
Reference:
Byron Station Request for Relief l3R-02 ASME Code Case N-578-1: Risk-Informed Requirements for Class 1,2, or 3 Piping, Method B Section XI, DMsion I Examination Category: Previously B-F, B-J, C-F-i, and C-F-2 now incorporated into R-A
==
Description:==
Determination of Additional Examinations per Code Case N-578-1 Paragraph 2430 CODE REQUIREMENT
-2430 AddItional ExaminatIons (a) Examinations performed in accordance with -2500 that reveal flaws or relevantconditions exceeding the acceptance standards of -3000 shall be extended to include additional examinations. The additional examinations shall Include piping structural elements described in Table 1 with the same oostulated failure mode and the same or higher failure potential.
(1) The number of additional elements shall be the number of piping structural elements with the same postulated failure mode originally scheduled for that fuel cycle.
(2) The scope of the additional examinations may be limited to those Hiah-Safetv-Sianiflcant (HSS~Diping structural elements within systems, whose materials and service conditions are determined by an evaluation to have the same postulated failure mode as the piping structural element that contained the original flaw or relevant condition.
(b) If the additional examinations required by -2430(a) reveal flaws or relevant conditions exceeding the acceptance standards of -3000, the examination shall be further extended to include additional examinations.
(1) These examinations shall Include all remaining piping elements within Table 1 whose postulated failure modes are the same as the piping structural elements originally examined in
-2430(a)
(2) An evaluation shall be performed to establish when those examInations are to be conducted.
The evaluation must consider failure mode and potential.
(C) For the inspection period following the period in which the examinations of -2430(a) or (b) were completed, the examinations shall be performed as originally scheduled in accordance with -2400.
Underlined portions of the requirements of the code case Identify issues addressed In this technical approach.
Exelon Byron Station 2-35 Revision 0
ISI Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITiON NUMBER: 13T-02 REVISION 0 (Page 2 of 3)
POSITION Table I3T-02-1: System DIstribution in N-578-1 Risk Matrix Categories containing Byron Station Unit 1 and 2 Welds N-578-1 CONSEQUENCE CATEGORY TABLE I-S LOW MEDIUM HIGH HIGH CATEGORY 5(H) CATEGORY 3 ~~~S)
MEDIUM CATEGORY 6(M) CATEGORY 2
,~cvsi AFRCRY.(SX)
~O : CATEGORY4.~1.
LOW .A,j Cs CV. FW Ms (RC, RH?_RY_SD_SI RISK GROUPS MEDIUM CAT 4 & 5 HIGH CAT 1,2 & 3 Note 1: AF/FW/MS welds exempted from RISI due to single DM (FAC) by incorporation Into station FAC program.
Note 2: 1 RH and 1 AC system welds limited to Unit 1.
Note 3: SX welds removed from RISI and default into Service Water Inspection program.
Table l3T-02-2: Distribution of Degradation Mechanisms, HSS Piping Systems, and Risk Categories APPUCABLE CONSEQUENCE CATEGORIES UNIT 1 LOW MEDIUM HIGH RC RH SI CV w ~ ~ ~ RC RH SI AF cs cv FW MslRc RH flY SD SI
. .~ ~: ~ =
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~ ~j__~j ~ ~ ~ ~ ~ ~ 629
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Mm.is - - . *. * . ~ ~ ~8 6 14
~j
- u.O R1i6
.L
-~-
2 ~. ~ ~ ~2 ~
4 LRL2O * - - * * * ~87..: 172. 192 ~. 18 40& 200 M 4 267. 1592 TOTALS 0 0 0 153 3 0 254 107 172 192 254 178 584 200 125 4 261 APPLICABLE CONSEQUENCE CATEGORIES UNIT 2 LOW MEDIUM HIGH RC RH SI CV RC RH SI AF cs cv FW MS I RC RH RY SI
~
- = = =
~
~
I
- 242 1 * ~ 242 H ~- *.~~. ~- p- ~~ ~ -*~~* -~ .. ...,_ . ..,___..
~J R1.18 . . *.; ~ ~ * ~ 242 ~ ~
- 242 Ui < . ~
~
D flu 150 1 asa 20
- 180 ,
30 ,
614 d~ M -mis ~ 8 6 14
< . .~.- ~ .*~ *~ ~ ~.. *. ..
2 nile 2 ~ 2 L R1.20 88 164 200 169 377 215 84 243 1540
=
101*1.50 0 =01503 0253108164200484169545215120243 =
Note: Identifies entire population of DM. Individual welds may be counted more than once due to multiple DM present.
Exelon Byron Station 2-36 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: 13T-02 REVISION 0 (Page 3 of3)
Paraaraoh -2430(a): Additional Examination Selection Criteria by Failure Potential of Reiected Comoonent CATEGORY 1: Selections remain within Category 1.
CATEGORY 5: Selections may be taken from Categories 5(M) and 2 CATEGORY 2: Selections may be taken from CategorIes 5(M) and 2.
CATEGORY 4: Selections may be taken from Categories 1, 4, 5(M), and 2.
Paragrach -2430(a)(1): Additional Examination Selection Criteria by Failure Mode of Relected Cornoonent Criteria of additional selection is based upon the item number classification shown in N-578-1 Table 1.
Additional selections are not restricted by the Risk Category of the rejected component.
Paraaraoh -2430(a)(2): Limitation of the Scooe of Additional Examinations Populations subject to the additional examinations may be limited to those components with the same material and service condition as the rejected component. The required numberof additional examinations is not reduced by this limitation. High-Safety-SignIficant piping structural elements are Identified as those components included in Risk Categories 1,2,3,4, and 5.
Paraaraoh -2430(b)(1): Second Exoanslon Scooe of Additional Examinations The second population subject is lImited to the failure mode (degradation mechanism) of the original component. AD HSS components of the same item number, regardless of Risk Category, are subject to this expansion.
Paraçiraoh -2430(b)(2); Scheduling of the Second Exoansion Scooe The second expansion selections need not be entirely examined in the current refueling cycle. The sequence and schedule of the additional examinations will be determined based on the failed component features.
Paragrach -2430(c): Return to Original Schedule of Comoonent Selection and Examination In the initial expansion population, credit may be taken for examinations performed on components scheduled later in the same Inspection Period (i.e., the initial expansion may include components scheduled for the next refueling outage). The scheduling of components with other degradation mechanisms is not effected by the additional examination scope(s).
Exelon Byron Station 2-37 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: 13T-03 REVISION 0 (Page lot 1)
COMPONENT IDENTIFICATION Code Class: 2 and 3
Reference:
IWA-5244(b)(2)
Examination Category: C-H, D-B Item Number C7.l0, D2.l0
==
Description:==
System Leakage Testing of Non-Isolable Buried Components.
Component Number: Non-lsolable Buried Pressure Retaining Components CODE REQUIREMENT IWA-5244(b)(2) requires non-isolable buried components be tested to confirm that flow during operation is not impaired.
POSITION Article IWA-5000 provides no guidance in setting acceptance criteria for what can be considered adequate flow. In lieu of any formal guidance provided bythe Code, Byron Station has established the following acceptance criteria:
- For opened ended lines on systems that require Inservlce Testing (1ST) of pumps, adherence to 1ST acceptance criteria Is considered as reasonable proof of adequate flow through the lines.
- For lines in which the open end is accessible to visual examination while the system is in operation, visual evidence of flow discharging the line is considered as reasonable proof of adequate flow through the open ended line.
- For open ended portions of systems where the process fluid Is pneumatic, evidence of gaseous discharge shall be considered reasonable proof of adequate flow through the open ended line.
Such test may include passing smoke through the line, hanging balloons or streamers, using a remotely operated blimp, using thermography to detect hot air, etc.
This acceptance criteria will be utilized In order to meet the requirements of IWA-5244(b)(2).
Byron Stations position Is that proof of adequate flow is all that is required for testing these open ended lines and that no further visual examination Is necessary. This is consistent with the requirements for buried piping, which is not subject to visual examination.
Exelon Byron Station 2-38 Revision 0
IS! Program Plan Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER: 131-04 REVISION 0 (Page lofi)
COMPONENT IDENTIFICATION Code Class: 1,2, and 3
Reference:
IWA-5221 IWA-5222 Examination Category: B-P, C-H, D-B Item Number B15.l0, C7.l0, D2.l0
==
Description:==
Valve Seats as Pressurization Boundaries.
Component Number: All Pressure Testing Boundary Valves CODE REQUIREMENT IWA-5221 requires the pressurization boundary for system leakage testing extend to those pressure retaining components under operating pressures during normal system service.
PosmoN Byron Stations position is that the pressurization boundary extends up to the valve seat of the valve utilized for isolation. For example, inorder to pressure test the Class 1 components, the valve that provides the Class break would be utilized as the Isolation point. In this case the true pressurization boundary, and Class break, Is actually at the valve seat.
Any requirement to test beyond the valve seat Is dependent only on whether or not the piping on the other side of the valve seat is ISI Class 1,2, or 3.
In order to simplify examination of classed components, Byron Station will perform a VT-2 visual examination of the entire boundary valve body and bonnet (during pressurization up to the valve seat).
Exelon Byron Station 2-39 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 3.0 WELDS AND COMPONENTS ISI PLAN The Byron Station Welds and Components ISI Plan includes ASME Section XI nonexempt pressure retaining welds, piping structural elements, pressure retaining bolting, attachment welds, pump casings, valve bodies, reactor vessel interior, reactor vessel welded core support structures, reactor vessel interior attachments, reactor vessel removable core support structures, and steam generator tubing of 151 Class 1, 2, and 3 components that meet the criteria of (WA-i300. These components are identified on the 151 CBDs listed in Section 2.3, Tables 2.3-i and 2.3-2. Procedure ER-AA-330-002, Inservice Inspection of Welds and Components, Implements the ASME Section Xl Welds and Components ISI Plan.
This ISI Program Plan also includes component augmented inservice inspection examinations specified by documents other than ASME Section Xl.
3.1 BYRON STATION NONEXEMPT 1St CLASS COMPONENTS The Byron Station lSl Class 1 components subject to examination are those that are not exempted under the criteria of Subarticle IWB-12201n the 1989 EditIon, No Addenda of ASME Section XI (see Section 3.1.2 be$o~).The Byron Station ISI Class 2 and 3 components Identified In lSI CBDs are those not exempted under the criteria of Subarticles IWC-1 220 and Subarticle IWD-1220 in the 2001 Edition through the 2003 Addenda of ASME Section Xl. A summary of Byron Station Units 1, 2, and 0 (Common) ASME Section Xl nonexempt components is included in Section 7.0.
3.1.1 IdentifIcation of ISI Class 1, 2, and 3 Nonexempt Components (SI Class 1, 2, and 3 components are identIfied on the ISI Isometric and Component Drawings listed in Section 2.4, Tables 2.4-1 and 2.4-2. Welded attachments are also Identified by controlled Byron Station support drawings.
3.1.2 10 CFR 50.55a(b)(2)(xi) specifies that the 1989 Edition, No Addenda of ASME Section XI, Subarticle IWB-i 220 shall be used in lieu of the 2001 Edition through the 2003 Addenda of ASME Section XI, Subarticle IWB-1 220.
IWB-1220, Components Exemot from Examination (1989 Edition, No Addenda) -
The following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWB-2500 per the Code paragraph referenced:
(a) [IWB-1220(a) is not utilized at Byron Station]
(b)(l) piping of NPS 1 and smaller, except for steam generator tubing; (b)(2) components and their connections in piping of NPS 1 and smaller; (c) [IWB-1 220(c) is not utilized at Byron Station]
Exelon Byron Station 3-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 3.2 RISK-INFORMED EXAMINATION REQUIREMENTS Piping structural elements that fall under RISI Category A-A are risk ranked as High (1, 2, and 3), MedIum (4 and 5), and Low (6 and 7). Per the EPRI Topical Reports TR-1 12657, Rev. B-A, TA-i 006937, Rev. 0-A, and Code Case N-578-i, piping structural elements ranked as High or Medium Risk are subject to examination while piping structural elements ranked as Low Risk are not subject to examinations (except for pressure testing). Thin wall welds that were excluded from volumetric examination under ASME Section Xl rules per Table IWC-2500-1 are included in the element scope that is potentially subject to RISI examination at Byron Station.
Piping structural elements may be excluded from examination (other than pressure testing) under the fISt Program If the only degradation mechanism present for a given location is Inspected for under certain other station programs such as the Flow Accelerated Corrosion (FAC) or Microbiologically Induced Corrosion (MIC)
Programs. These piping structural elements will remain part of the FAC or Service Water programs that already perform for cause Inspections to detect these degradation mechanisms. Piping structural elements susceptible to FAC or MIC and pitting along with another degradation mechanism (e.g., thermal fatigue) are retained as part of the RISI scope and are included in the element selection for the purpose of performing exams to detect the additional degradation mechanism. The RISI Program element examinations are performed in accordance with Relief Request l3R-02.
Exelon Byron Station 3-2 Revision 0
IS! Program Plan Units I & 2, Third Interval 4.0 SUPPORT ISI PLAN The Byron Station Support 1St Plan includes the supports of ASME Section XI nonexempt ISI Class 1, 2, and 3 components as described in Section 3.0. Procedure ER-AA-330-003, Visual Examination of Section Xl Component Supports, implements the ASME Section Xl Support lSl Plan.
4.1 BYRON STATION NONEXEMPT lSl CLASS SUPPORTS The Byron Station ISI Class 1, 2, and 3 nonexempt supports are those which do not meet the criteria of Subarticle IWF-1 230 of ASME Section XI. A summary of the Byron Station Units 1, 2, and 0 (Common) ASME Section XI nonexempt supports is included in Section 7.0.
4.1.1 Identification of ISI Class 1, 2, and 3 Nonexempt Supports 151 Class 1, 2, and 3 supports are identified on the ISI Isometrics and Component Drawings listed in Section 2.4, Tables 2.4-1 and 2.4-2. Supports are also identified by controlled Byron Station support drawings.
4.2 SNUBBER EXAMINATION AND TESTING REQUIREMENTS 4.2.1 ASME Section Xl Paragraphs IWF-5200(a) and (b) and IWF-5300(a) and (b) require VT-3 Visual Examination and Inservice Tests of snubbers to be performed in accordance with the Operation and Maintenance of Nuclear Power Plants (OM),
Standard ASME/ANSI OM, Part 4. As allowed by 10 CFR 50.55a(b)(3)(v}, Byron Station Will use Subsection ISTD, Inservice Testing of Dynamic Restraints (Snubbers)
In Light Water Reactor Power Plants, ASME OM Code, 2001 Edition through the 2003 Addenda, to meet the requirements in ASME Section Xl Paragraphs IWF-5200(a) and (b) and IWF-5300(a) and (b). A summary of the Byron Station Units 1, 2, and 0 (Common) safety-related and important to safety snubbers is included in Section 7.0.
