ML20217H306

Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports

ML20217H306
Person / Time
Site:	Brunswick
Issue date:	04/16/1998
From:	Crider J, Gary Young CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20217H282	List: BSEP-98-0087, Forwards Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports. Third 10-Yr ISI Interval Common for Bsep,Units 1 & 2 ML20217H306
References
PROC-980416, NUDOCS 9804290347
Download: ML20217H306 (818)

Text

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CP&L CAROLINA POWER & LIGHT COMPANY l BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 AND 2 4Y ,#5 4M THIRD INSPECTION INTERVAL i

INSERVICE INSPECTION PROGRAM FOR CLASS 1,2, & 3 COMPONENTS AND THEIR SUPPORTS l REVISION O Prepared By: Jerry W. Crider Date #[/3/f6

/, ii Reviewed By: &4 med Authonzed Nuclear Inservice Inspjoux) 'N Date 8M/W '

Approved By: 1./ M Date / '/!El Supervisor - Equipment Performance /

Approved By: . OcS I N Date W/A <8 flanager Dit dk Engineering Support Cection O 4 l BSEP, Units 1 & 2, ISI Program l Revision 0 l Page 1 of 21 l

REVISION

SUMMARY

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. TABLE OF CONTENTS Paae No.

Re visio n S u m m a ry. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 List of Effective Pa g e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Ta ble of C o n te nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 4 1 n t rod u ct io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Peferences....................................................................................................5 Background......................................................................................................7 ASME Section XI Code, Edition and Addenda.. . ............................... ............ ... .. 8 Third Inspection Interval and Inspection Periods..... ... ................................... ...... 8 Code Classification of Components............. ...... ... .....................................9 Boundary of System Classification....... ... . ... ................ ......... . .... ......... .. ......... 9 -

Inservice Inspection (ISI) Prog ram....... .. . ... . ....... .... ... ....... ... . ......... ... ......... 10 C ode S u b sectio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 0

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Augmented Inspection Requirements............. ........ . ......... ........ ... .. .. ... ........ 15 Table 1, Relief Requests and Extent of Application...... ........... .. ..............16 Table 2, Code Cases and Extent of Application............................. ........................ 17 Table 3, Systems Subject to inspection and Exemption Applicability..... ... ........... 19 Table 4, Calibration Blocks... ........... . ...... . . . . . . . . . . . . . . .............................21 Appendix A, Requests for Relief Appendix B, Unit 1 Inspection Plan and Schedule Summary Tables Appendix C, Unit 2 Inspection Plan and Schedule Summary Tables t

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1 INTRODUCTION Section 55a, Codes and Standards, of Part 50 of Title 10 of the Code of Federal Regulations requires that each operating license for a boiling or pressurized water-cooled nuclear power facility be subject to the conditions in paragraph (g), inservice inspection Requirements. Paragraph (g)(4) of Section 55a requires that Class 1,2, and 3 components (including their supports) meet the requirements set forth in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Except for I design and access provisions and the preservice examination requirements, the rules and requirements of the ASME Section XI Code are to be met, to the extent practical, ,

within the limitations of design, geometry, and material of construction of the i components.

Paragraph (g)(4) of Section 55a also requires that inservice examination of components and system pressure tests conducted during successive Inspection Intervals comply with the requirements in the latest edition and addenda of the ASME Section XI Code incorporated by reference in paragraph (b)(2) of Section 55a on the date twelve months prior to the start of the interval. The third successive Inspection Interval for the Brunswick Steam Electric Plant (BSEP), Unit 1 and 2, will be effective on May 11,1998.

Accordingly, Carolina Power & Light Company (CP&L) has prepared this document, Brunswick Steam Electric Plant's Inservice Inspection Program for Class 1, 2, & 3  ;

Components and Their Supports, to comply with the requirements of the 1989 Edition  !

(no Addenda) of the ASME Section XI Code and the applicable limitation and mMfication listed in paragraph (b) of Section 55a. The 1989 Edition of the ASME Section XI Code was the latest edition and addenda incorporated by reference in paragraph (b)(2) of Section 55a on the date twelve months prior to the beginning of the Third Inspection Interval.

2 REFERENCES l

l' 2.1 Regulatory Documents 2.1.1 Section 55a (@55a), " Codes and Standards", of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.55a) 2.1.2 Part 50.2 of Title 10 of the Code of Federal Regulations (10 CFR 50.2) 2.1.3 Appendix A of Title 10 of the Code of Federal Regulations 2.1.4 Generic Letter 86-01, " Safety Concerns Associated with Pipe Breaks in the BWR Scram System" 2.1.5 Generic Letter 88-01, *NRC Position On IGSCC in BWR Austenitic Stainless Steel Piping" 2.1.6 Generic Letter 90-09, " Alternate Requirements for Determining the Interval for the Visual Inspection of Snubbers" 2.1.7 NUREG-0313,

• Material Selection and Processing Guidelines for BWR Boundary Piping Coolant Pressure," Revision 2 l BSEP, Units 1 & 2, ISI Program l Revision 0 l Page 5 of 21 l l

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2.1.8 NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking" 2.1.9 NUREG-0737,

• Integrity of Systems Outside Containment Likely to Contain Radioactive Material," Item lli.D.1.1 2.1.10 Regulatory Guide 1.150, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and inservice Examination" 2.1.11 Regulatory Guide 1.26, " Quality Group Classifications and Standards for Water , Steam , and Radioactive-Waste-Containing Components in Nuclear Power Plants," Revision 2 2.1.12 Regulatory Guide 1.147, " Inservice inspection Code Case Acceptability, ASME Section XI, Division 1" (latest approved revision) 2.1.13 Standard Review Plan, Section 5.2.1.1, " Compliance with the Code and Standard Rule,10 CFR 50.55a" 2.1.14 Standard Review Plan, Section 5.2.4,

• Reactor Coolant Pressure Boundary inservice Inspection and Testing" 2.1.15 Standard Review Plan, Section 6.6, " Inservice Inspection of Class 2 and 3 Components" 2.2 Code and Standards 2.2.1 ASME Section lll Code, " Rules of Construction of Nuclear Power Plant Components," 1965,1968, and 1986 Edition 2.2.2 ASME Section XI Code, " Rules for Inservice inspection of Nuclear Power Plant Components," 1974 Edition through the Summer 1975 Addenda, 1977 Edition through the Summer 1978 Addenda,1989 Edition (no Addenda) 2.2.3 ASME Code Cases, " Nuclear Components" 2.2.4 USA Standard (USAS) Code for Pressure Piping, B31.1.0, " Power Piping," 1967 and 1986 Edition 2.3 License Bases Documents 2.3.1 Safety Evaluation for the BSEP, Unit 1 and 2 2.3.2 BSEP, Unit 1 and 2 Technical Specifications 2.3.3 BSEP, Unit 1 and 2 Final Safety Analysis Report and Updated Final Safety Analysis Report 2.3.4 Corporate Quality Assurance Program 2.4 Plant Documents 2.4.1 Engineering Procedure, ENP-16, " Procedure For Administrative Control of Inservice Inspection Activities" 2.4.2 Calculation EEBNP-MISC-0B21-1009, "ASME Section XI Code Class 1 Line Exemption (lWB-1220)"

2.4.3 OBNP-TR-001, " Inservice inspection Technical Report" .

I 2.4.4 Plant Procedure, PLP-8, " Repair / Replacement Program" l BSEP, Units 1 & 2. ISI Program l Revision 0 l Page 6 of 21 l L

2.5 Correspondences 2.5.1 Letter from the Nuclear Regulatory Commission (NRC) to Carolina Power and Light (CP&L), Dated July 1,1985,

Subject:

Inservice Inspection Interval 2.5.2 Letter from CP&L to NRC, Dated March 6,1996,

Subject:

Second Inservice inspection interval Extension 3 BACKGROUND On February 7,1970, the Atomic Energy Commission issued the construction permits (Nos. CPPR-67 & CPPR-68) which authorized construction of the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. Along with the applicable Design Specifications, the Construction Codes used in the design and construction of the general category of pressure retaining components were the 1965 and 1968 Edition of ASME Section lil Code, the 1967 Edition of USAS B31.1.0, and/or the 1965 Edition of ANSI B31.7.

Following construction and testing, Unit 2 was placed in commercial operation in November 1975. In March of 1977, Unit 1 was placed in commercial operation.

Accordingly, the First inspection Interval began November 1975 for Unit 2 and March 1977 for Unit 1.

During the First inspection interval, the Inservice Inspection Program for Class 1,2, and 3 Components complied with the (1) 1970 Edition, (2) 1974 Edition with Summer 1975 Addenda, and/or (3) 1978 Edition with Summer 1978 Addenda of the ASME Section XI Code. Pursuant to 10 CFR 50.55a, the Edition and Addenda of the ASME Section XI Code was updated each inspection Period (i.e., every 40 months) during the First inspection Interval.

In July of 1985, a request to begin the Second Inspection Interval for Unit 1 and 2 on a common date was granted. Accordingly, the Second Inspection interval for both units began on July 10,1986. During the Second Inspection interval, the 1980 Edition with Winter 1981 Addenda of the ASME Section XI Code was used unless otherwise permitted.

in March of 1996, the Nuclear Regulatory Commission (NRC) was notified of Carolina Power and Light Company's (CP&L) intent to extend the Second Inspection interval for Units 1 and 2 to May 10,1998. The basis for the extension was the out of service time during the Second Inspection Interval.

The Third Inspection Interval for the BSEP, Units 1 and 2, will become effective on May 11,1998. Unless otherwise authorized, the Inservice inspection Program for Class 1,2,

& 3 components and their supports will comply with the applicable requirements of the 1989 Edition (no Addenda) of the ASME Section XI Code and the applicable limitation

< and modification listed in paragraph (b) of Section 55a.

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I l 4 ASME SECTION XI CODE, EDITION AND ADDENDA 4.1 For the Third Inspection Interval, CP&L has prepared the BSEP's, Unit 1 and 2, l

Inservice inspection (ISI) Program for Class 1, 2, & 3 Components and Their l Supports (hereafter referred to as the ISI Program) to comply with the applicable rules and requirements of the 1989 Edition (no Addenda) of the ASME Section XI Code (hereafter referred to the ASME Section XI Code).

4.2 CP&L has determined that conformance with certain ASME Section XI Code requirements for the Third Inspection interval is impractical, results in hardship or unusual difficulty, and/or that alternative requirements will provide an acceptable level of quality and safety. For this reason, requests for relief from the requirements of the ASME Section XI Code will be submitted for approval pursuant to 55a(a)(3)(i), @55a(a)(3)(ii), or 55a(a)(g)(5)(iii).

4.2.1 A list summarizing the requests for relief supporting the Third Inspection ,

Interval is provided in Table 1. A description of the relief, the basis for relief, and the proposed alternative for each of these requests are provided j in Appendix A.

4.3 Periodically, the ASME Committee approves Code Cases that provides alternatives to the requirements of the ASME Section XI Code. CP&L has identified several ASME Code Cases that may be implemented during the Third I Inspection Interval.

4.3.1 A list summarizing these ASME Code Cases is provided in Table 2. Those ASME Code Cases not authorized for usage in Regulatory Guide 1.147 will also be submitted as a Relief Request. For this reason, these ASME Code Cases will also be listed in Table 1.

l 5 THIRD INSPECTION INTERVAL AND INSPECTION PERIODS 5.1 The Third Inspection interval for BSEP, Unit 1 and 2, will become effective on May 11,1998, and will end on May 10,2008. The Third Inspection interval will comply l

with the applicable requirements of IWA-2432, inspection Program B, of the l ASME Section XI Code.

5.2 in accordance with the ASME Section XI Code, IWB-2412, IWC-2412, and IWD-2412, the Third Inspection Interval is divided into three successive inspection l Periods as determined by calendar years of plant service. The First, Second, and Third Inspection Period are three (3), tour (4), and three (3) years in length, respectively. The start and end dates for the three Inspection Periods are as follows:

First inspection Period: May 11,1998 to May 10,2001 l

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l Second Inspection Period: May 11,2001 to May 10,2005 l

Third Inspection Period: May 11,2005 to May 10,2008 6 CODE CLASSIFICATION OF COMPONENTS In accordance with the ASME Section XI Code, IWA-1400(a), CP&L has determined the appropriate Code classification for each pressure retaining component in Unit 1 and 2.

The rules for the classification of these components were developed employing the guidance outlined in the documents listed below.

6.1 Part 50.2 of Title 10 of the Code of Federal Regulations 6.2 Regulatory Guide 1.26, " Quality Group Classifications and Standards for Water ,

Steam , and Radioactive-Waste-Containing Components in Nuclear Power Plants" 6.3 Standard Review Plan, Section 5.2.1.1, " Compliance with the Code and Standard >

Rule,10 CFR 50.55a" 6.4 Standard Review Plan, Section 5.2.4, " Reactor Coolant Pressure Boundary Inservice Inspection and Testing" 6.5 Standard Review Plan," Inservice Inspection of Class 2 and 3 Components" 6.6 Safety Evaluation for the BSEP, Unit 1 and 2 6.7 BSEP, Unit 1 and 2, Final Safety Analysis Report and Updated Final Safety Analysis Report 6.8 Corporate Quality Assurance Program 7 BOUNDARY OF SYSTEM CLASSIFICATION 7.1 in accordance with the ASME Section XI Code, IWA-1400(a), CP&L has identified the system boundary for each class of components subject for inspection. Those systems and the identification of acronyms used are listed in Table 3.

7.2 The boundary classification for these systems are identified on BSEP's Piping and Instrument Diagrams (P&lDs) for Unit 1 and 2. A listing of the applicable P&lDs for each of these systems is provided in Table 3.

7.2.1 On each applicable P&lD, the boundary classification has been graphically identified with a bisected flag. The bisected flag illustrates the ASME t Section XI Code classification application on each side of the boundary. A l BSEP. Units 1 & 2. ISI Program l Revision 0 l Page 9 of 21 l u

1 character "1", "2", or "3", within the flag, specifies the applicable rules of the ASME Section Code which applies to the bounded system or subsystem.  ;

A "" within a flag or the absence of a flag indicates that the bounded system or portion thereof is not subject to the inservice inspection requirements of the ASME Section XI Code.

8 INSERVICE INSPECTION (ISI) PROGRAM 8.1 In accordance with the ASME Section XI Code, IWA-1400(c), CP&L has prepared the ISI Program for Class 1,2, and 3 components subject to examination or test. l The ISI Program includes the information outlined in IWA-2420, inspection Plan and Schedules, of the ASME Section XI Code. The guidance provided in Appendix F, Preparation of Inspection Plans, of the ASME Section XI Code was also followed to the extent practical.  ;

I 8.2 During the Third Inspection Interval, CP&L expects the ISI Program to be revised l periodically in response to such activities as incorporation of approved Relief Requests, design changes to the units, and/or regulatory changes. Accordingly, CP&L will revise the ISI Program to reflect these changes and maintain the updated ISI Program available for review. Unless requested, the revised ISI Program will not be re-filed with the appropriate authorities.

8.3 in accordance with the ASME Section XI Code, IWA-2110(a)(1), a detailed review of the ISI Program has been performed by an Authorized Nuclear Inservice Inspector (ANil). Future revisions to the ISI Program 611 be submitted to the ANil l for review as required by IWA-2110(a)(2.) i 9 CODE SUBSECTIONS 9.1 The Subsections of the ASME Section XI Code listed below are applicable to the ISI Program.

9.1.1 Subsection IWA - General Requirements Subsection IWA provides the general requirements for components subject to requirements of inservice inspection. Unless otherwise authorized, the requirements outlined i.1 this Suusection will be met during the Third Inspection Interval.

9.1.1.1 In accordance with IWA-1400(j), repair / replacement activities will be performed in accordance with an approved

! Repair / Replacement Program. Plant procedure, PLP-08, I

Repair / Replacement Program, defines the managerial and administrative controls for completion of repair / replacement activities.

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l 9.1.2 Subsection IWB - Requirements for Class 1 Components of Light-Water Cooled Power Plant Subsection IWB provides the rules and requirements for inservice inspection, repair, and replacement of Class 1 pressure retaining components and their integral attachments. Unless otherwise authorized, the rules and requirements outlined in this Subsection will be met during the l

Third Inspection Interval.

9.1.2.1 For the Third Inspection interval, CP&L will use the criteria specified in IWB-1220 for the exclusion of components from volumetric and surface examination requirements of IWB-2500.

The specific exemptions applied to each system, containing Class 1 1 components, are identified in Table 3. I I

9.1.2.2 Unit 1 and 2 components subject to examination and testing, as specified in Table IWB-2500-1, are identified in Appendix B and C, respectively. For each Examination Category, a summary table has been developed and provides the following applicable information by system: (1) Item No., (2) Code classification, (3) types of components, (4) examination or test method to be performed, (5) calibration blocks, (6) individual components or weldments subject to examination or test, (7) examination or test schedule, (8) reference to drawings locating the weld or component, and (9) identification of Relief Requests and/or ASME Code Cases being used.

9.1.2.3 The implementation schedule for the performance of examination and tests has been prepared for each applicable Examination ,

Category and is shown in Appendix B and C. A "Yes" identifies )

those components or weldments selected for examination during the appropriate inspection Period.

9.1.2.4 As permitted by 55a(b)(2)(ii), the extent of examination (i.e.,

number of welds to be examined) for Class 1 piping welds (i.e.,

Examination Category B-J) will be determined using the applicable requirements of Table IWB-2500 and Table IWB-2600 of the ASME Section XI Code,1974 Edition through the Summer 1975 Addenda.

9.1.2.4.1 Since @55a(b)(2)(ii) does not address the selection I process successive interval, the weldments selected for

[ examination during the Second Inspection Interval will be re-selected for the Third Inspection Interval to the extent practical. The re-selection of these weldments follows the intent of the ASME Section XI Code as l BSEP, Units 1 & 2, ISI Program l Revision 0 l Page 11 of 21 l l

l described in Footnote (2) of Table IWB-2500-1, l Category B-J. I 9.1.2.5 The calibration blocks used to support the volumetric examination of Class 1 weldments are listed in Table 4. The material specification and sizes for these calibration blocks are also provided in Table 4.

