RNP-RA/12-0023, Inservice Inspection Program for the Fifth Ten-Year Interval
| ML12082A009 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/14/2012 |
| From: | Kamilaris C Progress Energy Carolinas, Progress Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/12-0023 RNP-PM-008 | |
| Download: ML12082A009 (113) | |
Text
10 CFR 50.55a Progress Energy Serial: RNP-RA/12-0023 MAR 1 42012 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 INSERVICE INSPECTION PROGRAM FOR THE FIFTH TEN-YEAR INTERVAL Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(g)(5)(i), Carolina Power and Light (CP&L) Company, now doing business as Progress Energy Carolinas, Inc., is submitting the "Fifth Ten-Year Interval Inservice Inspection Program" for the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The HBRSEP, Unit No. 2, Fifth Ten-Year Interval begins on July 21, 2012.
10 CFR 50.55a(g) requires inservice inspection (ISI) of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components and their supports. 10 CFR 50.55a(g)(4)(ii) requires that ISI programs conducted during successive ten-year inspection intervals following the initial ten-year interval comply with the requirements of the latest edition and addenda of the Code, incorporated by reference in paragraph (b) of 10 CFR. 50.55a, twelve months prior to the start of the ten-year interval, subject to the limitations and modifications listed within paragraph (b) of that section. Therefore, the HBRSEP, Unit No.2, "Fifth Ten-Year Interval Inservice Inspection Program" is based on the requirements of the ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, 2007 Edition with 2008 Addenda.
The HBRSEP, Unit No.2, "Fifth Ten-Year Interval Inservice Inspection Program" includes requests for relief from ASME Code requirements. Appendix C of Attachment I to this submittal contains a summary listing of these relief requests. Attachment II to this submittal provides the detailed descriptions, bases, and proposed alternative examinations or requirements associated with each request for relief.
Progress Energy Carolinas, Inc.
l
'(34 7
Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550
United States Nuclear Regulatory Commission Serial: RNP-RA/12-0023 Page 2 of 2 As noted above, the HBRSEP, Unit No. 2, Fifth Ten-Year Interval begins on July 21, 2012. The first refueling outage of the Fifth Ten-Year Interval is Refueling Outage 28 (RO-28), which is currently scheduled to begin in September 2013. In order to support implementation of the Fifth Ten-Year Interval ISI Program, and to facilitate preparations for RO-28, CP&L requests NRC approval of the associated relief requests by July 7, 2012.
If you have any questions regarding this matter, please contact Richard Hightower at (843) 857-1329.
Sincerely, Chris Kamilaris Manager - Support Services - Nuclear PSF/psf Attachments:
I.
II.
Fifth Ten-Year Interval Inservice Inspection Program Relief Requests c:
V. M. McCree, NRC, Region II A. T. Billoch-Colon, NRC, NRR NRC Resident Inspectors
United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/12-0023 83 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 FIFTH TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM
H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Owner:
Progress Energy Post Office Box 1551 Raleigh, North Carolina 27602-1551 Plant:
Progress Energy H.B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550 Fifth Ten-Year Interval Inservice Inspection Program RNP-PM-008 Service Dates:
Construction Permit:
Operating License:
Commercial Operation:
Fifth Interval:
July 12, 1966 July 31, 1970 March 7, 1971 07/21/2012 through 02/18/2022 I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Table of Contents 2.0..A b stra ct.............................................................................................................................................. ---
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4.0* Other Pro grams Conftaining Parts With Details 7
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8 Q~gAppjicable Editions and Addenda to ASME Section XI 10 76....0.................................................................................................................................
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10.0 ASME Code Cases 11 11.0 Administrative Control Documents 11
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12.0 Development of the Inspection Program 12 15.0 Records 13
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20.0 Subsection IWD for Class 3 Components 25
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21.0 Subsection IWF for Class 3 Compo ndeCn opoettupos 56
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8..0 Appendijix A - P&ID/ASME Code Boundary Drawin~gs (Flow Diagrams).................
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.Appe jndix. E. - Augmented ISI Examination.Progra.ms.
74 Append~ix F - ISI Zone/isometric References 77 Aýppendix.G.- C~la~s~s 1 Accep~ta~nce C~riter~ia............................................80 Appendix H - Class 2 Acceptance Criteria 81 Aýppendqix I - Class 3.Acceptance Criteria 8~1 Appenjdix J - Component Support Acceptance Stanqdards 8
R evision...........................Sum............m..................
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 1.0 Acronyms and Abbreviations Listed within this section are acronyms and abbreviations utilized within this document:
AC Auxiliary Coolant AIA Authorized Inspection Agency AFW Auxiliary Feedwater ANII Authorized Nuclear Inservice Inspector ASME American Society of Mechanical Engineers BC Branch Connection BIT Boron Injection Tank B&PV Boiler and Pressure Vessel CCW Component Cooling Water CF Chemical Feed CFR Code of Federal Regulations CHG Charging CRDM Control Rod Drive Mechanism CRS Code Required Surface CRV Code Required Volume CS Containment Spray CV Containment Vessel CVC Chemical and Volume Control CVCS Chemical and Volume Control System DW Demineralized Water DP Design Pressure DT Design Temperature FO Fuel Oil FP Fire Protection FW Feedwater GWD Gaseous Waste Disposal HBRSEP H. B. Robinson Steam Electric Plant HVAC Heating, Ventilation, and Air Conditioning HVH Heating, Ventilation, and Air Handling HX Heat Exchanger ISI Inservice Inspection IVSW Isolation Valve Seal Water LWD Liquid Waste Disposal I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 1.0 (Cont'd) Acronyms and Abbreviations MD Motor-Driven MS Main Steam MT Magnetic Particle Testing (Examination)
N/A Not Applicable NDE Non-Destructive Examination NOP Normal Operating Pressure NOT Normal Operating Temperature NRC Nuclear Regulatory Commission NPS Nominal Pipe Size PASS Post Accident Sampling System P&ID Piping and Instrumentation Diagram PLP Plant Program Procedure PP Penetration Pressurization PS Primary Sampling PT Liquid Penetrant Testing (Examination)
RVLIS Reactor Vessel Level Indication System PWR Pressurized Water Reactor PZR Pressurizer PE Progress Energy RC Reactor Coolant RCS Reactor Coolant System RCP Reactor Coolant Pump RGX Regenerative Heat Exchanger RHR Residual Heat Removal RPV Reactor Pressure Vessel SD Steam-Driven SFPC Spent Fuel Pool Cooling SG Steam Generator SGBD Steam Generator Blowdown SI Safety Injection SIS Safety Injection System SMLS Seamless SS Stainless Steel SW Service Water t
Thickness of Component, Pipe, etc.,
TE Terminal End TMM Technical Management Procedure TRM Technical Requirements Manual (PLP-100)
UFSAR Updated Final Safety Analysis Report UT Ultrasonic Testing (Examination)
VT Visual Testing (Examination)
WD Waste Disposal I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 2.0 Abstract This document provides the bases for the H. B. Robinson Steam Electric Plant, Unit No. 2, Fifth Ten-Year Interval Inservice Inspection Program.
This Program was developed and prepared to meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda, and is subject to the limitations and modifications of 10 CFR 50.55a(b)(2), with the exception of design and access provisions and preservice examination requirements. This Program identifies those components, systems, and their supports that are subject to examination and testing.
Additional requirements for augmented examinations are identified within Appendix E, "Augmented ISI Examination Programs."
This Program contains requests for relief from certain Code requirements. The bases for these relief requests and proposed alternative examinations or requirements are summarized within Appendix C, "Relief Requests." More detailed descriptions, bases, and proposed alternative examinations or requirements associated with each request for relief were submitted as a separate enclosure to the NRC submittal that transmitted the HBRSEP, Unit No. 2, Fifth Ten-Year Interval Inservice Inspection Program.
Tables have been developed showing the bases for selection of components and are contained within the Fifth Ten-Year Interval Inservice Inspection Program.
Definitions of terms are provided within Plant Operating Manual procedures PLP-025, "Inservice Inspection Programs", TMM-038, "Inservice Examination Program" and EGR-NGGC-0210, "ASME Section XI Inservice Inspection Examination Program/Plan Administration".
3.0 Introduction 3.1 This document details the bases of the Long Term Inservice Inspection Program for the Fifth Ten-Year Interval for HBRSEP, Unit No. 2.
3.2 The Inservice Inspection Program for Class 1, Class 2, and Class 3 systems and components was developed after giving due consideration to the following documents, to the extent practical, within the limitations of design, geometry, and materials of construction:
3.2.1 Code of Federal Regulations, 10 CFR 50.55a 3.2.2 ASME Code, 2007 Edition with 2008 Addenda, Sections V and XI I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 3.2.3 Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water Steam and Radioactive Waste Containing Components of Nuclear Power Plants," Revision 2, June 1975 3.2.4 Regulatory Guide 1.83, "Inservice Examination of Pressurized Water Reactor Steam Generator Tubes," Revision 1, July 1975 3.2.5 Regulatory Guide 1.147, "Inservice Inspection Code Case Applicability ASME Section XI", latest revision.
3.2.6 NUREG-0800, "NRC Standard Review Plan," Section 6.6, Paragraph 1.7 (Class 2 Augmented Inspections) 3.2.7 NUREG-0800, "NRC Standard Review Plan," Branch Technical Position MEB 3-1, "High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment" 3.2.8 NUREG-0800, NRC Standard Review Plan, Sections 9.5.4 and 9.5.8, Essential Class 3 Diesel Systems 3.2.9 Branch Technical Position APCSB 3.1, paragraph B.2.c(4) 3.2.10 HBRSEP, Unit No. 2, Technical Specifications 3.2.11 HBRSEP, Unit No. 2, Updated Final Safety Analysis Report 3.2.12 First, Second, Third and Fourth Ten-Year Inservice Inspection Program & Plans 3.2.13 MRP-146S - Materials Reliability Program Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines 3.2.14 MRP-192 Materials Reliability Program Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants 3.2.15 WCAP-1 6913-P, Revision 1, "Operability Assessment and Plant Applicability Evaluation for Pressurizer Heater Sleeve Leakage in Westinghouse Designed Pressurizer."
3.2.16 MRP-227-A - Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines.
3.2.17 MRP-228 - Materials Reliability Program: Inspection Standard for PWR Internals RNP-PM-008 Revision 0 Page 6 of 82
H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 4.0 Other Programs Containing Parts With Details 4.1 The plant IST Program, TMM-004, "Inservice Inspection Testing," addresses inservice testing of Class 1, 2 and 3 pumps and valves.
4.2 The steam generator eddy current testing program is in accordance with the HBRSEP, Unit No. 2, Technical Specifications, and is implemented by fleet procedure EGR-NGGC-0208, "Steam Generator Integrity Program," and plant procedure TMM-1 12, "Steam Generator Inspection (Refueling Outage)."
4.3 Snubber inspection and testing is implemented by plant procedure TMM-006, "Shock Suppressor (Snubber) Inspection and Testing Program." Snubber visual examinations are performed in accordance with EST-032, "Visual Inspection of Hydraulic and Mechanical Shock Suppressors," and functional testing is performed in accordance with EST-033, "Functional Testing of Hydraulic and Mechanical Shock Suppressors (Snubbers)."
4.4 Containment IWE/IWL examinations are addressed by the containment inspection programs and are implemented in accordance with procedures TMM-124, "Inservice IWE/IWL Program," and EST-150, "Containment Inspection (IWE/IWL), CM-764 "Inspection and Repair of the CV Liner and Insulation., RNP-PM-006, "Second Ten-Year Interval Inservice IWE/IWL Inspection Program" and RNP-PM-007, "Second Ten-Year Interval Inservice IWE/IWL Inspection Plan".
4.5 The repair/replacement program is implemented by TMM-015, "Inservice Repair and Replacement."
4.6 The pressure testing program is implemented by TMM-020, "Inservice Pressure Testing Program."
4.6.1 Per the requirements of WCAP-1 6913-P, Revision 1 and the commitment to NEI-03-08, RNP shall perform the following.
4.6.1.1 Each PWR with stainless steel heater sleeves is required to conduct a visual inspection of all heater sleeves. This VT-2 examination requirement is accomplished by the examinations performed under EST-083-2:
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 4.6.1.2 At each refueling outage, a visual inspection (VT-2 in accordance with IWA-2212 of Section Xl of the ASME Code) of the visible, without removal of insulation, portion of all heater sleeves and adjacent and nearby insulation for evidence of primary coolant leakage.
4.6.1.3 If there is evidence of primary coolant leakage that cannot be attributed to other sources (e.g. from a nearby valve, residue of other material, etc.), take the appropriate actions (i.e., NDE where applicable or destructive examination) to characterize the crack orientation and location in all sleeves for which visual inspection showed evidence of leakage. This shall be captured in the utility's Corrective Action Program.
4.7 Non-destructive examination procedures and personnel qualifications are addressed within the nuclear NDE manual, NGGM-PM-001 1, "NDEP-A, Nuclear NDE Program and Personnel Process," or an approved vendor Quality Assurance Program.
5.0 Program History 5.1 During the First Ten-Year Inservice Inspection Interval, the first two periods were conducted in accordance with the ASME B&PV Code,Section XI, 1971 Edition. The last period was conducted in accordance with the ASME B&PV Code, Section Xl, 1974 Edition with Addenda through summer 1975. The first Ten-Year Interval began in March 1971, and ended in March 1981.