Corporate procedure ER-AA-330-004, Visual Examination of Technical Specification Snubbers, implements the visual inspection program for safety related and important to safety snubbers. Corporate procedures ER-AA-330-010, Administration of Snubber Functional Testing, ER-AA-330-01 1, Snubber Service Life Monitoring Program, and Station procedures BVP 200-6, 1/2BVSR 7.B-2, and 1/2BVSR 7.B-3 are used to implement the functional testing and service life monitoring requirements for safety-related and important to safety snubbers.
The ASME Section Xl (SI Program uses Subsection IWF to define support inspection requirements. The lSl Program maintains the Code Class snubbers in the populations subject to inspection per Subsection IWF. This is done to accommodate scheduling and inspection requirements (such as insulation removal) of the related attachment hardware per Paragraphs IWF-5200(c) and IWF-5300(c). (See Section 4.2.2 below.)
4.2.2 ASME Section Xl Paragraphs IWF-5200(c) and IWF-5300(c) require integral and non-integral attachments for snubbers to be examined in accordance with Subsection IWF Exelon Byron Station 4-1 Revision 0
IS! Program P!an Units 1 & 2, Third Interval of the Code. This results in VT-3 visual examination of the snubber attachment hardware including lugs, bolting, pins, and clamps.
The ASME Section Xl 1St Program uses Subsection IWF to define the inspection requirements for all Class 1, Class 2, and Class 3 supports, regardless of type. The lSl Program maintains the Code Class snubbers In the support populations subject to inspection per Subsection IWF. This is done to facilitate scheduling, preparation including insulation removal, and inspection requirements of the snubber attachment hardware (e.g., Iugs, bolting, pins, and clamps) per IWF-5200(c) and IWF-5300(c).
Exelon Byron Station 4-2 Revision 0
IS! Program Plan Units. 1 & 2, Third Interval 5.0 SYSTEM PRESSURE TESTING ISI PLAN The Byron Station System Pressure Testing (SPT) ISI Plan includes all pressure retaining ASME Section Xl, lSl Class 1, 2, and 3 components, with the exception of those specifically exempted by Paragraphs IWC-5222(b) and IWD-5240(b). All RISI piping structural elements, regardless of risk classification, remain subject to pressure testing as part of the current ASME Section Xl program.
The SPT (SI Plan performs system pressure tests and visual inspections on the ISI Class 1, 2, and 3 pressure retaining components to verify system and component structural integrity. This program conducts both Periodic and Interval (10-year frequency) pressure tests as defined in ASME Section Xl InspectIon Program B.
Procedure ER-AA-330-O01, Section Xl Pressure Testing, implements the ASME Section Xl System Pressure Testing ISI Plan. In addition to the ASME Section Xl requirements, Byron Stations SPT 151 Plan also includes augmented examination commitments.
5.1 BYRON STATION NONEXEMPT 151 CLASSED SYSTEMS All Class 1 pressure retaining components, typically defined as the reactor coolant pressure boundary, are required to be tested. Those portions of Class 2 and 3 systems that are required to be tested include the pressure retaining boundaries of components required to operate or support the system safety functions. Class 2 and 3 open ended discharge piping and components are excluded from the examination requirements per IWC-5222(b) and IWD-5240(b).
5.1.1 IdentIfication of Class 1, 2, and 3 Components All components subject to ASME Section Xl System Pressure Testing and augmented pressure testing are shown on the color coded ISI CBDs listed in Section 2.3, Tables 2.3-1 and 2.3-2.
5.1.2 Identification of System Pressure Tests The System Pressure Test Boundary Drawings used to define which systems, or portions of systems, fall under a specific test are also shown on the color coded 151 CBDs listed in Section 2.3, Tables 2.3-1 and 2.3-2.
5.2 RISK-INFORMED EXAMINATIONS OF SOCKET WELDS Socketwelds selected for examination under the RISI Program are to be Inspected with a VT-2 exam each refueling outage per ASME Code Case N-578-i (see footnote 12 in Table 1 of the Code Case). To facilitate this, socket welds selected for inspection under the RISI Program shall be pressurized each refueling outage in accordance with Paragraph IWA-521 1(a).
Exelon Byron Station 5-1 Revision 0
ISI Program Plan Units 1 & 2, Third Interval 6.0 CONTAINMENT (SI PLAN 6.1 INTRODuC11ON The Byron Station Containment ISI Plan Includes ASME Section Xl 1St Class MC pressure retaining components and their integral attachments, and Class CC components and post-tensioning systems that meet the criteria of Subarticle IWA-1 300. These components are identified on the ClSl Drawings listed In Section 2.4, Table 2.4-3 and 2.4-4. This Containment ISI Plan also includes information related to augmented examination areas, component accessibility, and examination review. The CISI Program component examinations are performed in accordance with Relief Request l3R-01.
The inspection of containment structures, components, and post-tensioning systems are performed per
- 1. ER-AA-330-005, Visual Examination of Section Xl Class CC Concrete Containment Structures
- 2. ER-AA-330-006, Inservice Inspection and Testing of the Pre-Stresses Concrete Containment Post Tensioning Systems
- 3. ER-AA-330-007, Visual Examination of Section Xl Class MC Surfaces and Class CC Liners 6.2 CLASS MC AND CC COMPONENTS The Byron Station 1St Class MC and CC components identified on the CISI Drawings are those not exempted under the criteria of Subarticles IWE-1220 and Subarticle IWL-1 220 In the 2001 Edition through the 2003 Addenda of ASME Section Xl. A summary of Byron Station Units 1 and 2 ASME Section XI nonexempt CISI components is included In SectIon 7.0.
The process for scoping Byron Station components for inclusion in the CISI Plan is included in the containment sections of the ISI ClassIfication Basis Document. These sections include a listing and detailed basis for inclusion of containment components.
Components that are classified as Class MC and CC must meet the requirements of ASME Section Xl in accordance with 10 CFR 50.55a(g)(4). Supports of IWE components are not required to be examined in accordance with 10 CFR 50.55a(g)(4).
6.2.1 Identification of ISI Class MC and CC Nonexempt Components lSl Class MC and CC components are identified on the CISI Drawings listed in Section 2.4, Tables 2.4-3 and 2.4-4.
Exelon Byron Station 6-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 6.2.2 Identification of ISI Class MC and CC Exempt Components The process for exempting Byron Station components from the CISI Plan per IWE-1 220 and IWL-1 220 is included in the containment sections of the ISI Classification Basis Document. These sections include discussions of exempt components and the bases for those exemptions.
6.3 AUGMENTED EXAMINATIONS AREAS Metal containment components potentially subject to augmented examination per (WE-i 240 have been evaluated in the containment sections of the lSl Classification Basis Document. These sections define the areas that are subjected to augmented examination.
Similarly, concrete surfaces may be subject to Detailed Visual examination in accordance with IWL-2310, if declared to be Suspect Areas by the examineror the Responsible Engineer.
No significant conditions are currently identified in the Second CISI Interval as requiring application of additional augmented examination requirements under IWE-1 240.
6.4 COMPONENT ACCESSIBIUTY Class MC pressure retaining components subject to examination shall remain accessible for either direct or remote visual examination from at least one side per the requirements of ASME Section Xl, Subarticle IWE-i230.
6.5 RESPONSIBLE INDIVIDUAL AND ENGINEER ASME Section Xl Subsection IWE requires the Responsible Individual to be involved in the development, performance, and review of the CISI examinations. The Responsible Individual shall meet the requirements of ASME Section XI, Subarticle IWE-2320.
ASME Section Xl Subsection IWL requires the Responsible Engineer to be involved in the development, approval, and review of the CISI examinations. The Responsible Engineer shall meet the requirements of ASME Section Xl, Subarticle IWL-2320.
Exe!on Byron Station 6-2 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 7.0 COMPONENT
SUMMARY
TABLES 7.1 INSERVICE INSPECTiON
SUMMARY
TABL~
The following Tables 7.1-1 and 7.1-2 provide a summary of the ASME Section Xl component, support, system pressure testing, and augmented examinations and tests for the Third Inspection Interval at Byron Station Units 1, 2, and 0 (Common).
If a particular Category and Item Numberdo not apply to Byron Station, they are not included in these tables.
The format of the Inservice Inspection Summary Tables Is as depicted below and provides the following information:
EXAMINATiON ITEM NUMBER (OR CATEGORY (WITH RISK CATEGORY DESCRIPTION RELIEF REQJ CATEGORY OR AUGMENTED REQUIREMENTS TOTAL NUMBER TA&P BY SYSTEM NUMBER NOTES DESCRIPTION) NUMBER)
(1) (2) (3) (4) (5) (6) (7)
(1) Examination Category and Examination Category
Description:
Provides the examination category and description as identified in ASME Section Xl, Tables IWB-2500-i, IWC-2500-1, IWD-2500-1, IWE-2500-1, IWF-2500-1, and IWL-2500-1.
Examination Category R-A from Code Case N-578-1 Is used in lieu of ASME Section Xl Categories B-F, B-J, C-F-i, and C-F-2 to Identify Class 1 and 2 piping structural elements for the RISI program. Only those examination categories applicable to Byron Station are identified.
In addition to the ASME Section Xl Categories, Category M~.4/Ais used to identify Augmented ISI examinations and other Byron Station commitments.
(2) Item Number (or Risk Category Number OR Augmented Number):
Provides the item number as identified in ASME Section Xl, Tables IWB-2500-1, IWC-2500-i, IWD-2500-1, IWE-2500-1, IWF-2500-1, and IWL-2500-
- 1. Only those item numbers applicable to Byron Station are Identified.
For piping structural elements under the RISI Program, the Risk Category Number (e.g., 1-5) is used in place of the Item Number.
In addition to the ASME Section Xl Item Numbers, Item Numbers RG1 .14, ECCS, 0737, and GL8805 are used to identify Augmented (Si examinations and other Byron Station commitments.
Exelon Byron Station 7-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval (3) Item Number
Description:
Provides the description as identified in ASME Section Xl, Tables IWB-2500-1, IWC-2500-i, IWD-2500-1, and IWF-2500-1.
In addition to the ASME Section Xl Item Numbers, a description of the Risk Categories for Class 1 and 2 piping structural elements is provided for the RISI Program.
For Augmented 1St examinatIon commitments, a description of the Augmented requirement is provided.
(4) Exam Requirements:
Provides the examination methods required by ASME Section Xl, Tables IWB-2500-i, IWC-2500-1, IWD-2500-i, IWE-2500-1, IWF-2500-1, and IWL-2500-i.
Provides the examination requirements for augmented components from Byron Station commitments or relief requests.
Provides the examination requirements for piping structural elements under the RlSl Program are in accordance with the EPRI Topical Reports TR-112657, Rev. B-A, TA-i006937, Rev. 0-A, and Code Case N-578-1.
(5) Total Number by System:
Provides the system designator (abbreviations). See Section 2.3, Tables 2.3-1 and 2.3-2 for a list of these systems.
This column also provides the number of components within a particular system for that Item Number, Risk Category Number, or Augmented Number.
Note that the total number of components by system are subject to change after completion of plant modifications, design changes, and 1St system classification updates.
(6) Relief Request/TA&P Number:
Provides a listing of Relief RequestlTA&P numbers applicable to specific components the ASME Section Xl Item Number, Risk Category Number, or Augmented Number. Relief requests that generically apply to all components, or an entire class are not listed, If a Relief RequestlTA&P Number is identified, see the corresponding relief request in Section 8.0 or the technical approach and position in Section 2.5. If a Relief RequestlTA&P Number is generic to all components, the Number is not listed in these tables.
Exe!on Byron Station 7-2 Revision 0
IS! Program Plan Units 1 & 2, Third Inter~aI (7) Notes:
Provides a listing of program notes applicable to the ASME Section Xl Item Number, Risk Category Number, or Augmented Number. If a program note number is Identified, see the corresponding program note at the end of the Table 7.i-2.
Exelon Byron Station 7-3 Revision 0
IS! Program Plan Units 1 & 2, Third !nte,vai Unit 1 & 0 Inservice Inspection Summary Table 7.1-1 ITEM EXAM TOTAL NUMBER REUEF REOJ EXAMINATION CATEGORY NUMBER DESC~PTION
. REQUIREMENTS BY SYSTEM TA&P NUMBER B-A Bi .11 Circumferential Shell Welds (Reactor Vessel) Volumetric RPV: 3 .
Pressure Retaining Bi .21 Circumterential Head Welds (Reactor Vessel) Volumetric RPV: 2 Welds in Reactor Vessel Bi .30 Shell-to-Flange Weld (Reactor Vessel) Volumetric RPV: I 81.40 Head-to-Flange Weld (Reactor Vessel) Volumetric & RPV: 1 Surface B-B 82.11 Circumferential Shell-To-Head Welds (Pressurizer) Volumetric PZR: 2 Pressure Retaining 82.12 Longitudinal Shell-To-Head Welds (Pressurizer) Volumetric PZR: 2 Welds in Vessels Other Than Reactor Vessels B2.40 Tube Sheet-To-Head Weld (Steam Generator) Volumetric SG: 4 B-D B3.90 Nozzle-to-Vessel Welds (Reactor Vessel) Volumetric RPV: 8 Full Penetration Welds of B3.100 Nozzle Inside Radius Section (Reactor Vessel) Volumetric RPV: 8 Nozzles in Vessels 83.110 Nozzle-to-Vessel Welds (Pressurizer) Volumetric PZR: 6 I3R-03, 83.120 Nozzle Inside Radius Section (Pressurizer) See Note PZR: 6 13R-03 14 B3.140 Nozzle Inside Radius Section (Steam Generator) See Note SG: 8 14 Exe!on Byron Station 7-4 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 1 & 0 Inservice Inspection Summary Table 7.1-1 EXAM TOTAL NUMBER RELIEF REQ.! NOTES EXAMINATION CATEGORY NUMBER O~ON REQUIREMENTS BY SYSTEM TA&P NUMBER B-G-1 B6.iO Closure Head Nuts (Reactor Vessel) Visual, VT-i RPV: 3 3 Pressure Retaining 86.20 Closure Studs (Reactor Vessel) Volumetric RPV: 3 3 Bolting, Greater Than 2 In Diameter 86.40 Threads in Flange (Reactor Vessel) Volumetric RPV: 1 3 86.50 Closure Washers, Bushings (Reactor Vessel) Visual, VT-i RP%/: 3 3 86.90 Bolts and Studs (Steam Generator) Volumetric SG: 8 3 B6.100 Flange Surface, When Connection Disassembled (Steam Generator) Visual, VT-i SG: 8 3 86.110 Nuts, Bushings, and Washers (Steam Generator) Visual, VT-i SG: 8 3 86.170 Nuts, Bushings, and Washers (Piping) Visual, VT-i RPV: 1 3 B6.1B0 Bolts & Studs (Pumps) Volumetric RC: 4 3 86.190 Flange Surface, When Connection Disassembled (Pumps) Visual, VT-i RC: 4 3 B6.200 Nuts, Bushings, and Washers (Pumps) Visual, VT-i RC: 4 3 86.210 Bolts & Studs (Valves) Volumetric RC: 8 3 B6.220 Flange Surface, When Connection Disassembled (Valves) Visual, VT-i AC: 8 3 B6.230 Nuts, Bushings, and Washers (Valves) Visual, VT-i AC: 8 3 B-G-2 B7.10 Bolts, Studs, & Nuts (ReactorVessel) Visual, VT-i RPV: 2 3 Pressure Retaining B7.20 Bolts, Studs, & Nuts (Pressurizer) Visual, VT-i PZR: 1 3 Bolting, 2 and Less In B7.50 Bolts, Studs, & Nuts (Piping) Visual, VT-i CV: 4 3 Diameter AC: 4 RY: 4 SI:8 B7.60 Bolts, Studs, & Nuts (Pumps) VISUal, VT-i RC: 4 3 87.70 Bolts, Studs, & Nuts (Valves) Visual, VT-i RC: 4 3 RH: 4 RY: 3 SI: 18 Exe!on Byron Station 7-5 Revision 0
IS! Program Plan Units 1 & 2, Third Interval UnIt 1 & 0 Inservlce Inspection Summary Table 7.1-1 ITEM EXAM TOTAL NUMBER REUEF REQ.!