9.1.2.6 Weld overlay repairs are applied to various location in the Reactor Coolant Recirculation system in both Unit 1 and 2. Unit 1 has ten (10) Category E weld overlay repairs in service and Unit 2 has fourteen (14) Category E weld overlay repairs in service. These weld overlay repairs meet the applicable requirements outlined in Section 4.4.1 and 4.4.2 of NUREG-0313. Since their application, these repairs have been examined in accordance with l requirements specified in Generic Letter 88-01 and NUREG-0313. l Accordingly, CP&L has not included these weldments under l Examination Category B-J, Pressure Retaining Welds in Piping. '

Unless otherwise authorized, CP&L will continue examining these weldments in accordance with requirements specified in Generic Letter 88-01 and NUREG-0313.

9.1.3 Subsection IWC - Requirements for Class 2 Components of Light-Water Cooled Power Plant Subsection IWC provides the rules and requirements for inservice inspection, repair, and replacement of Class 2 pressure retaining components aria their integral attachments. Unless otherwise authorized, the rules and requirements outlined in this Subsection will be met during the Third Inspection Interval.

9.1.3.1 For the Third Inspection interval, CP&L will use the criteria specified in IWC-1220 for the exclusion of components from volumetric and surface examination requirements of IWC-2500.

The specific exemptions applied to each system, containing Class 2 components, are identified in Table 3.

9.1.3.2 Unit 1 and 2 components subject to examination and testing, as specified in Table IWC-2500-1, are identified in Appendix B and C, respectively. For each Examination Category, a summary table has been developed and provides the following applicable information by system: (1) Item No., (2) Code classification, (3) types of components, (4) examination or test method to be performed, (5) calibration blocks, (6 individual components or weldments subject to examination or test, (7) examination or test schedule, (8) reference to drawings locating the weld or l BSEP, Units 1 & 2. ISI Program l Revision 0 l Page 12 of 21 l L

component, and (9) identification of Relief Requests and/or ASME Code Cases being used. '

9.1.3.3 The implementation schedule for the performance of examination and tests has been prepared for each applicable Examination Category and is shown in Append x B and C. A "Yes" identifies those components or weldments selected for examination during the appropriate inspection Period.

9.1.3.4 The calibration blocks used to support the volumetric examination of Class 2 weldments are listed in Table 4. The material specification and sizes for these calibration blocks are also provided in Table 4.

9.1.4 Subsection IWD - Requirements for Class 3 Components of Light-Water Cooled Power Plant Subsection IWD provides the rules and requirements for inservice inspection, repair, and replacement of Class 3 pressure retaining components and their integral attachments. Unless otherwise authorized, the rules and requirements outlined in this Subsection will be met during the Third Inspection Interval.

9.1.4.1 For the Third Inspection Interval, CP&L will use the criteria specified in IWD-1220 for the exclusion of components from volumetric and surface examination requirements of IWD-2500.

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The specific exemptions applied to each system, containing Class 3 components, are identified in Table 3.

9.1.4.2 Unit 1 and 2 components subject to examination and testing, as ,

specified in Table IWD-2500-1, are identified in Appendix B and C, i respectively. For each Examination Category, a summary table  !

has been developed and provides the following applicable l information by system: (1) Item No., (2) Code classification, (3) types of components, (4) examination or test method to be performed, (5) individual components subject to examination or i test, (6) examination or test schedule, (7) reference to drawings locating the weld or component, and (8) identification of Relief Requests and/or ASME Code Cases being used.

9.1.4.3 The implementation schedule for the performance of examination and tests has been prepared for each applicable Examination l Category and is shown in Appendix B and C. A "Yes" identifies those components or weldments selected for examination during the appropriate inspection Period.

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9.1.5 Subsection IWF - Requirements for Class 1, 2, 3, and MC Comp Onent Supports of Light-Water Cooled Power Plant Subsection IWF provides the rules and requirements for inservice j inspection of Class 1, 2, and 3 component supports. Unless. otherwise l authorized, the rules and requirements outlined in this Subsection will be met during the Third Inspection Interval.

9.1.5.1 During the Third inspection Interval, the alternative requirements for ASME Code Case N-491 will be used for determining components supports subject to examination and for establishing the examination requirements for Class 1, 2, and 3 component

supports.

t 9.1.5.2 For the Third Inspection Interval, CP&L will use the criteria j specified in Code Case N-491 (-1230) for the exclusion of component supports from examination.

9.1.5.3 Unit 1 and 2 component supports subject to examination, as l specified in ASME Code Case N-491, are identified in Appendix B l and C, respectively. For Examination Category F-A, a summary table has been developed and provides the following applicable information by system: (1) Item No., (2) Code classification, (3) individual component supports subject to examination, (4) examination method to be performed, (5) examination schedule, (6) reference to drawings locating the component supports, and (7) identification of Relief Requests and/or ASME Code Cases being used.

9.1.5.4 The implementation schedule for the performance of examination has been prepared for each applicable Examination Category and is shown in Appendix B and C. A "Yes" identifies those component supports selected for examination during the appropriate Inspection Period.

9.2 The Subsections listed below are outside the scope of this ISI Program. These Subsections will be addressed in separate inspection or Testing Programs.

9.2.1 Subsection IWE - Requirements for Class MC Components of Light-Water Cooled Power Plant l

l 9.2.2 Subsection IWL - Requirements for Class CC Components of Light-Water Cooled PowerPlant 9.2.3 Subsection IWP - Inservice Testing of Pumps in NuclearPower Plants 9.2.4 Subsection IWV-Inservice Testing of Valves in Nuclear Power Plants l BSEP, Units 1 & 2, ISI Program l Revision 0 l Page 14 of 21 l l

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10 AUGMENTED INSPECTION REQUIREMENTS Unless otherwise authorized, CP&L will meet the applicable augmented requirements l contained in the documents listed below during the Third Inspection Interval.

10.1 10 CFR 50.55a(g)(6)(ii)(A), " Augmented Examination Of The Reactor Vessel" 10.2 Generic Letter 86-01, " Safety Concerns Associated with Pipe Breaks in the BWR Scram System" 10.3 Generic Letter 88-01, "NRC Position On IGSCC in BWR Austenitic Stainless Steel Piping" l

10.4 Generic Letter 90-09, " Alternate Requirements for Determining the Interval for the .

Visualinspection of Snubbers"

10.5 NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line l Nozzle Cracking" 1 )

10.6 NUREG-0737, " Integrity of Systems Outside Containment Likely to Contain Radioactive Material," item lil.D.1.1 10.7 Regulatory Guide 1.150, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examination" l

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TABLE 1 - RELIEF REQUESTS AND EXTENT OF APPICATION-( ;, , ISI Class Relief .. .

n 1

Request # Relief Roquest Title - 1 2 3 Remarks - ,< i

(

RR-1 Documentation Requirements for Inservice / / / This request for rehef to use Code Case N-532 was approved for (Rev. 0) Inspection, Repair, and Replacement use during the Second Inspection interval and is being re-submitted Activities (Code Case N 532) for approval pursuant to $55a(a)(3)(i)

RR-2 High Pressure Coolant injection (HP) Pump / This request for relief for the HP pump studs was approved for use (Rev. 0) Stud Examination during the Second inspection interval and is being re-submitted for approval pursuant to 55a(a)(3)(ii).

RR-3 inservice inspection interval Requirement / / / This request for rehef to use Code Case N-535 is being re.

(Rev. 0) (Code Case N-535) submitted for approval pursuant to $55a(a)(3)(i).  !

RR-4 Botting for Control Rod Housing / This request for rehef to use Code Case N-547 is being re-(Rev. 0) (Code Case N-547) submitted for approval pursuant to $55a(a)(3)(ii).

3-5 integrally Welded Support Attachments / This request for rehef to use Code Case N-509 was approved for (Rev. 0) (Code Case N-509) use during the Second Inspection interval and is being re-submitted

• or approval pursuant to $55a(a)(3)(it RR-6 Class 1 Longitudinal Piping Welds / This request for relef to use Code Case N-524 was approved for (Rev. 0) (Code Case N-524) use during the Second inspection interval and is being re-submitted for approval pursuant to 55a(a)(3)(ii)

RR-7 Reactor Pressure Vessel (RPV) Skirt / This request for relief for the RPV skirt support was approved for (Rev. 0) Support use dunng the Second inspection Interval and is being re-submitted for approval pursuant to $55a(g)(5)(iii)

RR-8 Snubber Testing and Examination / / / This request for rehef to test and examined snubbers in accordarice (Rev. 0) with Technical Specification is being submitted for approval pursuant to $55a(a)(3)(ii).

RR-9 Afternate Pressure Test Requirements for / / / This request for rehef to use Code Case N 416-1 was approved for (Rev. 0) Welded Repairs / Replacements use during the Second Inspection interval and is being re-submitted (Code Case N-416-1) for approval pursuant to $55a(a)(3)(ii).

RR-10 Alternate Requirements for 10 Year System / / / This request for rehef to use Code Case N-498-1 was approved for (Rev. 0) Hydrostatic Pressure Test use during the Second inspection interval and is being re-submitted (Code Case N-498-1) for approval pursuant to $55afa)(3)(ii).

RR-11 Pressure Test on Buned Piping / This request for re'ief for the testing of the Service Water buned (Rev. 0) piping is being submitted for approval pursuant to $5a(a)(3)(ii)

RR-12 Examination Category B-D, Examination / This request for rehef for hmited examination coverage is being (Rev. 0) Coverage submitted for approval pursuant to $55a(g)(5)(iii).

RR-13 Examination Category B-J, Examination / This request for relief for hmited examination coverage is being (Rev. 0) Coverage submitted for approval pursuant to $55a(g)(5)(iii).

RR-14 Examination Category C-F-2, Examination / This request for rehef for hmited examination coverage is being (Rev. 0) Coverage submitted for approval pursuant to $55afg)(5)(iii).

RR-15 Sequence of Component Examinations / / This request for rehef for the sequence of examination of (Rev. 0) components is being submitted for approval pursuant to l55a(a)(3)(ii).

RR-16 VT-2 Examination Personnel Qualifications / / / This request for rehef to use Code Case N-546 is being submitted (Rev. 0) (Code Case N-546) for approval pursuant to $55a(a)(3)(ii).

RR-17 Leakage at Bolted Connection / / / This request for rekef for the examination of bolted connections is (Rev. 0) being submitted for approval pursuant to $55a(a)(3)(ii).

RR-18 Transfer of Procedure Ouah6 cation / / / This request for rehef to use Code Case N-573 is being submitted (Rev. 0) Records (Code Case N-573) for approval pursuant to $55afa)(3)(i).

RR-19 Wall Thickness Restoration of Class 2 and / / This request for rehef to use Code Case N-561 is being submitted (Rev. 0) High Energy Class 3 Carbon Steel Piping for approval pursuant to $55a(a)(3)(i).

(Code Case N-561)

RR 20 Wall Thickness Restoration of Class 3 / This request for rehef to use Code Case N-562 is being submitted (Rev. 0) Moderate Energy Carbon Steel Piping for approval pursuant to $55a(a)(3)(i).

(Code Case N-562)

RR-21 Examination Categones with Less Than / / This request for rehef for Examination Categones with less than

} (Rev. 0) Three items or Welds three items or welds is being submitted for approval pursuant to l $55afa)(3)(ii).

} RR-22 Additional Examination of Class 1 / This request for rehef for Examination Categones with less than (Rev. 0) Components three items or welds is being submitted for soproval pursuant to

$55a(a)(3)(ii).

RR 23 Examination Category B.A, Examination / This request for rekef for hmited examination coverage is being (Rev. 0) Coverage submitted for approval pursuant to $55a(g)(5)(iii)

RR-24 Examination Category B-F, Examination / This request for rehef for hmited examination coverage is being (Rev. 0) Coverage submitted for approval pursuant to $55a(g)(5)(iii)

RR 25 Examination Category C-B, Examination / This request for rehef for hmited examination coverage is being (Rev. 0) Coverage submitted for approval pursuant to %55afo)(5)(iii).

l l BSEP, Units 1 & 2, ISI Program l Revision 0 l Page 16 of 21 l

_ _ _ _ _ _ _ _ _ . - -- w -- --Q

1 l TABLE 2 - CODE CASES AND EXTENT OF APPLICATION > v -

0~

.., , ,y + *

';, ISI Class , ,Lc Code" "

Case # Co'de Case Title '

1' 2' 3 Remarks / *

N-307-1 Revised Ultrasonic Examination Volume for Class 1 / This Code Case is authonzed for use per Regulatory Bolting When the Examinations are Conducted From Guide 1.147, the Center-Drilled Holes.

N-356 Certification Period for Levelill NDE Personnel / / / This Code Case is authonzed for use per Regulatory Guide 1.147.

N-416-1 Alternative Pressure Test Requirements for Welded / / / This Code Case was approved for use dunng the Repairs or installation of Replacement items by Second inspection interval and is being re-submitted Welding. Class 1,2, and 3 for approval (RR-9).

N432 Repair Welding Using Automatic or Machine Gas / / / This Code Case is authonzed for use per Regulatory Tungsten-Arc Welding Temper Bead Technique Guide 1.147.

N-435-1 Alternative Examination Requirements for / This Code Case is authonzed for use per Regulatory Vessels With Wall Thickness 2 in. Or Less Guide 1.147.

N-457 Qualification Specimen Notch Location for Ultrasonic / / This Code Case !s authonzed for use per Regulatory Examination of Bolts and Studs Guide 1.147.

N 458 Magnetic Particle Examination of Coated Matenals / / This Code Case is authonzed for use per Regulatory Guide 1.147.

l N-460 Attemative Examination Coverage for Class 1 and Class / / This Code Case is authonzed for use per Regulatory I Welds Guide 1.147.

N-461 Altem4W Rule', for Piping Calibration Block Thickness / / This Code Case is authonzed for use per Regulatory Guide 1.147.

N-463-1 Evaluation Procedures and Acceptance Cntena for / This Code Case is authonzed for use per Regulatory Flaws in Class 1 Ferritic Piping that Exceed the Guide 1.147.

Acceptance Standards of IWB-3514.2 N485-1 Eddy Current Examination of Coated Femtic Surfaces / / This Code Case is authorized for use per Regulatory as an Alternative to Surface Examination Guide 1.147.

N489 Altemative Rules for Levellli NDE Qualification / / / This Code Case is authonzed for use per Regulatory Examination Guide 1.147.

N-4901 Attemative Vision Test Requirements for Nondestructive / / / This Code Case is authonzed for use per Regulatory Examiners Guide 1.147.

N-491 Alternative Rules for Examination of Class 1,2,3, and / / / This Code Case is authonzed for use per Regulatory MC Component Supports of Light-Water Cooled Power Guide 1.147.

Plants E941 Pipe Specific Evaluation Procedures and Acceptance / This Code Case is authorized for use per Regulatory Cnteria for Flaws in Class 1 Ferntic Piping that Exceed Guide 1.147.

the Acceptance Standards of IWB-3514 2 N-495 Hydrostatic Testing of Releef Valves / / This Code Case is authonzed for use per Regulatory Guide 1.147.

N-498-1 Alternative Rules for 10-Year Hydrostatic / / / This Code Case was approved for use dunng the Pressure Testing for Class 1,2, and 3 Systems Second inspection interval and is being re-submitted for approval (RR-10).

N-503 Limited Certification of Nondestructive Examination / / / This Code Case is authorized for use per Regulatory Personnel Guide 1.147.

N-504 Alternative Rules for Repair of Class 1,2, and 3 / / / This Code Case is authorized for use per Regulatory Austenitic Stainless Steel Piping Guide 1.147.

N-509 Attemative Rules for the Selection and Examination of / This Code Case was approved for use dunng the Class 1,2, and 3 Integrally Welded Attachments Second Inspection interval and is being re-submitted for approval (RR-5).

N-524 Attemative Examination Requirements for Longitudinal / This Code Case was approved for use dunng the Welds in Class 1 and 2 Piping Second inspection interval and is being re-submitted for approval (RR-6).

N-532 Attemative Requirements to Repair and Replacement / / / This Code Case was approved for use dunng the Documentation Requirements and inservice Summary Second Inspection Interval and is being re-submitted Report Preparation and Submission as Required by for approval (RR-1).

IWA-4000 and IWA-6000 N-535 Attemative Requirements for Inservice / / / This Code Case is not authonzed for use per inspection Intervals Regulatory Guide 1.147 and for this reason, is being submitted for approval (RR-3).

N-546 Alternative Requirements for Qualifications of VT-2 / / / This Code Case is not authonzed for use per Examination Personnel Regulatory Guide 1.147 and for this reason, is being submitted for approval (RR-16).

l BSEP, Units 1 & 2, ISI Program l Revision 0 l Page 17 of 21 l b

I TABLE 2-CODE CASES AND EXTENTOF APPLICATION. m' j

ISI Class - '

l Code ..' .

Case # Code Case Title 2 3 Remarks -

N-547 Alternative Examination Requirements for Pressure / T his Code Case is not authonzed for use per Retaining Bolting of Control Rod Drive (CRD) Housings Regulatory Guide 1,147 and for this reason, is being submitted for approval (RR-4)

N 561 Alternative Requirements for Wall Thickness / / This Code Case is not authonzed for use per Restoration of Class 2 and High Energy 3 Carbon Steel Regulatory Guide 1,147 and for this reason, is being Paping submitted for approval (RR-19).

, N-562 Alternative Requirements for Wall Thtckness / This Code Case is not authonzed for use per

( Restoration of Class 3 Moderate Energy Carbon Steel Regulatory Guide 1.147 and for this reason, is being Piping submitted for approval (RR-20).

I N-573 Transfer of Procedure Quahfication Records Between / / / This Code Case is not authonzed for use per Owners Regulatory Guide 1,147 and for this rea1on, is being submitted for approvat (RR-18).