5.2 The Second Ten-Year Inservice Inspection Interval was conducted in accordance with the ASME B&PV Code,Section XI, 1977 Edition with Addenda through Summer 1978. The second Ten-Year Interval began in March 1981, and ended in February 1992.
5.3 The Third Ten-Year Inservice Inspection Interval was conducted in accordance with the ASME B&PV Code,Section XI, 1986 Edition. The third Ten-Year Interval began in February 1992, and ended in February 2002. An interval extension of 349 days occurred in 1984/1985 due to the length of a steam generator replacement outage. This interval extension resulted in a Third Ten-Year Interval start date of February 1992 versus March 1991.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 5.4 The Fourth Ten-Year Inservice Inspection Interval is being conducted in accordance with the ASME B&PV Code,Section XI, 1995 Edition, 1996 Addenda. The Fourth Ten-Year Interval began on February 19, 2002, and was scheduled to end on February 18, 2012. As allowed by ASME Section XI, IWA-2430(d)(1), the interval is being extended to allow for the completion of RO-27 which was postponed to January 18, 2012 and the recent change to 10CFR50.55a which endorsed the 2007 Edition/2008 Addenda of ASME Section XI which will be applied to the Fifth Ten Year Interval Inservice Inspection Program and Plan. The new date for the end of the fourth interval is 7/20/2012.
5.5 The Fifth Ten Year Interval Inservice Inspection Interval is being conducted in accordance with the ASME B&PV Code,Section XI, 2007 Edition, 2008 Addenda. The fifth interval start date is July 21, 2012 and ends of February 18, 2022 5.6 Based on the requirements identified in 10CFR50.55a(g)(4)(ii), a licensee whose inservice inspection interval commences during the 12 through 18-month period after July 21, 2011 may delay the update of their Appendix VIII program by up to 18 months after July 21, 2011. The current ASME Code applied to Appendix VIII is ASME Boiler & Pressure Vessel Code,Section XI, Appendix VIII, 1995 Edition with 1996 addenda through the 2001 Edition with no addenda. (EPRI Internal Report IR-2005-80). Upon completion of the update to the 2007 Edition, 2008 Addenda, this step may be revised for historical purposes.
5.7 The construction permit for HBRSEP, Unit No. 2, was issued on July 12, 1966, to Carolina Power & Light Company who serves as the Owner of Record. Dates for intervals and periods are as follows:
Interval Period 1 Period 2 Period 3 1
3/71 - 2/74 2/74 - 3/78 3/78 - 3/81 2
3/81-6/85 6/85-10/88 10/88-2/92 3
2/92 - 2/95 2/95 - 2/99 2/99 - 2/02 4
2/02-2/05 2/05-2/09 2/09-7/12 5
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 6.0 Applicable Editions and Addenda to ASME Section Xl 6.1 The ASME B&PV Code, 2007 Edition with 2008 Addenda, was incorporated by reference into 10 CFR 50.55a(b)(2) on July 21, 2011. In accordance with 10 CFR 50.55a(g)(4)(ii), Inservice Inspection requirements applicable to HBRSEP, Unit No. 2, for nondestructive examination and system pressure testing during the Fifth Ten-Year Interval are in accordance with this edition of the Code.
7.0 Classifications 7.1 System classifications for the Inservice Inspection Program are based on the requirements of 10 CFR 50 and Regulatory Guide 1.26, Revision 2. Class 1 system boundaries were developed based on 10 CFR 50.2 and the HBRSEP, Unit No. 2, UFSAR. Class 2 and 3 system boundaries were developed based on Regulatory Guide 1.26, Revision 2, and the HBRSEP, Unit No. 2, UFSAR.
7.2 Optional construction of a component within a system boundary to a classification higher than the minimum class established in the component design specification will not affect the overall system classification that determines the applicable rules of Section XI.
7.3 Portions of piping penetrating the containment vessel that are required to be constructed to Class 1 or 2 requirements for piping, and that may differ from the classification of the balance of piping systems, will not affect the overall system classification that determines the applicable rules of Section XI.
7.4 Piping and Instrumentation Diagrams identify specific boundaries for Class 1, 2, and 3 systems to which this program applies. Reference Appendix A, "P&ID/ASME Code Boundary Drawings (Flow Diagrams)," for a listing of P&ID's associated with each system.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 8.0 Inspection Program 8.1 Examinations of components are scheduled in accordance with "Inspection Program" identified under IWB-241 1, IWC-241 1, and IWD-241 1, IWF-241 0, and Tables IWB2411-1, IWC2411-1, and IWD-2411-1, IWF-2410-1 for Class 1, 2, and 3 systems and components. Examinations are scheduled, to the extent practical, based upon the preceding sequence of examinations performed in the First, Second, Third and Fourth Ten-Year Interval Inservice Inspection Programs.
8.2 In order to be consistent in determining percentages, HBRSEP, Unit No. 2, utilized the requirements of IWB-241 1, IWC241 1, and IWD-241 1, and IWF-2410. When calculating percentage requirements, values were rounded up to the nearest whole number.
9.0 Regulatory Guides 9.1 Regulatory Guides to HBRSEP, Unit No. 2, for the purposes of this Program are identified within Section 3.2.
10.0 ASME Code Cases 10.1 ASME Code Cases applicable to HBRSEP, Unit No. 2, are identified within Appendix D, "Applicable Code Cases." Some Code Cases may have received NRC review and endorsement by the NRC through incorporation into Regulatory Guide 1.147. Other Code Cases not incorporated within Regulatory Guide 1.147 may be invoked as guidance or by reference with a request for relief. For instances where an HBRSEP, Unit No. 2, relief request references a Code Case that has not yet received NRC endorsement, and this Code Case is incorporated into subsequent revisions of the Regulatory Guide, HBRSEP, Unit No. 2, may continue to use the approved relief request provided any limitations in the Regulatory Guide are followed.
11.0 Administrative Control Documents 11.1 The Fifth Ten-Year Interval Inservice Inspection Program is administratively controlled by plant procedures PLP-025, "Inservice Inspection Programs,"TMM-038, "Inservice Examination Program" and EGR-NGGC-0210, "ASME Section XI Inservice Inspection Examination Program/Plan Administration".
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 12.0 Development of the Inspection Program 12.1 The Fifth Ten-Year Interval Inservice Inspection Program for components and systems subject to examination was developed using the guidance provided within the ASME B&PV Code,Section XI, 1995 Edition with 1996 Addenda, Appendix F, "Preparation of Inspection Plans" as well as previous Inservice Inspection Ten Year Programs.
12.2 Plant controlled P&IDs, isometric, and component drawings were used to develop the scope of examinations contained within this program. During examinations, the most recent revision of these drawings will be used to complete each examination item.
13.0 Augmented Examinations 13.1 Augmented examinations and associated requirements within the scope of the Fifth Ten-Year Interval Inservice Inspection Program are identified within Appendix E, "Augmented ISI Examination Programs." ANII involvement in Augmented Examinations is not required, nor prohibited.
13.2 The Fifth Ten Year Interval Plan contains a section identified as "AUGMENT" delineating out the items associated with the Augmented Examination Program. Scheduling of Augmented items is identified in the Fifth Ten Year Inservice Inspection Plan, RNP-PM-009.
13.3 The Code Category utilized for augmented examinations is "AUGMENT" and the Code Item Number identified in Appendix E is the "ITEM NUMBER" utilized in IDDEAL.
13.4 When planning for inspections associated with MRP-227-A & MRP-228 on the Reactor Vessel Internals Aging Management Program (future),
consideration should be given for the optimum scheduling sequence and combination for inspections, such as combining visual examinations with ultrasonic examination of bolting in the same area of the vessel in order to minimize radiation dose to the examination personnel and reduce inspection task durations.
14.0 Program Code Boundary Drawings 14.1 Code-required boundaries for Class 1, 2, and 3 systems are identified by a triangle box on the P&IDs. The P&IDs applicable to the HBRSEP, Unit No.
2, Fifth Ten-Year Inservice Inspection Program are identified within Appendix A, "P&ID/ASME Code Boundary Drawings (Flow Diagrams)."
14.2 Unless otherwise indicated, the "Q" flag is coincident with the system code class designation.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 15.0 Records 15.1 Records for the Fifth Ten-Year Interval Inservice Inspection Program, including equipment calibration records, calibration standards, examination and test procedures, results of activities, final reports, certifications, and corrective actions taken or recommended, will be developed and maintained in accordance with Article IWA-6000, "Records and Reports."
15.2 Non-destructive examination data packages will be submitted to the ISI Specialist following completion of the inservice inspection activity.
15.3 Final reports will be generated for non-destructive examination activities performed on Class 1, 2, or 3 systems, components, supports, system pressure tests, repairs and replacements.
15.4 Final reports will contain, as a minimum, the information required on the NIS-1, as applicable. The NIS-1 will be prepared and certified by Progress Energy, and verified and signed by the ANII upon completion following a refueling outage.
15.5 An Owners Report for Repair/Replacement Activities, Form NIS-2 or NIS-2A, will be prepared, as necessary, certified by Progress Energy, and verified and signed by the ANII.
15.6 Final reports following inservice inspection outages will be submitted to the NRC within ninety days (90) of the end of the outage, i.e., output breaker closed, in accordance with Article IWA-6200. The final report will include the following Owner's Data Reports:
15.6.1 NIS-1, Owner's Report for Inservice Inspections (The NIS-1 will contain a listing of the examinations performed during the refueling outage.)
15.6.2 NIS-2 or NIS-2A, Owner's Report for Repair/Replacement Activity 15.7 An Inservice Examination Summary report will be generated and vaulted with the NDE records as a QA record for online ISI. The Inservice Examination Summary report for online ISI will also be included in 15.6.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 16.0 Repairs, Replacements and Modifications 16.1 HBRSEP, Unit No. 2, will implement the repair and replacement requirements delineated within the ASME B&PV Code, Section Xl, 2007 Edition with 2008 Addenda, in accordance with plant procedure TMM-015, "Inservice Inspection Repair and Replacement Program."
17.0 Inservice Inspection Plan and Schedules 17.1 The Fifth Ten-Year Interval Inservice Inspection Plan (RNP-PM-009) and schedule tables for inservice examination of systems and components are controlled as a separate document. Periodic revisions to the plan and schedule will be made, as required, to accommodate program additions, deletions, updates, and substitutions, as necessary via a DRR per PRO-NGGC-0203 "Development and Approval Of NGG Directives, Interface Agreements, And Program Manuals".
17.2 The Fifth Ten-Year Interval Inservice Inspection Program has been divided by ISI isometric drawings (HBR2-10618 series). These drawings identify the weld locations, hanger locations, and other examination areas for each system. (Reference Appendix F, "ISI Zone/Isometric References")
17.3 The Fifth Ten-Year Interval Inservice Inspection Plan contains the applicable information for ASME B&PV Code Examination Category, Item Number, etc.,
as it pertains to Section XI requirements.
17.4 Welds and other components that are subject to examination have been identified on ISI isometric drawings. Newly identified welds are added to the Program/Plan with the next highest sequential weld number, or by designation of an alpha character from an adjacent weld.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.0 Subsection IWB for Class 1 Components 18.1 Bases and Scope The Class 1 system boundaries are based upon the requirements of 10 CFR 50.2 and the HBRSEP, Unit No. 2, UFSAR. Specific examinations are based on the requirements of the ASME B&PV Code,Section XI, Table IWB-2500-1, as indicated below.
1 In accordance with IWB-1 220, "Components Exempt from Examination,"
the following components or parts of components are exempted from the volumetric and surface examination requirements of IWB-2500, "Examination Categories." These Class 1 component exemptions are based on the ASME B&PV Code,Section XI, 2007 Edition, 2008 Addenda IWB requirements. Also note that there is no Class 1 systems exempt from surface or volumetric examinations for reasons other than size.
- 2. Components connected to the reactor coolant system and part of the reactor coolant pressure boundary that are of such a size and shape so that, upon a postulated rupture, the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power. The emergency core cooling systems are excluded from the calculation of make-up capacity.
- 3. Components and piping segments NPS 1 (DN 25) and smaller, except for steam generator tubing; a)
Components and piping segments which have one inlet and one outlet, both of which are NPS 1 (DN 25) and smaller; b)
Components1 and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross sectional area does not exceed the cross sectional area defined by the OD of NPS 1 (DN
- 25) pipe.
c)
Reactor vessel head connections and associated piping, NPS 2 (DN
- 50) and smaller, made inaccessible by control rod drive penetrations.
1 For heat exchangers, the shell side and tube side may be considered separate components I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.2 Table IWB-2500-1, Examination Category B-A Table B-A provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-A, "Pressure Retaining Welds in Reactor Vessel." Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
- 1. The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-241 1, "Inspection Program" subsections (a)(2) and (a)(3), which allows examinations to be partially deferred or deferred, respectively, to the end of an inspection interval.