EXAMINATION CATEGORY DESCffiFflON NOTES NUMBER REQUIREMENTS BY SYSTEM IMP NUMBER B-K B10.i0 Welded Attachments (Pressure Vessels) Surface PZR: 2 15 Welded Attachments for Vessels, Piping, Pumps, BiO.20 Welded Attachments (Piping) Surface CV: i and Valves SI:_6 B-L-2 B12.20 Pump Casings (Pumps) Visual, VT-3 AC: 4 Pump Casings B-M-2 B12.50 Valve Bodies, Exceeding NPS 4 (Valves) Visual, VT-3 AC: i2 Valve Bodies RH:4 RY: 3 SI:_18 B-N-i B13.10 Vessel Interior (and Head Accessible Surfaces) (Reactor Vessel) Visual, VT-3 RPV: 2 Interior of Reactor Vessel B-N-2 Bi 3.50 Interior Attachments Within Beltline Region (Reactor Vessel) Visual, VT-i RPV: 1 Welded Core Support B13.60 Interior Attachments Beyond Belthne Region (Reactor Vessel) Visual, VT-3 RPV: 1 Structures and Interior Attachments to Reactor .
Vessels B-N-3 Bi3.70 Core Support Structure (Reactor Vessel) Visual, VT-3 RPV: 1 Removable Core Support Structures Exe!on Byron Station
- 7-6 Revision 0
IS! Program Plan Units 1 & 2, ThirdInterval Unit 1 & 0 Inservlce Inspection Summary Table 7.1-1 EXAMINATION CATEGORY ITEM EXAM TOTAL NUMBER REUEFREQJ NOTES NUMBER DESCR~TION REQUIREMENTS BY SYSTEM IMP NUMBER B-O B14.10 Welds In CAD Housing (Reactor Vessel) Volumetric or RPV: 45 Pressure Retaining (10% of Peripheral CAD Housing welds to be inspected. 45 of 78 Surface Welds in Control Rod welds are kientitied as peripheral)
Housings B-P B15.iO System Leakage Test (IWB-5220) Visual, VT-2 CV 13T-04 All Pressure Retaining RC Components RH RY SI 8-0 B16.20 Steam Generator Tubing in U-Tube Design Volumetric Per SG: 4 Steam Generator Tubing Tech Specs Exelon Byron Station 7-7 Revision 0
ISI Program Plan Units 1 & 2, Third Interval UnIt 1 & 0 Inservlce Inspection Summary Table 71-1 EXAMINATION CATEGORY ITEM EXAM TOTAL NUMBER REUEF REOJ NOTES NUMBER DESCffiFflON REQUIREMENTS BY SYSTEM TA&P NUMBER C-A Ci.iO Shell Circumferential Welds (Pressure Vessels) Volumetric RH: 2 Pressure Retaining SG: 4 Welds In Pressure Vessels Ci .20 Head Circumferential Welds (Pressure Vessels) Volumetric RH: 2 SG:_4 Cl .30 Tubesheet-to-ShelI-Weld Welds (Pressure Vessels) Volumetric SG: 4
- C-B C2.21 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Welds Without Volumetric & RH: 4 l3R-04 4 Pressure Retaining Reinforcing Plate, Greater Than 1/2 Nominal Thickness (Pressure Surface Nozzle Welds in Vessels Vessels) SG:8 C2.22 Nozzle Inside Radius Section Without Reinforcing Plate, Greater Than Volumetric RH: 4 l3R-04 4, 1/2 Nominal Thickness (Pressure Vessels) SG: 0 6 C-C C3.10 Welded Attachments (Pressure Vessels) Surface RH: 2 Welded Attachments for C320 Welded Attachments (Piping) Surface AF: 1 Vessels, Piping, Pumps, CS: 2 and Valves ~ CV:2 MS: 28 RH: 9 SI: 10 SX: 21 VQ: 4 C3.30 Welded Attachments (Pumps) Surface CS: 12 I3R-05 CV: 8 RH: 6 Exelon Byron Station
- 7-8 - - - - - Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 1 & 0 Inservlce Inspection Summary Table 7.1-1
. ITEM EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY DESC~PUON NOTES NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER C-H C7.1O System Leakage Test (IWC-5220) Visual, VT-2 AB 13T-03, All Pressure Retaining AF 13T04 Components BR CC CS CV DG FC FP FW .
IA MS NT OG PC PR PS AC RE RF RH
. SA SD SI Exelon Byron Station 7-9 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 1 & 0 Inservice Inspection Summary Table 7.1-1 ITEM EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY DESCffiFflON NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER ~°~
C-H C7.iO System Leakage Test (IWC-5220) Visual, VT-2 SX l3T-03, All Pressure Retaining VQ 13T04 Components(Continued) WE WM Wo Exelon Byron Station 7-10 Revision 0
IS! Program Plan Units 1 & 2, Third Inter/al Unit 1 & 0 Inservlce Inspection Summary Table 7.1-1 EXAMINATION CATEGORY ITEM EXAM TOTAL NUMBER RELIEF REQ.!
DESCRWflON NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER D-A Dl.10 Welded Attachments (Pressure Vessels) Visual, VT-i CC: 2+2 2 Welded Attachments for DG: 12 Vessels, Piping, Pumps, FC: 2 and Valves RH: 2 SX: 8 01.20 Welded Attachments (Piping) Visual, VT-i AF: 8 2 CC: 61÷4 SX: 43+10 D1.30 Welded Attachments (Pumps) Visual, VT-I AF: 8 2 SX: 0+4 Exelon Byron Station 7-11 Revision 0
IS! Program Plan Units 1 & 2, Third Interval UnIt 1 & 0 Inservlce Inspection Summary Table 7.1-1 EXAMINATION CATEGORY ITEM EXAM TOTAL NUMBER RELIEF REQ.!
NUMBER DESCRIPTION REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES D-B D2.10 System Leakage Test (IWD-5221) Visual, VT-2 AS I3R-07, All Pressure Retaining AF 13T-03, Components BR l3T-04 CC CV DG Do FC FP FW PS RE RH RY SA SI Sx WE WM wo Exelon Byron Station 7-12 Revision 0
IS! Program Plan Units I & 2, Third Interial UnIt 1 & 0 Inservlce Inspection Summary Table 7.1-1 EXAMINATION ITEM CATEGORY NUMBER DESCRIFflON EXAM TOTAL NUMBER RELIEF REQ.!
REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES E-A El .11 Containment Vessel Pressure Retaining Boundary - General Visual 318 13R-01 7 Containment Surfaces Access~,leSurface Area
~ El .11 Containment Vessel Pressure Retaining Boundary - Visual, VT-3 75 13R-01 7 Bolted Connections, Surfaces 11 El .30 ContaInment Vessel Pressure Retaining Boundary - General Visual 1 I3R-01 7 Moisture Barriers E-C E4.i 1 Containment Surface Areas - Visual, VT-i 0 13R-01 7 Containment Surfaces Visible Surfaces 12 Requiring Augmented E4.12 Containment Surface Areas - Volumetric I3R-01 7 Examination (Thickness) 13 Surface Area Grid, Minimum Wall Thickness Location Exelon Byron Station 7-13 Revision 0
IS! Program Plan Units 1 & 2, Third Inter/a!
Unit 1 & 0 Inservice Inspection Summary Table 7.1-1 EXAMINATION CATEGORY ITEM DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.! NOTES NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER F-A Fl.10 Class 1 Piping Supports Visual, VT-3 CV: 134 1 Supports AC: 91 RH: 20 RY: 32 SI:_190 Fl.20 Class 2 PIping Supports Visual, VT-3 AF: 26 1 CS:52 CV:66 FW: 39 MS:27 ~
RH:61 SI: 157 SX:.157 ~
VO:5 F1.30 Class 3 PipIng Supports Visual, VT-3 AF: 563 . 1, CC: 326+26 2 SX: 373+248 Exelon Byron Station 7-14 Revision 0
IS! Program Plan Units 1 & 2, ThirdInter/al UnIt 1 & 0 S Inservice Inspection Summary Table 7.1-1 ITEM EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY NUMBER DESCRWIION REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES F-A Fl.40 Supports Other Than Piping Supports Visual, VT-3 AF: 2 1 Supports (CIassl,2,and3) CC:3+2 (Continued) CS: 4+2 CV:8 DG:2 FC: 1 AC: 25 RH: 10 RY:5 SI:4 SX: 6 Exelon Byron Station 7-15 Revision 0
181 Program Plan Units 1 & 2, Third Interval UnIt 1 & 0 Inservice Inspection Summary Table 7.1-1 ITEM EXAMINATION CATEGORY NUMBER EXAM TOTAL NUMBER RELIEF REQ.!
DESCRIPTION REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES L-A L1.1 1 Concrete Surfaces - General Visual 42 13R-01 7 Concrete All Accessible Surface Areas L1.12 Concrete Surfaces - Detailed Visual I3R-01 7 Suspect Areas (No Suspect Areas Identified)
L-B 12.10 Tendon IWL-2522 483 l3R-0l 7 Unbonded POSt- 12.20 Tendon - IWL-2523.2 483 I3R-0l 7 Tensioning System Wire or Strand
[2.30 Tendon - Detailed Visual 966 l3R-0l 7 Anchorage Hardware and Surrounding Concrete 12.40 Tendon- IWL-2525.2(a) l3R-0l 7 Corrosion Protection Medium 12.50 Tendon - IWL-2525.2(b) 13R-01 7 Free Water Exe!on Byron Station 7-16 Revision 0
IS! Program Plan Units 1 & 2, Third Inter/a!
Unit I & 0 lnservlce Inspection Summary Table 7.1-1 RISK EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY CAT DES RIPTION REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES NUMBER A-A 1 Risk Category 1 Elements See notes FW: 127 I3R-02 8, Risk-Informed PIPW)9 2 Risk Category 2 Elements See notes AF: 20 l3TOi 9.
~
13T-02 10 AC: 176 RY: 39 4 Risk Category 4 Elements See notes AF: 87 CS: 172 CV: 192 MS: 178 AC: 408 RH: 200 RY:84 SD: 4 SI: 267 5 Risk Category 5 Elements See notes CV: 153 AC: 3 SI: 254 Exelon Byron Station 7-17 Revision 0
IS! Program Plan Units I & 2, Third Interval UnIt 1 & 0 Inservlce Inspection Summary Table 7.1-1 EXAMINATION CATEGORY DESCRI EXAM TOTAL NUMBER REUEF REQ.! NOTES NUMBER PT1ON REQUIREMENTS BY SYSTEM TUP NUMBER N/A 3.6.2 Examination of High Energy Circumferential and Longitudinal Piping Volumetric or N/A 5, Augmented Components Welds (MEB 3-1, UFSAR 3.6.1 and 3.6.2). Surface 10 RG1.14 Augmented Examination Of Reactor Coolant Pump Flywheel Per Volumetric, AC: 4 Regulatory Guide 1.14. Surface &
Visual ECCS Information Notice 79-19, Pipe Cracks in Stagnant Borated Water Volumetric SI: 94 Systems at PWR Plants.
0737 Leak testing and periodic visual examinations of systems outside of Visual, VT-2 CS primarycontainment which could contain highly radioactive fluids during CV a serious transient or accident (NUREG 0737). FC GW OG PS RH SI GL8805 Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Visual, VT-2 AC Pressure Boundary Components in PWR Plants.
Exelon Byron Station 7-18 RevIsion 0
IS! Program Plan Units 1 & 2, ThirdInterval UnIt 2 Inservlce Inspection Summary Table 7.1-2 EXAMINATION ITEM CATEGORY NUMBER DESCRIPflON EXAM TOTAL NUMBER RELIEF REQ.! NOTES REQUIREMENTS BY SYSTEM TA&P NUMBER B-A BI .11 Circumferential Shell Welds (Reactor Vessel) Volumetric RPV: 3 Pressure Retaining 81.21 Circumferential Head Welds (Reactor Vessel) Volumetric RPV: 2 Welds in Reactor Vessel Bi .30 Shell-to-Flange Weld (Reactor Vessel) Volumetric RPV: I Bi .40 Head-to-Flange Weld (Reactor Vessel) Volumetric & RPV: 1 Surface B-B B2.1 1 Circumferential Shell-To-Head Welds (Pressurizer) Volumetric PZR: 2 Pressure Retaining B2.12 Longitudinal Shell-To-Head Welds (Pressurizer) Volumetric PZR: 2 Welds in Vessels Other Than Reactor Vessels B2.40 Tube Sheet-To-Head Weld (Steam Generator) Volumetric SG: 4 B-D 83.90 Nozzle-to-Vessel Welds (Reactor Vessel) Volumetric RPV: 8 Full Penetration Welds 01 83.100 Nozzle Inside Radius Section (Reactor Vessel) Volumetric RPV: 8 Nozzles In Vessels 83.110 Nozzle-to-Vessel Welds (Pressurizer) Volumetric PZR: 6 13R-03 B3120 Nozzle Inside Radius Section (Pressurizer) See Note PZR: 6 13A-03 14 83.140 Nozzle Inside Radius Section (Steam Generator) See Note SG: 8 14 Exelon Byron Station 7-19 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservice Inspection Summary Table 7.1-2 ITEM EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY DESCRIPTION NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES B-G-1 86.10 Closure Head Nuts (Reactor Vessel) Visual, VT-i RPV: 3 3 Pressure Retaining 86.20 Closure Studs (Reactor Vessel) Volumetric RPV: 3 3 Bolting. Greater Than 2 In Diameter 86.40 Thre~in Flange (Reactor Vessel) Volumetric RPV: 1 3 86.50 Closure Washers, Bushings (Reactor Vessel) Visual, VT-i RPV: 3 3 86.180 Bolts & Studs (Pumps) Volumetric AC: 4 3 86.190 Flange Surface, When Connection Disassembled (Pumps) Visual, VT-i AC: 4 3 86.200 Nuts, Bushings, and Washers (Pumps) Visual, VT-i RC: 4 3 86.210 Bolts & Studs (Valves) Volumetric RC: 8 3
- 86.220 Range Surface, When Connection Disassembled (Valves) Visual, VT-i RC: 8 3 86.230 Nuts, Bushings, and Washers (Valves) Visual, VT-i AC: 8 3 B-G-2 B7.10 Bolts, Studs, & Nuts (Reactor Vessel) Visual, VT-i RPV: 2 3 Pressure Retaining B7.20 Bolts, Studs, & Nuts (Pressurizer) Visual, VT-i PZR: 1 3 BoltIng, 2 and Less In B7.30 Bolts, Studs, & Nuts (Steam Generator) Visual, VT-i SG: 4 Diameter 3 B7.50 Bolts, Studs, & Nuts (Piping) Visual, VT-i CV: 4 3 AC: 4 RY: 4 51:8 B7.60 Bofts, Studs, & Nuts (Pumps) Visual, VT-i RC: 4 3 B7.70 Bolts, Studs, & Nuts (Valves) Visual, VT-i AC: 4 3 RH:4 RY: 3 Sl:18 ~
Exelon Byron Station 7-20 - Revision 0
IS! Program Plan Units 1 & 2, Third Interial Unit 2 Inservlce Inspection Summary Table 7.1-2 EXAMINATION CATEGORY ITEM DESCRIFflON EXAM TOTAL NUMBER RELIEF REQ.!
NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES B-K BiO.i0 Welded Attachments (Pressure Vessels) Surface PZR: 2 15 Welded Attachments for Vessels, Piping, Pumps, BiO.20 and Valves Welded Attachments (Piping) Surface CV: 1 SI: 7 B-L-2 812.20 Pump Casings (Pumps) Visual, VT-3 AC: 4 Pump Casings B-M-2 B12.50 Valve Bodies, Exceeding NPS 4 (Valves) Visual, VT-3 AC: 12 Valve Bodies RH: 4
. RY:3 SI:_18 B-N-i Bi3.10 Vessel Interior (and Head Accessible Surfaces) (Reactor Vessel) Visual, VT-3 RPV: 2 Interior of Reactor Vessel B-N-2 Bi3.50 Interior Attachments Within Betthne Region (Reactor Vessel) Visual, VT-i RPV: 1 Welded Core Support 813.60 Interior Attachments Beyond Beltilne Region (Reactor Vessel) Visual, VT-3 RPV: 1 Structures and Interior .
Attachments to Reactor Vessels B-N-3 813.70 Core Support Structure (Reactor Vessel) Visual, VT-3 RPV: 1 Removable Core Support ~
Structures ~
Exelon Byron Station 7-21 Revision 0
IS! Program Plan Units 1 & 2, Third Interval UnIt 2 Inservice Inspection Summary Table 7.1-2 EXAMINATION CATEGORY NUMBER EXAM TOTAL NUMBER RELIEF REQJ TA&P NUMBER NOTES
~M DESCRIPTION REQUIREMENTS BY SYSTEM 8-0 Bi4.i0 Welds in CRD Housing (Reactor Vessel) Volumetric or RPV: 45 Pressure Retaining (10% of Peripheral CRD Housing welds to be Inspected. 45 of 78 Surface Welds in Control Rod welds are kientifled as peripheral)
Housings B-P B15.i0 System Leakage Test (IWB-5220) Visual, VT-2 CV l3T-04 All Pressure Retaining AC Components RH RY SI 8-0 B16.20 Steam Generator Tubing In U-Tube Design Volumetric Per SG: 4 Steam Gen. Tubing Tech Specs Exelon Byron Station 7-22 Revision 0
ISI Program Plan Units 1 & 2, Third Interval UnIt 2 Inservlce Inspection Summary Table 7.1-2
~1EM DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY BY SYSTEM TA&P NUMBER NOTES NUMBER REQUIREMENTS C-A Ci.10 Shell Circumferential Welds (Pressure Vessels) Volumetric RH: 2 Pressure Retaining SG: 12 Welds in Pressure Cl .20 Head Circumferential Welds (Pressure Vessels) Volumetric RH: 2 Vessels SG: 4 Ci .30 Tubesheet-to-Shell-Weld Welds (Pressure Vessels) Volumetric SG: 4 C-B C2.21 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Welds Without Volumetric & RH: 4 13R-04 4 Pressure Retaining Reinforcing Plate, Greater Than 1/2 Nominal Thickness (Pressure Surface Nozzle Welds in Vessels Vessels) SG:12 C2.22 Nozzle Inside Radius Section Without Reinforcing Plate, Greater Than Volumetric RH: 4 l3R-04 4, 1/21 Nominal Thickness (Pressure Vessels) SG: 0 6 C-C C3.i0 Welded Attachments (Pressure Vessels) Surface RH: 2 Welded Attachments for C3.20 Welded Attachments (Piping) Surface CS: 3 Vessels, Piping, Pumps, .
and Valves CV:2 FW: 4 MS:32 RH: 6 SI: 12 SX: i3 VQ:4 C3.30 Welded Attachments (Pumps) Surface CS: 12 l3R-05 CV:8 RH: 6 Exelon Byron Station 7-23 -- - Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservlce Inspection Summary Table 7.1-2 EXAMINATION CATEGORY ITEM DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.!
NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER C-H C7.10 System Leakage Test (IWC-5220) Visual, VT-2 AB I3T-03, All Pressure Retaining AF I3T~04 Components BR CC CS CV DG FC FP FW LA MS NT OG PC PR PS AC RE RF RH SA SD SI Exelon Byron Station 7-24 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservlce Inspection Summary Table 7.1-2 EXAMINATION CATEGORY ITEM DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.!
NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES C-H C7.l0 System Leakage Test (IWC-5220) Visual, VT-2 SX l3T-03, All Pressure Retaining VQ 13T-04 Components) WE (Continued) WM Wo Exelon Byron Station 7-25 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservlce Inspection Summary Table 7.1-2 EXAMINATION CATEGORY ITEM EXAM TOTAL NUMBER RELIEF REQ.!
DESCRIPTION NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES D-A D1.10 Welded Attachments (Pressure Vessels) Visual, VT-i CC: 2 Welded Attachments for DG: 12 Vessels, Piping, Pumps, and Valves FC: 2 RH:2 SX: 8 Di 20 Welded Attachments (Piping) Visual, VT-i AF: 11 CC:4 SX:_15 D1.30 Welded Attachments (Pumps) Visual, VT-i AF: 8 Exelon Byron Station 7-26 Revision 0
IS! Program Plan Units 1 & 2, Third Interval UnIt 2 Inservlce Inspection Summary Table 7.1-2 ITEM DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER D-B D2.10 System Leakage Test (IWD-5221) Visual, VT-2 AB 13R-07, All Pressure Retaining AF l3T-03, Components BR 13T-04 CC CV DG DO FC FP FW PS RE RH RY SA SI Sx WE WM Wo Exelon Byron Station 7-27 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservice Inspection Summary Table 7.1-2 EXAMINATION CATEGORY
~ EXAM TOTAL NUMBER REUEF REQ.!
DESCRIPTION NUMBER REQUiREMENTS BY SYSTEM TA&P NUMBER NOTES E-A E1.il Containment Vessel Pressure Retaining Boundary - General Visual 318 l3R-0l 7 Containment Surfaces Accessible Surface Area El .11 Containment Vessel Pressure Retaining Boundary - Visual, VT-3 120 13R-01 7 Bolted Connections, surfaces ii El .30 Containment Vessel Pressure Retaining Boundary - General Visual I 13R-0l 7 Moisture Bafflers E-C E4.i 1 Containment Surface Areas - Visual, VT-i 0 l3R-0l 7 Containment Surfaces Visible Surfaces i2 Requiring Augmented E4.12 Containment Surface Areas Examination
- Volumetric 13R-01 7 Surface Area Grid, Minimum Wall Thickness Location (Thickness) 13 Exelon Byron Station 7-28 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unft 2 Inservlce Inspection Summary Table 7.1-2 ITEM EXAMINATiON CATEGORY NUMBER EXAM TOTAL NUMBER RELIEF REQ.!
DESCRIPTION TA&P NUMBER NOTES REQUIREMENTS BY SYSTEM F-A Fl .10 Class 1 PipIng Supports Visual, VT-3 CV: 143 1 Supports RC: 86 RH: 26 RY: 37 SI:_175 Fl.20 Class 2 PipIng Supports Visual, VT-3 AF: 30 1 CS:55 CV: 57 FW:97 MS:32 RH: 74 SI: 147 SX: 155 VO: 5 Fl .30 Class 3 PIping Supports - Visual, VT-3 AF: 448 1 CC:52 SX: 277 Exelon Byron Station 7-29 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 inservice Inspection Summary Table 7.1-2 EXAMINATION CATEGORY ITEM DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.! NOTES NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER F-A Fl.40 Supports Other Than Piping Supports Visual, VT-3 AF: 2 1 Supports (Class 1,2, and 3) CC: 3 (Continued) CS: 6 CV: 8 DG:2 FC: 1 RC:25 RH: 10 RY: 5 SI: 4 SX: 4 Exelon Byron Station 7-30 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservlce Inspection Summary Table 7.1-2 ITEM TOTAL NUMBER REUEF REQJ EXAMINATION CATEGORY DESCRIPTION EXAM NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER NOTES L-A Li .11 Concrete Surfaces - General Visual 42 13R-01 7 Concrete All Accessible Surface Areas Ll.12 Concrete Surfaces - Detailed Visual - 13R-01 7 Suspect Areas (No Suspect Areas Identified)
L-B L2.10 Tendon IWL-2522 483 l3RO1 7 Unbonded Post ~20 Tendon - IWL-2523.2 483 13R-0l 7 Tensioning System Wire or Strand L2.30 Tendon - Detailed VIsual 966 13R-01 7 Anchorage Hardware and Surrounding Concrete L2.40 Tendon - IWL-25252(a) -- l3R-O1 7 Corrosion Protection Medium L2.50 Tendon - IWL-25252(b) -- l3R-01 7 Free Water Exelon Byron Station 7 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unft 2 Inservlce Inspection Summary Table 7.1-2 RISK EXAM TOTAL NUMBER RELIEF REQ.!
EXAMINATION CATEGORY CAT DESCRIPTION NOTES REQUIREMENTS BY SYSTEM TA&P NUMBER NUMBER R-A 1 Risk Category 1 Elements See notes FW: 242 I3R-02 8, Risk-Informed Piping 2 RIsk Categ~2 Elements See notes AF: 20 13T01 9, ExaInat~ons 13T-02 10 AC: 168 RY: 34 4 Risk Category 4 Elements See notes AF: 88 CS: 164 CV: 200 MS: 169 AC: 377 RH: 215 RY:84 SI: 243 5 Risk Category 5 Elements See notes CV: 150 AC: 2 SI: 253 Exelon Byron Station
- 7-32 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Inservice inspection Summary Table 7.1-2 EXAMINATION CATEGORY DESCRIPTION EXAM TOTAL NUMBER RELIEF REQ.! NOTES AI*p NUMBER REQUIREMENTS BY SYSTEM TA&P NUMBER N/A 3.6.2 ExamInation of High Energy Circumferential and Longitudinal Piping Volumetric or N/A 5, Augmented Components Welds (MEB 3-1, UFSAR 3.6.1 and 3.6.2). Surface 10 RG1.14 Augmented Examination Of Reactor Coolant Pump Fl)wheel Per Volumetric, RC: 4 Regulatory Guide 1.14. Surface &
Visual ECCS Information Notice 79-19, Pipe Cracks in Stagnant Borated Water Volumetric Sl:98 Systems at PWR Plants.
0737 Leak testing and periodic visual examinations of systems outside of Visual, VT-2 CS primaiy containment which could contain highly radioactive fluids during CV a serious transient or accident (NUREG 0737). FC GW 06 PS RH SI GL8805 Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Visual, VT-2 RC Pressure Boundary Components In PWR Plants.
Exelon Byron Station 7.33 Revision 0
IS! Program Plan Units 1 & 2, Third Interval inservice Inspection Program Notes Inservice Inspection Summary Table Note # Note Summary 1 lSl snubber visual examinations are performed in accordance with the ASME OM Code, Subsection ISTD Program. The number of Byron Station Units 1,2, and 0 (Common) suppoils identified includes snubbers for the visual examination of the integral and nonintegral attachments per Paragraphs IWF-5200(c) and IWF-5300(c). The snubbers are scheduled and administratively tracked In the ISl Program; however, the ASME OM Code, Subsection ISTD Program will be the mechanism for actually performing the visual examinations scheduled within the lSl Program. For a detailed discussion of the snubber program, see Section 4.2.
2 The Unit 1 populatIon counts include those components that are common to both units (typically designated as ~Commorfor Unit 0. These Common components are referenced In Table 7.1-1 following a + symbol to designate the Common Unit 0.
3 Valve bolting is characterized by one entry per valve, pump, piping flanges, or vessel manways not by the actual total number of bolts or studs.
When the examination is required for a given items bolting, all bolts shall be Inspected. The reactor vessel closure head studs, nuts, and washers (54 total for each item) are examined during more than one Inspection Period. The number of separate examinations for each item identifies the population of these components.
4 The RHR Heat Exchanger nozzles at Byron Station are designed with reinforcing plates Internal to the heat exchanger (See Relief Request l3R-07 for a configuration detail). Typically, these reinforcing plates are on the outside of the nozzle making the nozzle-to-shell weld inaccessible for examination. ASME Section Xl Item Numbers C2.32 and C2.33 cover examination requirements for these cases; however, they do not address configurations when the reinforcing plate Is internal.
For this case, Byron Station has classified these welds as Item Number C2.21 since the nozzles do have reinforcing plates, and the nozzle-to-sheD weld is accessible for volumetric examination. In addition, Byron Station has submitted Relief Request l3R-07 that addresses the limited volumetric coverage and commits to performing a surface examination on all the nozzles of this type.
5 The population counts reported represents the number of non-exempt circumferential welds. Longitudinal welds are also subject to examination, but actual counts are not reported here. Byron Station examines the portion of the longitudinal weld that falls within the Intersecting circumferential weld examination volume.
6 Subsection IWC, Table IWC-2500-1, Examination Category C-B, Item C2.22 requires volumetric examination of the nozzle inner radii of nozzles without reinforcing plates in vessels with nominal thickness> 1/2 in. The main steam nozzle was designed with an internal multiple venturi type flow restrictor with an equivalent throat diameter of 16 inches. This design Is used to limit the flow in the event of a postulated steam line break.
This design does not utilize a radius nozzle as described in Figures IWC-2500-4(a) and (b,) and therefore is not considered as a Examination Category C-B, Item Number C2.22 component.
Exelon Byron Station 7-34 - - Revision 0
IS! Program Plan Units 1 & 2, Third Interial Inservice Inspection Program Notes inservice Inspection Summary Table Note # Note Summary 7 Exam lnptlon requirements of Cateciorv E-A comoonents Includes all unique identified inspectable surface areas, i.e., Each penetration Is one component (total 158).