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01 3-0 SA106 GR.B 0.594" 10" l 014-B SA333 GR.1or 6 0.719" 10" l 016-0 SA333 GR.6 1.094" 14" l 017-8 A333 GR.6 1.375" 18" l 018-B SA 333 1.031* 20"

! 019-B A106 1 218" 24" t

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030-8 A106-68 GR B 0.375" 14" 031-B ASTM A106 0.375" 16" 034-B SA106 GR 8 1.650" 9" l 036-B SA106 GR B 0 950" 6" 039-B SA312 GR.304H 0.930" 6" 045-BR SA533 GR B 3 000" 15" x 6" 046-B SA312 TP316 3 020" 18" x 6" 047-B SA533 GR C 5 875" 27" x 9 500" 048-8 SB168-70 INCO 328 0 875" 13 750" j 051-B A312 0.337" 4" l 054-B SA182 GR. F316L 0 950" 15 750" 055-B A350 GR LF2 0 725" 10" 057-B SA508 CL2 8 000" 16" x 14" 059-B SA333 GR.6 0 844" 12" 060-B SA508-74 CL2 6.500" 20" x 12" l i C31-B SA106 GR B 0 843" 10" l 062-B SA106 GR B 0.843" 16" C33-0 SA106 GR B 0 562" 24" 036-B A:06 GR.B 1.530" 24" 068-B SA533 GR B 2020" 8 450" x 4.220" C39-B SA533 GR B 2 000" 15" x 6.100" 071-B SA516 GR.70 0 875" 10" x 6" 072-D SA516 GR.70 1.125" 17 x 6" 073-B SA106 GR.B 0 594" 8" 075-8 SA106 GR B 0 938" 14" 076-B SA106 GR.B 0 688" 12" 077-B SA106 GR B 0.750" 14" 078-B SA508 CL2 8 000" 20" x 12" 079-8 SA105 CL2 8.000" 7" x 7" 081-B SA193 GR B7 (4142) 3 000" 14"L 082-B SA106 GR.B 0.375" 20" OG3-B SB166 / A105 1.145" 13.250" 090-8 SA106 GR B 0432" 6" 091-B SA106 GR B 0 500" 8" 092-8 SA106 GR.B 0.375" 12" 096-B A106 GR.B 0 490" 20" 097-B A106 GR B 0.375" 24" l 114-8 SA376, 316NG 0.730" 12" 115-B SA376 TP316 1 000" 16" l

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l BSEP, Units 1 & 2. ISI Program l Revision 0 l Page 21 of 21 l L s

APPENDIX A, REQUESTS FOR RELIEF i

i i

i f

l

1 RELIEF REQUEST: RR-1 (Rav. 0)

SUBJECT:

DOCUMENTATION REQUIREMENTS FOR INSERVICE INSPECTION, REPAIR, AND REPLACEMENT ACTIVITIES (CODE CASE N-532)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the documentation requirements for inservice inspection, repsir, and replacement activities for Class 1, 2, and 3 components (including their supports).

This request for relief will apply to the documentation requirements at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Article IWA-6000 of the ASME Section XI Code,1989 Edition, requires the owner to prepare and submit the Owners Report for Inservice Inspection Form NIS-1, and the Owners Report for Repair or Replacements, Form NIS-2.

REQUESTED RELIEF: l Relief is requested from the requirements to prepare and submit the Owners Report for Inservice Inspection, Form NIS-1, and the Owners Report for Repair or Replacements, Form NIS-2 as required by Article IWA-6000 of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(i), Carolina Power and Light (CP&L) is requesting approval to implement alternative requirements to those specified in Article IWA-6000, Records and Reports. CP&L proposes to implement the alternative requirements outlined in ASME Code Case N-532, Alternative Requirements to Repair and Replacement Documentation Requirements and inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000.

l The alternative requirements outlined in ASME Code Case N-532 have been evaluated by CP&L, and CP&L has determined that implementation of these requirements will provide an acceptable level of quality and safety for the following reasons:

1. ASME Code Case N-532 provides alternative requirements for the documentation of l

inservice inspection, repair, and replacement activities for components (including their supports) that are classified ASME Code Class 1,2, and 3. Implementation of this ASME Code Case will still require the reviews and approvals by the Authorized Nuclear Inservice Inspection (ANil). In addition, CP&L will be required to prepare the Repair / Replacement Plan in accordance with IWA-6340 of the ASME Section XI Code,1992 Edition.

2. The alternative requirements of ASME Code Case N-532 simplifies reporting, particularly for repair and replacement activities, and reduces the frequency of summary reports from once per outage to once per Inspection Period. The implementation of this ASME Code Case will l Page 1 of 2 l

l

RELIEF REQUEST: RR-1 (Rsv. 0)

SUBJECT:

DOCUMENTATION REQUIREMENTS FOR INSERVICE INSPECTION, REPAIR, AND REPLACEMENT ACTIVITIES (CODE CASE N-532) significantly reduce man-hours being spent after each outage without jeopardizing the quality or availability of records.

3. CP&L considers the alternative requirements of this ASME Code Case an improvement over the reports required by the 1989 Edition of the ASME Section XI Code. For example, Form OAR-1, includes the status of examination credited and percent credited by Examination Category. This type of information provides a more comprehensive report on the status of BSEP's Inservice inspection Program.

4. ASME Code Case N-532 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on December 12, 1994. This approval signifies the requirements outlined in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants.

5. ASME Code Case N-532 was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second Inspection Interval. As specified in the Safety Evaluation Report, the implementation of this ASME Code Case would provide an acceptable level of quality and safety at BSEP, Unit 1 and 2. The alternative requirements evaluated by the NRC for use during the Second Inspection Interval has not changed.

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the alternative requirements of ASME Code Case N-532. Accordingly, CP&L will prepare and submit the Owners Activity Report for Inservice Inspection, Form OAR-1 and the Repair / Replacement Certification Record, Form NIS-2A in accordance with the alternative requirements of ASME Code Case N-532. The other applicable requirements of Article IWA-6000 of the ASME Section XI Code,1989 Edition, will be met.

REFERENCES:

1.ASME Code Case N-532, Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000 (Approved Date: December 12,1994)

2. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) and 1992 Edition

3. NRC Letter to CP&L,

Subject:

Approval of Code Case N-532 as an Alternative to the Required Inservice Inspection Report Requirements (TAC NOS. M94200 and M94201)

Page 2 of 2 j

RELIEF REQUEST: RR-2 (Rav. 0)

SUBJECT:

HIGH PRESSURE COOLANT INJECTION PUMP STUD EXAMINATION COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the High Pressure Coolant injection (HP) main pump studs subject to examination per Table IWC-2500-1, Examination Categor/ C-D (Item No.

C4.30). This request for relief will apply to the HP main pump studs at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Table IWC-2500-1, Examination Category C-D (Item No. C4.30) of the ASME Section XI Code, 1989 Edition, requires each of the HP main pump studs to be volumetrically examined either in place under load or upon disassembly of the connection.

REQUESTED RELIEF:

Relief is requested for performing a volumetric examination of 100% of the HP main pump studs subject to examination as specified in Table IWC-2500-1, Examination Category C-D (Item No.

C4.30) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

A volumetric examination of the HP main pump studs requires removal of the stud cap nuts, which are torqued to 8,000 foot-pounds. Carolina Power & Light (CP&l.) attempted removal of the nuts during the 1996 refueling outage (B111R1) using HyTorc equipment, but these attempts were unsuccessful. Further attempts to non-destructively remove the stud cap nuts could potentially damage the studs or pump casing. The seventeen (17) studs are inaccessible for in-place examinations from the top of each stud due to protective cap nuts. Eight (8) studs are inaccessible from the bottom due to the design of the pump casing. The remaining nine (9) studs are accessible for a volumetric examination from the bottom of each stud.

In accordance with 10 CFR 50.55a(a)(3)(ii), CP&L is requesting approval to implement an alternative examination requirement to those specified in Table IWC-2500-1, Examination Category C-D (Item No. C4.30). CP&L proposes to perform a volumetric examination on nine (9) of the seventeen (17) inaccessible studs. CP&L also proposes to examined the remaining 8 studs in accordance with Table IWC-2500-1, Examination Category C-D (item No. C4.30) if the HP main pump requires disassembly for maintenance or repair during the Third Inspection Interval.

This alternative requirement has been evaluated by CP&L, and CP&L has aetermined that implementation of this alternative requirement will provide an acceptable level of quality and safety for the following reasons:

Page 1 of 2 i

RELIEF REQUEST: RR-2 (R::v. 0)

SUBJECT:

HIGH PRESSURE COOLANT INJECTION PUMP STUD EXAMINATION

1. During the Second Inspection Interval, a volumetric examination was performed on nine (9) of the seventeen (17) studs (i.e., greater than 50 percent of the HP main pump studs) with no indications or degradation noted. This sampling provided an acceptable assurance that the remaining eight (8) inaccessible studs (#1,2,3, 9,10,12,13, & 17) had not experienced significant degradation. The nine (9) studs examined during the Second Inspection Interval will be reexamined during the Third inspection Interval. This same sampling of the HP main pump studs will provide an acceptable level of quality and safety.

2. As required by Table IWC-2500-1, Examination Category C-H, a visual (VT-2) examination of the pressure retaining boundary of the HP main pump is performed once per inspection Period during the required pressure tests. The visual examination is also an acceptable method for detecting degradation of the pressure retaining bolted connection. These visual examinations are performed more frequently than the volumetric examination required by Table IWC-2500-1, Examination Category C-D (Item No. C4.30).

3. The alternative requirement to perform an volumetric examination on the accessible nine (9) studs was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second Inspection Interval. As specified in the Safety Evaluation Report, the implementation of this alternative requirement would provide an acceptable level of quality and safety at BSEP, Unit 1 and 2. The alternative requirement, to perform a volumetric examination on the accessible nine (9) studs, evaluated by the NRC for use during the Second Inspection Interval has not changed.

PROPOSED /,LTERNATIVE:

During the Third inspection Interval, CP&L will perform a volumetric examination on the accessible nine (9) studs. This volumetric examination will be performed from the bottom of each stud while in-place. In addition, CP&L will perform a volumetric examination on the remaining eight (B) studs if the HP main pump is disassembled for maintenance or repair during the Third Inspection Interval.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

2. NRC Letter to CP&L, Date: September 8,1997,

Subject:

Approval for Use of Code Case N-509 and Relief from ASME Code,Section XI, Requirements for Examination of High Pressure Coolant injection Pump Studs (TAC NOS. M98734 and M98735) l Page 2 of 2

RELIEF REQUEST: RR-3 (Rsv. 0)

SUBJECT:

INSERVICE INSPECTION INTERVAL REQUIREMENTS (CODE CASE N-535)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

Tin request for relief is applicable to the scheduling inservice inspections for Class 1,2, and 3 components inspected under inspection Program B of the ASME Section XI Code,1989 Edition.

This request for relief will apply to the scheduling of inservice inspections at the Brunswick /

Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Paragraph IWA-2430(d) of the ASME Section XI Code,1989 Edition, outlines requirements for scheduling inservice inspections for components inspected under Inspection Program B.

REQUESTED RELIEF:

Relief is requested from the requirements for scheduling inservice inspections for components l inspected under Inspection Program B specified in paragraph IWA-2430(d) of the ASME Section XI Code,1989 Edition.

! BASIS FOR REQUESTING RELIEF:

in accordance with 10 CFR 50.55a(a)(3)(i), Carolina Power and Light (CP&L) is requesting approval to implement alternative requirements to those specified in paragraph IWA-2430(d).

l CP&L proposes to implement the alternative requirements outlined in ASME Code Case N-535, Alternative Requirements for Inservice Inspection Intervals.

The alternative requirements outlined in ASME Code Case N-535 have been evaluated by CP&L, and CP&L has determined that implementation of these requirements will provide an acceptable level of quality and safety for the following reasons:

1. ASME Code Case N-535 provides alternative requirements for scheduling inservice inspection of components inspected under inspection Program B. Implementation of this ASME Code Case will not alter the examination method, examination frequency, or function of these Class 1,2, or 3 components (including their supports) at BSEP, Unit 1 and 2.

2. The alternative requirements of ASME Code Case N-535 clarifies situations that are not explicitly described in the 1989 Edition of the ASME Section XI Code. This ASME Code Case was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on December 12, 1994. Following approval, the provision stated within this ASME Code Case has been incorporated in paragraph IWA-2430(d) of the 1996 Edition of l the ASME Section XI Code. Both actions signifies the requirements outlined in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants.

1 Page 1 of 2

RELIEF REQUEST: RR-3 (Rsv. 0)

SUBJECT:

INSERVICE INSPECTION INTERVAL REQUIREMENTS (CODE CASE N-535)

PROPOSED ALTERNATIVE:

During the Third inspection Interval, CP&L will implement the alternative requirements of ASME Code Case N-535.

REFERENCES:

1. ASME Code Case N-535, Alternative Requirements for Inservice Inspection Interval (Approval Date: December 12,1994)

2. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

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RELIEF REQUEST: RR-4 (Rav. 0)

SUBJECT:

BOLTING FOR CONTROL ROD HOUSING (CODE CASE N-547)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the bolting of the Control Rod Drive (CRD) housings subject to examination in accordance with Table IWB-2500-1, Examination Category B-G-2 (Item No. B7.80). This request for relief will apply to the bolting of the Control Rod Drive (CRD) housings at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Table IWB-2500-1, Examination Category B-G-2 (Item No. B7.80), requires a visual (VT-1) examination of CRD housings' bolting when disassembled.

REQUESTED RELIEF:

Relief is requested from the visual (VT-1) examination of CRD housings bolting as specified in Table IWB-2500-1, Examination Category B-G-2 (Item No. B7.80) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to discontinue the visual examination of CRD housing bolting as required per Table IWB-2500-1, Examination Category B-G-2 (ltem No. B7.80). CP&L proposes to (1) implement ASME Code Case N-547, Alternative Requirements for Pressure Retaining Bolting of Control Rod Drive (CRD) Housings, for those bolted connections being reinstalled with new botting or (2) perform a VT-1 examination of the bolting that has been in service prior to their reinstallation.

ASME Code Case N-547 has been evaluated by CP&L, and CP&L has determined that implementation of this ASME Code Case will provide an acceptable level of quality and safety for the following reasons:

1. ASME Code Case N-547 will discontinue the visual examination of bolting on CRD housing as specified in Table IWB-2500-1, Examination Category B-G-2 (Item No. B7.80). The ASME Committee determined that a visual examination of the CRD housing bolting was no longer required. CP&L agrees that the visual examination of this bolting, unless being reinstalled, is unwarranted and does not increase the level of quality and safety at BSEP, Unit 1 and 2. CP&L has determined that implemeritation of this ASME Code Case will eliminate personnel exposure associated with the examination of this bolting when disassembled. Thus, the continued examination of this bolting as specified in Table IWB-2500-1 Examination Category B-G-2 (Item No. B7.80) will create a hardship for CP&L without a compensating increase in quality and safety.

Page 1 of 2

RELIEF REQUEST: RR-4 (R::v. 0)

SUBJECT:

BOLTING FOR CONTROL ROD HOUSING (CODE CASE N-547)

2. ASME Code Case N-547 was approved by the ASME's Main Committee and the Board of.

Nuclear Codes and Standards on August 24,1995. Following approval, the provision stated within this ASME Code Case has been incorporated in the 1995 Addenda of the ASME Section XI Code. Thus, the ASME Section XI Code no longer requires the examination of the CRD bolting when disassembled. Both of the actions described above signify that discontinuing this examination will provide an acceptable level of quality and safety for nuclear power plants.

3. As required by Table IWB-2500-1, Examination Category B-P, a visual (VT-2) examination of the pressure retaining boundary of the CRD housing is performed each refueling outage l during the required pressure tests. The performance of this visual examination is an acceptable method for detecting degradation of the pressure retaining bolted connection.

Imp lementation of this ASME Code Case will not alter this examination requirement.

PROPOSED ALTERNATIVE:

When a CRD housing bolted connection is disassembled and the bolting is to be reused, CP&L will perform a VT-1 examination of the bolting prior to reinstallation. If the bolted connection is reinstalled with new bolting, CP&L will implement the alternative requirement of ASME Code Case N-547 during the Third Inspection Interval.

REFERENCES:

1. ASME Code Case N-547, Attemative Requirements for Pressure Retaining Bolting of Control Rod Drive (CRD) Housings (Approval Date: August 24,1995)

2. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) l l

l Page 2 of 2

RELIEF REQUEST: RR-5 (R:v. 0)

SUBJECT:

INTEGRALLY WELDED SUPPORT ATTACHMENT (CODE CASE N-509)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

! This request for relief is applicable to the Class 3 integral attachment welds subject to examination in accordance with Table IWD-2500-1, Examination Category D-B (Item No. D2.20, l D2.30, D2.40, D2.50 & D2.60). This request for relief will apply to Class 3 integral attachment welds at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Table IWD-2500-1, Examination Category D-B (Item No. D2.20, D2.30, D2.40, D2.50 & D2.60) requires a visual (VT-3) examination of integral attachment welds each Inspection Interval.

REQUESTED RELIEF:

l l Relief is requested from the visual (VT-3) examination of integral attachment welds as specified l in Table IWD-2500-1, Examination Category D-B (ltem No. D2.20, D2.30, D2.40, D2.50 &

D2.60) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

ASME Code Case N-509 provide alternative requirements for the selected and examination of Class 1,2, and 3 integrally welded attachments. During the Third Inspection Interval, Carolina l Power and Light (CP&L) will not implement this ASME Code Case for Class 1 and Class 2 l integral attachment welds. Unlike for Class 3 integral attachment welds, implementation of these alternative requirements will not enhance the examination method for Class 1 and Class 2 integral attachment welds. For this reason, CP&L will comply with the applicable requirements of the ASME Section XI Code,1989 Edition, for Class 1 and Class 2 integral attachment welds.

l In accordance with 10 CFR 50.55a(a)(3)(i), CP&L is requesting approval to use the alternative l requirements for Class 3 integral attachment welds to those specified in Table IWD-2500-1, Examination Category D-B (ltem No. D2.20, D2.30, D2.40, D2.50 & D2.60). CP&L proposes to (1) implement the alternative requirements outlined in ASME Code Case N-509, Alternative Rules for the Selection and Examination of Class 1,2, and 3 Integrally Welded Attachments, for Class 3 integral attachment welds ud (2) examine a minimum ten (10) percent sample for integral attachment welds under Examination Category D-A.

ASME Code Case N-509 have been evaluated by CP&L, and CP&L has determined that implementation of this ASME Code Case for Class 3 integral attachment welds will provide an acceptable level of quality and safety for the following reasons:

1. The implementation of this ASME Code Case enhance the examination of Class 3 integral i attachment welds by requiring a visual (VT-1) examination in lieu of the visual (VT-3) ,

i Page 1 of 3 I I

RELIEF REQUEST: RR-5 (Rsv. 0) l

SUBJECT:

INTEGRALLY WELDED SUPPORT ATTACHMENT (CODE CASE N-509) examination required by Table IWD-2500-1, Examination Category D-B (Item No. D2.20, D2.30, D2.40, D2.50 & D2.60). The requirements for a visual (VT-1) examination is more stringent and more likely to identify the types of degradation that are most detrimental to a welded attachments. Although an examination of a smaller sampling is allowed, this ASME Code Case still requires additional and successive examinations for attachment welds whose examinations reveal flaws or relevant conditions that exceed the acceptance standards of Section XI.