Table B-A mNumber of Number Scheduled by, Item Parts Examined N
rPeriod Numbers Welds.1 2
B1.11 Circumferential 3
0 0
3 B1.12 Longitudinal 9
0 0
9 B1.21 Circumferential 1
0 0
1 B1.22 Meridional 6
0 0
6 B1.30 Shell-to-Flange 1
0 0
1 Welds B1.40 Head-to-Flange 0
0 0
0 Weld Totals 20 0
0 20 Category B-A, Item Numbers B13.40 components.
and B13.51, are not associated with RNP I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.3 Table IWB-2500-1, Examination Category B-B Table B-B provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-B, "Pressure Retaining Welds in Vessels Other Than Reactor Vessels." Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
Table B-B Number Scheduled by Item umber of Period Numbers P
- xWelds, B2.11 Circumferential 2
0 1
1 B2.12 Longitudinal 2
0 1
1 B2.40 Tubesheet-to-3 0
0 Head Weld B2.51 Circumferential 3
0 0
0 B2.80 Tubesheet-to-3 0
0 0
Shell Welds Totals 13 1
2 2
.1.
.1.
Category B-B, Item Numbers B2.21, B2.22, B2.31, B2.70, are not associated with RNP components.
B2.32, B2.52, B2.60 or I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.4 Table IWB-2500-1, Examination Category B-D Table B-D provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-D, "Full Penetration Welded Nozzles in Vessels - Inspection Program B." Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
18.4.1 The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-241 1, "Inspection Program" subsection (a)(2), which allows examinations to be partially deferred to the end of an inspection interval.
Table B-D Item Number
'Number'Scheduled by Nmer
=Parts Examined of Period Nur___...__
Welds 1
2 3
B3.90 Reactor Vessel Nozzle-to-6 0
0 6
Vessel Welds B3.1 00 Reactor Vessel Nozzle 6
0 0
6 Inside Radius Section B3.120 1 Pressurizer Nozzle Inside 6
1 2
2 Radius Section B3.140 1 Steam Generator Nozzle 6
2 2
2 Inside Radius Section B3.150 Nozzle-to-Vessel Welds 6
0 0
0 B3.160 Nozzle Inside Radius 6
0 0
0 Section Totals 36 3
4 16 Totals 36 3
4 16 Category B-D, Item Numbers B3.110 and RNP components.
B3.130, are not associated with 1 Per the requirements of 10CFR50.55a(b)(2)(xxi)(A) The provisions of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items B3.40 and B3.60 (Inspection Program A) and Items B3.120 and B3.140 (Inspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of this section. A visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of this section, with a limiting assumption on the flaw aspect ratio (i.e., all = 0.5), may be performed instead of an ultrasonic examination.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.5 Table IWB-2500-1, Examination Category B-F Table B-F provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-F, "Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles." Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
18.5.1 The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-241 1, "Inspection Program" subsection (a)(2), which allows examinations to be partially deferred to the end of an inspection interval.
Table B-F Item Number
-Number Scheduled Parts Examined of by Period Number Welds 1
2 3
NPS 4 or Larger B5.10 Nozzle-to-Safe End Butt 6
0 0
6 Welds NPS 4 or Larger B5.40 Nozzle-to-Safe End Butt 6
2 2
2 Welds NPS 4 or Larger B5.70 Nozzle-to-Safe End Butt 6
2 2
2 Welds Totals 18 4
4 10 Category B-F, Item Numbers B5.20, B5.30, B5.50, B5.60, B5.80, B5.90, B5.100, B5.1 10 or B5.120, are not associated with RNP components.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.6 Table IWB-2500-1, Examination Category B-G-1 Table B-G-1 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-G-1, "Pressure Retaining Bolting, Greater Than 2 inches in Diameter." Refer to Appendix D for applicable Code Cases.
- 1. The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-241 1, "Inspection Program"subsection (a)(4), which allows examinations to be deferred until disassembly of a component for maintenance, repair/replacement activity, or volumetric examination.
Table B-G-1....
Number Item Number of Scheduled by Numer Parts Examined BoltingP NuJm ber i...d Assemblies 1
2 3
B6.10 Closure Head Nuts 50 0
0 50 B6.20 Closure Studs 50 0
0 50 B6.40 Threads in Flange 50 0
0 50 B6.50 Closure Washers, 50 0
0 50 Bushings B6.180 Bolts and Studs 72 24 24 24 B6.190 1 Flange Surface, when 3
0 0
0 connection disassembled B6.200 Nuts, Bushings, and 72 24 24 24 Washers Totals 347 48 48 248 L
Category B-G-i, Item Numbers B6.60, B6.70, B6.80, B6.90, B6.100, B6.110, B6.120, B6.130, B6.140, B6.150, B6.160, B6.170, B6.210, B6.220 and B6.230, are not associated with RNP components.
1 Required when disassembled which includes the 1 inch (25mm) annular surface of flange surrounding each stud.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.7 Table IWB-2500-1, Examination Category B-G-2 Table B-G-2 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-G-2, "Pressure Retaining Bolting, 2 Inches and Less in Diameter."
- 1. The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-241 1, "Inspection Program" subsection (a)(4), which allows examinations to be deferred until disassembly of a component for maintenance, repair/replacement activity, or volumetric examination.
- 2. All B-G-2 items are scheduled each refueling outage as contingency examinations during the interval. As the examinations are completed when a disassembly occurs on a component, the Fifth Ten Year Interval Inspection Plan, RNP-PM-009 is updated to reflect the current status of examinations completed.
~~~Table B-G-2 Ite
'Number of Number Scheduled Nmer Parts Examined Bolting by Period Number__
_______Assemblies 1
2 3
B7.20 Bolts, Studs, and Nuts 1
0 0
0 B7.30 Bolts, Studs, and Nuts 6
0 0
0 B7.50 Bolts, Studs, and Nuts 6
0 0
0 B7.60 Bolts, Studs, and Nuts 3
0 0
0 B7.70 Bolts, Studs, and Nuts 28 0
0 0
Totals 44 0
0 0
Category B-G-2, Item Numbers B7.10 components.
or B7.40, are not associated with RNP I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.8 Table IWB-2500-1, Examination Category B-J Table B-J provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-J, "Pressure Retaining Welds in Piping." Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
- 1. The original selection regarding the extent of examinations for Class 1 piping welds was determined by the requirements of Table IWB-2500-1, Examination Category B-J, in accordance with 10 CFR 50.55a(b)(2)(ii), Pressure-retaining welds in ASME Code Class 1 piping (applies to Table IWB-2500 and IWB-2500-1 and Category B-J). If the facility's application for a construction permit was docketed prior to July 1, 1978, the extent of examination for Code Class 1 pipe welds may be determined by the requirements of Table IWB-2500 and Table IWB-2600 Category B-J of Section Xl of the ASME B&PV Code in the 1974 Edition and addenda through the Summer 1975 Addenda or other requirements the NRC may adopt.
Table B-J Item Number Number Scheduled Parts Examined Nby Period
- Number, P
Eaie of Welds 2
B9.1 1
>4" Circumferential Welds 178 9
13 23 B9.21
< 4" Circumferential Welds 137 14 17 6
B9.31 NPS 4" or Larger 7
0 0
2 B9.32 Less Than NPS 4" 20 3
0 2
B9.40 Socket Welds 388 33 33 32 Totals 730 59 63 65 730 59 63 65 Category B-J, components.
Item Number B9.22 is not associated with any RNP I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.9 Table IWB-2500-1, Examination Category B-K Table B-K provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-K, "Welded Attachments for Vessels, Piping, Pumps, and Valves."
- 1. Welded attachments for piping inspected under Item Number B10.20 are scheduled in accordance with Notes (4) and (5) of Table IWB-2500-1, Examination Category B-K, as found within the ASME B&PV Code, Section Xl, 2007 Edition with the 2008 Addenda.
- 2. Examinations scheduled for B10.30 are based on Note 4 of ASME Section XI, which states in part "For multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination."
- 3. Examinations scheduled B10.20 are based on Note 5 of ASME Section XI, which states "For piping, pumps and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined."
~~~Table B-K f
Number Scheduled ýby, Item Numberof Number Parts Examined Welds 2Period 1
2 3.
B10.20 Welded Attachments 41 2
2 1
B10.30 Welded Attachments 9
0 0
1 Totals 50 2
2 2
h Category B-K, Item Number 810.10 or 810.40 is not associated with any RNP components.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.10 Table IWB-2500-1, Examination Category B-L-2 Examination Category B-L-2, Table IWB-2500-1, provides the examination scope and schedule for "Pump Casings." Inspections scheduled under Item No. B132.20 includes visual examination of the interior of one of three RCPs when disassembled for maintenance, repair, or volumetric examination.
Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively. The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-241 1, "Inspection Program," subsection (a)(4), which allows examinations to be deferred until disassembly of a component for maintenance, repair/replacement activity, or volumetric examination.
- 1. All B-L-2 items are scheduled each refueling outage as contingency examinations during the interval. As the examinations are completed when a disassembly occurs on a component, the Fifth Ten Year Interval Inspection Plan, RNP-PM-009 is updated to reflect the current status of examinations completed.
Table B-L-2 item Number of Number Scheduled by Parts Examined Welds or Period Number Components 1
2 3
B12.20 Pump Casing 3
0 0
0 (B-L-2)
Totals 3
0 0
0 Examination is required only when a pump disassembled for maintenance, or repair in accordance with Note (2) of Table IWB-2500-1, Examination Category B-L-2, as found within the ASME B&PV Code,Section XI, 2007 Edition with the 2008 Addenda. Examination of the internal pressure retaining surfaces made accessible for examination by disassembly. If a partial examination is performed and a subsequent disassembly of that pump or valve allows a more extensive examination, an examination shall be performed during the subsequent disassembly. A complete examination is required once per interval, if disassembled.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.11 Table IWB-2500-1, Examination Category B-M-2 Examination Category B-M-2 provides the examination scope and schedule for "Valve Bodies." The percentage of scheduled examinations for Examination Category B-M-2 was developed in accordance with IWB-241 1, "Inspection Program," subsection (a)(4), which allows examinations to be deferred until disassembly of a valve for maintenance or repair.
- 1. Valve examinations identified under Examination Category B-M-2, Item No. B12.50, have been grouped based on size, constructional design, manufacturing method, and function in accordance with Note (3) of Table IWB-2500-1, Examination Category B-M-2. These valve groupings are as follows:
Group 1: RHR-750, RHR-751 (14")
Group 2: SI-876A, SI-876B, SI-876C (8")
Group 3: SI-875A, SI-875B, SI-875C, SI-875D, SI-875E, SI-875F (10")
- 2. All B-M-2 items are scheduled each refueling outage as contingency examinations during the interval. As the examinations are completed when a disassembly occurs on a component, the Fifth Ten Year Interval Inspection Plan, RNP-PM-009 is updated to reflect the current status of examinations completed.
[
Table B-M'2..
Item Numberof Number Scheduled by Nmer Parts Examined Valves per Period Group 1,_
2, 3
Group 1 2
0 0
0 B12.50*
Group 2 3
0 0
0 Group 3 6
0 0
0 I
Totals
]
11 Jo0 0
[0 Examination is required only when a pump or valve is disassembled for maintenance, repair, or volumetric examination in accordance with Note (2) of Table IWB-2500-1, Examination Category B-M-2, as found within the ASME B&PV Code,Section XI, 2007 Edition with the 2008 Addenda.
A complete examination is required once per interval for each group, if disassembled.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.12 Table IWB-2500-1, Examination Categories B-N-I, B-N-2, and B-N-3 Table B-N-1 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-N-i, "Interior of Reactor Vessel." The scope of examinations performed under this Examination Category include VT-3 visual examination of accessible areas above and below the reactor core made accessible for examination by removal of components during normal refueling activities (once each inspection period). Refer to Appendix C for applicable Relief Requests. The percentage of scheduled examinations for this Examination Category is not applicable in accordance with IWB-241 1, "Inspection Program," subsection (a)(1).
- 1. Table B-N-2 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-N-2 (PWR), Item Nos. B1 3.50 and B1 3.60, "Interior Attachments Within Beltline Region," and "Interior Attachments Beyond Beltline Region," respectively. The scope of examinations performed under these Item Numbers includes VT-3 visual examination of interior attachments beyond the beltline region (once per interval). The required percentage of examinations for B-N-2 are not applicable for examinations deferred to the end of an inspection interval as delineated within IWB-241 1, "Inspection Program," subsection (a)(3).
- 2. Table B-N-3 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-N-3, "Core Support Structure." The scope of examinations performed under this Examination Category includes VT-3 visual examination of accessible surfaces of the core support structures when removed from the reactor vessel (once per interval). To reduce radiation exposure, 100% of the required examinations will be deferred to the end of the interval in accordance with Table IWB-2500-1, thereby allowing these examinations to be completed during a single, scheduled refueling outage. The required percentage of examinations for B-N-3 are not applicable for examinations deferred to the end of an inspection interval as delineated within IWB-241 1, "Inspection Program," subsection (a)(3).
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
_________Table B-N-I, B-N-2, and B-N-3 NumeNumber Parts Exami~ned of~
~
eue ~
Number Peio B13.10 Vessel Interior (B-N-1) 1 1
1 1
B13.60 Interior Attachments Beyond 1
0 0
1 B13.60_
Beltline Region (B-N-2) 1_0_0_1 B13.70 Core Support Structure (B-N-3) 1 0
0 1
Totals 3
1 1
3 Totals 1
1 3
3 Category B-N-i, B-N-2, B-N-3, Item Number B13.20, B13.30, B13.40 and B1 3.50, are not associated with any RNP components.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.13 Table IWB-2500-1, Examination Category B-O Table B-O provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-O, "Pressure Retaining Welds in Control Rod Housings." The required extent of this examination is 10% of the peripheral control rod housings. HBRSEP, Unit No. 2, has 28 control rod housings on the periphery. The required percentage of examinations for this Examination Category is not applicable for examinations deferred to the end of an inspection interval as delineated within IWB-241 1, "Inspection Program" subsection (a)(3).