Bolted Connections: Each connection bolt group is counted as 1 Item (I.e., 20 bolt flange connection equals 1 Item).
Examination requirements of Cateoorv L-A comDonents Counted three main Areas (Exterior wall, Exterior Dome, and Tendon gallery ceiling)
Examination requirements of Cateaorv L-B components Equals total number of bearing plates (each bearing plate includes Anchorage hardware and surrounding concrete)
Includes (4) Distinct Areas:
Horizontal Wall Tendons 402 bearing plates Dome Tendons 240 bearing plates Upper Vertical Tendons 162 bearing plates Lower Vertical Tendons 162 bearing plates (Total) (966 bearing plates) 8 For the Third Inspection Interval, Byron Stations Class 1 and 2 piping inspection program will be governed by risk-Informed regulations. The RISI Program methodology Is described in the EPRI Topical Reports TR-i 12657, Rev. B-A. TR-1006937, Rev. 0-A, and Code Case N-578-i. The RISI Program scope will be implemented as an alternative to the 2001 Edition through the 2003 Addenda of the ASME Section XI examination program for Class 1 B-F and B-J welds and Class 2 C-F-i and C-F-2 welds In accordance with 10 CFR 50.55a(a)(3)(i).
9 ExamInation requirements for Class I and 2 pIping structural elements within the RISI Program are determined by the various degradation mechanisms present at each individual piping structural element See EPRI Topical Reports TR-1 12657, Rev. B-A, TR-1 006937, Rev. 0-A, and Code Case N-578-1 for specific exam method requirements.
10 For the Third Inspection Interval, the RISI Program scope has been expanded to include welds in the BER piping, also referred to as the HELB region, which includes several non-class welds that fall within the BER augmented inspection program. All BER augmented welds will be evaluated under the RISI methodology and will be integrated into the RISI Program under the 10 CFR 50.59 change process. Additional guidance for adaptation of the RISI evaluation process to BER piping is given in EPRI TR-1006937 Rev. 0-A. Thus, these welds will be categorized and selected for examination in accordance with the EPRI Topical Reports TR-112657, Rev. B-A, TR-1006937, Rev. 0-A, and Code Case N-578-1_in lieu of the original commitment to NUREG 0800 in UFSAR Section 3.6.2.
Exelon Byron Station
- - 7-35 Revision 0
IS! Program Plan Units 1 & 2, Third Inteival Inservice Ins )ectlon Program Notes lnservice Inspection Summary Table Note # Note Summary 11 Bolted connections examined per Item E1.1 1 require a VT-3 exam once per interval and each time the connection is disassembled during a scheduled El .11 exam. Additionally, a VT-i exam shall be performed it degradation or flaws are identified during the VT-3 exam. These modifications are required by 10 CFR 50.55a(b)(2)(ixXG) and 10 CFR 50.55a(b)(2)(lx)(H).
12 Item E4.l 1 requires VT-f visual examination In lieu of Detailed Visual examination, as modified by 10 CFR 50.55a(b)(2)Qx)(G).
13 The ultrasonic examination acceptance standard specified In IWE-3511.3 for Class MC pressure-retaining components must also be applied to metallic liners of Class CC pressure-retaining components, as modified by 10 CFR 50.55a(b)(2XIx)(I).
14 Per 10 CFR 50.55a(b)(2)(xxl)(A), Table IWB-2500-1 examination requirements, the provisions of Table IWB-2500-1, Examination Category B-D, Items B3.120 and B3.140 in the i998 Edition must be applied when using the 1999 Addenda through the Latest edition and addenda, and requires that a visual examination with enhanced magnification may be performed on the Inside radius section in place of an ultrasonic examInation.
15 Per 10 CFR 50.55a(b)(2)(xxi)(C), Table IWB-2500-1 examination requirements, the provisions of Table IWB-2500-1, Examination Category B-K, Item B10.10, of the 1995 Addenda must be applied when using the 1997 Addenda through the latest edition and addenda incorporated by reference in Paragraph (bX2) of this section.
Exelon Byron Station 7-36 Revision 0
IS! Program Plan Units 1 & 2, Third Interial 7.2 SNUBBER INSPECTiON
SUMMARY
TABLES The foflowing Tables 7.2-1 and 7.2-2 provide a summary of the ASME OM Code, Subsection ISTD, Snubber examinations and testing for the Third Inspection Interval at Byron Station Units 1, 2, and 0 (Common).
The format of the Snubber Inspection Summary Tables is as depicted below and provides the folløwing information:
I ASME Ii O&M ARTICLE 1 I I RE QUIREM I I I I O&M CODE I D ESCRIP11 ON EXAM ENTS f TOTALS Ii FREQUENCY NOTES
~ SUBSECTiON NUMBER ~
~ (1) (2) J (~) ~ (4) J (5) (8) (7)
(1) ASME O&M Code Subsection:
Provides the applicable Code for Operation and Maintenance of Nuclear Power Plants (O&M) subsection number and a description as obtained from ISTD. Only applicable subsections to Byron Station are Identified.
(2) O&M Article Number.
Provides the article numberas identified in ISTD. Only those article numbers applicable to Byron Station are Identified.
(3) Article Number
Description:
Provides the article description as Identified in ISTD. Identifies the methods selected to be performed at Byron Station.
(4) Exam Requirements:
Provides the examination and test method(s) required by ISTD.
(5) Totals:
Provides the total number of snubbers that pertain to that article of ISTD.
Note that the total number of snubbers are subject to change after completion of plant modifications and design changes.
(6) Frequency:
Provides the frequency for examinations and testing as addressed in ISTD and approved ISTD Code Cases.
(7) Notes:
Provides a listing of program. notes applicable to the ISTD article number. If a program note number Is identified, see the corresponding program note at the end of the Table 7.2-2.
Exelon Byron Station 7-37 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 1 & 0 Snubber Inspection Summary Table 7.2-1 ASME O&u *~iCLE EXAM 08CM CODE SUBSECTiON NUMBER DESCRIPTiON REQUIREMENTS TOTALS FREQUENCY NOTES ISTD ISTD-4200 Accessible and In-Accessible Snubbers (1 populatIon) Visual, VT-3 228 Once every 1 Snubber 10 Years Examinations ISTD ISTD-5200 10% Functional Test Plan Functional 68 Every Outage 2 Snubber Type 1 Snubbers (PSA-1/4, PSA-1/2) Testing Testing iO% Functional Test Plan . FunctIonal 132 Every Outage 2 Type 2 Snubbers (PSA-1, PSA-3, PSA-lO) Testing 10% Functional Test Plan Functional 9 Every Outage 2 Type 3 Snubbers (PSA-35, PSA-100) Testing 10% Functional Test Plan Functional 8 Every Outage 2 Type 4 Snubbers (Paul Munroe Steam Generator Snubbers) Testing 10% Functional Test Plan Functional 11 Every Outage 2 Type 5 Snubbers (LISEGA 30 SerIes) Testing Exe!on Byron Station
- - - - 7-38 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Unit 2 Snubber Inspection Summary Table 7.2-2 ASME 08CM ARTICLE 08CM CODE SUBSECTiON NUMBER DESCRIPTION TOTALS FREQUENCY NOTES REQUIREMENTS ISTD ISTD-4200 Accessible and In-Accessible Snubbers (1 population) Visual. VT-3 317 Once every 1 Snubber 10 Years Examinations ISTD ISTD-5200 10% FuncljonaJ Test Plan Functional 61 Every Outage 2 Snubber Type 1 Snubbers (PSA-1/4, PSA-1/2) Testing Testing 10% Functional Test Plan Functional 226 Every Outage 2 Type 2 Snubbers (PSA-1, PSA-3, PSA-lO) Testing 10% FunctIonal Test Plan Functional 14 Every Outage 2 Type 3 Snubbers (PSA-35, PSA-100) Testing 10% Functional Test Plan Functional 8 Every Outage 2
. Type 4 Snubbers (Boeing Steam Generator Snubbers) Testing 10% Functional Test plan FunctIonal 8 Every Outage 2 Type 5 Snubbers (USEGA 30 Series) Testing Exelon Byron Station 7-39 Revision 0
!SI Program Plan Units 1 & 2, Third Interval Snubber Program Notes Snubber Inspection Summary Table 7.2-2 NOte# Note Summary 1 Examinations perlormed per Code Case OMN-13, Requirements for Extending Snubber lnservice Visual Examination Interval at LWR Power Plants.
2 Per ISTD 2001 Edition through the 2003 Addenda. Article ISTD-5240 Test Frequency.
Exelon Byron Station 7-40 Revision 0
IS! Program Plan Units I &2,Thirdlnteival 8.0 RELIEF REQUESTS FROM ASME SECTION Xl This section contains relief requests written per 10 CFR 50.55a(a)(3)(i) for situations where alternatives to ASME Section Xl requirements provide an acceptable level of quality and safety; per 10 CFR 50.55a(a)(3)Qi) for situations where compliance with ASME Section Xl requirements results in a hardship or an unusual difficulty without a compensating increase In the level of quality and safety; and per 10 CFR 50.55a(g)(5)(iii) for situations where ASME Section Xl requirements are considered impractical.
The following NRC guidance was utilized to determine the correct 10 CFR 50.55a Paragraph citing for Byron Station relief requests. 10 CFR 50.55a(a)(3)(i) and 10 CFR 50.55a(a)(3)(ii) provide alternatives to the requirements of ASME Section XI, whIte 10 CFR 50.55a(g)(5)(iiI) recognizes situational impracticalities.
10 CFR 50.55a(a)f3)ffl: Cited in relief requests when alternatives to the ASME Section XI requirements which provide an acceptable level of quality and safety are proposed. Examples are relief requests which propose alternative NDE methods and/or examination frequency.
10 CFR 5.55a(a~(3~(lU:Cited in relief requests when compliance with the ASME Section Xl requirements is deemed to be a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Examples of hardship and/or unusual difficulty include, but are not limited to, excessive radiation exposure, disassembly of components solely to provide access for examinations, and development of sophisticated toohng that would result In only minimal increases in examination coverage.
10 CFR 50.55p(QW5I(IIfl: Cited in relief requests when conformance with ASME Section Xl requirements is deemed impractical.
Examples of impractical requirements are situations where the component would have to be redesigned, or replaced to enable the required inspection to be performed.
An index for Byron Station relief requests is included in Table 8.0-1. The 13R-XX relief requests are applicable to ISI, SPT, and CISI.
The following relief requests are subject to change throughout the inspection interval.
Exelon Byron Station 8-1 Revision 0
IS! Program Plan Units I & 2, Third Interval TABLE 8.0-1 RELIEF REQUEST INDEX Sheet I of2 RELIEF REVISION DESCRIPTION OF RELIEF REQUEST!
NRC APPROVAL
SUMMARY
1 2
3 REQUEST DATE STATUS I3R-01 1 Submitted (ISI & CISI) Synchronization of Ten-Year ISI Intervals between Unit I 9/12/05 and Unit 2 for Class 1, 2, and 3. In addition, alignment of Containment
. Inservice Inspection (CISI) Ten-Year Intervals for Class MC and CC with
~ the synchronized Unit I and 2 Ten-Year ISI Interval. SubmItted separately on 11/08/05.
l3R-02 0 Submitted (151) Alternate Risk-Informed Selection and Examination Criteria for 9/12/05 Category B-F, B-J, C-F-I, and C-F-2 Pressure Retaining Piping Welds.
l3R-03 0 Submitted (151) Limited Volumetric Examination of the Pressurizer Surge Nozzle-9/12/05 to-Vessel Head Weld and Surge Nozzle Inside Radius Section.
13R-04 0 Submitted (151) LimIted Volumetric Examination of Residual Heat Removal Heat
. 9/12/05 Exchanger Nozzle-to-Vessel Welds and Nozzle Inside Radius Section.
13R-05 0 Submitted (ISI) Limited Surface Examination of Centrifugal Charging (CV) Pumps, 9/12/05 ContaInment Spray Pumps, and Residual Heat Removal Pumps Attachment Welds.
I3R-06 0 SubmItted (ISI) Repair of Control Rod Drive Mechanism (CRDM) Canopy Seal 9/12/05 Welds in Accordance with IWA-4000.
l3R-07 0 Drafted (SPT) Alternative Examination Requirements of ASME Section XI, IWA-9/12/05 5244, Buried Piping.
13R-XX 0 Drafted (1St) Alternate Rules for the Inservice Inspection of the Pressurizer 9/12/05 SeIsmic Lug Welds.
I3R-XX 0 Drafted (151) Limited Examinations on Pressurizer Spray, Safety, and Relief 9/12/05 Nozzle-to-Vessel Welds.
- 13R-XX 0 Drafted (ISI) Limited Volumetric Examination of Reactor Pressure Vessel Head-9/12/05 to-Flange Weld.
I3R-XX 0 Drafted (ISI) Limited Volumetric Examination of Reactor Vessel Circumferential 9/12/05 Shell Welds.
13R-XX 0 Drafted (151) Limited Volumetric Examination of the Reactor Vessel Outlet 9/12/05 Nozzle-to-Vessel Welds.
13R-XX 0 Drafted (P01 & ISI) Alternative Requirements Dissimilar Metal Piping Welds 9/12/05 Subject to Examination Using Procedures, Personnel, and Equipment
~ Qualified to ASME Section XI, Appendix VIII, Supplement 10 Criteria.
I3R-XX 0 Drafted (POt & ISI) Alternative Requirements for Implementation of Appendix 9/1 2/05 VIII, Supplements 2 and 10 as Coordinated by Supplement 14.
I3R-XX 0 Drafted (PDI & ISI) Alternative Requirements to Appendbc VII of ASME Section 9/12/05 Xl, Vll-4240, Annual Training.
l3R-XX 0 Drafted (P01 & ISI) Alternative requirements to Appendix VIII, Supplement 4, 9/12/05 Qualification Requirements for the Clad/Base Metal Interface of Reactor Vessel.
Note 1: The NRC grants relief requests pursuant to 10 CFR 50.55a(g~6XI)when Coderequirements cannot be met and proposed alternatIves do not meet the crltetia of 10 CFR 50.55(aX3). The NRC authorizes relief requests pursuant to 10 CFR 50.55a(aX3Xi) if the proposed alternatives would provide an acceptable level of quality and safety or under (3)QI) If compliance with the specified requirements would result In hardship or unusual dIfficulties ~4thout a compensating increase in the level of Exelon Byron Station 8-2 Revision 0
IS! Program Plan Units 1 & 2, Third Interval Note 2: ThIs column represents the status of the latest revision. Relief Request Status Options:
Authorized Approved foruse In an NRC SEA (See Note 1); Granted Approved for use In an NRC SER (See Note 1);
Authorized Conditionally Approved for use in a NRC SEA that Imposes certain conditions; Granted Conditionally Approved for use In a NRC SER that in~iposescertain conditions; DenIed Use denied In a NRC SEA; Expired Approval for relief has expired; Withdrawn- Relief has been withdrawn by the station; Not Required The NRC has deemed the relIef unnecessary in an SER or RAI; Cancelled. Relief has been cancelled by the station prior to issue; Drafted Drafted relief awaiting submittal and/or pending approval; and Submitted- Relief has been submitted to the NRC by the station and is awaiting approval Note3: The revision listed is the latest revision of the subject relief request. The date this revision became effective Is the date of the approving SEA that Is listed in the fourth column ofthe table. The date noted In the second column Is the date of the ISI Pro~am Plan revision when the relIef request was Incorporated Into the document.