2. ASME Code Case N-509 implements a sampling plan similar to Code Case N-491 for i component supports, which has been incorporated for usage into Regulatory Guide 1.147.

Furthermore, ASME Code Case N-509 requires selection of component supports for examination in accordance with the ASME Section XI Code,1989 Edition with the 1990 Addenda, which includes the same selection criteria as ASME Code Case N-491. Since a sampling selection of component supports in accordance with ASME Code Case N-491 provides an acceptable level of quality and safety, then selecting a similar sampling of integral attachment welds associated with component supports selected for examination in accordance with ASME Code Case N-509 also provides an acceptable level of quality and safety.

3. Limiting the extent of examination, to a sample population of a certain type of weld, is an acceptable methodology per the ASME Section XI Code for ensuring the detection of service-induced degradation. Extending this sampling philosophy to Class 3 integral attachment welds will provide an equivalent level of quality and safety for those welds. This smaller sample size receives an equal or more extensive examination while reducing personnel radiation exposure.

4. ASME Code Case N-509 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on November 25,1992. Following approval, the provision stated within.this ASME Code Case has been incorporated 1995 Addenda of the ASME Section XI Code. Both actions signifies that the sampling of Class 3 integral attachment welds will provide an acceptable level of quality and safety for nuclear power plants.

5. ASME Code Case N-509 was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second Inspection Interval. As specified in the Safety Evaluation Report, the implementation of this ASME Code Case would provide an acceptable level of quality and safety at BSEP, Unit 1 and 2. The alternative requirements evaluated by the NRC for use on Class 3 integral attachment welds during the Second Inspection interval has not changed. The acceptance of ASME Code Case N-509 was also included in the i proposed revision to Regulatory Guide 1.147 (i.e., Draft DG-1050).

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the alternative requirements outlined ASME Code Case N-509 for Class 3 integral attachments welds. In addition, CP&L will Page 2 of 3

I RELIEF REQUEST: RR-5 (Rsv. 0)

SUBJECT:

INTEGRALLY WELDED SUPPORT ATTACHMENT (CODE CASE N-509) examine a minimum ten (10) percent sampling of the integral attachment welds under Examination Category D-A.

REFERENCES:

1. ASME Code Case N-509, Alternative Rules for the Selection and Examination of Class 1,2, and 3 Integrally Welded Attachments (Approval Date: November 25,1992)

2. ASME Code Case N-491, Alternative Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plant (Approval Date: March 14,1991)

! 3. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components,

( 1989 Edition (no Addenda) and 1989 Edition with the 1990 Addenda

4. Regulatory Guide 1.147, inservice Inspection Code Case Acceptability, ASME Section XI Division 1 l 5. NRC Letter to CP&L, Date: September 8,1997,

Subject:

Approval for Use of Code Case N-l 509 and Relief from ASME Code,Section XI, Requirements for Examination of High Pressure Coolant Injection Pump Studs (TAC NOS. M98734 and M98735) l l

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Page 3 of 3

RELIEF REQUEST: RR-6 (R::v. 0)

SUBJECT:

CLASS 1 LONGITUDINAL WELDS (CODE CASE N-524)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the Class 1 longitudinal piping welds subject to examination in accordance with Table IWB-2500-1, Examination Category B-J (Item 9.12). This request for relief will apply to Class 1 longitudinal piping welds at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

1 ASME SECTION XI CODE REQUIREMENT:

l Table IWB-2500-1, Examination Category B-J (Item 9.12) requires a surface and volumetric l examination of at least a pipe-diameter length but not more than 12 inches of each longitudinal

! weld selected for examination.

REQUESTED RELIEF:

Relief is requested from the surface and volumetric examination of longitudinal welds as

! specified in Table IWB-2500-1, Examination Category B-J (Item 9.12) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use the alternative requirements for the surface and volumetric examination of Class 1 longitudinal welds to those specified in Table IWB-2500-1, Examination Category B-J (item 9.12). CP&L proposes to implement the alternative requirements outlined in ASME Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping. ,

Unit 1 and 2 does not contain any Class 2 longitudinal welds. Therefore, the alternative requirements outlined in ASME Code Case N-524 for Class 2 longitudinal welds are not applicable.

ASME Code Case N-524 have been evaluated by CP&L, and CP&L has determined that j implementation of this ASME Code Case for Class 1 longitudinal welds will provide an acceptable level of quality and safety for the following reasons:

1. Longitudinal welds are not produced in the field or fabrication shops as is the case of a circumferential weld Longitudinal piping welds for Class 1 applications were made by the piping manufacturer under controlled conditions which produced higher quality welds and more uniformed residual stress patterns. These welds were examined in accordance with the appropriate ASTM or ASME specifications with additional nondestructive examination requirements imposed by the purchasing specifications. The manufacturing controls specified by the appropriate ASTM or ASME specifications along with the additional examinations imposed by the purchasing specification provides assurance of the structural Page 1 of 3 L

RELIEF REQUEST: RR-6 (Rsv. 0)

SUBJECT:

CLASS 1 LONGITUDINAL WELDS (CODE CASE N-524) integrity of the longitudinal weld at the time the piping is manufactured.

2. Inservice inspections have provided assurance of the structural integrF of the longitudinal welds during the service life of the plant to date. Based on results i these inservice inspections, BSEP has not experienced degradation that would warrant continued examination beyond the intersection area or volume bounded by this ASME Code Case. If any degradation associated with a longitudinal weld were to occur, it is expected that it would be located at the intersection with a circumferential weld. The inspection of this intersection is within the scope of this ASME Code Case.

3. ASME Code Case N-524 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on August 9,1993. Following approval, the provision stated within this ASME Code Case has been incorporated in the 1995 Addenda of the ASME Section XI Code. Both actions signify that the examination of longitudinal welds as described in ASME Code Case N-524 and the 1995 Addenda will provide an acceptable level of quality and safety for nuclear power plants.

4. A significant accumulation of person-rem is associated with the examination of Class 1 longitudinal welds. The radiological exposure associated with the examination of longitudinal welds are dependent on the time it would take to remove and reinstall insulation and interference, prepare the weld for examination, and perform the examinations. Therefore, the imposition of the examination requirements for longitudinal welds as described in the 1989 Edition of the ASME Section XI Code constitutes a hardship to BSEP without a )

compensating increase in quality and safety.

5. ASME Code Case N-524 was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second Inspection Interval. As specified in the Safety Evaluation Report, the implementation of this ASME Code Case would provide an acceptable level of l quality and safety at BSEP, Units 1 and 2. The alternative requirements evaluated by the )

NRC for the examination of longitudinal welds during the Second Inspection interval has not  !

changed. The acceptance of ASME Code Case N-524 was also included in the proposed revision to Regulatory Guide 1.147 (i.e., Draft DG-1050).

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the alternative requirements outlined 4 ASME Code Case N-524 for the examination of longitudinal welds.

REFERENCES:

1. ASME Code Case N-524, Alternative Rules for Longitudinal Welds in Class 1 and 2 Piping (Approval Date: August 9,1993)

Page 2 of 3

RELIEF REQUEST: RR-6 (R:v. 0)

SUBJECT:

CLASS 1 LONGITUDINAL WELDS (CODE CASE N-524)

2. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) and 1989 Edition with the 1990 Addenda

3. NRC Letter to CP&L, Dated January 17, 1996, Approval of Code Case N-524 as an j Alternative to the Requirements for the Examination of Longitudinal Welds in Class 1 and 2 Piping (BSEP 95-0512) (TAC Nos. M93902 and M93903) 1 l

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Page 3 of 3 l )

RELIEF REQUEST: RR-7 (R:;v. 0)

SUBJECT:

REACTOR PRESSURE VESSEL SKIRT SUPPORT COMPONENT FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the Class 1 Reactor Pressure Vessel (RPV) skirt support ct the Brunswick Steam Electric Plant (BSEP), Units 1and 2.

ASME SECTION XI CODE REQUIREMENT:

For component supports, BSEP will implement the alternative requirements specified in ASME Code Case N-491 during the Third Inspection Interval. Examination Category F-A (item No.

F1.40) of ASME Code Case N-491 requires 100% of supports, other than piping supports, to be examined.

REQUESTED RELIEF:

Relief is requested from the visual (VT-3) examination of the internal circumference of the RPV skirt support as specified in Examination Category F-A (Item No. F1.40) of ASME Code Case N-491. j BASIS FOR REQUESTING RELIEF:  ;

in accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting approval to not perform the visual (VT-3) examination on the interior surface of the RPV skirt support. CP&L will perform the required visual (VT-3) examination on the exterior surface of the RPV skirt support. CP&L has evaluated not performing the visual (VT-3) examination on the interior surface and has determined that implementation of the request for relief will provide an acceptable level of quality and safety for the following reasons: l

1) The design bases failure mode of the RPV skirt support is buckling caused by primary  ;

bending compressive stress. After forming, the material has ample ductility and is expected I to exhibit significant plastic deformation prior to fracture. Any service induced damage would be associated with buckling failure and would be evident during the visual (VT-3) ,

examination of the exterior surface. Thus, the visual (VT-3) examination of the exterior l surface will provide assurance of the continued structural integrity of the RPV skirt support.

2) A visual (VT-3) examination of the interior surfaces of the RPV skirt support is impractical i and constitutes a hardship to BSEP without a compensating increase in quality and safety.

in order to examine the interior surface of the RPV skirt support, insulation is required to be l removed. Removing the insulation and leaving it in the skirt support area during the  !

l examination is not possible because of the limited space between the control rod drives and the skirt support area. Removal of the insulation outside the skirt support area is not possible without damaging the insulation. The access opening to the skirt support area is 18 inches in diameter and the size of the insulation sections is a minimum of 20 inches by 30-5/8 inches. In addition, the insulation is constructed of inner and outer casings of 304 stainless steel and the inner radiation shields of aluminum alloy (e.g., mirror-type insulation).

Page 1 of 2

RELIEF REQUEST: RR-7 (Rev. 0)

SUBJECT:

REACTOR PRESSURE VESSEL SKIRT SUPPORT ]

l Removal of the insulation would require disassembly by either unscrewing each piece of the l insulation or by cutting and would result in permanent damage to the insulation. Thus, l reinstallation of the existing insulation would not be possible due to this damage. For this l reason, new insulation would be required to be designed and installed in place of the l existing insulation. The tasks associated with the removal and reinstallation would result in a significant hardship to CP&L for the following reasons: (1) radiation exposure of approximately 1.4 R per unit (removal and reinstallation); (2) costs associated with the design packages required to document installation of new insulation; (3) material costs of new insulation (approximately $30,000 per unit), and (4) cost reduction in radwaste volume of approximately $26,129 per unit.

l 3) A request for relief to not perform the visual (VT-3) examination on the interior surface of the RPV skirt support was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second Inspection Interval. The basis for requesting relief, that was evaluated by the NRC for uses during the Second Inspection Interval, has not change.

l PROPOSED ALTERNATIVE: .

l During the Third Inspection Interval, CP&L proposes no alternative examination of the RPV skirt l support's interior surfaces CP&L will perform the visual (VT-3) examination of the RPV skirt l support's exterior surfaces as required by ASME Code Case N-491. )

REFERENCES:

I

1. Letter from NRC to CP&L, Dated: January 25,1996,

Subject:

Relief from American Society of Mechanical Engineers (ASME) Code Requirement to Perform Visual Examination Of interior Surface of Reactor Pressure Vessel Support Skirt - Brunswick Steam Electric Plant, Units 1 and 2 (BSEP 95-0188)(TAC Nos. M92608 and M92609).

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l Page 2 of 2 L

RELIEF REQUEST: RR-8 (R:v. 0)

SUBJECT:

SNUBBER EXAMINATION AND TESTING COMPONENT FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Class 1, 2, and 3 snubbers at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Paragraph IWF-1220, Snubber inspection Requirements, requires the inservice inspection requirements for snubbers be in accordance with the requirements of Article IWF-5000. Article IWF-5000 requires preservice examinations and tests, inservice examinations and tests, and repairs and replacements to be in accordance with the first Addenda to ASME/ ANSI OM-1987, Part 4 (published in 1988). Examinations are to be performed using the visual (VT-3) examination method described in paragraph IWA-2213.

REQUESTED RELIEF:

Relief is requested from the requirements specified in paragraph IWF-1220 and Article IWF-5000 (i.e. the first Addenda to ASME/ ANSI OM Part 4,1987 (published in 1988)) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to implement alternative requirements to those specified in paragraph IWF-1220 and )

Article IWF-5000. CP&L proposes to implement the alternative requirements, for the examination and testing of snubbers.

The alternative requirements outlined in BSEP's Technical Specifications have been evaluated by CP&L, and CP&L has determined that implementation of these requirements will provide an acceptable level of quality and safety for the following reasons:

1. Snubber examinations are currently performed under BSEP's Technical Specification (3/4.7.5) which was previously amended per Generic Letter 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions." The stated purpose of the generic letter was to provide alternative guidance to snubber inspection schedules which were excessively restrictive. The alternative schedule was provided to alleviate the expenditure of unnecessary resources and prevent radiological exposure associated with the over restrictive examination schedule. The implementation of paragraph i

IWF-1220 and Article IWF-5000 (i.e., OM Part 4) would return the snubber examination l

program to the state which existed prior to publication of Generic Letter 90-09, effectively

~

canceling the benefits intended through the Generic Letter. Approval of the alternative requirements specified in this request for relief will save significant company resources and significantly reduce unnecessary radiological exposure to plant personnel when complying with the visual examination requirements without decreasing the confidence level in snubber Page 1 of 2

)

RELIEF REQUEST: RR-8 (R::v. 0)

SUBJECT:

SNUBBER EXAMINATION AND TESTING ,

operability. Therefore, the imposition of the requirements specified in paragraph IWF-1220 and Article IWF-5000 of the 1989 Edition of the ASME Section XI Code constitutes a hardship to BSEP without a compensating increase in quality and safety.

2. The current inspection program, as defined by BSEP's Technical Specification, provides for a level of quality and safety equal to or greater than that of the requirements specified in OM Part 4. For example, OM Part 4 provides for Failure Mode Grouping of snubbers which fail visual examination, meaning only those snubbers identified as being in that group would require shortened inspection intervals. Under the current inspection program, all snubbers in the population would be placed in a shortened inspection interval. On this basis the existing program is more conservative in corrective action than the OM Part 4 requirements.

3. The functional test plan required by OM Part 4 also includes Failure Mode Groups. The use of failure mode grouping is required even for a single failure, and in some cases allows for the failed snubber to be reclassified as acceptable with no further testing. This test plan is unconservative for the large snubber population which exists at BSEP (over 500 snubbers per unit) as compared to the current inspection program. The current inspection program 4 requires supplemental testing for all failures until the desired confidence level is assured with !

no allowances to reclassify failed snubbers.

PROPOSED ALTERNATIVE:

During the Third inspection Interval, CP&L wi!! implement the alternative requirements specified I

in BSEP's Technical Specification (currently outlined in 3/4.7.5). Upon approval of the Improved Technical Specification, these alternative requirements will be outlined in the

Technical Review Manual. The alternative requirements specified in BSEP's Technical  !

Specification will also be applied to preservice examinations and testing of snubbers that are repaired or replaced.

REFERENCES:

1. NRC Letter to Mr. J. V. Parrish (Gl2-96-195), Dated August 1,1996, Inservice inspection Program Relief Request for Snubber Inspection's for the Washington Public Power Supply System (WPPSS) Nuclear Project No 2 (WNP-2) (TAC No, M94580)

Page 2 of 2

RELIEF REQUEST: RR-9 (Rsv. 0)

SUBJECT:

ALTERNATIVE PRESSURE TEST REQUIREMENTS FOR WELDED REPAIRS / REPLACEMENTS (CODE CASE N-416-1)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the pressure test requirements for welded repairs or installation of replacement items by welding on Class 1,2, and 3 components at the Brunswick l Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT

l l

Paragraph IWA-4700(a) requires a system hydrostatic tests to be performed following a repair by welding unless exempted by IWA-4700(b).

l

! REQUESTED RELIEF:

l Relief is requested from the system hydrostatic test specified in IWA-4700(a) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use the alternative requirements to those specified in paragraph IWA-4700(a).

CP&L proposes to (1) implement the alternative requirements outlined in ASME Code Case N-416-1, Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement items by Welding, Class 1,2 and 3 and (2) perform a surface examination on the root pass of Class 3 butt and socket welds when the surface examination method is used in ,

accordance with the ASME Section lli Code.

The alternative requirements discussed above have been evaluated by CP&L, and CP&L has determined that implementation of this ASME Code Case and surface examination on the root pass of Class 3 butt and socket welds will provide an acceptable level of quality and safety for the following reasons: ,

i

1. Piping components are designed for a number o5 4(ferent loadings that are postulated to l occur under the various modes of plant operation. Hydrostatic testing only subjects the piping components to a small increase in pressure over the design pressure and, therefore, does not present a significant challenge to pressure boundary integrity. Accordingly, hydrostatic pressure testing is primarily regarded as a means to enhance leakage detection during the examination of components under pressure, rather than solely as a measure to determine the structuralintegrity of the components.

2. Since hydrostatic test pressures are higher than nominal operating pressures, hydrostatic pressure testing frequently requires significant effort to set-up and perform. The need to use l

1 Page 1 of 2 i

L.

l l

RELIEF REQUEST: RR-9 (R:;v. 0)

SUBJECT:

ALTERNATIVE PRESSURE TEST REQUIREMENTS FOR WELDED REPAIRSIREPLACEMENTS (CODE CASE N-416-1) special equipment (e.g., temporary attachment of test pumps and gauges) and the need for individual valve lineups, can cause the testing to become the critical path activity during outages. Experience has demonstrated that leaks are not being discovered as a result of hydrostatic test pressures propagating a preexisting through-wall flaw. Typically, when leaks are identified, they occur at flanges, packing, seals, etc., at normal operating pressure.

Therefore, the imposition of the pressure testing requirements specified in IWA-4700(a) of the 1989 Edition of the ASME Section XI Code constitutes a hardship to BSEP without a compensating increase in quality and safety.

3. ASME Code Case N-416-1 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on February 15, 1994. This approval signifies the requirements outlined in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants.