Table B-O Number Scheduled by
- item, Number ofPro
,*Parts i*
Examined Period...
Number P
x Welds B14.10 Welds in CRD 56 2
2 2
Housing I
I Totals 56 2
2 2
L L
J J
Category B-O, Item Number B14.10 or B14.21, are not associated with any RNP components.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.14 Table IWB-2500-1, Examination Category B-P Table B-P provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-P, "All Pressure Retaining Components."
- 1. The percentage of scheduled examinations for this Examination Category is not applicable in accordance with IWB-241 1, "Inspection Program"subsection (a)(1). Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
- 2. System leakage tests will be conducted in accordance with Articles IWA-5000 and IWB-5000, "System Pressure Tests," as stipulated within TMM-020, "Inservice Pressure Testing Program," including the following:
- a. The pressure requirements of IWB-5221, "Pressure."
- b. The boundary requirements of IWA-5221, "System Leakage Test Boundary," and IWB-5222, "Boundaries." Also note that system leakage tests conducted at or near the end of the inspection interval require the boundary to be extended to all Class 1 pressure retaining components. Relief has been granted to address instances where it is impractical for HBRSEP, Unit No. 2, to extend these boundaries.
- c. The holding time requirements of IWA-5213, "Test Condition Holding Time."
- d. The requirements of ASME Section Xl, WCAP-1 6913-P, Revision 1 requirements are being implemented each time EST-083-2 is performed. PER WCAP-16913-P, Revision 1, at each refueling outage, a visual inspection (VT-2 in accordance with IWA-2212 of Section Xl of the ASME Code) must be performed of the visible, without removal of insulation, portion of all heater sleeves, as well as all adjacent and nearby insulation for evidence of primary coolant leakage.
- e. In addition, WCAP-16913-P, Revision 1, also provides the basis for generic operability assessment for Westinghouse plants with postulated circumferentially oriented SCC in heater sleeves. It provides guidance for inspection expansion (types, number of sleeves, intervals of subsequent inspections) if circumferential flaws are discovered in pressurizer heater sleeves.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program EST-083-1 (VT-2 of Bolted Connections) & EST-083-2 (VT-2 Pressure Test), is performed during each refueling outage.
- The pressure test performed during the third period under B1 5.20 subsumes the test required by B15.10 I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 18.15 Table IWB-2500-1, Examination Category B-Q Table B-Q provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-Q, "Steam Generator Tubing." The steam generator eddy current testing program is in accordance with the HBRSEP, Unit No. 2, Technical Specifications, and is implemented by fleet procedure EGR-NGGC-0208, "Steam Generator Integrity Program," and plant procedure TMM-1 12, "Steam Generator Inspection (Refueling Outage)." The percentage of scheduled examinations for this Examination Category is not applicable in accordance with IWB-241 1, "Inspection Program" subsection (a)(1).
STable B-Q Number Scheduled by Item Number of Parts Examined Period Numbers Welds Steam Generator B16.20 Tubing in 10257 U-Tube Design Totals 10257 Category B-Q, Item Number B16.10 is not associated with any RNP components.
Percentage requirements are not applicable in accordance with IWB-241 1, subsection (a)(1).
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.0 Subsection IWC for Class 2 Components 19.1 Bases and Scope The Class 2 system boundaries are based upon the requirements of Regulatory Guide 1.26, and the HBRSEP, Unit No. 2, UFSAR. Specific examinations are in accordance with the ASME B&PV Code,Section XI, Table IWC-2500-1, as further described below.
- 1. The following components or parts of components within the residual heat removal (RHR), safety injection/emergency core cooling (ECC), and CV spray/containment heat removal (CHR) systems (or portions of systems) are exempt from the volumetric and surface examination requirements of IWC-2500, "Examination and Pressure Test Requirements," in accordance with IWC-1 221, "Components Within RHR, ECC, and CHR Systems or Portions of Systems," and IWC-1223, "Inaccessible Welds":
- a. For systems, except high pressure safety injection systems in pressurized water reactor plants:
- 1. components and piping segments NPS 4 (DN 100) and smaller
- 2. components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DN 100) and smaller
- 3. components1 and piping segments which have multiple inlets or outlets, whose cumulative cross sectional area does not exceed the cross sectional area defined by the OD of NPS 4 (DN 100) pipe
- b. For high pressure safety injection systems in pressurized water reactor plants:
- 1. components and piping segments NPS 1 1/2 (DN 40) and smaller
- 2. components and piping segments which have one inlet and one outlet, both of which are NPS 1 Y2 (DN 40) and smaller
- 3. components1 and piping segments which have multiple inlets or outlets, whose cumulative cross sectional area does not exceed the cross sectional area defined by the OD of NPS 1 1/2 (DN 40) pipe 1
For heat exchangers, the shell side and tube side may be considered separate components I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program c Vessels, piping, pumps, valves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems1 of pressurized water reactor plants.
1 Statically pressurized, passive safety injection systems of pressurized water reactor plants are typically called:
- a. accumulator tank and associated system
- b. safety injection tank and associated system
- c. core flooding tank and associated system
- d. Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
- e. Welds or portions of welds that are inaccessible due being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.
- 2. The following components or parts of components within systems (or portions of systems) other than residual heat removal (RHR), safety injection/emergency core cooling (ECC), and CV spray/containment heat removal (CHR) systems (or portions of systems) are exempt from the volumetric and surface examination requirements of IWC-2500, in accordance with IWC-1 222, "Components Within Systems or Portions of Systems Other Than RHR, ECC, and CHR Systems," and IWC-1223:
- a. For systems, except auxiliary feedwater systems in pressurized water reactor plants:
- 1. components and piping segments NPS 4 (DN 100) and smaller
- 2. components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DN 100) and smaller
- 3. components1 and piping segments which have multiple inlets or outlets, whose cumulative cross sectional area does not exceed the cross sectional area defined by the OD of NPS 4 (DN 100) pipe I For heat exchangers, the shell side and tube side may be considered separate components.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
- b. For auxiliary feedwater systems in pressurized water reactor plants:
- 1. components and piping segments NPS 1 1/2 (DN 40) and smaller
- 2. components and piping segments which have one inlet and one outlet, both of which are NPS 1 1/2/2 (DN 40) and smaller
- 3. components1 and piping segments which have multiple inlets or outlets, whose cumulative cross sectional area does not exceed the cross sectional area defined by the OD of NPS 1 1/2 (DN 40) pipe For heat exchangers, the shell side and tube side may be considered separate components
- c. Vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the system function is required) at a pressure equal to or less than 275 psig (1,900 kPa) and at a temperature equal to or less than 200°F (950C).
- d. Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
- e. Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.2 Table IWC-2500-1, Examination Category C-A Table C-A provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-A, "Pressure Retaining Welds in Pressure Vessels." Refer to Appendix D for applicable Code Cases.
_____________Table C-A Item N 1umber Numrner~Sched'iled by.
ItmParts Examined.
of Periodi 1
Welds 1
2 3~~
CI.10 Shell Circumferential 11 2
1 Welds C1.20 Head Circumferential 7
2 0
2 Welds C1.30 Tubesheet-to-Shell Weld 3
0 1
0 Totals 21 3
3 3
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.3 Table IWC-2500-1, Examination Category C-B Table C-B provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-B, "Pressure Retaining Nozzle Welds in Vessels."
C2.211 C2.221 Nozzle-to-Shell (or Head) Weld Nozzle Inside Radius Section 8
6 2
2 2
0 0
0 C2.311 Reinforcing Plate Welds to 8
0 0
4 Nozzle and Vessel Nozzle-to-Shell (or Head)
C2.332 Welds When Inside of 4
4 4
4 Vessel is Inaccessible Totals 22 4
2 4
Category C-B, Item Numbers C2.11, or C2.32, are not associated with any RNP components.
Examinations are scheduled in accordance with Note (4) of Table IWC-2500-1, Examination Category C-B, for multiple vessels of similar design, size, and service.
2 VT-2 visual examination is performed during pressure testing in accordance with Note (5) of Table IWC-2500-1, Examination Category C-B. This examination is required each period and is not included in the total period count.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.4 Table IWC-2500-1, Examination Category C-C Table C-C provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-C, "Welded Attachments for Vessels, Piping, Pumps, and Valves." Refer to Appendix D for applicable Code Cases.
- 1. Examinations are scheduled in accordance with Table IWC-2500-1, Examination Category C-C, Note (5), regarding Class 2 supports with welded attachments.
Table C-C, Number of, _Number Scheduled by Item Number of ExmndPeriod I
Number P
x Welds 1
2 3.
Welded C3.10 Wedd8 1
10 Attachments Welded C3.20 Atahen 171 2
5 4
Attachments Totals 179 3
6 4
Category C-C, Item Numbers C3.30, or C3.40, RNP components.
are not associated with any I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.5 Table IWC-2500-1, Examination Category C-D Table C-D provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-D, "Pressure Retaining Bolting Greater Than 2 inches in Diameter."
ý,Table C-D' Item Nmber o Number Scheduled by Itemb r Examined Period Number Parts aComponents C4.1 0 Bolts and Studs 1
0 1
0 Totals 1
0 1
0 I
I 0
There is no C-D, C4.20, C4.30 or C4.40 items associated with RNP.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.6 Table IWC-2500-1, Examination Category C-F-1 Table C-F-1 provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-F-i, "Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping." Refer to Appendix D for applicable Code Cases.
- 1. Welds selected for examination include 7.5%, but no less than 28 welds, of dissimilar metal, austenitic stainless steel, or high alloy welds. Some welds not exempted under IWC-1 220 are not required to be nondestructively examined in accordance with Examination Category C-F-1. These welds are included in the total weld count to which the 7.5%
sampling rate is applied and are listed as Examination Category C-F-le.
- 2. Distribution of examinations is consistent with Table IWC-2500-1, Examination Category C-F-i, Note (2), as follows:
a) Examinations are distributed among the Class 2 systems prorated, to the degree practical, on the number of nonexempt dissimilar metal, austenitic stainless steel, or high alloy welds in each system, i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category C-F-1 would be performed on that system; b) Within a system, examinations are distributed among terminal ends, dissimilar metal welds, and structural discontinuities prorated, to the degree practical, on the number of nonexempt terminal ends, dissimilar metal welds, and structural discontinuities in that system;
- and, c) Within each system, examinations are distributed between line sizes prorated to the degree practical.
- 3. Structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI B16.9), and pipe branch connections and fittings.
- 4. The welds selected for examination shall be reexamined in the same sequence during subsequent inspection intervals over the service lifetime of the piping component, to the extent practical.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
- 5. For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential welds.
- 6. For circumferential welds with intersecting longitudinal welds, volumetric examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential welds. The following requirements will also be met:
a) When longitudinal welds are specified and locations are known, examination requirements will be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential weld examination volume.
b) When longitudinal welds are specified but locations are unknown, or the existence of longitudinal welds is uncertain, examination requirements will be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Examination Category C-F-I-Weld Selection-Analysis System System Number of Welds.
System Total Required Required Number for.Welds System Minimum Number Examination Examination frWlsSse>
MnmmNme Catgoy Ct ry (C-F7-I + C-F-Ile)
Percentage of WeilIds qg Selection.
C-F7-I C-F7-I e Residual Heat 2045 71 135 206 28%
26 Removal Safety Injection 2080 415 127 542 72%
60 Service Water 4060 0
215 215 0%
0 Component 4080 0
26 26 0%
0 Cooling Water Containment 2080 01 148 148 0%
121 Spray Total Weld Count for 7.5%
Sample Selection 1137 Minimum Weld Sample 86 Selection There are no Examination Category C-F-1 welds in the Containment Spray System, Service Water System or Component Cooling Water System. Welds are exempt based on pipe thickness, i.e., less than 3/8 inch nominal wall, and are categorized as Examination Category C-F-le for counting purposes. HBRSEP, Unit No. 2, has committed to perform examinations on a "best effort" basis on twelve welds as described within Section 19.8, "Examination Category C-F-le."
Percentage requirements have been adjusted so that the sample selection equals 100% of the required examinations since no Examination Category C-F-1 welds are available for examination on the Containment Spray System.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
________Table C -F-1 Item System p'ipeNo.
Number Scheduled by Ite(Ssmt'
'Pip Parts Examined (System Total Selected for Period Numbers No.)
SizExamination 1
2 3
C5.1 1 Circumferential Weld RHR 14 in.
46 10 3
4 3
(2045)
RHR 12 in.
25 6
2 2
2 (2045)
SI C5.11 Circumferential Weld 14 in.
8 2
0 (2080)
SI10 in.
11 3
1 1
1 (2080)
S(
8 in 14 3
1 1
1 (2080)
SI 6 in.
3 1
0 0
1 (2080)
C5.21 Circumferential Weld S4 in.
87 16 5
6 5
(2080)
_3 in.