Exelon Byron Station 8-3 Revision 0
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST l3R-02 RevisIon 0
( Page 1 of 5)
Request for Relief for Alternate Risk-informed Selection and Examination Criteria for Category B-F, B-J, C-F-i, and C-F-2 Pressure Retaining Piping Welds In Accordance with 10 CFR 50.55a(a)(3X1) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: 1 and 2 Examination Category: B-F, B-J, C-F-i, and C-F-2 item Number: B5.1O, B5.40, B5.70, B9.1 1, B9.21, B9.22, B9.31, B9.32, B9.40, C5.11, C521, C5.30, C5.41, C5.51, C5.61, C5.70, and C5.81
Description:
Alternate Risk-informed Seiection and Examination Criteria for Category B-F, B-J, C-F-I, and C-F-2 Pressure Retaining Piping Welds Component Number: Pressure Retaining Piping 2.0 APPUCABLE CODE EDITION AND ADDENDA:
The lnservice Inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, 2001 Edition through the 2003 Addenda.
3.0 APPUCABLE CODE REQUIREMENT:
The following Code requirements are paraphrased from the 2001 Edition through the 2003 Addenda of ASME Section XI.
Table IWB-2500-1, Examination Category B-F, requires volumetric and surface examinations on all welds for Items B5.10, B5.40, and B5.70.
Table IWB-2500-1, Examination Category B-J, requires volumetric and/or surface examinations on a sample of welds for items B9. 11, B921, B9.22, B9.31, 89.32, and 89.40. The weld population selected for inspection includes the following:
- 1. All terminal ends in each pipe or branch run connected to vessels.
- 2. All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed either of the following limits under loads associated with specific seismic events and operational conditions:
- a. primary plus secondary stress intensity range of 2.4Sm for ferntic steel and austenitic steel.
- b. cumulative usage factor U of 0.4.
- 3. All dissimilar metal welds not covered under Category B-F.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST I3R-02 RevIsion 0 (Page 2 of 5)
- 4. Additional piping welds so that the total number of circumferential butt welds, branch connections, or socket welds selected for examination equals 25% of the circumferential butt welds, branch connection, or socket welds in the reactor coolant piping system. This total does not include welds exempted by IWB-1220 or welds in Item No. B9.22.
- 5. A 10% sample of PWR high pressure safety injection system circumferential welds in piping ~ NPS 11/2 and < NPS 4 shall be selected for examination. This sample shall be selected from locations determined by the Owner as most likely to be subject to thermal fatigue.
Table IWC-2500-1, Examination Categories C-F-i and C-F-2 require volumetric and/or surface examinations on a sample of welds for Items C5.1 1, C5.21, C5.30, C5.4i, C5.51, C5.61, C5.70, and C5.81. The weld population selected for inspection includes the following:
- 1. Welds selected for examination shall include 7.5%, but not less than 28 welds, of all dissimilar metal, austenitic stainless steel and high alloy welds (Category C-F-i) or of all carbon and low alloy steel welds (Category C-F-2) not exempted by IWC-1 220. (Some welds not exempted by IWC-1 220 are not required to be nondestructively examined per Examination Categories C-F-i and C-F-2.
These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) The examinations shall be distributed as follows:
- a. the examinations shall be distributed among the Class 2 systems prorated, to the degree practicable, on the number of nonexempt dissimilar metal, austenitic stainless steel and high alloy welds (Category C-F-i) or carbon and low alloy welds (Category C-F-2) In each system;
- b. within a system, the examinations shall be distributed among terminal ends, dissimilar metal welds, and structural discontinuities prorated, to the degree practicable, on the number of nonexempt terminal ends, dissimilar metal welds, and structural discontinuitles in the system; and
- c. within each system, examinations shall be distributed between line sizes prorated to the degree practicable.
4.0 REASON FOR REQUEST:
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative utilizing Reference 1 along with two enhancements from Reference 4 will provide an acceptable level of quality and safety.
As stated in Safety Evaluation Report Related to EPRI Risk-Informed lnservice inspection Evaluation Procedure (EPRI TR-1i2657, Revision B, July 1999)
(Reference 2):
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST 13R-02 RevIsion 0 (Page 3of5)
The staff concludes that the proposed AISI program as described in EPRI TA-i 12657, Revision B, is a sound technical approach and will provide an acceptable level of quality and safety pursuant to 10 CFR 50.55a for the proposed alternative to the piping lSl requirements with regard to the number of locations, locations of inspections, and methods of inspection.
The initial Byron Station RlSl Program was submitted during the Second Period of the Second Interval for Unit 1 and during the First Period of the Second Interval for Unit 2.
This initial RlSl program was developed in accordance with EPRI TR-1 12657, Revision B-A, as supplemented by Code Case N-578-1. The program was approved for use by the NRC via a Safety Evaluation as transmitted to Exelon on February 5, 2002 (Reference 5).
The transition from the 1989 Edition to the 2001 Edition through the 2003 Addenda of ASME Section Xl for Byron Stations Third Interval does not impact the currently approved Risk-informed 151 evaluation process used in the Second Interval, and the requirements of the new Code edition/addenda will be implemented as detailed in the Byron Station iSI Program Plan.
The Risk Impact Assessment completed as part of the original baseline RISI Program was an implementation/transition check on the initial impact of converting from a traditional ASME Section Xl program to the new RISI methodology. For the Third Interval lSl update, there is no transition occurring between two different methodologies, but rather, the currently approved RISI methodology and evaluation will be maintained for the new interval. As such, the original risk impact assessment is not a necessary element of the implementing process and is not required to be continually updated.
As an added measure of assurance, any new systems, portions of systems, or components being included in the RlSl Program for the Third Interval will be added to the Risk Impact Assessment performed during the previous interval. These components will be addressed within the evaluation at the start of the new interval to assure that the new Third Interval RlSl element selection provides an acceptable overall change-in-risk when compared to the old ASME Section Xl population of exams which existed prior to the implementation of the first RISI Program.
The actual evaluation and ranking procedure including the Consequence Evaluation and Degradation Mechanism Assessment processes of the currently approved (Reference 5) RlSl Program remain unchanged and are continually applied to maintain the Risk Categorization and Element Selection methods of EPRI TA-i 12657, Revision B-A. These portions of the RISI Program are reevaluated as major revisions of the site PRA occur and modifications to plant configuration are made. The Consequence Evaluation, Degradation Mechanism Assessment, Risk Ranking, and Element Selection steps encompass the complete living program process applied under the Byron RISI Program.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST l3R-02 RevIsion 0 (Page 4 of 5) 5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:
The proposed alternative originally implemented in the Risk Informed lnservice Inspection Plan, Byron Station Units 1 and 2 (Reference 3), along with the two enhancements noted below, provide an acceptable level of quality and safety as required by 10 CFR 50.55a(a)(3)Q). This original program along with these same two enhancements is currently approved for Byron Stations Second Inspection Interval as documented in Reference 5.
The Third Interval RISI Program will be a continuation of the current application and will continue to be a living program as described in the Reason For Request section of this relief request. No changes to the evaluation methodology as currently implemented under EPRI TA-i i 2657, Revision B-A, are required as part of this interval update. The following two enhancements will continue to be implemented.
In lieu of the evaluation and sample expansion requirements In Section 3.6.6.2, RiSI Selected Examinations of EPRI TA-i 12657, Byron Station will utilize the requirements of Subarticle -2430, Additional Examinations contained in Code Case N-578-1 (Reference 4). The alternative criteria for additional examinations contained in Code Case N-578-i provides a more refined methodology for implementing necessary additional examinations.
To supplement the requirements listed in Table 4-1, NSummary of Degradation-Specific inspection Requirements and Examination Methods~of EPRI TA-112657, Byron Station will utilize the provisions listed in Table 1, ExaminatIon Category A-A, Risk-Informed Piping Examinations contained in Code Case N-578-i (Reference 4). To implement Note 10 of this table, paragraphs and figures from the 2001 Edition through the 2003 Addenda of ASME Section Xl (Byron Stations code of record for the Third Interval) will be utilized which parallel those referenced in the Code Case for the 1989 Edition. Table 1 of Code Case N-578-i will be used as It provides a detailed breakdown for examination method and categorization of parts to be examined.
The Byron Station RISI Program, as developed in accordance with EPRI TA-i 12657, Rev. B-A (Reference 1), requires that 25% of the elements that are categorized as High risk (i.e., Risk Category i, 2, and 3) and 10% of the elements that are categorized as Medium risk (i.e., Risk Categories 4 and 5) be selected for Inspection.
For this application, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI TA-i 12657 while the guidance for the examination method and categorization of parts to be examined are provided by the EPRI TA-i 12657 as supplemented by Code Case N-578-i.
In addition to this risk-informed evaluation, selection, and examination procedure, all ASME Section Xl piping components, regardless of risk classification, will continue to receive Code required pressure testing as part of the current ASME Section XI program. VT-2 visual examinations are scheduled in accordance with the Byron Station pressure testing program, which remains unaffected by the RlSl program.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third !ntenaI 10 CFR 50.55a REUEF REQUEST 13R-02 RevIsion 0 (Page 5 of 5) 6.0 DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the third inspection interval for Byron Station Units 1 and 2.
7.0 PRECEDENTS~
Similar relief requests have been approved for:
Byron Station Second Inspection Interval Relief Request 12R-40 was authorized per SEA dated 2/5/02. The Third Inspection Interval Relief Request will utilize the identical RISI methodology that was previously approved in the Second Inspection Interval.
Dresden Station Fourth Inspection Interval Relief Request 14R-02 was authorized per SEA dated 9/4/03.
Quad Cities Station Fourth Inspection Interval Relief Request 14A-02 was authorized per SEA dated 1/28/04.
8.0 REFERENCES
~
- 1) Electric Power Research Institute (EPRI) Topical Report (TR) 112657 Rev. B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure, December 1999
- 2) W. H. Bateman (NRC) to G. L. Vine (EPRI) letter dated October 28, 1999 transmitting Safety Evaluation Report Related to EPRI Risk-Informed lnservice inspection Evaluation Procedure (EPRI TR-1 12657, Revision B, July 1999)
- 3) Initial Risk-Informed lnservlce Inspection Evaluation Byron Nuclear Power Station Units 1 and 2 (Dated August 2000)
- 4) American Society of Mechanical Engineers (ASME) Code Case N-578-1, Risk-Informed Requirements for Class 1, 2, or 3 PIping, Method B
- 5) A. J. Mendiola (NRC) to 0. D. Kingsley (Exelon) letter dated February 5,2002 transmitting Safety Evaluation of Second Interval Risk-Informed Inservice Inspection Program Relief Request Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-03 RevIsIon 0
( Page 1 of 5)
Request for RelIef for Hardship Or Unusual DIfficulty WIthout Compensating Increase In Level Of Quality Or Safety LImited Volumetric ExamInation of the Pressurizer Surge Nozzle-to-Vessel Head Weld and Surge Nozzle insIde Radius SectIon In Accordance wfth 10 CFR 50.55a(aX3)(ll) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: i
Reference:
IWB-2500, Table 1WB-2500-1 Examination Category: B-D Item Number: B3.1 10(2001 Edition through the 2003 Addenda) and B3.120 (1998 Edition with No Addenda per 10 CFA 50.55a(b)(2)(xxi)(A))
Description:
Limited Volumetric Examination of the Pressurizer Surge Nozzle-to-Vessel Head Weld and Surge Nozzle Inside Radius Section Component Number: 1RY-Oi-S, PN-0i and 1RY-01-S, PN-01-NIR (Unit 1) 2RY-01 -S/PN-01 and 2RV-Oi -S, PN-01 -NIR (Unit 2)
Drawing Number. I PZR-i -ISI (Unit 1) and 2PZR-1-lSl (Unit 2) 2.0 APPUCABLE CODE EDITION AND ADDENDA:
The inservice Inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, 2001 Edition through the 2003 Addenda.
Per 10 CFR 50.55a(b)(2)(xxi)(A), the provisions of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Item B3.120 (inspection Program B) In the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in Paragraph (b)(2) of this section.
3.0 APPUCABLE CODE REQUIREMENT:
The following Code requirements are paraphrased from the 200i Edition through the 2003 Addenda of ASME Section XI.
Table IWB-2500-i, Examination Category B-D, Item Numbers B3. 110 and B3. 120 require a 100% volumetric examination of Pressurizer Nozzle-to-Vessel Welds and Pressurizer Nozzle Inside Radius Section as detailed in Figure IWB-2500-7(b).
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-03 RevIsion 0 (Page 2 of 5) 4.0 REASON FOR REQUEST:
Pursuant to 10 CFR 50.55a(a)(3)(Ii), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The Byron Station Unit i and 2 Pressurizers include a single surge nozzle, which is welded to the lower head as shown in Figure 1. In order to perform the code required volumetric examinations on the nozzle-to-vessel weld and the nozzle inside radius section, the outer surface of the lower vessel head must be accessible for proper surface preparation and ultrasonic scanning.
The lower head is normally covered by a 4 inch thick, multi-layered stainless steel insulation which was not designed for removal. In order to remove the insulation, the 78 heater penetration cables shown in Figure 2 would have to be disconnected. In addition, each of the 78 convection stops, which are riveted to the Insulation, would have to be cut to facilitate the insulation removal per Figure 3.
The radiation exposure to plant personnel for the insulation removal, surface preparation, and examination is estimated to be 30 person-rem, based on an area dose rate of lOOmR/hour.
Even with the insulation removed, full volumetric examination coverage of the nozzle-to-vessel weld cannot be achieved. The surge nozzle geometry limits ultrasonic transducer contact, and thus scanning on the nozzle side of the weld is impractical.
On the vessel side of the weld, the heater penetrations obstruct scanning such that only a small percentage of the weld volume could be captured.
Very limited volumetric examination of the nozzle Inside radius section is achievable from the outside surface of the pressurizer with the insulation removed. The blend region would not be accessible to allow for an adequate surface preparation and examination. A limited exam would be possible if scanning was performed from the nozzle side; however, due to the complex geometry of the nozzle, the resulting coverage would provide very limited data from which to assess the condition of the inside radius.
Volumetric examination of the nozzle-to-head weld and nozzle inside radius section is also not practical from the vessel inside surface. The inside surface is accessible only by removing the manway. The radiation exposure for the removal and reinstallation of the manway Is estimated to be approximately 2 person-rem. In addition, the internal baffle plates would obstruct access to the debris screen and surrounding inside surfaces of the nozzle, thus prohibiting a volumetric examination and the alternative enhanced visual examination allowed by 10 CFR 50.55a(b)(2)(xxi)(A).