4. ASME Code Case N-416-1 was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second Inspection Interval. As specified in the Safety Evaluation Report, the implementation of this ASME Code Case would provide an acceptable level of quality and safety at BSEP, Units 1 and 2. The alternative requirements evaluated by the NRC, for pressure testing of welded repairs or installation of replacement items by welding, for uses during the Second inspection Interval has not changed. The acceptance of ASME Code Case N-416-1 was also included in the proposed revision to Regulatory Guide 1.147 (i.e., Draft DG-1050).

PROPOSED ALTERNATIVE:

During tne Third inspection Interval, CP&L will implement the alternative requirements outlined ASME Code Case N-416-1 for pressure testing of welded repairs or installation of replacement items by welding of Class 1,2 and 3 components. In addition to the alternative requirements specified in this ASME Code Case, CP&L will perform a surface examination on the root pass of Class 3 butt and socket welds when the surface examination method is used in accordance with the ASME Section 111 Code.

REFERENCES:

1. ASME Code Case N-416-1, Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement items by Welding, Class 1,2 and 3 (Approval Date: February 15, 1994)

2. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1

1989 Edition (no Addenda)

3. NRC Letter to CP&L, Dated November 1,1995, Approval of Code Case N-416-1 as an Alternative to the Required Hydrostatic Pressure Test (BSEP 95-0379) (TAC Nos. M93548 and M93549)

Page 2 of 2

RELIEF REQUEST: RR-10 (R",v. 0)

SUBJECT:

ALTERNATIVE REQUIREMENTS FOR 10 YEAR SYSTEM HYDROSTATIC PRESSURE TEST (CODE CASE N-498-1)

COMPONENTS FOR WHC.i RELIEF lS REQUESTED:

l This request for relief is applicable to Class 1,2, and 3 components subject to hydrostatic l testing in accordance with Table IWB-2500-1, Examination Category B-P; Table IWC-2500-1, l Examination Category C-H; and Table IWD-2500-1, Examination Category D-A, D-B, and D-C.

l This request for relief is applicable to Class 1,2, and 3 components at the Brunswick Steam ,

Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Table IWB-2500-1, Examination Category B-P; Table IWC-2500-1, Examination Category C-H; I and Table IWD-2500-1, Examination Category D-A, D-8, and D-C requires a system hydrostatic

! test once per Inspection Interval.

REQUESTED RELIEF:

Relief is requested from the system hydrostatic test specified in Table IWB-2500-1, Examination Category B-P; Table IWC-2500-1, Examination Category C-H; and Table IWD-2500-1, Examination Category D-A, D-B, and D-C of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use the alternative requirements to those specified in Table IWB-2500-1, Examination Category B-P; Table IWC-2500-1, Examination Category C-H; and Table IWD-2500-1, Examination Category D-A, D-8, and D-C of the ASME Section XI Code,1989 Edition.

CP&L proposes to implement the alternative requirements outlined in ASME Code Case N-498-1, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1,2, and 3 Systems.

ASME Code Case N-498-1 has been evaluated by CP&L, and CP&L has determined that implementation of this ASME Code Case will provide an acceptable level of quality and safety

for the following reasons

l 1. CP&L regards the system hydrostatic test as an enhanced leakage test, rather than a test of ,

the structu.alintegrity of the system. During a hydrostatic test, components within the test boundary are subject to a smallincrease in pressure over the design pressure. Thus, the j hydrostatic test does not present a significant challenge to the pressure boundary integrity.

~

Accordingly, this testing is primarily regarded as a means to enhance leakage detection, rather than as a measure to determine the structuralintegrity of the component.

Page 1 of 2 j

1 RELIEF REQUEST: RR-10 (Rr,v. 0)

SUBJECT:

ALTERNATIVE REQUIREMENTS FOR 10 YEAR SYSTEM HYDROSTATIC PRESSURE TEST (CODE CASE N-498-1) l

2. Since hydrostatic test pressures are higher than nominal operating pressures, hydrostatic pressure testing frequently requires significant effort to set-up and perform. The need to use special equipment (e.g., temporary attachment of test pumps and gauges) and the need for individual valve lineups, can cause the testing to become the critical path activity during outages. Experience has demonstrated that leaks are not being discovered as a result of hydrostatic test pressures propagating a preexisting through-wall flaw. Typically, when leaks are identified, they occur at flanges, packing, seals, etc., at normal operating pressure.

Therefore, the imposition of the pressure testing requirements specified in Table IWB-2500-1, Examination Category B-P; Table IWC-2500-1, Examination Category C-H; and Table IWD-2500-1, Examination Category D-A, D-B, and D-C of the 1989 Edition of the ASME Section XI Code constitutes a hardship to BSEP without a compensating increase in quality and safety.

l

3. ASME Code Case N-498-1 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on February 15, 1994. Following approval, the provision stated within this ASME Code Case has been incorporated in the 1994 Addenda of the l ASME Section XI Code. Both actions signify that the alternative requirements described in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants.

4. ASME Code Case N-498-1 was approved by the Nuclear Regulatory Commission (NRC) for implementation during the Second inspection Interval. As specified in the Safety Evaluation Report, the implementation of this ASME Code Case would provide an acceptable level of quality and safety at BSEP, Units 1 and 2. The acceptance of ASME Code Case N-498-1 was also included in the proposed revision to Regulatory Guide 1.147 (i.e., Draft DG-1050).

1 PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the alternative requirements outlined ASME Code Case N-498-1.

REFERENCES:

l l 1. ASME Code Case N-498-1, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1,2, and 3 Systems (Approval Date: February 15,1994)

2. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

3. NRC Letter to CP&L, Dated March 2,1995, Correction to the NRC's Letter Approving the use of Code Case N-498-1 as an Alternative to the Required Hydrostatic Pressure Test (TAC Nos. M90569 and M90570) l Page 2 of 2

RELIEF REQUEST: RR-11 (R^v. 0)

SUBJECT:

PRESSURE TEST ON BURIED PIPING COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This relief request is applicable to Class 3 buried (underground) components within the Service Water System subject to examination in accordance with Table IWD-2500-1, Category D-B.

This request for relief will apply to Class 3 buried (underground) components extending from the Service Water building to the Reactor and Diesel Generator Buildings at the Brunswick Steam Electric Plant (BSEP), Unit 1 and 2.

ASME SECTION XI_ CODE REQUIREMENT:

Paragraph l'NA-5244(b) of the ASME Section XI Code requires that buried piping be tested by measuring the change in flow between the ends of the buried components.

REQUESTED RELIEF:

Relief is requested for the requirements specified in IWA-5244(b) of the ASME Section XI Code, l 1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting l approval to use alternative requirements to those specified in IWA-5244(b). CP&L proposes to l (1) demonstrate adequate flow through the buried Service Water (SW) piping during the quarterly inservice testing of the Residual Heat Removal (RHR)/SW pumps and (2) demonstrate adequate flow from the SW Nuclear Header through the buried piping to the DG Jacket Water piping during the monthly testing of the Diesel Generators.

The alternative requirements described above have been evaluated by CP&L, and CP&L has determined that implementation of these requirements will provide an acceptable level of quality cnd safety for the following reasons:

1. No permanent flow measurement instrumentation is installed in the area of the underground piping. In addition, this portion of the Service Water System has no straight runs of pipe with sufficient length to permit accurate measurements using portable flow instrumentation (e.g.,

Controlotron). Thus, CP&L would be required to install special equipment and/or the need for individual valve lineups which can impact returning this safety related system to service.

l Therefore, the imposition of the requirements specified in IWA-5244(b) constitutes a hardship to BSEP without a compensating increase in quality and safety.

I

2. The function of the buried SW piping is to provide an adequate supply of inventory to the safety related pumps and equipment. Adequate flow through these buried portions of the headers is demonstrated during quarterly pump testing of the RHR/SW pumps under CP&L's Inservice Testing Program. CP&L also performs monthly testing of the Diesel Page 1 of 2

RELIEF REQUEST: RR-11 (R;v. 0) l l

SUBJECT:

PRESSURE TEST ON BURIED PIPING l

Generators (DG) that demonstrates adequate flow from the SW Nuclear Header through the buried piping to the DG Jacket Water piping. The satisfactory completion of this testing verifies adequate flow to applicable safety related components.

3. Every other refueling outage, a hydraulic performance test is also performed on the SW Nuclear Header piping. During the performance of this test, both Nuclear SW pumps are

' running and discharging into the Nuclear Header. This hydraulic performance test verifies a flow path through the Class 3 SW buried piping from the Nuclear Header and satisfactory completion of this testing verify adequate flow to applicable safety related components.

4. Every other refueling outage, this Class 3 SW buried piping is periodically drained and a visual examination performed from the inside of the pipe. Although this examination is not per the ASME Section XI Code, the purpose of this . visual examination is to detect

! degradation of this piping.

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will demonstrate adequate flow through the Class 3 SW buried piping in accordance with BSEP"s Inservice Testing Program and Technical Specifications. Accordingly, CP&L will perform periodic inservice testing of the RHR/SW pumps in accordance with the 1989 Edition of the ASME Section XI Code and monthly testing of the DG in accordance with BSEP's Technical Specifications.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

2. ASME OM (Part 6), inservice Testing of Pumps in Light-Water Reactor Power Plants,1987 Edition with 1988 Addenda l

l l

Page 2 of 2

[

RELIEF REQUEST: RR-12 (Rav. 0) i

SUBJECT:

EXAMINATION CATEGORY B-D, EXAMINATION COVERAGE COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Class 1 full penetration welds of nozzles in vessels subject l to examination per Table IWB-2500-1, Examination Category B-D. This request for relief will apply to Class 1 full penetration welds of nozzles at the Brunswick Steam Electric Plant (BSEP),

Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

During the Third Inspection Interval, BSEP is implementing ASME Code Case N-460, l Altemative Examination Coverage for Class 1 and Class 2 Welds. ASME Code Case N-460 allows a reduction of examination coverage provided the reduction in coverage for a given weld is less than 10 percent.

REQUESTED RELIEF:

Relief is requested from the alternative requirements specified in ASME Code Case N-460.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting l

approval to credit the limited examination of the components listed in Table 1. Because of j physical obstructions and/or component configuration, the examination coverage for these l components would not meet the alternative requirements specified in ASME Code Case N-460.

The acceptable deviation from the alternative requirements specified in ASME Code Case N-l 460 has been evaluated by CP&L, and CP&L has determined that performing the required l examinations on the component identified in Table 1 to the maximum extent practical will provide an acceptable level of quality and safety for the following reasons

1.Section XI of the ASME Code was issued January 1,1970. At the time of issuance, the design of BSEP, Units 1 and 2, was at a stage where literal compliance with the access requirements outlined in the ASME Section XI Code was not possible. For this reason, limitation associated with the components listed in Table 1 prevented CP&L from obtaining the required examination coverage specified in ASME Code Case N-460. In order to obtain required examination coverage, CP&L would have to implement design modification.

Implementation of a design modification for these components would result in a significant hardship to CP&L without a compensating increase in quality and safety.

2. Paragraph (g)(4) of 10 CFR 50.55a, Codes and Standards, requires that Class 1 components meet the requirements set forth in the ASME Section XI Code incorporated by Page 1 of 5 l

RELIEF REQUEST: RR-12 (Rsv. 0)

SUBJECT:

EXAMINATION CATEGORY B-D, EXAMINATION COVERAGE i

reference in paragraph (b), to the extent practical, within the limitation of design, geometry, and material of construction of the components. Since it was recognized that some plants (such as BSEP) were built before some of the ASME Standards were written, the above provisions outlined in 10 CFR 50.55a(g)(4) were written to address this situation. Pursuant l

to @55a(g)(4), CP&L examined the components listed in Table 1, to the maximum extent practical, during the Second Inspection Interval. During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

CP&L will also continue to evaluate advance techniques and incorporate them, to the extent practical, in the Third Inspection interval as they become available.

3. The extent of the nozzle welds not examined represents a small percentage of the total length of welds examined in accordance with Examination Category B-D. Thus, CP&L is confident that generic degradation of components within this Examination Category would be detected.

4. In addition to the examination specified in Examination Category B-D, CP&L performs a pressure test of the components listed in Table 1 each refueling outage in accordance with Examination Category B-P. The successful completion of these pressure tests will provide assurance of the component's structure integrity. If a defect is detected during one of these pressure tests, corrective measures would be taken prior to returning the component to service.

PROPOSED ALTERNATIVE:

None During the Third inspection Interval, CP&L will continue to examine the components listed in Table 1, to the maximum extent practical.

TABLE,1 r '

, ystem ' Component v >

ltem No.- Remarks e < ~ <-

RPV 1B11-RPV-N10 B3.90 The examination coverage for this weld is approximately 50 percent and approximately 60 percent of the base material.

RPV 1811-RPV-N11 A D3.90 The examination coverage for this weld is approximately 52 percent.

RPV 1B11-RPV-N11B B3.90 The examination coverage for this weld is approximately 52 percent.

RPV 1811 RPV-N12A B3.90 The examination coverage for this weld is approximately 69 percent.

RPV 1B11-RPV-N12B B3.90 The examination coverage for this weld is approximately 50 percent and approximately 60 percent of the base material.

RPV 1B11-RPV-N16A B3.90 The examination coverage for this weld is approximately 61 percent.

RPV 1B11-RPV-N16B B3.90 The examination coverage for this weld is approximately 61 percent.

! RPV 1 B11-RPV-N1 A B3.90 The examination coverage for this weld is approximately 50 Page 2 of 5

1 i

RELIEF REQUEST: RR-12 (Rsv. 0)  !

1

SUBJECT:

EXAMINATION CATEGORY B-D, EXAMINATION COVERAGE TABLES P " ' W *" - + - * ~ - ' ' ~ '

System Component . '

Item No; Remarks n? n(  ;':

percent.

~RPV 1811-RPV-N1B B3.90 The examination coverage for this weld is approximately 67 percent.

RPV 1811-RPV-N2A B3.90 The examination coverage for this weld is approximately 65 percent.

RPV 1B11-RPV-N2B B3.90 The examination coverage for this weld is approximately 65 percent.

RPV 1B11-RPV-N2C B3.90 The examination coverage for this weld is approximately 63 percent.

RPV 1811-RPV-N2D B3.90 The examination coverage for this weld is approximately 65 ,

percent.  !

RPV 1811-RPV-N2E B3.90 The examination coverage for this weld is approximately 65 percent.

RPV 1B11-RPV-N2F B3.90 The examination coverage for this weld is approximately 69 percent.

RPV 1811-RPV-N2G B3.90 The examination coverage for this weld is approximately 65 percent.

RPV 1B11-RPV-N2H B3.90 The examination coverage for this weld is approximately 63 percent.

RPV 1B11-RPV-N2J B3.90 The examination coverage for this weld is approximately 65 percent.

RPV 1811-RPV-N2K B3.90 The examination coverage for this weld is approximately 69 percent.

RPV 1811-RPV-N3A B3.90 The examination coverage for this weld is approximately 66 percent.

RPV 1B11-RPV-N3B B3.90 The examination coverage for this weld is approximately 66 percent.

RPV 1B11-RPV-N3C B3.90 The examination coverage for this weld is approximately 66 percent.

RPV 1811-RPV-N3D B3.90 The examination coverage for this weld is approximately 66 percent.

RPV 1B11-RPV-N4A B3.90 The examination coverage for this weld is approxirnately 63 percent.

RPV 1B11-RPV-N4B B3.90 The examination coverage for this weld is approximately 64 percent.

RPV 1B11-RPV-N4C B3.90 The examination coverage for this weld is approximately 63 l percent.

RPV 1811-RPV-N4D B3.90 The examination coverage for this weld is approximately 67 j percent. I RPV 1B11-RPV-NSA B3.90 The examination coverage for this weld is approximately 62 percent.

RPV 1B11-RPV-N5B B3.90 The examination coverage for this weld is approximately 68 percent.

RPV 1B11-RPV-N6A B3.90 The examination coverage for this weld is approximately 70 percent.

RPV 1811-RPV-N6B B3.90 The examination coverage for this weld is approximately 70 percent.

RPV 1B11-RPV-N7 B3.90 The examination coverage for this weld is approximately 70 percent.

Page 3 of 5

RELIEF REQUEST: RR-12 (Rnv. 0)

SUBJECT:

EXAMINATION CATEGORY B-D, EXAMINATION COVERAGE TABLE 1: e ,

"" C> T ~

^ ^

w

~ ' '

System Component" Item No.~ iRemarks - <

.+ ,- m RPV 1B11-RPV-N8A B3.90 The examination coverage for this weld is approximately 64 percent RPV 1811-RPV-N8B B3.90 The examination coverage for this weld is approximately 64 percent RPV 1B11-RPV-N9 B3.90 The examination coverage for this weld is approximately 50 l percent.

! RPV 2B11-RPV-N10 B3.90 The examination coverage for this weld is approximately 50 percent and approximately 60 percent of the base material.

RPV 2B11-RPV-N11 A B3.90 The examination coverage for this weld is approximately 57 percent.

l RPV 2B11-RPV-N11B B3.90 The examination coverage for this weld is approximately 57 percent RPV 2B11-RPV-N12A B3.90 The examination coverage for this weld is approximately 69 i percent.

RPV 2B11-RPV-N128 B3.90 The examination coverage for this weld is approximately 69 percent.

RPV 2811-RPV-N16A B3.90 The examination coverage for this weld is approximately 61 percent.

RPV 2811-RPV-N16B B3.90 The examination coverage for this weld is approximately 61 percent RPV 2B11-RPV-N1 A B3.90 The examination coverage for this weld is approximately 50 percent.

RPV 2B11-RPV-N1B B3.90 The examination coverage for this weld is approximately 67 percent.

RPV 2B11-RPV-N2A B3.90 The examination coverage for this weld is approximately 63 percent.

RPV 2B11-RPV-N2B B3.90 The examination coverage for this weld is approximately 62 percent RPV 2B11-RPV-N2C B3.90 The examination coverage for this weld is approximately 63 percent.

RPV 2B11-RPV-N2D B3.90 The examination coverage for this weld is approximately 63  ;

percent. l RPV 2B11-RPV-N2E B3.90 The examination coverage for this weld is approximately 63 l percent.

RPV 2811-RPV-N2F B3.90 The examination coverage for this weld is approximately 63 percent.

RPV 2811-RPV-N2G B3.90 The examination coverage for this weld is approximately 62 percent.

RPV 2811-RPV-N2H B3.90 The examination coverage for this weld is approximately 62 percent.