74 14 5
5 4
(2080)
212 38 12 14 12 (2080)
C5.41 Circumferential Weld SI 3 in.
4 1
0 0
1 (2080) 1 1
1 1
1 SI 2 in.
2 1
0 0
1 (2080)
Totals 486 95 30 33 32 L
h I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.7 Table IWC-2500-1, Examination Category C-F-2 Table C-F-2 provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-F-2, "Pressure Retaining Welds in Carbon Steel or Low Alloy Steel Piping." Refer to Appendix D for applicable Code Cases.
- 1. Examination of welds in piping less than or equal NPS 4 for the HBRSEP, Unit No. 2, high pressure safety injection system are scheduled in accordance with IWC-1 220, "Components Exempt from Examination."
The welds selected for examination include 7.5%, but not less than 28 welds, of carbon and low alloy steel welds not exempted under IWC-1220. Some welds not exempted under IWC-1 220 are not required to be nondestructively examined in accordance with Examination Category C-F-2. These welds are included in the total weld count to which the 7.5%
sampling rate is applied and are listed as Examination Category C-F-2e.
- 2. Distribution of examinations is consistent with Table IWC-2500-1, Examination Category C-F-2, Note (2), as follows:
a) Examinations are distributed among the Class 2 systems prorated, to the degree practical, on the number of nonexempt carbon and low alloy steel welds in each system. i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category C-F-2 would be performed on that system; b) Within a system, examinations are distributed among terminal ends and structural discontinuities prorated, to the degree practical, on the number of nonexempt terminal ends and structural discontinuities in that system; and, c) Within each system, examinations are distributed between line sizes prorated to the degree practical.
- 3. Structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI B16.9), and pipe branch connections and fittings.
- 4. The welds selected for examination will be reexamined in the same sequence during subsequent inspection intervals over the service lifetime of the piping component, to the extent practical.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
- 5. Only those welds showing reportable preservice transverse indications need to be examined by the ultrasonic method for reflectors transverse to the weld length direction, except that circumferential welds with intersecting longitudinal welds will meet Table IWC-2500-1, Examination Category C-F-2, Note (7).
- 6. For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds will be performed for those portions of the welds within the examination boundaries of intersecting circumferential welds.
- 7. For circumferential welds with intersecting longitudinal welds, volumetric examination of the longitudinal piping welds will be performed for those portions of the welds within the examination boundaries of intersecting circumferential welds. The following requirements will also be met:
a) When longitudinal welds are specified and locations are known, examination requirements will be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential weld examination volume.
b) When longitudinal welds are specified but locations are unknown, or the existence of longitudinal welds is uncertain, examination requirements will be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Examination a.egory -F-Feedwate 3umbe4 of5Weld%
lSyste Total Required Required System Examination Examination for Welds System Minimum Number
'Number W
SPercentage 2
.Category-Catgory
-J C-F-2 + C-F-2e)
Slcon of Welds.
C-F-2 elction V
Selection Main Steam 3020 68 23 91 35%
10 Feedwater 3050 44 6
50 19%
6 Auxiliary305175124%3 Feedwater 305175124%3 Total Weld Count for 7.5%
253 Sample Selection Minimum Weld Sample 28 Selection RNP-PM-008 Revision 0 Pag e45f8
H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program j
~>
Table C-F-2 ItemsteTota No.
~
Minimum Number I
Parts Examined (Syte pip Total SSelectedfor Scheduled by Period Numbers Size
-Examination 1,
3.
MS No.
1n 38622 3
C5.51 Circumferential Weld MS 26 in.
38 6
2 2
2 (3020) 8 in.
15 2
1 0
1 C5.51 Circumferential Weld FW 18 in.
6 1
0 1
0 (3050) 16 in.
38 6
2 2
2 C5.60 Circumferential Weld AFW 4in.
104 14 4
5 5
(3065)
C5.81 Circumferential Weld MS8 in.
15 2
1 0
1 (3020)
C5.81 Circumferential Weld AFW 4 in.
3 1
1 0
0 (3065)
Totals 219 32 11 10 11 I RNP-PM-008 Revision 0 1
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.8 Examination Category C-F-le Table C-F-I e provides a summary of welds that have been identified as Examination Category C-F-ie, "Exempt Welds (For Counting Purposes Only)."
- 1. Welds exempt under IWC-1220, "Components Exempt from Examination," and not required to be examined in accordance with Table IWC-2500-1, Examination Category C-F-i, are included in the total weld count to which the 7.5% sampling rate is applied. These welds have been identified as Examination Category C-F-i e and are for counting purposes only (no examinations are required).
- 2. Component support examinations are scheduled for this piping in accordance with Subsection IWF, "Requirements for Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Plants" (reference Section 21.0).
Table C-F-le System System Number Total Number of Welds Residual Heat 2045 135 Removal Safety Injection 2080 127 Containment Spray 2080 148 Service Water 4080 215 Component cooling 4060 26 Water I RNP-PM-008 I
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
- 3. There are no Examination Category C-F-1 welds in the Containment Spray System. These welds are identified as Examination Category C-F-1(e) (exempt) based on pipe thickness, i.e., less than 3/8 inch nominal wall. HBRSEP, Unit No. 2, has committed to perform examination of the twelve welds identified below on a "best effort" basis. These exams are identified in Appendix "E" as Item Number "E-8".
Containment Spray System Weld Selections Examination Category 0-F-2e S
(System No. 2080)
Number Scheduled by Pipe
~Pipe-t&-ToaPI rd Size
~Pipe TtlAPro 2 2 3
4 in.
0 2
0 0
0 8 in.
0 10 1
0 1
6 in.
17 134 3
4 3
4 in.
2 2
0 0
0 Totals 148 4
4 4
.L.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.9 Examination Category C-F-2e Table C-F-2e provides a summary of welds that have been identified as Examination Category C-F-2e, "Exempt Welds (For Counting Purposes Only)."
- 1. Welds exempt under IWC-1220, "Components Exempt from Examination," and not required to be examined in accordance with Table IWC-2500-1, Examination Category C-F-2, are included in the total weld count to which the 7.5% sampling rate is applied. These welds have been identified as Examination Category C-F-2e and are for counting purposes only (no piping examinations are required).
- 2. Component support examinations are scheduled for this piping in accordance with Subsection IWF, "Requirements for Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Plants" (reference Section 21.0).
Table C-F-2e System System Number Total Number of Welds Main Steam 3020 23 Feedwater 3050 6
Auxiliary Feedwater 3065 5
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 19.10 Table IWC-2500-1, Examination Category C-H Table C-H provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-H, "All Pressure Retaining Components."
Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
- 1. System leakage tests will be conducted in accordance Articles IWA-5000 and IWC-5000, "System Pressure Tests," as stipulated within TMM-020, "Inservice Pressure Testing Program," including the following:
The pressure requirements of IWC-5221, "Pressure."
The boundary requirements of IWA-5221, "System Leakage Test Boundary," and IWC-5222, "Boundaries." Also note that system leakage test boundaries include those portions of the system required to operate or support the safety function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
Relief has been granted to address instances where it is impractical for HBRSEP, Unit No. 2, to test certain system boundaries.
The holding time requirements of IWA-5213, "Test Condition Holding Time."
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Table C-H Code Number Scheduledby Period E~xamination-
,,S ystem T
.est',
+.
.. +
Examination item System/Test Description St Test
-,Category Number Number Procedure 1
2 3'
~N um b e r
,+
...+..,*+
C-H C7.10 SI Pump Discharge Piping 2080 EST-078 Outside Containment C-H C7.10 CV Spray Piping Outside 2080 EST-079 Containment C-H C7.10 RHR Piping Inside and 2045 EST-080 Outside Containment C-H C7.10 Auxiliary Feedwater Piping 3065 EST-082 Inside/Outside Containment C-H C7.10 SI Pump Discharge Piping 2080 EST-090 Inside Containment SI and CV Spray Pump C-H C7.10 Suction Piping Outside 2080 EST-091 Containment C-H C7.10 CVCS Piping Inside 2060 EST-127 Containment SG Secondary Side and 3005 EST-128 C-H C7.10 Associated Piping Inside and 3020 EST-077 Outside Containment 3050 SI Accumulators and C-H C7.10 Associated Class 2 Piping 2080 EST-129 Inside Containment C-H C7.10 CVCS Piping Outside 2060 EST-131 Containment Performed once each inspection period.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 20.0 Subsection IWD for Class 3 Components 20.1 Bases and Scope The Class 3 system boundaries are based upon the requirements of Regulatory Guide 1.26, and the HBRSEP, Unit No. 2, UFSAR. Specific examinations are in accordance with the ASME B&PV Code, Section X1, Table IWD-2500-1, as further described below.
- 1.
The examination requirements shall apply to pressure retaining components and welded attachments on Class 3 systems in support of the following functions:
(b) reactor shutdown (c) emergency core cooling (d) containment heat removal (e) atmosphere cleanup (f) reactor residual heat removal (g) residual heat removal from spent fuel storage pool
- 2.
The following components or portions of components are exempted from the VT-I visual examination requirements of IWD-2500:
- a. components and piping segments NPS 4 (DN 100) and smaller
- b. components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DN 100) and smaller
- c. components1 and piping segments which have multiple inlets or outlets, whose cumulative cross sectional area does not exceed the cross sectional area defined by the OD of NPS 4 (DN 100) pipe
- d. Components that operate at a pressure of 275 psig or less and at a temperature of 200OF or less in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, CV spray/containment heat removal, and safety injection/emergency core cooling.
- e. Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe RNP-PM-008 Revision 0 Page 52 of 82
H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 20.2 Table IWD-2500-1, Examination Category D-A Table D-A provides the examination scope and schedule for Table IWD-2500-1, Examination Category D-A, "Welded Attachments for Vessels, Piping, Pumps, and Valves."
- 1.
Examinations will include each vessel welded attachment most subject to corrosion, and each vessel welded attachment most subject to corrosion of one vessel for each multiple-vessel group associated with component supports. Examinations will also include 10% of the piping and pump welded attachments most subject to corrosion that are associated with component supports. The piping and pump welded attachment sample will be proportional to the total number of non-exempt welded attachments connected to the piping and pumps in each system.
- 2.
Conservatively, all D1.10 and D1.30 attachments have been included in the population, regardless of whether it is attached by welding or was integrally cast with the component.
Table D-A Minimum Minimum Number Item Parts NOT of No. of Required by Number Examined Welded Exams Period A
mRequired 1-2 3
Vessel 16 D1.10*
Welded (9 Vessels) 6 2
2 2
Attachments Piping D1.20 Welded 106 11 4
3 4
Attachments Pumps 16 D1.30*
Welded 1
6 2
2 2
Attachments (14 Pumps)
Totals 138 23 8
7 8
- Multiple vessel examination Category D-A, Item Number D1.40, are not associated with any RNP components.
RNP-PM-008 Revision 0 Page 53 of 82
H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 20.3 Table IWD-2500-1, Examination Category D-B Table D-B identifies the system leakage tests conducted in accordance with Table IWD-2500-1, Examination Category D-B, "Pressure Retaining Components." Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.
System leakage tests are conducted in accordance with Articles IWA-5000 and IWD-5000, "System Pressure Tests," as stipulated within TMM-020, "Inservice Pressure Testing Program." Additionally, system leakage tests will be conducted in accordance with the following:
- 1.
IWD-5221, "System Leakage Test."
The system leakage test shall be conducted at the system pressure obtained while the system, or portion of the system, is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability (e.g. to demonstrate system safety function or to satisfy technical specification surveillance requirements).
- 2.
IWD-5222, "Boundaries" (a) The pressure retaining boundary for closed systems includes only those portions of the system required to operate or support the safety function up to including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
(b) The pressure retaining boundary for non-closed systems (e.g.)
service water systems) includes only those portions of the system required to operate or support the safety function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. Open ended discharge piping is included in the pressure retaining boundary, provided it is periodically pressurized to conditions described in IWD-5221.
(c) The following portions of systems are excluded from examination requirements (1) items outside the boundaries of (a) above (2) items outside the boundaries of (b) above (3) open ended discharge piping that is not periodically pressurized to conditions described in IWD-5221 (4) portions of the system that are associated with a spray header or are normally submerged in its process fluid such that the external surfaces of the pressure retaining boundary are normally wetted during its pressurized conditions.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Table D3-B3 Test Numb-erScheduled by yst Code Ie System.
Tet P.eriod Examination :CodelItem.
- System Test Description Number
.Procedur Category Number Number Procedure 1
D-B D2.10 SW Piping Inside Containment 4060 EST-081*
to/from HVH Units D-B D2.10 AFW System Piping 3065 EST-082 D-B D2.10 Spent Fuel Pool Cooling 7110 EST-084 D-B D2.10 CCW Inside Auxiliary Building 4080 EST-088 D-B D2.1 0 Spray Additive Tank and 2080 EST-092 Associated Piping D-B D2.10 Steam Supply Piping to Steam-3065 EST-097 Driven AFW Pump D-B D2.10 Diesel Fuel Oil System Piping 5100 EST-098 CCW System Supply to RCPs, D-B D2.10 Excess Letdown HX, and CRDM 4080 EST-076 HVH Units D-B D2.10 FW Piping Inside and Outside 3050 EST-077 Containment D-B D2.10 CVCS and Associated Piping 2060 EST-093 D-B D2.10 SW Piping System 4060 EST-094 D-B D2.10 CVCS Piping Outside CV 2060 EST-131 Performed once each inspection period.