Based on the above information, the code required volumetric examination of the pressurizer nozzle-to-vessel lower head weld and associated nozzle inside radius section is deemed impractical. Even partial compliance with the specified requirements would result in hardship or unusual difficulty without a compensating Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST I3R-03 RevIsion 0 (Page 3of5) increase in the level of quality and safety. The personnel radiation hazards associated with limited data obtained by partial volumetric examination is not justified.
5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:
The pressurizer surge nozzle-to-vessel weld will be volumetrically examined if the lower head insulation is removed for any reason.
In addition, a VT-2 examination during system pressure testing per Examination Category B-P will be performed on the Pressurizer each refueling outage to verify leaktight integrity of these areas.
6.0 DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the third inspection interval for Byron Station Units 1 and 2.
7.0 ~EcEDENTS:
Similar relief requests have been approved for:
Byron Station Second Inspection Interval Relief Request l2R-03 was authorized per SEA dated 12/30/98.
Braidwood Station Second Inspection Interval Relief Request l2R-08 was granted per SEA dated 1/6/00.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50..55a RELIEF REQUEST 13R-03 RevIsion 0 (Page 4 of 5)
Debris Blend Region Screen FIGURE 2:
Vessel Centerline Distance to 1st Heater Surge Nozzle and Ring Heater Elements 1st Ring: 20 Heater Elements 2nd RIng: 26 Heater Elements 3rd Ring: 32 Heater Elements Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST 13R-03 RevIsIon 0 (Page 5 of 5)
Heater Pipe Case Pop-Rivet Sliding Convection Stop (78 RequIred)
Field Installed PZR 6
Pivot Point for Seal FIGURE 3:
Insulation Details Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST l3R-04 RevisIon 0
( Page 1 of 6)
Request for Relief for Alternate Risk-Informed ExamInatIon Criteria Limited Volumetric Examination Of Residual Heat Removal Heat Exchanger Nozzle-to-Shell Welds In Accordance with 10 CFR 50.55a(a)(3Xl) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: 2
Reference:
Table IWC-2500-1 Examination Category: C-B item Number: C2.21 and C2.22
Description:
Limited Volumetric Examination Of Residual Heat Removal Heat Exchanger Nozzle-to-Shell Welds and Nozzle Inside Radius Section Component Number~ 1 RH-02-AA/RHXN-01, 1 RH-02-AAJRHXN-02, 1 RH-02-AB/RHXN-01, 1 RH-02-AB/RHXN-02 (Unit 1) 2RH-02-AA/RHXN-01, 2RH-02-AA/AHXN-02, 2RH-02-AB/RHXN-01, 2RH-02-AB/RHXN-02 (Unit 2)
Drawing Number: 1RHX-1-ISI, Sheet 1 of 1 (UnIt 1) 2RHX-1-lSl, Sheet 1 of 1 (Unit 2) 2.0 APPUCABLE CODE EDITION AND ADDENDA:
The Inservice Inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, 2001 Edition through the 2003 Addenda.
3.0 APPLICABLE CODE REQUIREMENT:
The following Code requirements are paraphrased from the 2001 Edition through the 2003 Addenda of ASME Section Xl.
Table IWC-2500-1, Examination Category C-B, item Number C2.21 requires a surface and volumetric examination of Nozzle-to-Shell Welds for Nozzles without Reinforcing Plate in Vessels> 1/2 inch Nominal Thickness per Figures IWC-2500-4(a), (b), and (d).
Table IWC-2500-1, Examination Category C-B, Item Number C2.22 requires a volumetric examination of the Nozzle Inside Radius Section for Nozzles without Reinforcing Plate In Vessels> 1/2 inch Nominal Thickness per Figures IWC-2500-4(a),
(b), and (d).
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-04 RevisIon 0 (Page 2 of 6) 4.0 REASON FOR REQUEST:
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.
Component Configuration ConsIderations The Residual Heat Removal Heat Exchangers were fabricated with a nominal wall thickness of 0.875 inch and 14 inch diameter inlet and outlet nozzles that are 0.375w nominal wall thickness. As shown in Figure 1, the subject configuration Is best characterized as a fillet welded nozzle with an internal reinforcement pad. This configuration is not represented in the examination figures in IWC-2500-1 for Category C-B nozzles. The configuration is similar to that shown in Figure 1WC-2500-4(c),
except for the internal location of the reinforcing pad. Conservatively, the examination requirements for the RHR Heat exchanger (RHRHX) nozzles have been specified using Examination Figure IWC-2500-4(d).
Due to the geometrical constraints of this nozzle design, the ultrasonic examination of nozzle-to-vessel welds (item C2.21) will not achieve 90% coverage. The ultrasonic examination performed from the nozzle outside surface would be obstructed by the reinforcement fillet weld iocated directly above the nozzle-to-vessel weld and the adjacent features on the shell-side of the nozzles (shell-to-flange and the shell-to-lower head welds). This fillet weld restricts inspection transducer movement and limits available examination angles. Based on previous data and coverage plots, it is estimated that 98.26% of the examination volume could be reached In the axial direction and 0% with the limited circumferential scans. The total scanning percentage achievable would be less than 50%. (See Figure 2 of this report for scan coverage plots.)
Design and Operational ConsIderations A finite element analysis was also performed and submitted to the USNRC Staff for review (See Section 8.0 References) in support of earlier relief requests at both Byron and Braidwood Stations. The results of this analysis showed that the inside diameter (l.D.) of the nozzle is in compression and the outside diameter (O.D.) is in tension.
Consequently, any service-induced flaw would be expected to initiate at the O.D. of the nozzle where the weld membrane stresses are in tension. Performance of surface examinations each inspection period will provide the best means for detection of expected service induced flaws and provide assurance that a service Induced defect will be identified prior to component failure. Ultrasonic examinations of the RHRHX nozzle-to-vessel weld will not provide detection capabilities of expected service-induced flaws beyond that provided by surface examination. Additionally, continued performance of ultrasonic examinations would require extensive resources, unnecessary radiation exposure to the examiners, and significant cost without a commensurate increase in quality or public safety.
Furthermore, Technical Basis LTR-PAFM-03-24, prepared by Westinghouse in August 2003 in support of an ASME Section Xl Code action, concludes, the regenerative and Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-04 RevIsion 0 (Page 3 of 6) residual heat exchangers are carefully designed and constructed to ASME Code rules.
The weld regions of these components have not been designed for volumetric inspection, and such inspections are time consuming and can be extremely dose intensive.
These heat exchangers do not have a severe duty cycle, and service experience has been good. The design transients for the vessels are very minimal because the component only operates during the shutdown phase of a fuel cycle. Considering the low safety significance of these heat exchangers and the large flaw tolerance, continuation of the volumetric and surface examinations results in a hardship without a commensurate increase in the level of quality and safety.
Unobstructed Available Examination Techniques The outside surfaces of all of these nozzle-to-vessel welds are accessible for surface technique examinations due to the internal location of the reinforcing pads. in lieu of the ASME Section Xl volumetric examinations required on the RHR HX C2.21 nozzle welds of only one of the like heat exchangers, the station will take advantage of the accessibility of these welds for surface examination and the entire weld population of RHR HX C2.21 nozzle welds will each be examined once over the interval.
Also, due to the unique configuration of the nozzle reinforcing pads being on the internal surface, the nozzle inner radius (Item C2.22) is inaccessible for examination.
The Inside corner of the reinforcing pads themselves could become accessible if the heat exchanges were ever disassembled and would be treated as the exam area should this access from the inside become available for other maintenance or repair reasons.
Finally, a visual (VT-2) examination of each heat exchanger, nozzle, and associated piping is performed three times per interval (each inspection Period per ExamInation Category C-H).
Based on this information, reasonable assurance of the continued inservice structural integrity of the subject welds will be achieved through the proposed alternative examinations.
5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:
An ASME Section Xl surface examination will be performed once per interval on each nozzle-to-vessel weld of the Byron Station RHR Heat Exchangers.
In addition, when disassembly of a heat exchanger is conducted for maintenance or repair purposes, a visual (VT-i) examination will be performed. The exam will be on one inlet and one outlet nozzle inner radii in one heat exchanger per unit and will be performed either directly or remotely, to the extent practical, once in the interval.
All other ASME Section Xl requirements pertaining to the RHA Heat Exchangers will continue to receive the Code required examinations. Vessel shell weld volumetric examinations, vessel support examinations, and pressure testing (VT-2 once during Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST 13R-04 RevIsIon 0 (Page 4of 6) each period) are performed and scheduled in accordance with the Byron Station Inservice inspection Program.
6.0 DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the third inspection interval for Byron Station Units 1 and 2.
7.0 PRECEDENTS
Similar relief requests have been approved for:
Byron Station Second inspection Interval Relief Request 12R-05 was authorized per SEA dated 1/13/98.
Braidwood Station Second Inspection Interval Relief Request i2R-07 was authorized per SEA dated 9/1 0/99.
8.0 REFERENCES
Harold D. Pontious, Jr. (CornEd) letter to USNAC Document Control Desk, Supplemental Information Regarding the Fracture Mechanics Evaluation of Residual Heat Removal System Heat Exchanger Inlet and Outlet Nozzle to Shell Welds, dated November 9, 1994.
Denise M. Saccomando (CornEd) letter to USNRC Document Control Desk Supplement to Fracture Mechanics Evaluation of Residual Heat Removal System Heat Exchanger Inlet and Outlet Nozzle to Shell Welds, dated December 20 1994.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-04 RevIsion 0 (Page 5 of 6)
RHR Vessel Wall 0 1 5/8 Filliet r Dimensions Shown Are Nominal 0.875 T
Reference:
Joseph Oat Corporation Drawing #5621 Vertical Residual Heat Exchanger Details.
Reinforcement Pad 1.250 T See Detail RHR Nozzle A 3/8 ODFilliet 14O x 0.375 NomInal Walt V
A 5/8 Filllet 3/16 ID Flillet Shell 1/4 x 450 Axis Chamfer Corners Detail A:
Reinforcement Pad 20 J Not To Scale FIGURE 1:
RHR Vessel/Nozzle Configuration I I Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST l3R-04 RevisIon 0 (Page 6 of 6)
FIGURE 2:
Examination Requirements applied from Figure IWC-2500-4(d)
Reinforcement Plate Vessel NOTE: Transducer exit point offset 0.20 Shell from front edge of 700 and 0.10 of side edge of 450 transducer/wedge assembly a
Surface Weld Exam A-B Axial l~Leg G Inner Radius IS. ~ect,on Axial 2nd Leg
- S.
S. G-H /
0.745 I 0~o0.S. / / I, Nozzle ()
IS. ~, x..
I~ Hf~ Note: Weld ID surface ground flush.
Actual surface is more irregular than 0.745 Volumetric Weld Exam CD-EF shown here.
TABLE 1: Estimated Coveraqe of Ultrasonic Examination
- 450 Shear Circumferential: Clockwise 0.00%
- 450 Shear Circumferential: Counter-Clockwise 0.00%
700 Shear Axial: Nozzle-to-Shell Direction 96.51 %
~70°Shear Axial: Shell-to-Nozzle Direction (using Shell-side 2nd leg of beam) 100.00%
Accumulative Coverage 49.13%
- Due to the size of the fillet weld, the circumferential beam is unable to acquire the examination volume. Transducer exit point is beyond the E F side of the examination volume.
- The equivalent to a Shell-to-Nozzle direction is achieved using the reflected 2~leg of the Nozzle-to-Shell scan.
The required volume for the Inner Radius Section cannot be achieved from the outside surface of the vessel. The interface between the vessel shell and inside reinforcement plate will not transmit the ultrasonic beam.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST I3R-05 Revision 0
( Page 1 of 4)
Request for Relief for Alternative RequIrements for the Limited Surface Examination of Centrifugal Charging (CV) Pumps, ContaInment Spray Pumps, and Residual Heat Removal Pumps Attachment Welds In Accordance with 10 CFR 50.55a(aX3XI) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: 2
Reference:
IWC-2500, Table IWC-2500-1 Examination Category: C-C Item Number: C3.30
Description:
Limited Surface Examination of Centrifugal Charging (CV)
Pumps, Containment Spray Pumps, and Residual Heat Removal Pumps Attachment Welds Component Numbers: 1/2CS-01 -PA & 1/2CS-01 -PB, CSP E-01, CSP E-02, and CSP E-03 1/2CV-01-PA & 1/2CV-01-PB, CVP E-01, CVP E-02, CVP E-03, and CVP E-04 1/2RH-01-PA & 1/2RH-01-PB, RHP E-01, RHP E-02, and RHP E-03 Drawing Numbers: 1VCT-1 -151 (Unit 1) and 2VCT-1-ISI (Unit 2) for CS Pumps 1RHP-1-ISI (Unit 1) and 2RHP-1-lSl (Unit 2) for CV and RH Pumps 2.0 APPLICABLE CODE EDITION AND ADDENDA:
The lnservice inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, 2001 Edition through the 2003 Addenda.
3.0 APPLICABLE CODE REQUIREMENT:
The following Code requirements are paraphrased from the 2001 Edition through the 2003 Addenda of ASME Section XI.
Table IWC-2500-1, Examination Category C-C, Item Number C3.30 requires a 100%
surface examination of pump welded attachments per Examination Figure IWC-2500-5.
4.0 REASON FOR REQUEST:
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.
Due to the design of the Centrifugal Charging Pumps, Containment Spray Pumps, and Residual Heat Removal Pumps support lugs, portions of the associated attachment Exe/on Byron Station
IS! Program Plan - -~ Units 1 & 2, Third Interval -
10 CFR 50.55a REUEF REQUEST t3R-05 Revision 0 (Page 2of4) welds are inaccessible for the code required surface examination. The inaccessible areas are shown in Figures 1 and 2. As detailed in these figures, the portion of the subject weld within the recess between the pumps and the support lug does not provide sufficient clearance to perform a surface examination. The concrete support pedestal also limits access to lower portions of the attachment weld. These obstructions can not be removed without destructive activities or redesigning the pump supports.
Because the subject welds are not full penetration welds, performance of an alternative visual (VT-i), examination on the inaccessible weld length (in addition to the required surface exams) will provide satisfactory assurance of the structural integrity of these welds. In addition, a VT-2 examination during system pressure testing per Examination Category C-H will also be performed on the Centrifugal Charging Pumps, Containment Spray Pumps, and Residual Heat Removal Pumps each inspection period to verify leak tight integrity of these components. Based on this information, reasonable assurance of the continued inservice structural Integrity of the subject welds will be achieved.
5.0 PROPOSED A%.TERNATIVE AND BASIS FOR USE:
The Code required surface examination will be performed on the accessible portions of the subject welds. in addition, a visual, VT-i examination will be performed on the portions of the subject welds that are inaccessible for surface examination.
6.0 DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the third inspection interval for Byron Station Units 1 and 2.
7.0 PRECEDENTS
Similar relief requests have been approved for Byron Station Second Inspection Interval Relief Request l2R-06 was authorized per SER dated 1/13/98.