RPV 2B11-RPV-N2J B3.90 The examination coverage for this weld is approximately 56 percent RPV 2B11-RPV-N2K B3.90 The examination coverage for this weld is approximately 63 percent.

RPV 2B11-RPV-N3A B3.90 The examination coverage for this weld is approximately 66 percent.

RPV 2B11-RPV-N3B B3.90 The examination coverage for this weld is approximately 66 percent RPV 2B11-RPV-N3C B3.90 The examination coverage for this weld is approximately 66 Page 4 of 5

RELIEF REQUEST: RR-12 (R v. 0)

SUBJECT:

EXAMINATION CATEGORY B-D, EXAMINATION COVERAGE TABLE 1" *~ 2 - - ,

System Component item No. Remarks - - ,

percent.

RPV 2B11-RPV-N3D B3.90 The examination coverage for this weld is approximately 66 l percent. {

RPV 2B11-RPV-N4A B3.90 The examination coverage for this weld is approximately 61 percent.

RPV 2B11-RPV-N4B B3.90 The examination coverage for this weld is approximately 65 percent. l RPV 2B11-RPV-N4C B3.90 The examination coverage for this weld is approximately 61 percent.

RPV 2B11-RPV-N4D B3.90 The examination coverage for this weld is approximately 65 l percent.

RPV 2B11-RPV-NSA B3.90 The examination coverage for this weld is approximately 62 percent.

RPV 2B11-RPV-NSB B3.90 The examination coverage for this weld is approximately 62 percent.

RPV 2B11-RPV-N6A B3.90 The examination coverage for this weld is approximately 70 l percent.

RPV 2B11-RPV-N6B B3.90 The examination coverage for tnis weld is approximately 70 percent.

l RPV 2B11-RPV-N7 B3.90 The examination coverage for this weld is approximately 70 )

percent.

RPV 2B11-RPV-NBA B3.90 The examination coverage for this weld is approximsely 62 percent.

RPV 2B11-RPV-N88 B3.90 The examination coverage for this weld is approximately 62 percent.

RPV 2B11-RPV-N9 B3.90 The examination coverage for this weld is approximately 60 percent.

RPV 2-B11-RPV-N11 A-lRS B3.100 The examination coverage for this weld is approximately 89

, percent.

RPV 2-B11-RPV-N118-IRS B3.100 The examination coverage for this weld is approximately 89 percent.

RPV 2-B11-RPV-N2B-IRS B3.100 The examination coverage for this weld is approximately 89 percent.

I

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

2. Section 55a (@55a), Codes and Standards, of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.55a)

3. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds 1 l

Page 5 of 5

I l

RELIEF REQUEST: RR-13 (Rsv. 0) l

SUBJECT:

EXAMINATION CATEGORY B-J, EXAMINATION COVERAGE COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Class 1 pressure retaining welds in piping subject to examination per Table IWB-2500-1, Examination Category B-J, at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

During the Third Inspection interval, BSEP is implementing ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds. ASME Code Case N-460 allows a reductior, of examination coverage provided the reduction in coverage for a given weld is less than 10 percent.

REQUESTED RELIEF:

Reliefis requested from the alternative requirements specified in ASME Code Case N-460.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting approval to credit the limited examination of the components listed in Table 1. Because of physical obstructions and/or component configuration, the examination coverage for these components would not meet the alternative requirements specified in ASME Code Case N-460.

The acceptable deviation from the alternative requirements specified in ASME Code Case N-460 has been evaluated by CP&L, and CP&L has determined that performing the required examinations on the component identified in Table 1, to the maximum extent practical, will provide an acceptable level of quality and safety for the following reasons:

1.Section XI of the ASME Code was issued January 1,1970. At the time of issuance, the design of BSEP, Units 1 and 2, was at a stage where literal compliance with the access requiremente outlined in the ASME Section XI Code was not possible. For this reason, limitation associated with the components listed in Table 1 prevented CP&L from obtaining the required examination coverage specified in ASME Code Case N-460. In order to obtain required examination coverage, CP&L would have to implement design modification.

Implementation of a design modification for these components would result in a significant hardship to CP&L without a compensating increase in quality and safety.  ;

i l l 2. Paragraph (g)(4) of 10 CFR 50.55a, Codes and Standards, requires that Class 1 components meet the requirements set forth in the ASME Section XI Code incorporated by

- reference in paragraph (b), to the extent practical, within the limitation of design, geometry, and material of construction of the components. Since it was recognized that some plants Page 1 of 3

RELIEF REQUEST: RR-13 (Rsv. 0)

SUBJECT:

EXAMINATION CATEGORY B-J, EXAMINATION COVERAGE (such as BSEP) were built before some of the ASME Standards were written, the above provisions outlined in 10 CFR 50.55a(g)(4) were written to address this situation. Pursuant to 55a(g)(4), CP&L examined the components listed in Table 1, to the maximum extent practical, during the Second Inspection Intewal. During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

CP&L will also continue to evaluate advance techniques and incorporate them, to the extent practical, in the Third Inspection Interval as they become available.

3. The extent of the welds not examined represents a small percentage of the total length of welds examined in accordance with Examination Category B-J. Thus, CP&L is confident that generic degradation of components within this Examination Category would be detected.

4. In addition to the examination specified in Examination Category B-J, CP&L performs a pressure test of the components listed in Table 1 each refueling outage in accordance with Examination Category B-P. The successful completion of these pressure tests will provide assurance of the component's structure integrity. If a defect is detected during one of these pressure tests, corrective measures would be taken prior to returning the component to service.

PROPOSED ALTERNATIVE:

None During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

TABLE 1 :

System Component - item No. Remarks CS 1E213-1-3-FWCSA6 B9.11 The examination coverage for this weld is approximately 88 i percent.

CS 1E217-3-7-FWCSB3 89.11 The examination coverage for this weld is approximately 81 percent.

CS 1E21FF-8-FW1CS17 B9.11 The examination coverage for this weld is approximately 64 percent.

RCR 1832RECIRC-22-AM-4 B9.11 The examination coverage for this weld is approximately 50 percent.

RCR 1B32RECIRC-28-A-16 B9.11 The examination coverage for this weld is approximately 60 percent.

RCR 1832RECIRC-28-A-6 B9.11 The examination coverage for this weld is approximately 54 percent.

RCR 1832RECIRC-28-B-9 B9.11 The examination coverage for this weld is approximately 36 l percent. )

RHR 1E1184-3-84-FWRHRA3 89.11 The examination coverage for this weld is approximately 86 percent.

RCR 1832RECIRC-28-A-9BC-1 B9.11 The examination coverage for this weld is approximately 55 percent.

Page 2. of 3

RELIEF REQUEST: RR-13 (Rsv. 0)

SUBJECT:

EXAMINATION CATEGORY B-J, EXJ4MINATION COVERAGE

TABLE C W'r " "i - "

• 4 O'VeW' -

4 System Component o '

Item No. Rs5rksh {W - - ' - ,

RCR 1832RECIRC-22-BM-3BC 09.11 The examination coverago io! this weld is approximately 63 percent.

CS 2E213-2-3-FWW5 B9.11 The examination coverage for this weld is approximately 74 percent.

MS 2B21PS1 A3-24-SWJ B9.11 The examination coverage for this weld is approximately 50 percent.

MS 2B21PS1 AS-24-FWA6 B9.11 The examination coverage for this weld is approximately 75 percent.

MS 2B21PS1D5-24-SWA B9.11 The examination coverage for this weld is approximately 50 percent.

RCR 2B32FF-12-FWRRA10A B9.11 The examination coverage for this weld is approximately 68 percent.

RCR 2B32FF-12-FWRRA13A 89.11 The examination coverage for this weld is approximately 36 percent.

RCR 2B32RECIRC-22-BM-2 B9.11 The examination coverage for this weld is approximately 50 percent.

RCR 2B32RECIRC-28-B-14 B9.11 The examination coverage for this weld is approximately 50 percent.

RCR 2B32RECIRC-28-B-9 B9.11 The examination coverage for this weld is approximately 80 percent.

RCR 2B32RECIRC-4-A-6 B9.11 The examination coverage for this weld is approximately 50 percent.

RCR 2832RECIRC-4-B-6 B9.11 The examination coverage for this weld is approximately 50 percent.

RCR 2B32RECIRC-4-B-7 89.11 The examination coverage for this weld is approximately 50 percent.

RHR 2E1184-3-84-FWR4 89.11 The examination coverage for this weld is approximately 64 percent.

RWC 2G3114-1-14-FW1954A B9.11 The examination coverage for this weld is approximately 75 percent.

RCR 2B32RECIRC-28-A-12BC B9.31 The examination coverage for this weld is approximately 49 percent.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

2. Section 55a (@55a), Codes and Standards, of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.55a)

3. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds Page 3 of 3

RELIEF REQUEST: RR-14 (R:;v. 0)

SUBJECT:

EXAMINATION CATEGORY C-F-2, EXAMINATION COVERAGE COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Class 2 pressure retaining welds subject to examination per Table IWC-2500-1, Examination Category C-F-2, at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. j ASME SECTION XI CODE REQUIREMENT:

During the Third Inspection Interval, BSEP is implementing ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds. ASME Code Case N-460 allows a reduction of examination coverage provided the reduction in coverage for a given weld is less than 10 percent.

REQUESTED RELIEF:

Relief is requested from the alternative requirements specified in ASME Code Case N-460.

BASIS FOR REQUESTING RELIEF: )

In accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting approval to credit the limited examination of the components listed in Table 1. Because of physical obstructions and/or component configuration, the examination coverage for these components would not meet the alternative requirements specified in ASME Code Case N-460.

The acceptable deviation from the alternative requirements specified in ASME Code Case N-460 has been evaluated by CP&L, and CP&L has determined that performing the required examinations on the component identified in Table 1, to the maximum extent practical, will provide an acceptable level of quality and safety for the following reasons:

1.Section XI of the ASME Code was issued January 1,1970. At the time of issuance, the design of BSEP, Units 1 and 2, was at a stage where literal compliance with the access requirements outlined in the ASME Section XI Code was not possible. For this reason, limitation associated with the components listed in Table 1 prevented CP&L from obtaining the required examination coverage specified in ASME Code Case N-460. In order to obtain required examination coverage, CP&L would have to implement design modification.

Implementation of a design modification for these components would result in a significant hardship to CP&L without a compensating increase in quality and safety.

2. Paragraph (g)(4) of 10 CFR 50.55a, Codes and Standards, requires that Class 2 components meet the requirements set forth in the ASME Section XI Code incorporated by reference in paragraph (b), to the extent practical, within the limitation of design, geometry, and material of construction of the components. Since it was recognized that some plants Page 1 of 3

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RELIEF REQUEST: RR-14 (R:v. 0) I

SUBJECT:

EXAMINATION CATEGORY C-F-2, EXAMINATION COVERAGE (such as BSEP) were built before some of the ASME Standards were written, the above provisions outlined in 10 CFR 50.55a(g)(4) were written to address this situation. Pursuant to @55a(g)(4), CP&L examined the components listed in Table 1, to the maximum extent practical, during the Second Inspection Interval. During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1, to the maximum extent practical.

l CP&L will also continue to evaluate advance techniques and incorporate them, to the extent practical, in the Third Inspection Interval as they become available.

3. The extent of the welds not examined represents a small percentage of the total length of welds examined in accordance with Examination Category C-F-2. Thus, CP&L is confident l that generic degradation of components within this Examination Category would be detected.

4. In addition to the examination specified in Examination Category C-F-2, CP&L performs a pressure test of the components listed in Table 1 each inspection Period in accordance with Examination Category C-H. The successful completion of these pressure tests will provide assurance of the component's structure integrity. If a defect is detected during one of these pressure tests, corrective measures would be taken prior to returning the component tc service.

PROPOSED ALTERNATIVE:  ;

None During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1, to the maximum extent practical. l l

d TABLE 1: -

System Component . ltem No. Remarks - - '

CS 1E216-39-SWC C5.51 The examination coverage for this weld is approximately 70 l percent.

RHR 1E11106-13-FW150 C5.51 The examination coverage for this weld is approximately 35 percent.

RHR 1E1144-15-SWA C5.51 The examination coverage for this weld is approximately 89 percent.

RHR 1E1146-15-FW60-2 C5.51 The examination coverage for this weld is approximately 73

percent.

RHR 2E1138-109-FW48D C5.51 The examination coverage for this weld is approximately 75 percent.

RHR 2E114-155-FW5 C5.51 The examination coverage for this weld is approximately 83 percent.

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Page 2 of 3

RELIEF REQUEST: RR-14 (R:v. 0)

SUBJECT:

EXAMINATION CATEGORY C-F-2, EXAMINATION COVERAGE

REFERENCES:

l 1. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) l 2. Section 55a (@55a), Codes and Standards, of Part 50 of Title 10 of the Code of Federal l Regulations (10 CFR 50.55a) l 3. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds l

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l Page 3 of 3

RELIEF REQUEST: RR-15 (R:;v. 0)

SUBJECT:

SEQUENCE OF COMPONENT EXAMINATIONS COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Class 1 and 2 components subject to the requirements of IWB-2420(a) and IWC-2420(a) at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, respectively.

ASME SECTION XI CODE REQUIREMENT:

Paragraph IWB-2420(a) and IWC-2420(a) requires the sequence of component examinations established during the First inspection Interval is to be repeated during each successive inspection interval, to the extent practical.

REQUESTED RELIEF:

Relief is requested from the requirements specified in IWB-2420(a) and IWC-2420(a) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use an alternative requirement to those specified in paragraph IWB-2420(a) and IWC-2420(a). CP&L proposes to sequence component examinations, established during the Second Inspection interval, to the extent practical.

The alternative requirement discussed above has been evaluated by CP&L, and CP&L has determined that sequencing of component examinations established during the Second Inspection Interval, to the extent practical, will provide an acceptable level of quality and safety for the following reasons:

1. During the First inspection Interval, BSEP was required to update the ISI Program to the latest Edition and Addenda of the ASME Section XI Code incorporated by reference in 10 CFR 50.55a each inspection Period (i.e., every 40 months). Accordingly, BSEP implemented several Editions and Addenda of the ASME Section XI Code (e.g.,1970 Edition,1974 Edition with Summer 1975 Addenda, and 1977 Edition with Summer 1978 Addenda). In several cases, the extent and/or frequency of examination specified in Table IWB-2500-1 and IWC-2500-1 listed in these Editions and Addenda have changed significantly in the 1989 Edition of the ASME Section XI Code. For example, the selection criteria outlined in the 1977 Edition (with Summer 1978 Addenda) for Examination Category C-F does not match the selection criteria outlined in the 1989 Edition for Examination Category C-F-1 or C-F-2. Thus, sequencing component examinations established during the l

Page 1 of 2 i

RELIEF REQUEST: RR-15 (R:v. 0)

SUBJECT:

SEQUENCE OF COMPONENT EXAMINATIONS First inspection Interval in the Third Inspection Interval is impractical and would constitute a hardship to BSEP without a compensating increase in quality and safety.

l

2. During the First inspection Interval and the establishment of the Second Inspection Interval, minimum examination completion percentages were applied to the item Number (not the <

Category as currently required). During this period of time, BSEP interpreted the requirements of IWB-2412(a) and IWC-2412(b) to apply to each item Number. This approach required examiners to enter radiation fields more than once to complete the required examinations. For example, the Head-to-Flange weld was divided into thirds and one-third of the weld was examined each Inspection Period. For the Third Inspection Interval, percentage for each applicable Examination Category has been applied as required by the 1989 Edition of the ASME Section XI Code. Thus, following the same examination sequence established during previous intervals, without consideration for ALARA, constitutes a hardship to BSEP without a compensating increase in quality and safety.

3. The requirement of IWB-2412(a) and IWC-2412(a) is to ensure initially selected components are reexamined during each inspection Interval, to the extent practical. The phrase "to the extent practical" allows the owner to take acceptable deviations from this requirement.

CP&L considered re-sequencing components to reduce personnel exposure an acceptable deviation. During the Third Inspection Interval, CP&L has re-selected the components examined during the Second Inspection Interval, as required, to comply with the applicable Examination Categories. CP&L is also maintaining the same examination sequence, as established during the Second Inspection Interval, for those components that did not pose a personnel exposure hardship if the same sequence was maintained. For those components j that posed a hardship, CP&L has optimize their examination sequence to minimize l personnel exposure as allowed by IWB-2412(a) and IWC-2412(a). To extent practical, CP&L has re-sequenced these examinations to minimize the time period between l examination. For example, the complete Head-to-Flange weld is scheduled to be examined in the First inspection Period.

PROPOSED ALTERNATIVE:

During the Third inspection Interval, CP&L will sequence component examinations established during the Second Inspection Interval, to the extent practical.

REFERENCE:

i

1. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

Page 2 of 2

I i RELIEF REQUEST: RR-16 (Rev. 0)

SUBJECT:

VT-2 EXAMINATION PERSONNEL QUALIFICATIONS (CODE CASE N-546)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the qual:fication of personnel performing visual (VT-2) examination of Class 1,2, and 3 components at the Brunswick Steam Electric Plant (BSEP),

Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Subarticle IWA-2300 provides the qualifications of nondestructive examination (NDE) personnel. Paragraph IWA-2312 states that personnel performing visual examinations shall be qualified and certified to comparable levels of qualifications as defined in SNT-TC-1A and the employer's written practice.

REQUESTED RELIEF:

Relief is requested from the applicable qualification requirements for personnel performing visual (VT-2) examination of Class 1,2, and 3 components specified in IWA-2300 of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use alternative requirements for the qualification of visual (VT-2) examination personnel to those specified in Subarticle IWA-2300. CP&L proposes to implement the alternative requirements outlined in ASME Code Case N-546, Alternative Requirements for Qualification of VT-2 Examination Personnel.