RNP-PM-008 Revision 0 Page 55 of 82-]
H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 21.0 Subsection IWF for Class 1, 2, 3, and MC Component Supports 21.1 Bases and Scope The Class 1, 2, 3, and MC component support boundaries are based on the requirements of 10 CFR 50.2, Regulatory Guide 1.26, and the HBRSEP, Unit No. 2, UFSAR. Specific examinations are based on the requirements of the ASME B&PV Code, Section Xl, Table IWF-2500-1, as indicated below.
The term "component support" includes supports for such items as vessels and pumps, and supports for piping that are treated separately for selection purposes. These supports also include snubber supports to the building and piping, outside of the snubber cylinder pin-to-pin exclusive which is examined under the Snubber Program (TMM-006).
1 Exemptions from support examination requirements are in accordance with Article IWF-1000, "Scope and Responsibility," subsection IWF-1230, "Supports Exempt from Examination". Supports exempt from the examination requirements of Article IWF-2000, "Examination and Inspection," are those connected to piping and other items exempt from volumetric, surface, VT-1, or VT-3 visual examination under the following:
IWB-1 220, "Components Exempt from Examination" IWC-1220, "Components Exempt from Examination" IWD-1 220, "Components Exempt from Examination" IWE-1220, "Components Exempt from Examination" 2
In addition, portions of supports that are inaccessible due to being encased in concrete, buried underground, or encapsulated by guard pipe, are also exempt from the requirements of Article IWF-2000.
- 3.
Component supports selected and examined are those supports for components, i.e., vessels, pumps, etc., that are required to be examined in accordance with the following:
IWB-2500, "Examination and Pressure Test Requirements" IWC-2500, "Examination and Pressure Test Requirements" IWD-2500, "Examination and Pressure Test Requirements"
- 4.
Supports examined for piping are selected in accordance with the percentages and sampling requirements of Table IWF-2500-1 from the support population of all piping not exempted under IWB-1 220, IWC-1220, and IWD-1220, in accordance with IWF-2510, "Supports Selected for Examination."
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program
- 5.
Supports have been categorized in the Fifth Ten-Year Interval Inservice Inspection Program to identify support types by component support function as follows:
A - Deadweight hangers B - Restraints (multi-directional)
C - Thermal Movement (spring hangers)
- 6.
Support types A, B and C have been further categorized in IDDEAL in accordance with the table identified in the Fifth Ten-Year Interval Plan (RNP-PM-009).
- 7.
Examinations will be in accordance with Table IWF-2500-1, Examination
- 8.
Category F-A, and will include 25% of Class 1, 15% of Class 2, and 10% of Class 3 supports on non-exempt piping, including piping supports located on piping classified as Examination Category C-F-le and C-F-2e for Class 2 piping
- 9.
The total percentage sample will be comprised of supports from each system where the individual sample sizes are proportional to the total number of non-exempt supports of each type and function within each system. Fractional numbers shall be rounded up to the nearest whole number.
- 10.
For multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
- 11.
To the extent practical, the same supports selected for examination during the first inspection interval shall be examined during each successive inspection interval.
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H.B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program 21.2 Table IWF-2500-1, Examination Category F-A Table F-A provides the examination scope and schedule for Table IWF-2500-1, Examination Category F-A, "Supports."
Table F-*
Percent Minimum Number No.m o
Schijedueby
,Number Cls Su~pports.
Req'uired Supports Pro Require~d
-- i Class 1 F1.10 Piping 198 25%
50 17 17 17 Supports Class 2 F1.20 Piping 533 15%
80 26 27 27 Supports Class 3 F1.30 Piping 465 10%
47 16 16 16 Supports Supports Other Than 94 supports F1.401 Piping on 46 1001%
442 14 14 16 Supports components (Class 1, 2, (24 Groups) 3, and MC) I I _II II_
1 Components scheduled in accordance with Table IWF-2500-1, Examination Category F-A, Note (3), for multiple components.
2 Refer to Appendix C for applicable Relief Requests.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Supports Other Than Piping Supports (F-A, F1.40)
Number No. Scheduled By GroupCNoumbernofs o
Number of NmGreupr ofSupports Supports Peid in Group in Group Required 1
2 3
Reactor Vessel 1
3 3
0 0
3 Pressurizer 1
1 1
0 0
1 Regenerative Heat 1
6 0
0 0
0 Exchanger2 SG (Primary Side) 3 12 4
2 2
0 Reactor Coolant 3
9 3
0 0
3 Pump Boron Injection Tank 1
4 4
1 1
2 RHR Heat Exchanger 2
4 2
0 2
0 (Primary Side)
SG (Secondary Side) 3 15 5
0 0
5 RHR Pump 2
2 1
0 1
0 SI Pump 2
2 1
0 1
0 CV Spray Pump 2
2 1
0 1
0 Non Regenerative 1
2 2
2 0
0 Heat Exchanger EDG Coolers 2
2 2
0 1
0 RHR Heat Exchanger 2
4 2
2 0
0 (Secondary Side)
CCW Heat Exchanger 2
4 2
2 0
0 SFPC Heat 1
2 2
0 2
0 Exchanger CCW Surge Tank 1
2 2
0 0
2 SW Pump 4
4 1
0 1
0 SW Strainers 2
2 1
0 0
1 SW Booster Pump 2
2 1
0 1
0 CCW Pump 3
3 1
0 1
1 1
0 1
4 2
2 0
0 SFPC Pump 2
2 1
1 0
0 Totals 46 94 44 12 15 17 1 Components scheduled in accordance with Examination Category F-A, Item Note (3).
2 Refer to Appendix C for applicable Relief Requests.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix AP&IDIASME Code Boundary Drawings (Flow Diagrams)
Drawing No.
Sheet No.
System Acronym P&ID Title G-190196 1
3020 MS Main & Extraction Steam G-1 90197 1
3065 AFW Feedwater, Condensate & Air Evacuation G-1 90197 4
3050 FW Feedwater, Condensate & Air Evacuation G-190197 4
3065 AFW Feedwater, Condensate & Air Evacuation G-1 90199 2
4060 SW Service & Cooling Water G-190199 4
4060 SW Service & Cooling Water G-1 90199 5
4060 SW Service & Cooling Water G-1 90199 6
4060 SW Service & Cooling Water G-190199 7
4060 SW Service & Cooling Water G-190199 8
4060 SW Service & Cooling Water G-1 90199 9
4060 SW Service & Cooling Water G-1 90199 10 4060 SW Service & Cooling Water G-190202 3
3065 DW Primary & Makeup Water G-190204-A 2
4060 SW Emergency Diesel Generator G-190204-A 3
4060 SW Emergency Diesel Generator G-190204-C 1
3015 CF Chemical Feed G-190204-D 2
5100 FO Fuel Oil G-190234 1
3010 SGBD Steam Generator Blowdown & Wet Layup G-190261 2
8100 PP Penetration Pressurization G-190261 4
8100 PP Penetration Pressurization G-1 90262 1
8175 IVSW Isolation Valve Seal Water G-190304 1
8150 HVAC HVAC - Turbine, Fuel, Aux., Reactor, &
Radwaste Buildings 5379-353 1
2115 PS Primary Sampling 5379-376 1
4080 AC, CCW Component Cooling Water 5379-376 2
4080 AC, CCW Component Cooling Water 5379-376 3
4080 AC, CCW Component Cooling Water 5379-376 4
4080 AC, CCW Component Cooling Water 5379-684 1
2060 CHG, CVCS CVCS Boron Recirculation Distillate 5379-685 1
2060 CHG, CVCS CVCS Purification & Makeup 5379-685 2
2060 CHG, CVCS CVCS Purification & Makeup 5379-685 3
2060 CHG, CVCS CVCS Purification & Makeup 5379-686 1
2060 CHG, CVCS CVCS Boron Recirculation Process & Storage 5379-920 3
7060 WD, LWD Liquid Waste Disposal I RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix A (Continued)
P&ID/ASME Code Boundary Drawings (Flow Diagrams)
Drawing No.
Sheet No.
System Acronym P&ID Title 5379-921 2
7070 WD, GWD Gaseous Waste Disposal 5379-1082 1
2080 SI, SIS Safety Injection 5379-1082 2
2080 SI, SIS Safety Injection 5379-1082 3
2080 SI, SIS Safety Injection 5379-1082 4
2080 SI, SIS Safety Injection 5379-1082 5
2080 SI, SIS Safety Injection 5379-1484 1
2045 AC, RHR Residual Heat Removal 5379-1485 1
7110 AC, SFPC Spent Fuel Pit Cooling 5379-1971 1
2005 RC, RCS Reactor Coolant System 5379-1971 2
2005 RC, RCS Reactor Coolant System HBR2-6490 1
2118 PASS Containment Vapor and Pressure Sampling HBR2-6933 1
2075 PASS Post Accident CV Venting & H2 Recombiner HBR2-8255 2
6175 FP Fire Protection HBR2-8255 3
6175 FP Fire Protection HBR2-9067 1
1055 RVLIS Reactor Vessel Level Indicator Switches HBR2-7063 1
N/A N/A Flow Diagram Legends HBR2-7063 2
N/A N/A Flow Diagram Legends RNP-PM-008 Revision 0 1
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix B Calibration Block List
,'i Material Item No.
Block ID RNP Part No.
Size Schedule atiHeat Number Application'
~~~Specification HetNmr Apicto 11 CPL-10A 0072547862 21/2" "T"
A-376 316 D8770 Pipe 2
CPL-20 0071591846 1 1/2" T'
A-515 GR70 66B093 Skirt 3
CPL-21 0071591754 11/2...
T" A-312 316H 87623 Pipe 4
CPL-22 0071503577 2"
S/160 A-376 304 01003 Pipe 5
CPL-23 0071591820 3"
S/160 A-312 316H 26896 Pipe 6
CPL-24 0071503569 4"
S/160 A-376 316 M9290 Pipe 7
CPL-25 0071591689 6"
S/40 A-333 GB.6 32849 Pipe 8
CPL-26 0071591663 6"
S/40S A-312 304 M9959 Pipe 9
CPL-27 0071591697 8"
S/40S A-312 316 M0937 Pipe 10 CPL-28 0071591762 8"
S/120 A-312 304 M0176 Pipe 11 CPL-29 0071591705 8"
S/140 A-376 316 4-098 Pipe 12 CPL-30 0071591648 10" S/40S A-312 316 K24123 Pipe 13 CPL-31 0071591812 10" S/120 A-312 304 6-448 Pipe 14 CPL-32 0071591853 10" S/140 A-312 304 D61232 Pipe 15 CPL-33 0071591713 12" S/40S A-312 316 8052221 Pipe 16 CPL-34 0071503551 12" S/140 A-312 304 F0959 PZR Surge Line 17 CPL-35 0071591796 14" S/40 A-358 316 14085 Pipe 18 CPL-36 0071803886 14" S/140 A-312 304 1762 Pipe 19 CPL-37 0071591747 14" S/160 A-312 304 4-483 Pipe 20 CPL-38 0071591804 16" S/120 A-333 GR.6 42794 Pipe 21 CPL-39 0071591788 24" S/80 A-106 N13070 Pipe 22 CPL-40 0071591861 32" 1.203" SA-156 GR70 802N67160 Pipe 23 CPL-41 0071591721 16" S/80S A-312 304 26265 Pipe 24 CPL-42 0071817720 0.313".T" SA-240 303 856455 Flat 25 CPL-43 0071817688 0.438" "T"
SA-240 303 856455 Flat I RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix B (Continued)
Calibration Block List Item No.
Block ID RNP Part No.
Size Scdhedule Materialon Application Specification HetNmr Aplcio 26 CPL-44 0071817753 5.0".T" SA-533 D8366-5 PZR 27 CPL-45 0071817761 31/2" "T"
A-508 123P118 FW Nozzle 28 CPL-46 0071817787 8"
S/40S A-312 316 M0937 Pipe 29 CPL-47a 0072237324 2.006" "T"
SA-240 304 F07931 BIT 30 CPL-47B 0071591671 14" S/10 SA-312 304 182 Piping 31 CPL-47 0072699796 8"
"T" SA-533 CL. 1 TP. B D8366-5 RPV Head 32 CPL-48 0072699846 8"
S/160 A-106 GR. B 50465 MS Nozzles 33 CPL-49 0072699861 0.875" "T"
SA-240 304 F07931 RHR HX 34 CPL-51 0072699754 5.0".
"T" A-508 122P169 S/Gs 35 CPL-56 0072699879 26" 1.042" A-1 55-KC-55 CL. 1 3G6735 MS 36 CPL-57 0072699887 18" S/100 SA-508 CL. 2 128097 FW 37 CPL-54 0072699911 16" S/100 A-106 GR. B 82565 FW 38 CPL-50a 0072699937 3 1/2Y" "T"
A-533 CL. 1 TP. B D8366 SGs 39 RV-1 0072545064 10"
'T" A-508 CL. 2 BW-PC-3 Ligaments 40 RV-2 0072545098 4""T"..
T" A-508 CL. 2 BW-PC-3 RPV Flange &
Nozzle 41 RV-3 0072545122 10.5".