Byron Station First Inspection Interval Relief Request NR-13 was granted per SER dated 12/6/91.
Braidwood Station Second Inspection Interval Relief Request l2R-02 was authorized per SEA dated 1/6/00.
Exelon Byron Station
!S! Program Plan Units 1 & 2, Third lnteria!
10 CFR 50.55a REUEF REQUEST 13R-05 Revision 0 (Page 3of4)
_____CONCRETE SUPPORT INACCESSIBLE AREAS VIEW A-A VIEW B-B A
~ ~
CVP E-01 CVP E-02 A CVP E-03 CVP E-04 II I!
~\
B B FIGURE 1: CV Pump Attachment Welds Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST I3R-05 RevIsIon 0 (Page 4 of 4)
WELDED ATTACHMENT PUMP VIEW A-A CONCRETE SUPPORT INACCESSIBLE AREAS PUMP CASING DISCHARGE NOZZLE CSP E-01 RHP E-01 FIGURE 2: CS and RH Pump Attachment Welds Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST l3R-06 RevisIon 0 (Page 1 of 5)
Request for Relief for AlternatIve Requirements to the Repair/Replacement of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds In Accordance with IWA-4000 In Accordance with 10 CFR 50.55a(a)(3)(I) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: 1
Reference:
IWA4000 Examination Category: N/A Item Number: N/A
Description:
Repair/Replacement of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds in Accordance with IWA-4000 Component Number. Reactor CRDM Canopy Seal Welds Class 1 Appurtenance to the Reactor Vessel.
2.0 APPLICABLE CODE EDmON AND ADDENDA:
The lnservice InspectiOn program is.based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, 2001 Edition through the 2003 Addenda.
3.0 APPUCABL.E CODE REQUIREMENT:
The following Code requirements are paraphrased from the 2001 Edition through the 2003 Addenda of ASME Section Xl.
The CRDM assemblies were designed and fabricated to the ASME Section III, 1974 Edition through summer, 1974 Addenda.
1WA-4000 of ASME Section Xl requires that repairs be performed in accordance with the owners original construction Code of the component or system, or later editions and addenda of the Code. The canopy seal weld is described in Section Ill and a repair to this weld would require the following activities:
- a. Excavation of the rejectable indications,
- b. A surface examination of the excavated areas,
- c. Re-welding and restoration to the original configuration and materials, and
- d. Final surface examination.
Exelon Byron Station
IS! Program P!an Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST l3R-06 RevisIon 0 (Page 2 of 5) 4.0 REASON FOR REQUEST:
The principal issues leading to this relief request are the excavation of the existing weld, the accompanying radiation dose received during the excavation and examination activities, and the weld material used for the repair or replacement.
Due to the nature of the flaw, the excavation of the leaking portion of the weld would necessitate a cavity that extends. completely through wall. A liquid penetrant examination (PT) of this cavity is required to verify the removal of the rejectable flaw or to verify that the flaw is removed or reduced to an acceptable size. This PT examination would depositthe penetrant materials onto the inner surfaces of the component. This material would not be readily removable prior to re-welding due to the inaccessibility of the insidesurface. The remaining penetrant material would introduce contaminants.to~thenew weld metal and reduce the quality of the repair weld. The configuration of thecanopy assembly would prevent the establishment and maintenance of an adequate back-purge during the welding process and would further reduce the quality of the repaired weld.
The CRDM canopy seal welds are located above the reactor vessel closure head, which is highly congested. and. subject to high radiation levels. The high radiological dose associated with strictcomptiance to these requirements would be contrary to the intent of the as low as reasonably achievable (ALARA) radiological controls program.
Most of the repair activitieswouidbe performed remotely using robotic equipment.
This will reduce the.radiationexposureto personnel involved in the welding process.
However, the required excavationand PT examinations would necessitate hands-on access to the canopy weldand. are estimated to result in a total occupational radiation dose of 1.688 person-Rem pecCRDM canopy seal weld. The excavation and PT examinations are activitlesthat would not be required if granted relief from these requirements and, thus, represent the estimated occupational radiation dose savings.
This dose estimate Is comprised. of the following:
ACTIVITY DOSE (PERSON-REM)
MANUAL EXCAVATION OFFLAW&
Access/egress to pertorm the excavatIon (0.035 per trip, 1 trip required) 0.035 Performance of the excavation (total residence time of fIve minutes) 0.090 PT OF EXCAVATED AREAS~
Access/egress to perform the:exarnlnatlon (0.035 per trip, 5 trips required) 0.175 Performance of the PT examination (total residence time often minutes) 0.180 FINAL PT OF NEW WELD:
Access/egress to perform theexamination (0.035 per trip, 5 trips required) 0.175 Performance of the PTexamlnatlon (total residence time of ten minutes) 0.180 Dose estimates are based on survey.
TOTAL EXPOSURE FOR ALL ACTiViTiES #02-2489, dated 9/20/02 performed on the Byron Station UnIt 2 0.835 head canopy area.
Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST l3R-06 RevisIon 0 (Page 3of 5)
IWA-4200 requires that the repair material conform to the original design specification or Section Ill. In this case, the replacement material would have the same resistance to stress corrosion cracking as the original material. Use of the original material does not guarantee that the repaired component will continue to maintain leakage integrity throughout the intended life of the item.
Applicable portions of ASME Code Case N-504-2, Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Section Xl, Division 1, will be used as guidance for repair by weld overlay to provide a new leakage barrier. In lieu of performance of PT examinations of CRDM seal weld repairs or replacement, a 5X or better magnification visual examination will be performed after the welding is completed. In addItion, Alloy 52 nickel-based weld repair material will be used rather than austenitic stainless steel as required by Code Case N-504-2.
Alloy 52 nickel-based weld repair material was selected rather than austenitic stainless steel for the repair because of its resistance to stress corrosion cracking.
Consequently, the ferrite requirements of Code Case N-504-2 do not apply. The suitability of the replacement material has been evaluated and is determined to be compatible with the existing component and will provide a leakage barrier for the remainder of the intended life of the CRDM.
The alternative method of repair is being requested to facilitate contingency repair efforts during future outages within the third ten-year inservice inspection interval. The alternative nondestructive examination method is being requested to facilitate examination of either a repair or replacement of a CRDM canopy seal weld during the third ten-year inservice inspection interval.
Industry experience with failure analyses performed on leaking canopy seal welds removed from service at other plants has attributed the majority of the cases to transgranular stress corrosion cracking (SCC). The size of the opening where the leakage occurs has been extremely small, normally a few thousandths of an inch. The crack orientations vary, but often radiate outward such that a pinhole appears on the surface, as opposed to a long crack. The SCC results from exposure of a susceptible material to residual stress, which is often concentrated by weld discontinuities, and to a corrosive environment. A corrosive environment can form with water being trapped in the cavity behind the seal weld that is mixed with air initially in the cavity, resulting in a higher oxygen content than is in the bulk primary coolant.
5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE Following the guidance of Code Case N-504-2, the CRDM canopy seal weld flaws will not be removed, but an analysis of the repaired weldment has been performed using Paragraph (g) of the Code Case as guidance to assure that the remaining flaw will not propagate unacceptably. The canopy seal weld is not a structural weld, nor a pressure-retaining weld, but provides a seal to prevent reactor coolant leakage if the mechanicai joint leaks. The weld buildup is considered a repair in accordance with Exelon Byron Station
IS! Program Plan Units I & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST l3R-06 Revision 0 (Page4of5)
IWA-41 10. Applicability of the original Code of construction or design specification is mandated because the weid is performed on an appurtenance to a pressure-retaining component. The alternative CRDM canopy seal weld repair uses a gas tungsten arc welding (GTAW) process controlled remotely.
A visual examination of the repaired/replaced weld will be performed using methods and personnel qualified to the standards of ASME VT-i requirements. The visual examination will be performed using the welding equipment video camera with 5X or better magnification within several inches of the weld, qualified to ensure identification of flaws to assure an adequate margin of safety is maintained. The examination technique will be demonstrated to resolve a 0.001 thick wire against the surface of the weld. The repaired/replaced weld will be examined for quality of workmanship and discontinuities will be evaluated and dispositioned to ensure the adequacy of the new leakage bamer.
The automated GTAW weld repair and alternate VT-I examination methods result in significantly lower radiation exposure because the equipment is remotely operated after setup. A post-maintenance pressure test (VT-2) at nominal temperature and pressure will be performed.
Repair/replacement activities, using the process described in this relief request, shall be documented on the required NIS-2 / NIS-2A forms. This relief request will be identified on the NIS-2 I N$S-2A forms in iieu of an adopted or invoked ASME Code Case. The repair documents will be reviewed by the Authorized Nuclear Inspector, and maintained in accordance with the requirements for archMng permanent plant records.
6.0 DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the third inspection interval for Byron Station Units I and 2.
7.0 PRECEDENTS
Similar relief requests have been approved for:
Exelon Corporations Byron Nuclear Plant, by letter dated September 16, 2003; Carolina Power and Light Companys Shearon Harris Nuclear Power Plant, by letter dated November 6, 1998; Northern States Powers Prairie Island Nuclear Generating Station, by letter dated January22, 1999; Tennessee Valley Authoritys (TVA) Watts Bar Nuclear Plant, by letter dated August 25,1999; TVAs Sequoyah Nuclear Plant, by letter dated September 12, 2000; Pacific Gas & Electrics Diablo Canyon Power Plant, by letter dated June 5, 2001; and Exelon Byron Station
IS! Program Plan Units 1 & 2, Third Interval 10 CFR 50.55a REUEF REQUEST 13R-06 RevIsion 0 (Page 5 of 5)
STP Nuclear Operating Company~sSouth Texas Project Electric Generating Station, by letter dated November 5, 2002.
Exelon Byron Station
1SI Program Plan - Units 1 & 2, Third Inter/a!
9.0 REFERENCES
The references used to develop this Inservice Inspection Program Plan include:
- 1. Code of Federal Regulations, Title 10.
Part 50, Paragraph 2, Definitions, the definition of Reactor Coolant Pressure Boundary.
Part 50, Paragraph 50.55a, Codes and Standards.
Part 50, Appendix J, Option B.
SECY-96-080, Issuance of Final Amendment To 10 CFR 50.55a To Incorporate By Reference The ASME Boiler And Pressure Vessel Code, Section Xl, Division 1, Subsection IWE and IWL.
- 2. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1, Inservice Inspection of Nuclear Power Plant Components, 1989 Edition with No Addenda.
1995 EdItion through the 1995 Addenda 1995 Edition through the 1997 Addenda 1998 Edition with No Addenda 2001 Edition with No Addenda 2001 Edition through the 2003 Addenda.
- 3. ASME Boiler and Pressure Vessel Code, Section Ill, Division 1, Rules For Construction of Nuclear Power Plant Components, 2001 Edition through the 2003 Addenda.
- 4. ASME OM Code, Code For Operation and Maintenance of Nuclear Power Plants, 2001 Edition through the 2003 Addenda.
- 5. USAS B31 .1.0-1967, Power Piping.
- 6. Regulatory Guide 1.26, Revision 3, Quality Group Classifications andStandards for Water-, Steam-, and Radioactive Waste- Containing Components of Nuclear Power Plants.
- 7. Regulatory Guide 1.147, Inserice Inspection Code Case Acceptability, ASME Section XI, Division 1
- 8. Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code
- 9. NRC letter dated May 17, 1990, Stephen P. Sands, NRC to Thomas J. Kovach, Commonwealth Edison Company- Safety Evaluation of Containment Leak Chase Channels-Byron Station Unit Nos. 1 and 2, Braidwood Station Unit Nos. 1 and 2.
- 10. Byron Station UnIts 1 and 2 Updated Final Safety Analysis Report (UFSAR).
Exelon Byron Station 9-1 Revision 0
IS! Program Plan Units 1 & 2, Third Interval
- 11. Byron Station Technical Specifications, Limiting Conditions for Operation and Surveillance Requirements, with Amendments through Number 108.
- 12. Byron Station Technical Specifications, Bases.
- 13. Byron Station Technical Requirements Manual.
- 14. NRC NUREG 0737, dated November 1980, ClarIfication of TM! Action Plan Requirements.
- 15. Byron Station Procedures.
- 16. Exelon Corporate Procedures.
- 17. Byron Station Units 1 and 2 lSl Classification Basis Document Third Ten-Year Inspection Interval.
- 18. Byron Station Units 1 and 2 1St Selection Document Third Ten-Year Inspection Interval.
- 19. Branch Technical Position MEB 3-i, dated November 24, 1975, High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment.
- 20. Regulatory Guide 1.14, Revision 1, Reactor Coolant Pump Flywheel Integrity.
- 21. Regulatory Guide 1.137, RevIsion 1, Fuel-Oil Systems for Standby Diesel Generators.
- 22. EPRI Topical Report TA-i 12657, Rev. B-A, Final Report, Revised Risk-Informed Inservice Inspection Evaluation Procedure, December 1999.
- 23. NRC SEA related to EPRI Topical Report TA-i 12657, Rev. B, Final Report, Revised Risk-Informed Inservice Inspection Evaluation Procedure, July 1999, dated October 28, 1999.
- 24. CornEd Risk-Informed Inservice Inspection Project Definition of RIS! Scope for Byron Station Units 1 and2, dated April 17, 2000.
- 25. CornEd Risk-Informed Inservice Inspection Evaluation (Final Report) for Byron Station Units 1 and 2, dated August 8, 2000.
- 26. EPRI Topical Report TA-i 006937, Rev. 0-A, Extension of the EPRI Risk-Informed Inservice Inspection (RI-lSl) Methodology to Break Exclusion Region (BER)
Programs, August 2002.
Exelon Byron Station 9-2 Revision 0
IS! Program Plan Units 1 & 2, Third Interval
- 27. NRC SEA related to EPRI Topical Report TA-i006937, Rev. 0, Extension of the EPRI Risk-Informed Inservice Inspection (At-ISI) Methodology to Break Exclusion Region (BEA) Programs, dated June 27, 2002.
- 28. ER-AA-330, Conduct of lnservice Inspection Activities
- 29. ER-AA-330-00I,Section XI Pressure Testing
- 30. ER-AA-330-002, lnservice Inspection of Welds and Components
- 31. EA-AA-330-003, Visual Examination of Section Xl Component Supports
- 32. ER-AA-330-004, Visual Examination of Technical Specification Snubbers
- 33. ER-AA-330-005, Visual Examination of Section XI Class CC Concrete Containment Structures
- 34. ER-AA-330-006, Inservlce Inspection and Testing of The Pre-Stressed Concrete Containment Post Tensioning Systems
- 35. ER-AA-330-007, VIsual Examination of Section Xl Class MC Surfaces and Class CC Liners
- 36. ER-AA-330-009, ASME Section XI Repair/Replacement Program
- 37. ER-AA-330-01 0, Snubber Functional Testing
- 38. ER-AA-330-01 1, Snubber Service Life Monitoring Program Exelon Byron Station 9-3 Revision 0