ASME Code Case N-546 has been evaluated by CP&L, and CP&L has determined that implementation of this ASME Code Case for the visual (VT-2) examination of Class 1,2, and 3 components will provide an acceptable level of quality and safety for the following reasons:

1. The purpose of a visual (VT-2) examination is to locate evidence of leakage from pressure retaining components during the conduct of a system pressure test. Unlike other visual examinations (VT-1 or VT-3), personnel locating evidence of leakage do not require the same level of qualification requirements needed to determined the mechanical and structural condition of components. The plant experience, training, and visual acuity requirements specified in this ASME Code Case provide adequate qualification for personnel performing visual (VT-2) examinations at BSEP, Units 1 and 2.

j j 2. This ASME Code Case allows the visual (VT-2) examination of properly trained personnel that are already present during the performance of a system pressure test (e.g., Operators, f System Engineers, etc.). Implementation of this ASME Code Case would eliminate requiring

! personnel (such as QC personnel) who only perform the VT-2 examination to enter a Page 1 of 2

RELIEF REQUEST: RR-16 (Rsv. 0)

SUBJECT:

VT-2 EXAMINATION PERSONNEL QUALIFICATIONS (CODE CASE N-546) radiation field. This reduction in number of personnel involved in the pressure test will reduce personnel exposure at BSEP. Therefore, the imposition of the qualification requirements for personnel performing visual (VT-2) examination specified in IWA-2300 of the 1989 Edition of the ASME Section XI Code constitutes a hardship to BSEP without a compensating increase in quality and safety.

3. ASME Code Case N-546 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on August 24,1995. This approval signifies the requirements outlined in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants.

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the alternative requirements of ASME Code Case N-546.

REFERENCES:

1. ASME Code Case N-546, Alternative Requirements for Qualification of VT-2 Examination Personnel (Approved Date: August 24,1995)

2. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) l l

Page 2 of 2 l l l I

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RELIEF REQUEST: RR-17 (R:v. 0)

SUBJECT:

LEAKAGE AT BOLTED CONNECTIONS COMPONENTS FOR WHICH RELIEF iS REQUESTED:

This request for relief is applicable to the Class 1, 2 and 3 pressure retaining components subject to system pressure testing at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

! If leakage occurs at a bolted connection, paragraph IWA-5250(a)(2) requires the removal of the bolting, a visual (VT-3) examination of the bolting for corrosion, and an evaluation in tccordance with paragraph IWA-3100.

l l

REQUESTED RELIEF:

Relief is requested from the corrective measures requirements specified in paragraph IWA-5250(a) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF: i i

in accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting l approval to use alternative requirements to those specified in paragraph IWA-5250(a). CP&L proposes to implement the following alternative requirements:

(1)If bakage is discovered at a Class 1 bolted connection, the leakage will be stopped or an engineering evaluation will be performed in accordance with an approved plant procedure to address acceptability of the connection.

(2)If leakage is discovered at a Class 2 or 3 bolted connection in systems transporting a corrosive medium (borated or salt water), a visual (VT-3) examination will be performed on the connection for evidence of degradation. Upon completion of the visual (VT-3) examination, an engineering evaluation will be performed in accordance with an approved plant procedure to address acceptability of the connection.

The alternative requirements discussed above have been evaluated by CP&L, and CP&L has determined that implementation of these alternative requirements will provide an acceptable l level of quality and safety for the following reasons:

1. Paragraph IWA-5250(a)(2) requires that if leakage occurs at a bolted connection, the bolting '

shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100. CP&L has evaluated the implementation of this requiremer,t and has determined this Code provision can have an adverse impact on plant operation and personnel exposure.

i For example, the disassembly and re-assembly of components for the performance of the visual (VT-3) examination on the bolting has the potential to delay to the return of a safety l

related system to service, delay of plant startup following the completion of the Class 1  !

Page 1 of 3

1

. RELIEF REQUEST: RR-17. (Rav. 0)

SUBJECT:

LEAKAGE AT BOLTED CONNECTIONS 1

leakage test, and the potential for significant additional radiation dose. Thus, the imposition of the requirements specified in paragraph IWA-5250(a)(2) constitutes a hardship to BSEP q without a compensating increase in quality and safety. J

- 2. Since the normal Class 1 pressure boundary of a BWR contains only demineralized water and a significant portion of the pressure retaining bolting used this applications are made of stainless steel materials, the likelihood of severe corrosion is minimal. While stainless steel bolting is more susceptible to stress corrosion cracking under certain conditions, the detection of this type of corrosion on botting material is difficuit with the visual (VT-3) visual examination technique.

3. A majority of the bolted connection leakage found during the ASME Section XI leakage test each refueling outage are associated with the Control Rod Drive (CRD) housing connections. This is a common industry occurrence and in most cases the leakage stops within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of being pressurized to 1000 psig. In addition, a number of CRDs are replaced each refueling outage, As with current practice, the bolting is replaced and a baseline visual (VT-1) examination performed prior to installetion. Should leakage be detected at these CRDs, the provision of paragraph IWA-5250(a)(2) would mandate removal of the bolting and a VT-3 examination to be performed on bolting that has just been examined and not been exposed to the service environment Thus, the removal of the bolting for the sole purpose of performing a visual (VT-3) examination would result in personnel exposure without a compensating increase in quality and safety.

4. The majority of the Class 2 systems transports a non-corrosive medium such as demineralized water, nitrogen, or air. Since the medium is non-corrosive, the bolted connections associated with these system would not be susceptible to severe corrosion.

Thus, the disassembly and re-assembly of a bolted connection for the performance of the j visual (VT-3) examination of the bolting has the potential to delay to the return of a safety j related system to service.  !

PROPOSED ALTERNATIVE: I During the Third Inspection Interval, CP&L will implement the following alternative requirements:  ;

S -(1)If leakage is discovered at a Class 1 bolted connection, the leakage will be stopped or an engineering evaluation will be performed in accordance with an approved plant procedure to address acceptability of the connection.

(2)If leakage is discovered at a Class 2 or 3 bolted connection in systems transporting a corrosive medium (borated or salt water), a visual (VT-3) examination will be performed on ,

the- connection for evidence of degradation. Upon completion of the visual (VT-3) j examination, an engineering evaluation will be performed in accordance with an approved plant procedure to address acceptability of the connection.

l Page 2 of 3'

RELIEF REQUEST: RR-17 (R:,v. 0) ,

1

SUBJECT:

LEAKAGE AT BOLTED CONNECTIONS

REFERENCES:

1. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

I 1

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Page 3 of 3

RELIEF REQUEST: RR-18 (Rev. 0) l

SUBJECT:

TRANSFER OF PROCEDURE QUALIFICATION RECORDS (CODE CASE N-573)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicab!e to the welding and brazing procedure qualification records for Class 1,2, and 3 components (including their supports) at the Brunswick Steam Electric Plant l

(BSEP), Units 1 and 2.

I ASME SECTION XI CODE REQUIREMENT:

! Paragraph IWA-4400(a) of the ASME Section XI Code,1989 Edition, requires welding (including l brazing) to be performed in accordance with Welding Procedure Specifications (WPS) that have l been qualified by the owner or repair organization in accordance with the requirements of the l codes specified in the Repair Program in accordance with paragraph IWA-4120.

l l

REQUESTED RELIEF:

l

Relief is requested from the requirements specified in paragraph IWA-4400(a) of the ASME l Section XI Code,1989 Edition.

l l BASIS FOR REQUESTING RELIEF:

l In accordance with 10 CFR 50.55a(a)(3)(i), Carolina Power and Light (CP&L) is requesting approval to implement alternative requirements to those specified in paragraph IWA-4400(a).

CP&L proposes to implement the alternative requirements outlined in ASME Code Case N-573, Transfer of Procedure Qualification Records Between Owners.

l l

The alternative requirements outlined in ASME Code Case N-573 have been evaluated by  !

l CP&L., and CP&L has determined that implementation of these requirements will provide an l acceptable level of quality and safety for the following reasons:

1. The alternative requirements of ASME Code Case N-573 allows the transfer of a procedure qualification record (PQR) qualified by one owner to another owner. ASME Code Case N- l 573 requires the owner to certify that the testing was performed in accordance with ASME ,

Section IX and the procedure qualification was conducted in accordance with a Quality Assurance Program that satisfies the requirements of paragraph IWA-1400. CP&L has evaluated the alternative requirements specified for the owner qualifying the POR and determined them acceptable for assuring quality and safety at BSEP.

2. The alternative requirements of ASME Code Case N-573 specify an acceptable level of controls for the owner accepting a PQR. For example, CP&L would be required to (1) review and accept the responsibility of the POR and (2) demonstrate technical competence in r application of the received POR by completing a performance qualification test using the i

Page 1 of 2

RELIEF REQUEST: RR-18 (R3v. 0)

SUBJECT:

TRANSFER OF PROCEDURE QUALIFICATION RECORDS (CODE CASE N-573) parameters of a resulting WPS. These actions will ensure the acceptability of the POR prior to it being used at BSEP.

3. ASME Code Case N-573 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on March 12,1997. This approval signifies the requirements t outlined in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants. CP&L agrees that implementation of this ASME Code Case will

! provide an acceptable level of qualiiy and safety.

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the alternative requirements of ASME Code Case N-573.

REFERENCES:

l

1. ASME Code Case Code Case N-573, Transfer of Procedure Qualification Records Between l Owners (Approved Date: March 12,1997)

2. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

Page 2 of 2

RELIEF REQUEST: RR-19 (Rsv. 0)

SUBJECT:

WALL THICKNESS RESTORATION OF CLASS 2 AND HIGH ENERGY CLASS 3 CARBON STEEL PIPING (CODE CASE N-561)

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the Class 2 and high-energy Class 3 carbon steel piping at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Article IWA-4000 provides the rules and requirements for repair of pressure retaining components.

REQUESTED RELIEF:

Relief is requested to use the requirements specified in ASME Code Case N-561, Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class 3 Carbon Steel Piping, as a supplement to the rules and requirements specified in Article IWA-4000 of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with,10 CFR 50.55a(a)(3)(i), Carolina Power and Light (CP&L) is requesting approval to implement the requirements of ASME Code N-561 for Class 2 and high-energy (i.e.,

greater than 200 F or 275 psig maximum operating conditions) Class 3 carbon steel piping.

CP&L proposes to implement the requirements specified in this ASME Code Case as a supplement to the rules and requirements specified in Article IWA-4000.

The reqvirements outlined in ASME Code Case N-561 have been evaluated by CP&L, and CP&L has determined that implementation of these requirements will provide an acceptable level of quality and safety for the following reasons:

1. The requirements of ASME Code Case N-561 allows carbon steel piping experiencing internal thinning or pitting to be restored by means of a weld-deposited carbon or low-alloy steel reinforcement (i.e., weld overlay) on the outside surface of the piping. This type of repair was approved for austenitic stainless steel piping (ASME Code Case N-504) and authorized for use by the Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.147 (Revision 11). CP&L has reviewed the requirements of ASME Code Case N-561 and ASME Code Case N-504 and determined the controls governing the design, installation, and examination to be comparable. Thus, CP&L has determined that the implementation of ASME Code Case N-561 would provide the same acceptable level of quality and safety at BSEP as ASME Code Case N-504.

2. The General Requirements specified in ASME Code Case N-561 will provide appropriate controls for evaluating the wall thickness restoration. An initial evaluation must be perforrned 1

Page 1 of 2

i

}

l RELIEF REQUEST: RR-19 (R::v. 0)

SUBJECT:

WAL-L THICKNESS RESTORATION OF CLASS 2 AND HIGH ENERGY CLASS 3 CARBON STEEL PIPING (CODE CASE N-561) to establish the existing average wall thickness, the extent of the degradation, and impact of the repair on the piping. This evaluation is also required to consider the cause of degradation. CP&L has evaluated these requirements and determined them to be acceptable. If this ASME Code Case is used, CP&L will perform this evaluation in accordance with a plant approved procedure.

l l 3. The wall thickness restoration activity will be performed in accordance with CP&L's l Repair / Replacement Program. Performance of this activity in accordance with CP&L's Repair / Replacement Program will ensure the requirements specified in paragraph IWA-4140 l are met and the services of the Authorized Inspection Agency are used. Upon completion of this activity, a NIS-2 or NIS-2 A Form will be completed and approved. )

4. ASME Code Case N-561 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on December 31,1996. This approval signifies the requirements outlined in this ASME Code Case will provide an acceptable level of quality and safety for nuclear power plants. CP&L agrees that the implementation of this ASME l

Code Case will provide an acceptable level of quality and safety.

1 PROPOSED ALTERNATIVE:

[ During the Third Inspection Interval, CP&L will implement (as required) the requirements of l ASME Code Case N-561. CP&L will not implement these provisions on conditions involving corrosion-assisted cracking or any other form of cracking.

REFERENCES:

i l

1. ASME Code Case Code Case N-561, Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class 3 Carbon Steel Piping (Approved Date:

December 31,1996) i

2. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

3. Regulatory Guide 1.147, *lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1" (Revision 11) l Page 2 of 2

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RELIEF REQUEST: RR-20 (Rov. 0) l

SUBJECT:

WALL THICKNESS RESTORATION OF CLASS 3 MODERATE ENERGY CARBON STEEL PIPING (CODE CASE N-562) l COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to the Class 3 moderate energy carbon steel piping at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

l ASME SECTION XI CODE REQUIREMENT:

Article IWA-4000 provides the rules and requirements for repair of pressure retaining components.

l REQUESTED RELIEF:

l Relief is requested to use the requirements specified in ASME Code Case N-562, Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate Energy Carbon Steel Piping, as a supplement to the rules and requirements specified in Article IWA-4000 of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(i), Carolina Power and Light (CP&L) is requesting approval to implement the requirements of ASME Code N-562 for Class 3 moderate energy (i.e., less than or equal to 200 F or 275 psig maximum operating conditions) carbon steel piping.

CP&L proposes to implement the requirements specified in this ASME Code Case as a supplement to the rules and requirements specified in Article IWA-4000. l The requirements outlined in ASME Code Case N-562 have been evaluated by CP&L, and CP&L has determined that implementation of these requirements will provide an acceptable level of quality and safety for the following reasons:  ;

1. The requirements of ASME Code Case N-562 allows carbon steel piping experiencing internal thinning or pitting to be restored by means of a weld-deposited carbon or low-alloy steel reinforcement (i.e., weld overlay) on the outside surface of the piping. This type of repair was approved for austenitic stainless steel piping in ASME Code Case N-504 and authorized for use by the Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.147 (Revision 11). CP&L has reviewed the requirements of ASME Code Case N-562 and ASME Code Case N-504 and determined the controls governing the design, installation, and examination to be comparable. Thus, CP&L has determined that the implementation of ASME Code Case N-562 would provide the same acceptable level of quality and safety at BSEP as ASME Code Case N-504.

2. The General Requirements specified in ASME Code Case N-562 will provide appropriate controls for evaluating the wall thickness restoration. An initial evaluation must be performed Page 1 of 2

i RELIEF REQUEST: RR-20 (R:;v. 0)

SUBJECT:

WALL THICKNESS RESTORATION OF CLASS 3 MODERATE ENERGY CARBON STEEL PIPING (CODE CASE N-562) to establish the existing average wall thickness, the extent of the degradation, and impact of the repair on the piping. This evaluation is also required to consider the cause of degradation. CP&L has evaluated these requirements and determined them to be acceptable. If this ASME Code Case is used, CP&L will perform this evaluation in )

accordance with a plant approved procedure.

3. The wall thickness restoration activity will be performed in accordance with CP&L's Repair / Replacement Program. Performance of this activity in accordance with CP&L's Repair / Replacement Program will ensure the requirements specified in paragraph IWA-4140 are met and the services of the Authorized Inspection Agency are used. Upon completion of this activity, a NIS-2 or NIS-2 A Form will be completed and approved.

4. ASME Code Case N-562 was approved by the ASME's Main Committee and the Board of Nuclear Codes and Standards on December 31,1996. This approval signifies the requirements outlined in this ASME Code Case will provide an acceptable -level of quality and safety for nuclear power plants. CP&L agrees that the implementation of this ASME Code Case will provide an acceptable level of quality and safety.

PROPOSED ALTERNATIVE:

, During the Third Inspection Interval, CP&L will implement (as required) the requirements of ASME Code Case N-562. CP&L will not implement these provisions on conditions involving corrosion-assisted cracking or any other form of cracking.

REFERENCES:

1. ASME Code Case Code Case N-562, Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate Energy Carbon Steel Piping (Approved Date: December 31,

1996)

2. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) l

3. Regulatory Guide 1.147," Inservice inspection Code Case Acceptability, ASME Section XI, ,

1 Division 1" (Revision 11) l l

l l

l l

l Page 2 of 2  ;

l.. _ --

)

i RELIEF REQUEST: RR-21 (Rev. 0)

SUBJECT:

EXAMINATION CATEGORIES WITH LESS THAN THREE ITEMS OR WELDS COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Code Class 1 and 2 components at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

Paragraphs IWB-2412(a) and IWC-2412(a) requires that the examinations in each Examination Category be completed in accordance with the a- antage requirements of Tables IWB-2412-1 and IWC-2412-1, respectively.

REQUESTED RELIEF:

Relief is requested from the requirements specified in paragraphs IWB-2412(a) and IWC-2412(a) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use an alternative requirement to those specified in paragraph IWB-2412(a) and IWC-2412(a) of the ASME Section XI Code,1989 Edition. CP&L proposes tre use the requirements outlined in paragraph IWB-2412(a) and IWC-2412(a) of the ASME Section XI Code,1989 Edition, with the following exception: If there is less than three items or welds to be examined in an Examination Category, the items or welds may be examined in any two periods, or in any one period if there is only one item or weld, in lieu of the percentage requirements of Table IWB-2412-1 or IWC 2412-1. i i

The alternative requirement discussed above has been evaluated by CP&L, and CP&L has l determined that implementation of these alternative requirements will provide an acceptable level of quality and safety for the following reasons:

1. Paragraphs IWB-2412(a) and IWC-2412(a) of the 1989 Edition infers that if a plant has less ,

than three items or welds, the owner must still distribute the corresponding examinations over three inspection Periods to meet the percentage requirements. This results in dividing )

an examination between Inspection Periods or performing an examination more than once '

during the same Interval. Neither provides an additional level of quality or safety and both impose an unnecessary burden on CP&L due to equipment and scaffolding setup time and personnel radiation exposure.

4 Page 1 of 2 w _-__

RELIEF REQUEST: RR-21 (Rsv. 0)

SUBJECT:

EXAMINATION CATEGORIES WITH LESS THAN THREE ITEMS OR WELDS

2. Recognizing this burden to the owners, paragraphs IWB-2412(a) and IWC-2412(a) were revised in the 1994 Addenda. Thus, permitting the owners with less than three items or welds in an Examination Category an alternative to the percentage requirements specified in Table IWB-2412-1 or IWC 2412-1. As evaluated by CP&L, this revision to these Code paragraphs provides an acceptable level of quality and safety at BSEP. Approval of this change to the ASME Section XI Code by the ASME Main Committee and the Board of Nuclear Codes and Standards also signifies this exception to the percentage requirements of Table IWB-2412-1 or IWC 2412-1 will provide an acceptable level of quality and safety for nuclear power plants.