"T" SA-533 CL. 1 TP. B D8366-5 RPV Shell 42 RV-4 0072545163 6"
"T" SA-533 CL. 1 TP. B D8366-5 RPV Bottom Head 43 RV-5 0072545189 3"
"T" A-508 CL. 2 &
8651885 RPV Safe End SA-182 TP. 316 44 CPL-58 0073168932 8"
S/160 A-376 316 M0035 Piping 45 CPL-59 0073168882 10" S/160 SA-376 316 2543-4-1 Piping 46 CPL-60 0073741340 7"
DIA.
4340 TO SA-193 Spare RPV Studs 47 CPL-61 0073741357 2.5" DIA.
A-479 TP. B-410 99069 BIT Studs I RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix B (Continued)
Calibration Block List Item No.
Block ID RNP Part No.
Size Schedule Material Specification Heat Number, Application 48 CPL-62 0073570111 3.30" DIA.
SA-540 GR. B23 Spare RCP Studs 49 CPL-63 0073741233 Irregular SA-508 CL. 2 6-5858 FW Inner Radius 50 CPL-64 0073741365 Irregular SA-508 CL. 2 31-3212 MS Inner Radius 51 CPL-61A 0073828972 2.5" DIA.
A-479 TP B-410 31067 BIT Studs (Spare) 52 CPL-65 0073985855 6"
S/10 A-312 304 81547 Piping 53 CPL-66 0073985889 6"
S/40 A-312 304 90191 Piping 54 CPL-67 0073985897 8"
S/10 A312 304 A030501 Piping 55 CPL-65A 0073854606 27.5" 0.6" "T" SA-376 K2980 Wrought SS 56 CPL-66A 0073854598 31" 0.383" "T" SA-351 CF8A 5160C-1 Cast Elbow 57 CPL-68 0000001069 16" 1.5" CrMo A234 WP 22 1322B FW Reducer 58 CPL-69 0000001070 18" 1.44" CrMo A234 WP 22 1322B FW Reducer 59 CPL-70 0076324559 4"
S/80 A312 TP316 MR022 Piping 60 CPL-71 0076324560 3"
S/80 A312 TP316 K37872 Piping 61 CPL-72 0076324561 2"
S/80 A312 TP316 443571 Piping 62 CPL-73 0076325201 10" Sch/140 A182 F316 1822ANE BC Block 64 CPL-74 0076325202 7.0" RPV Studs AISI 4340 TO SA-SPARE RPV Studs 193 65 CPL-75 0076325203 3.5" RCP Studs SA-540 GR B-23 11303 RCP Studs CL4 66 CPL-76 9220105787 5.75" PRZ Head SA-216 WCC 030710-2 PRZ Head 67 CPL-77 92220105792 N/A PDI A-304 / A304L A13979 PDI SS ALT BLK 68 CPL-78 92220105792 N/A PDI A-516-70 1H924 PDI CS ALT BLK 69 CPL-79 92220105792 N/A PDI A-316 / A316L 1S146 PDI SS ALT BLK 1 - Calibration block CPL/10A is obsolete and no longer used.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix C Relief Requests Relief Affected Examination itv No.
Examnation Area Alterntive Req uest~
Examinationsiaton re Status Number Component(s)
Category Examinations-,
RR-01 Pressurizer Surge B-D B3.120 Surge line nozzle inside radius None Submitted Line section RR-02 Regenerative Heat B-B B2.51 Circumferential head welds VT-3 visual Submitted Exchanger B2.80 Tubesheet-to-shell weld examination once B-D B3.150 Nozzle-to-vessel welds per period.
B3.160 Nozzle inside radius section B-J B9.32 Branch connections B9.21 Circumferential welds F-A F1.40 Associated supports RR-03 Reactor Vessel B-A B1.21 The accessible length of the None Submitted Bottom Head Peel RPV closure head peel Segment-To-Disk segment-to-disk Circumferential circumferential Weld RR-04 Pressure Test Full B-P B15.20 Pressurization of full boundary None Submitted Boundary RR-05 Borated Bolted B-P, C-H, D-B Bolted Connections None Submitted Connections RR-06 Surface B-F B5.10 Surface exam of RPV nozzle-None Submitted Examination of to-safe end welds Reactor Vessel Dissimilar Metal Welds L
Shaded Relief Requests are either Withdrawn, Superseded or Voided as identified in the Status Column.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix D Code Cases
- Cso.de" Examination Item Reg. Guide
-C ode Ex Item:*
. :.e t iii
-.,-Case Subject Category Number(s)
'1.147Rev.-_,1..
N-432-1 Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding N/A N/A 16 (GTAW) Temper Bead Technique, N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds All Applicable All Applicable 16 N-494-4 Pipe Specific Evaluation Procedures and Acceptance Criteria for Flaws in N/A N/A 16 Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2 and in Class 1 Austenitic Piping that Exceed the Acceptance Standards of IWB-3514.3.
N-504-4 Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel N/A N/A 16 Piping The provisions of Section Xl, Nonmandatory Appendix Q, "Weld Overlay Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments,"
must also be met. In addition, the following conditions shall be met: (a) the total laminar flaw area shall not exceed 10% of the weld surface area, and no linear dimension of the laminar flaw area shall exceed the greater of 3 inches or 10% of the pipe circumference; (b) the finished overlay surface shall be 250 micro-in (6.3 micrometers) root mean square or smoother; (c) the surface flatness shall be adequate for ultrasonic examination; and (d) radiography shall not be used to detect planar flaws under or masked by laminar flaws.
N-508-3 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of N/A N/A 16 Testing N-513-3 Evaluation Criteria for Temporary Acceptance of Flaws in Class 3 Piping N/A N/A 16 The repair or replacement activity temporarily deferred under the provisions of this Code Case shall be performed during the next scheduled outage.
N-516-3 Underwater Welding N/A N/A 16 Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(a)(3) regarding the technique to be used in the weld repair or replacement of irradiated material underwater.
N-526 Alternative Requirements for Successive Inspections of Class 1 and 2 N/A N/A 16 Vessels III_
I Conditionally Acceptable Code Cases are shown in Italic and approved for use in Regulatory Guide 1.147 Latest Revision, with the Conditionally Acceptable Requirement identified in BOLD.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix D Code Cases (Cont'd)
Code Examination Item Reg. Guide Case Subject Category Number(s) 1.147 Rev.
N-528-1 Purchase, Exchange, or Transfer of Material Between Nuclear Plant Sites N/A N/A 16 The requirements of 10 CFR Part 21, "Reporting of Defects and Noncompliance" (Ref. 5), are to be applied to the nuclear plant site supplying the material as well as to the nuclear plant site receiving the material that has been purchased, exchanged, or transferred between sites.
N-532-4 Alternative Requirements to Repair and Replacement Documentation N/A N/A 16 Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000.
N-533-1 Alternative Requirements for VT-2 Visual Examination of Class 1, 2, and 3 B-P, C-H, D-B B15.10 16 Insulated Pressure Retaining Bolted Connections B115.20 Prior to conducting the VT-2 examination of Class 2 and Class 3 C7.10 components not required to operate during normal plant operation, a 10 D2.10 minute holding time is required after attaining test pressure. Prior to conducting the VT-2 examination of Class 2 and Class 3 components required to operate during normal plant operation, no hold time is required, provided the system has been in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated components or 10 minutes for non-insulated components.
N-534 Alternative Requirements for Pneumatic Pressure Testing N/A N/A 16 N-537 Location of Ultrasonic Depth Sizing Flaws Appendix VIII Appendix VIII 16 N-552 Alternative Methods - Qualification for Nozzle Inside Radius Section from the Appendix VIII, N/A 16 Outside Surface Supplement 5 To achieve consistency with the 10 CFR 50.55a rule change published September 22, 1999 (64 FR 51370), incorporating Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," to Section X1, add the following to the specimen requirements: "At least 50 percent of the flaws in the demonstration test set must be cracks and the maximum misorientation must be demonstrated with cracks. Flaws in nozzles with bore diameters equal to or less than 4 inches may be notches." Add to the detection criteria, "The number of false calls must not exceed three."
Conditionally Acceptable Code Cases are shown in Italic and approved for use in Regulatory Guide 1.147 Latest Revision, with the Conditionally Acceptable Requirement identified in BOLD.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix D Code Cases (Cont'd)
Code Examination Item Reg. Guide Case Subject Category Number(s) 1.147 Rev.
N-553-1 Inservice Eddy Current Surface Examination of Pressure Retaining Pipe Welds N/A N/A 16 and Nozzle-to-Safe End Welds N-554-3 Alternative Requirements for Reconciliation of Replacement Items and Addition N/A N/A 16 of New Systems N-557-1 In-Place Dry Annealing of a PWR Nuclear Reactor Vessel N/A N/A 16 The secondary stress allowable of 3Sin, shown in Figure 1 of the Code Case, must be applied to the entire primary plus secondary stress range during the anneal.
N-566-2 Corrective Action for Leakage Identified at Bolted Connections N/A N/A 16 N-567-1 Alternative Requirements for Class 1, 2, and 3 Replacement Components, N/A N/A 16 N-573 Transfer of Qualifications Records Between Owners IWA-4000 IWA-4000 16 N-586-1 Alternative Additional Examination Requirements for Classes 1, 2, and 3 Piping, N/A N/A 16 Components, and Supports N-597-2 Requirements for Analytical Evaluation of Pipe Wall Thinning, N/A N/A 16 (1) Code Case must be supplemented by the provisions of EPRI Nuclear Safety Analysis Center Report 202L-R2,"Recommendations for an Effective Flow Accelerated Corrosion Program" (Ref. 6), April 1999, for developing the inspection requirements, the method of predicting the rate of wall thickness loss, and the value of the predicted remaining wall thickness. As used in NSAC-202L-R2, the term "should" is to be applied as "shall" (i.e., a requirement).
(2) Components affected by flow-accelerated corrosion to which this Code Case are applied must be repaired or replaced in accordance with the construction code of record and Owner's requirements or a later NRC approved edition of Section III, "Rules for Construction of Nuclear Power Plant Components," of the ASME Code (Ref. 7) prior to the value of tp reaching the allowable minimum wall thickness, tmin, as specified in -
3622.1 (a)(1) of this Code Case. Alternatively, use of the Code Case is subject to NRC review and approval per 10 CFR 50.55a(a)(3).
(3) For Class I piping not meeting the criteria of -3221, the use of evaluation methods and criteria is subject to NRC review and approval per 10 CFR 50.55a(a)(3).
(4) For those components that do not require immediate repair or I replacement, the rate of wall thickness loss is to be used to determine a RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Code
-Examination Item Reg. Guide Cas
-14 Rev.a-Cs ____________
Category Number(s) 1.147Rev.
suitable inspection frequency so that repair or replacement occurs prior to reaching allowable minimum wall thickness, tmin.
(5) For corrosion phenomenon other than flow accelerated corrosion, use of the Code Case is subject to NRC review and approval. Inspection plans and wall thinning rates may be difficult to justify for certain degradation mechanisms such as MIC and pitting.
N-600 Transfer of Welder, Welding Operator, Brazer, and Brazing Operator N/A N/A 16 Qualifications Between Owners N-616 Alternative Requirements for VT-2 Visual Examination of Classes 1, 2, 3 N/A N/A 16 Insulated Pressure Retaining Bolted Connections (1) Insulation must be removed for VT-2 examination during the system pressure test for any 17-4 PH stainless steel of 410 stainless steel stud or bolt aged at a temperature below 11001F or with hardness above Rc 30.
(2) For A-286 stainless steel studs or bolts, the preload must be verified to be below 100 ksi or the thermal insulation must be removed and the joint visually examined.
(3) Prior to conducting the VT-2 examination of Class 2 and Class 3 components not required to operate during normal plant operation, a 10-minute holding time is required after attaining test pressure. Prior to conducting the VT-2 examination of Class 2 and Class 3 components required to operate during normal plant operation, no holding time is required, provided the system has been in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated components or 10 minutes for non-insulated components.
N-619 Alternative Requirements for Nozzle Inner Radius Inspections for Class 1 B-D B3.120 16 Pressurizer and Steam Generator Nozzle B3.140 In lieu of a UT examination, licensees may perform a visual examination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table (the external surface is from point M to point N in the figure).
N-624 Successive Inspections N/A N/A 16 N-629 Use of Fracture Toughness Test Data to Establish Reference Temperature for N/A N/A 16 Pressure Retaining Materials RNP-PM-008 Revision 0 Page 69 of 821
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program COCde
'bjt Examination Item Reg. Guide
,Case u
Category Number(s) 1.147 Rev.
N-638-4 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine N/A N/A 16 GTAW Temper Bead Technique (1) Demonstration for ultrasonic examination of the repaired volume is required using representative samples which contain construction type flaws.
(2) The provisions of 3(e)(2) or 3(e)(3) may only be used when it is impractical to use the interpass temperature measurement methods described in 3(e)(1), such as in situations where the weldment area is inaccessible (e.g., internal bore welding) or when there are extenuating radiological conditions.
N-639 Alternative Calibration Block Material N/A N/A 16 Chemical ranges of the calibration block may vary from the materials specification if (1) it is within the chemical range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.