3. The exception to the percentage requirements of Table IWB-2412-1 or IWC 2412-1 for Examination Category with less than three items or walds is a requirement specified in the 1995 Edition with the 1996 Addenda of the ASME Section XI Code. On December 3,1997, the Federal Register contained a notice to the public of the proposed change to 10 CFR 50.55a, Codes and Standards. This proposed change would incorporate by reference the use to the 1995 Edition with the 1996 Addenda of the ASME Section XI Code. In this proposed change to 10 CFR 50.55a, no limitations or modification to paragraphs IWB-2412(a) and IWC-2412(a) were made. Thus, the exception to the percentage requirements of Table IWB-2412-1 or IWC 2412-1 for Examination Category with less than three items or welds was determined to provide an acceptable level of quality and safety.

PROPOSED ALTERNATIVE: 1 During the Third Inspection Interval, CP&L will implement the requirements outlined in paragraph IWB-2412(a) and IWC-2412(a) of the ASME Section XI Code,1989 Edition, with the following exception: If there is less than three items or welds to be examined in an Examination Category, the items or welds may be examined in any two periods, or in any one period if there is only one item or weld, in lieu of the percentage requirements of Table IWB-2412-1 or IWC 2412-1.  !

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda), 1992 Edition with 1994 Addenda,1995 Edition with 1996 Addenda l 2.10 CFR Part 50, Section 55.a, Codes and Standards Page 2 of 2 u

RELIEF REQUEST: RR-22 (R:,v. 0)

SUBJECT:

ADDITIONAL EXAMINATIONS OF CLASS 1 COMPONENTS COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Code Class 1 components at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

i l

ASME SECTION XI CODE REQUIREMENT:

Paragraph IWB-2430(a) requires if examinations reveal indications exceeding the acceptance standards of Table IWB-3410-1, additional examinations are to be scheduled during the current l

outage. The additional examinations are to include the remaining welds, areas, or parts include-d in the inspection item listing which are scheduled for the current and subsequent inspection period. If the examinations for that inspection item are not scheduled in the subsequent period, the most immediate period containing scheduled examination shall be taken as the subsequent period.

REQUESTED RELIEF:

Relief is requested from the requirements specified in paragraph IWB-2430(a) of the ASME Section XI Code,1989 Edition.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(a)(3)(ii), Carolina Power and Light (CP&L) is requesting approval to use alternative requirements to those specified in paragraph IWB-2430(a) of the ASME Section XI Code,1989 Edition. CP&L proposes to use the requirements outlined in paragraph IWB-2430(a) of the ASME Section XI Code,1995 Edition with 1996 Addenda.

The alternative requirements discussed above have been evaluated by CP&L, and CP&L has determined that implementation of these alternative requirements will provide an acceptable level of quality and safety for the following reasons:

1

1. The requirements specified in paragraph IWB-2430(a) of the ASME Section XI Code,1989 Edition, infers that welds, areas, or parts scheduled for the subsequent inspection period are to be included even if the subsequent period is in the following inspection interval. Because of the equipment and scaffolding setup time and personnel radiation exposure to implement this requirement, the imposition of the additional examinations as described in the 1989 Edition of the ASME Section XI Code constitutes a hardship to BSEP without a

( compensating increase in quality and safety.

l

2. Recognizing the burden placed on the owner, paragraph IWB-2430(a) was revised in the

! 1991 Addenda of the ASME Section XI Code. Thus, permitting the owner to include an Page 1 of 2 L

i RELIEF REQUEST: RR-22 (R*,v. 0)

SUBJECT:

ADDITIONAL EXAMINATIONS OF CLASS 1 COMPONENTS l additional examinations of those welds, areas, or parts included in the inspection item equal l to the number scheduled to be performed during the present inspection period. As i evaluated by CP&L, this sampling of additional welds, areas, or parts provides an acceptable l

level of quality and safety at BSEP. Approval of this change to the ASME Section XI Code by the ASME Main Committee and the Board of Nuclear Codes and Standards also signifies this change will provide an acceptable level of quality and safety for nuclear power plants.

3. In addition, the revision to paragraph IWB-2430(a) requires the additional examination to be selected from components of similar material and service. Also, clarification was added that the addition selection may require inclusion of piping systems other than the one containing the flaw or relevant conditions. The inclusion of this addition requirement and clarification enhances the Code's intent for performing additional examination.

4. The changes to paragraph IWB-2430(a) incorporated in the 1991 Addends are the same requirements specified in the 1995 Edition with the 1996 Addenda of the ASME Section XI Code. On December 3,1997, the Federal Register contained a notice to the public of the proposed change to 10 CFR 50.55a, Codes and Standards. This proposed change would incorporate by reference the use to the 1995 Edition with the 1996 Addenda of the ASME Section XI Code, in this proposed change to 10 CFR 50.55a, no limitations or modification to paragraphs IWB-2430(a) were made. Thus, the requirements for additional examination were determined to provide an acceptable level of quality and safety.

PROPOSED ALTERNATIVE:

During the Third Inspection Interval, CP&L will implement the requirements outlined in paragraph IWB-2430(a) of the ASME Section XI Code,1995 Edition with 1996 Addenda.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda),1989 Edition with 1991 Addenda,1995 Edition with 1996 Addenda 2.10 CFR Part 50, Section 55.a Codes and Standards Page 2 of 2

RELIEF REQUEST: RR-23 (Rtv. 0)

SUBJECT:

EXAMINATION CATEGORY B-A, EXAMINATION COVERAGE l

COMPONENTS FOR WHICH RELIEF IS REQUESTED:

i This request for relief is applicable to Class 1 pressure retaining welds, in the reactor pressure vessel (RPV), subject to exa.mination per Table IWB-2500-1, Examination Category B-A. This request for relief will apply to Class 1 pressure retaining welds at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT: I l

Note 2 of Examination Category B-A defines the extent of the examination as essentially 100 percent of the weld length. During the Third Inspection Interval, BSEP is implementing ASME l Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds. ASME j Code Case N-460 allows a reduction of examination coverage provided the reduction in  !

coverage for a given weld is less than 10 percent.

REQUESTED RELIEF:

Relief is requested from the alternative requirements specified in ASME Code Case N-460.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting approval to credit the limited examination of the components listed in Table 1. Because of physical obstructions and/or component configuration, the examination coverage for these components would not meet the alternative requirements specified in ASME Code Case N-460.

The acceptable deviation from the alternative requirements specified in ASME Code Case N-460 has been evaluated by CP&L, and CP&L has determined that performing the required examinations on the component identified in Table 1, to the maximum extent practical, will provide an acceptable level of quality and safety for the following reasons:

1.Section XI of the ASME Code was issued January 1,1970. At the time of issuance, the design of BSEP, Units 1 and 2, was at a stage where literal compliance with the access requirements outlined in the ASME Section XI Code was not possible. For this reason, limitation associated with the components listed in Table 1 prevented CP&L from obtaining the required examination coverage specified in ASME Code Case N-460. In order to obtain l required examination coverage, CP&L would have to implement design modification.

l Implementation of a design modification for these components would result in a significant hardship to CP&L without a compensating increase in quality and safety.

2. Paragraph (g)(4) of 10 CFR 50.55a, Codes and Standards, requires that Class 1 components meet the requirements set forth in the ASME Section XI Code incorporated by Page 1 of 3

r l

RELIEF REQUEST: RR-23 (R::v. 0) l

SUBJECT:

EXAMINATION CATEGORY B-A, EXAMINATION COVERAGE reference in paragraph (b), to the extent practical, within the limitation of design, geometry, and material of construction of the components. Since it was recognized that some plants

! (such as BSEP) were built before some of the ASME Standards were written, the above provisions outlined in 10 CFR 50.55a(g)(4) were written to address this situation. Pursuant to @55a(g)(4), CP&L examined the components listed in Table 1, to the maximum extent practical, during the Second Inspection Interval. During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1, to the maximum extent practical.

CP&L will also continue to evaluate advance techniques and incorporate them, to the extent i practical, in the Third Inspection Interval as they become available.

3. The extent of the welds not examined represents a small percentage of the total length of welds examined in accordance with Examination Category B-A. Thus, CP&L is confident that generic degradation of components within this Examination Category would be detected. i

4. In addition to the examination specified in Examination Category B-A, CP&L performs a pressure test of the components listed in Table 1 each refueling outage in accordance with Examination Category B-P. The successful completion of these pressure tests will provide assurance of the component's structure integrity. If a defect is detected during one of these pressure tests, corrective measures would be taken prior to returning the component to service.

PROPOSED ALTERNATIVE:

None During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1, to the maximum extent practical. J i

TABLE .1 -

System Component ' Item No. Remarks RPV 1B11-RPV-F1 & F2 B1.30 This shell-to-flange weld was assigned two component identifications for tracking purposes. The combined 4 examination coverage for this weld is approximately 58 percent.

RPV 1811-RPV-C1, C2, & C3 B1.40 This head-to-flange weld was assigned three component identifications for tracking purposes. The combined examination coverage for this weld is approximately 73 percent.

RPV 2B11-RPV-E4A B1.12 The examination coverage for this weld is approximately 76 percent from the right side and approximately 75 percent from the left side.

RPV 2B11-RPV-F1 & F2 B1.30 This shell-to-flange weld was assigned two component identifications for tracking purposes. The combined examination coverage for this weld is approximately 58 I

percent.

Page 2 of 3 E

RELIEF REQUEST: RR-23 (Rsv. 0)

SUBJECT:

EXAMINATION CATEGORY B-A, EXAMINATION COVERAGE TABLE:16 m '

W *- ~' -

4

> m System Component , item No. Remarks.

RPV 2B11-RPV-C1, C2, & C3 B1.40 This head-to-flange weld was assigned three component identifications for tracking purposes. The combined examination coverage for this weld is approximately 68 percent.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

2. Section 55a (@55a), Codes and Standards, of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.55a)

3. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds l

l l

Page 3 of 3 e

i l

RELIEF REQUEST: RR-24 (Rsv. 0) {

)

SUBJECT:

EXAMINATION CATEGORY B-F, EXAMINATION COVERAGE COMPONENTS FOR WHICH RELIEF IS REQUESTED: l l

This request for relief is applicable to Class 1 pressure retaining dissimilar metal welds subject to examination per Table IWB-2500-1, Examination Category B-F, at the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

During the Third Inspection Interval, BSEP is implementing ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds. ASME Code Case N-460 allows a reduction of examination coverage provided the reduction in coverage for a given weld is less than 10 percent.

REQUESTED RELIEF:

Relief is requested from the alternative requirements specified in ASME Code Case N-460.

BASIS FOR REQUESTING RELIEF:

In accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting approval to credit the limited examination of the components listed in Table 1. Because of physical obstructions and/or component configuration, the examination coverage for these components would not meet the alternative requirements specified in ASME Code Case N-460.

The acceptable deviation from the alternative requirements specified in ASME Code Case N-460 has been evaluated by CP&L, and CP&L has determined that performing the required examinations on the component identified in Table 1 to the maximum extent practical will provide an acceptable level of quality and safety for the following reasons:

1.Section XI of the ASME Code was issued January 1,1970. At the time of issuance, the ,

design of BSEP, Units 1 and 2, was at a stage where literal compliance with the access l requirements outlined in the ASME Section XI Code was not possible. For this reason, limitation associated with the components listed in Table 1 prevented CP&L from obtaining the required examination coverage specified in ASME Code Case N-460. In order to obtain l required examination coverage, CP&L would have to implement design modification.

Implementation of a design modification for these components would result in a significant hardship to CP&L without a compensating increase in quality and safety.

2. Paragraph (g)(4) of 10 CFR 50.55a, Codes and Standards, requires that Class 1 components meet the requirements set forth in the ASME Section XI Code incorporated by reference in paragraph (b) to the extent practical within the limitation of design, geometry, and material of construction of the components. Since it was recognized that some plants Page 1 of 2 L

RELIEF REQUEST: RR-24 (R v. 0) l

SUBJECT:

EXAMINATION CATEGORY B-F, EXAMINATION COVERAGE (such as BSEP) were built before some of the ASME Standards were written, the above provisions outlined in 10 CFR 50.55a(g)(4) were written to address this situation. Pursuant to $55a(g)(4), CP&L examined the components listed in Table 1 to the maximum extent l practical during the Second Inspection Interval. During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

CP&L will also continue to evaluate advance techniques and incorporate them, to the extent practical, in the Third Inspection Interval as they become available.

3. The extent of the welds not examined represents a small percentage of the totallength of welds examined in accordance with Examination Category B-F. Thus, CP&L is confident that generic degradation of components within this Examination Category would be detected.

4. In addition to the examination specified in Examination Category B-F, CP&L performs a pressure test of the components listed in Table 1 each refueling outage in accordance with Examination Category B-P. The successful completion of these pressure tests will provide assurance of the component's structure integrity. If a defect is detected during one of these pressure tests, corrective measures would be taken prior to returning the component to service.

PROPOSED ALTERNATIVE:

None During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

i TABLE 1!

System Component '

ltem No. Remarks RHR 1832RD2B2-84-FWB33 B5.130 The examination coverage for this weld is approximately 76 percent.

RWC 1G3115-1-15-FWRWCUB2A B5.130 The examination coverage for this weld is approximately 87 percent.

RHR 2B32RD1A2-87-FWA33 B5.130 The examination coverage for this weld is approximately 50 percent.

RWC 1G3114-1-14-FW1949A B6.130 The examination coverage for this weld is approximately 75 percent.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda)

, 2. Section 55a ( 55a), Codes and Standards, of Part 50 of Title 10 of the Code of Federal l

Regulations (10 CFR 50.55a)

3. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds Page 2 of 2  !

L -- -

I RELIEF REQUEST: RR-25 (Rav. 0)

SUBJECT:

EXAMINATION CATEGORY C-B, EXAMINATION COVERAGE COMPONENTS FOR WHICH RELIEF IS REQUESTED:

This request for relief is applicable to Class 2 pressure retaining nozzle welds in vessel subject to examination per Table IWC-2500-1, Examination Category C-B, at the Brunswick Steam .

Electric Plant (BSEP), Units 1 and 2.

ASME SECTION XI CODE REQUIREMENT:

During the Third Inspection Interval, BSEP is implementing ASME Code Case N-460, Aiternative Examination Coverage for Class 1 and Class 2 Welds. ASME Code Case N-460 l allows a reduction of examination coverage provided the reduction in coverage for a given weld is less than 10 percent.

1 I

REQUESTED RELIEF: )

l Relief is requested from the alternative requirements specified in ASME Code Case N-460.

l j

BASIS FOR REQUESTING RELIEF

In accordance with 10 CFR 50.55a(g)(5)(iii), Carolina Power and Light (CP&L) is requesting approval to credit the limited examination of the components listed in Table 1. Because of physical obstructions and/or component configuration, the examination coverage for these components would not meet the niternative requirements specified in ASME Code Case N-460.

l The acceptable deviation from the alternative requirements specified in ASME Code Case N-460 has been evaluated by CP&L, and CP&L has determined that performing the required examinations on the component identified in Table 1 to the maximum extent practical will provide an acceptable level of quality and safety for the following reasons:

1.Section XI of the ASME Code was issued January 1,1970. At the time of issuance, the design of BSEP, Units 1 and 2, was at a stage where literal compliance with the access requirements outlined in the ASME Section XI Code was not possible. For this reason, I l

limitation associated with the components listed in Table 1 prevented CP&L from obtaining l the required examination coverage specified in ASME Code Case N-460. In order to obtain j required examination coverage, CP&L would have to implement design modification.

Implementation of a design modification for these components would result in a significant hardship to CP&L without a compensating increase in quality and safety.

l

2. Paragraph (g)(4) of 10 CFR 50.55a, Codes and Standards, requires that Class 2 components meet the requirements set forth in the ASME Section XI Code incorporated by reference in paragraph (b) to the extent practical within the limitation of design, geometry,

! and material of construction of the components. Since it was recognized that some plants Page 1 of 2 L

RELIEF REQUEST: RR-25 (R:,v. 0)

SUBJECT:

EXAMINATION CATEGORY C-B, EXAMINATION COVERAGE (such as BSEP) were built before some of the ASME Standards were written, the above provisions outlined in 10 CFR 50.55a(g)(4) were written to address this situation. Pursuant to @55a(g)(4), CP&L examined the components listed in Table 1 to the maximum extent practical during the Second Inspection Interval. During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

CP&L will also continue to evaluate advance techniques and incorporate them, to the extent practical, in the Third Inspection Interval as they become available.

3. The extent of the welds not examined represents a small percentage of the total length of welds examined in accordance with Examination Category C-B. Thus, CP&L is confident that generic degradation of components within this Examination Category would be detected.

4. In addition to the examination specified in Examination Category C-B, CP&L performs a pressure test of the components listed in Table 1 each Inspection Period in accordance with Examination Category C-H. The successful completion of these pressure tests will provide assurance of the component's structure integrity. If a defect is detected during one of these pressure tests, corrective measures would be taken prior to returning the component to service.

PROPOSED ALTERNATIVE:

None During the Third Inspection Interval, CP&L will continue to examine the components listed in Table 1 to the maximum extent practical.

-TABLE 1 -

System Component '

Item No. Remarks RHR 1E11HX-1 A-SWN3 C2.21 The examination coverage for this weld is approximately 62 percent.

RHR 1E11HX-1 A-SWN4 C2.21 The examination coverage for this weld is approximate!y 50 percent.

RHR 2E11HX-2A-SWN3 C2.21 The examination coverage for this weld is approximately 55 percent.

RHR 2E11HX-2A-SWN4 C2.21 The examination coverage for this weld is approximately 50 percent.

REFERENCES:

1. ASME Section XI Code, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (no Addenda) l 2. Section 55a ( 55a), Codes and Standards, of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.55a)

3. ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds Page 2 of 2 e

APPENDIX B, UNIT 1 INSPECTION PLAN AND SCHEDULE

SUMMARY

TABLES

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, t t t t e. t t t t t t n t t t t t t t t t t t t t t t t t.

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. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1

4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 S 0 C C C C C C C C C C C 2 2 1 C C C C C C C C C 0 C C C C C C C C C C C C C ee d s 0

6 0

6 0 0 0 6 6 6 0

6 0

6 0 0 0 6 6 6 0

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