N-641 Alternative Pressure-Temperature Relationship and Low Temperature N/A N/A 16 Overpressure Protection System Requirements N-643-2 Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water N/A N/A 16 Environment N-647 Alternative to Augmented Examination Requirements of IWE-2500 N/A N/A 16 A VT-1 examination is to be used in lieu of the "detailed visual examination." [Note: Draft Regulatory Guide DG-1070, "Sampling Plans Used for Dedicating Simple Metallic Commercial Grade Items for Use in Nuclear Power Plants" (Ref. 8), is being developed to provide acceptable guidelines for sampling criteria.]
N-648-1 Alternative Requirements for Inner Radius Examination of Class I Reactor N/A N/A 16 Vessel Nozzles In place of a UT examination, licensees may perform a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table (the external surface is from point M to point N in the figure).
N-649 Alternative Requirements for IWE-5240 Visual Examination N/A N/A 16 RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Code Examination Item Reg. Guide Case Subject Category Number(s) 1.147 Rev.
N-651 Ferritic and Dissimilar Metal Welding Using SMA W Temper Bead Technique N/A N/A 16 Without Removing the Weld Bead Crown for the First Layer N-652-1 Alternative Requirements to Categories B-G-1, B-G-2, and C-D Bolting B-G-1, B-G-2, C-D All 16 Examination Methods and Selection Criteria N-658 Qualification Requirements for Ultrasonic Examination of Wrought Austenitic N/A N/A 16 Piping Welds N-660 Risk-Informed Safety Classification for Use in Risk-Informed N/A N/A 16 Repair/Replacement Activities The Code Case must be applied only to ASME Code Classes 2 and 3, and non-Code Class pressure retaining components and their associated supports.
N-661-1 Alternative Requirements for Wall Thickness Restoration of Class 2 and 3 N/A N/A 16 Carbon Steel Piping for Raw Water Service (1) If the cause of the degradation has not been determined, the repair is only acceptable until the next refueling outage.
(2) When through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair is only acceptable until the next refueling outage.
N-662 Alternative Repair/Replacement Requirements for Items Classified N/A N/A 16 in Accordance with Risk-Informed Processes The Code Case must be applied only to ASME Code Classes 2 and 3, and non-Code Class pressure retaining components and their associated supports.
N-663 Alternative Requirements for Classes 1 and 2 Surface Examinations N/A N/A 16 N-665 Alternative Requirements for Beam Angle Measurements Using Refracted N/A N/A 16 Longitudinal Wave Search Units N-666 Weld Oveday of Class 1, 2, and 3 Socket Welded Connections N/A N/A 16 N-683 Method for Determining Maximum Allowable False Calls When Performing N/A N/A 16 Single-Sided Access Performance Demonstration in Accordance with Appendix VIII, Supplements 4 and 6 N-685 Lighting Requirements for Surface Examination N/A N/A 16 N-686-1 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3 N/A N/A 16 RNP-PM-008 Revision 0 Page 71 of 821
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Code Subject Examination Item
.Reg.
Guide.
'Case
.Su ec Category
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Number(s)
- 1. 147 Rev.
N-694-1 Evaluation Procedure and Acceptance Criteria for PWR Reactor Vessel Upper N/A N/A 16 Head Penetrations (a) The maximum instantaneous through-thickness stress distribution along the crack front and in the crack-length path must be used to calculate the crack driving force.
(b) The stress intensity factor expression of Raju and Newman (Ref. 11) is only applicable to cylindrical products having a ratio of wall thickness to inside radius between 0.1 and 0.25.
N-695 Qualification Requirements for Dissimilar Metal Piping Welds B-F B5.10 16 N-696 Qualification Requirements for Appendix VIII Piping Examinations Conducted B-J B9.11 16 From the Inside Surface N-700 Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded N/A N/A 16 Attachments for Examination N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate N/A N/A 16 Energy Class 2 or 3 Vessels and Tanks N-706-1 Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-N/A N/A 16 2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers N-722-1 Additional Examinations of PWR Pressure Retaining Welds in Class 1 AUGMENT E-16 Invoked per Components Fabricated with Alloy 600/82/182 Materials Federal Register (36232), dated, 6/21/2011, effective date, 7/21/2011 N-729-1 Alternative Examination Requirements for PWR Reactor Vessel Heads With AUGMENT E-1 1 Invoked per Nozzles Having Pressure Retaining Partial Penetration Welds Federal Register (36232), dated, 6/21/2011, effective date, 7/21/2011 N-731 Alternative Class 1 System Leakage Test Pressure Requirements N/A N/A 16 N-733 Mitigation of Flaws in NPS 2 (DN 50) and Smaller Nozzles and Nozzle Partial N/A N/A 16 Penetration Welds in Vessels and Piping by Use of a Mechanical Connection Modification N-735 Successive Inspection of Class 1 and 2 Piping Welds N/A N/A 16 N-739 Alternative Qualification Requirements for Personnel Performing Class CC N/A N/A 16 Concrete and Post-Tensioning System Visual Examinations N-753 Vision Tests N/A N/A 16 RNP-PM-008 Revision 0 Page 72 of 821
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Code Examination Item Reg. Guide Case*Subject Category Number(s) 1.147 Rev.
N-770-1 Alternative Examination Requirements for PWR Reactor Vessel Heads With AUGMENT E-17 Invoked per Nozzles Having Pressure Retaining Partial Penetration Welds Federal Register (36232), dated, 6/21/2011, effective date, 7/21/2011 Conditionally Acceptable Code Cases are shown in Italic and approved for use in Regulatory Guide 1.147 Latest Revision, with the Conditionally Acceptable Requirement identified in BOLD.
approved for use in Regulatory Guide 1.147 Latest Revision, with the Conditionally Acceptable Requirement identified in BOLD.
Per Regulatory Guide 1.147 Code Cases provide alternatives to existing Code requirements that the ASME developed and approved. The new Code Cases and revisions to existing Code Cases listed as approved in Tables 1 and 2 of this guide will be incorporated by reference into 10 CFR 50.55a. Code Cases approved by the NRC may be used voluntarily by licensees as an alternative to compliance with ASME Code provisions incorporated by reference into 10 CFR 50.55a. When a licensee initially implements a Code Case, 10 CFR 50.55a requires that the most recent version of that Code Case as listed in Tables 1 and 2 be implemented. If a Code Case is implemented by a licensee and a later version of the Code Case is incorporated by reference into 10 CFR 50.55a and listed in Tables 1 and 2 during the licensee's present 120-month ISI program interval, that licensee may use either the later version or the previous version. An exception to this provision would be the inclusion of a limitation or condition on the use of the Code Case that is necessary, for example, to enhance safety.
Licensees who choose to continue use of the Code Case during the subsequent 120-month ISI program interval will be required to implement the latest version incorporated by reference into 10 CFR 50.55a and listed in Tables 1 and 2. Code Cases may be annulled because the provisions have been incorporated into the Code, the application for which it was specifically developed no longer exists, or experience has shown that an examination or testing method is no longer adequate. After a Code Case is annulled and 10 CFR 50.55a and this guide are amended, licensees may not implement that Code Case for the first time. However, a licensee who implemented the Code Case prior to annulment may continue to use that Code Case through the end of the present ISI interval. An annulled Code Case cannot be used in the subsequent ISI interval unless implemented as an approved alternative under 10 CFR 50.55a(a)(3). If a Code Case is incorporated by reference into 10 CFR 50.55a and later annulled by the ASME because experience has shown that an examination or testing method is inadequate, the NRC will amend 10 CFR 50.55a and this guide to remove the approval of the annulled Code Case.
Licensees should not begin to implement such annulled Code Cases prior to the rulemaking. Notwithstanding these requirements, the Commission may impose new or revised Code requirements, including implementation schedules, that it determines are consistent with the Backfit Rule (10 CFR 50.109).
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix E Augmented ISl Examination Programs Numer Suc Ie
.Ato Soure Itm AcionResponse E-1 NRC Bulletin No. 79-13, "Cracking in Feedwater Ultrasonic inspection of steam generator feedwater nozzles, elbows, reducers, and weld System Piping" configurations and base metal each refueling outage. HBRSEP, Unit No. 2, will perform an augmented examination each refueling outage on the steam generator feedwater nozzle piping from the nozzle taper to a point one pipe diameter down on the first elbow. These examinations will continue each refueling outage until an engineering evaluation concludes these examinations are no longer required.
(Reference Serial RNPD/92-2981)
E-2 Information Notice No. 91-05, "lntergranular Stress NDE is being performed in accordance with NED-R-5225 Letter in File R9X-XXX-CA-A528.
Corrosion Cracking in Pressurized Water Reactor Fifth Ten Year Plan (RNP-PM-009) includes 1 accumulator per period.
Safety Injection Accumulator Nozzles" E-3 NRC Bulletin 88-08 and Supplements, "Thermal Evaluation of HBRSEP, Unit No. 2, unisolable piping systems connected to the RCS Stresses in Piping Connected to Reactor Coolant determined that the potential does not exist for unacceptable thermal stresses as defined in Systems" NRC Bulletin 88-08. (Reference Serials NLS-88-235 and NLS-90-100)
E-4 NRC Information Notice 82-37, "Cracking in the Examinations are performed as required by ASME Code. In addition, enhancements to the Upper Shell to the Transition Cone Girth Weld of a examinations are performed with the additional guidance of IN 90-04 which includes, Steam Generator at an Operating PWR," & NRC scanning at a higher gain, use of multiple transducers with optimal angles, careful plotting of Information Notice 90-04, "Cracking in the Upper indications and use of experienced examiners. Steam Generator girth weld examinations at Shell to the Transition Cone Girth Weld of Steam the upper transition cone, Weld 5, Sketches CPL-205, CPL-205A, and CPL-205B are Generators."
performed in accordance with ASME Section Xl and IEN 90-04 enhancements utilizing PDI techniques.
E-5 Reactor Coolant Pump Flywheels RCP pump flywheels will be visually examined at the first refueling outage after each ten-Technical Requirements Manual year inspection, at the fourth refueling outage after each ten-year inspection, and at each Section 5.5.7 fourth refueling outage thereafter. The outside surfaces will be examined by ultrasonic examination methods. Basis is Technical Requirements Manual (PLP-100) step 5.5.7 E-6 NUREG-0800, Section 3.6.2, Branch Technical Branch Technical Position MEB 3-1 required RNP to determine when a piping failure in fluid Position MEB 3-1 systems outside of containment would have an adverse effect on other components and equipment. In response, a detailed engineering analysis was completed in 1973 of the Residual Heat Removal, Chemical and Volume Control, Main Steam, Main Feedwater, Auxiliary Feedwater, and Steam Generator Blowdown Systems. At that time, modifications were made to eliminate areas of concern. Based on this analysis and the previously completed modifications, augmented ISI examinations on these systems are not required.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix E (Continued)
Augmented ISI Examination Programs Item Number Source Item Action Response E-7 NUREG-0800, Standard Review Plan, This requirement relates to welds in those portions of systems addressed in Standard Review Plan, Section 6.6 Section 6.6, paragraph 1.7. HBRSEP, Unit No. 2, has no additional required examinations in this area.
E-8 Augmented ISI Inspections on the CV Twelve welds will be examined in the CV Spray System during the Fifth Ten-Year Interval.
Spray System E-9 IE Bulletin 79-17, "Pipe Cracks in In response to IE Bulletin, 79-17 "PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT Stagnated Borated Water Systems at PWR PWR PLANTS, Revision 1, the nondestructive examination (NDE) program to be implemented for Plants".
portions of systems containing stagnant borated water is presented in the Attachment to Letter NLS-84-008, dated January 18, 1984, S. R. Zimmerman (RNP) to S. Varga (NRC), In-Service Inspection Program - Interval 2, March 7, 1981 to March 7, 1991. No evidence of intergranular stress corrosion cracking was found during any of the inspections identified in Letter, GD-79-2186, dated September 6, 1979, B. Furr (RNP) to J. O'Reilly (NRC), Response to IE Bulletin 79-17. No further action required.
E-1 0 MRP-1 39 R1 (Alloy 600 Examination Inspection requirement of MRP-1 39 R1, as modified by interim guidance letter 2009-31 for Alloy 600 Program) locations. Examination frequency is in accordance with guidelines established in MRP-139 and code Case N-722. RO-25 Hot Leg L/Cold Leg UT, RO-26 Hot Leg/Cold Leg VT, RO-27 Hot Leg/Cold Leg UT. In addition to the requirements of MRP-139 R1, the new requirements identified in 10CFR50.55a, dated 9/10/2008, ASME Code Case N-722 shall be used for future examinations inclusive of the limitations and modifications identified in 10CFR50.55a. Examinations originally performed to N-722 in RO-26 were identified as E-10. The examinations associated with N-722 have been removed from Augment E-1 0 and are now in Augment E-1 6 with history for tracking. E-1 0 is inactive as of 7/21/2011 whereupon 10CFR50.55a invoked ASME Code Case N-770-1, which is now addressed by AUGMENT E-17.
E-1 1 Reactor Vessel Head Penetration Visual Inspection requirement of EA-03-009 for RX Head Penetrations. Examination frequency is in Examination Program.
accordance with guidelines established in EA-03-009. The examination requirements per EA-03-009 (which has been superseded by 10CFR50.55a dated 9/10/2008) are complete and based on the new requirements identified in 10CFR50.55a, dated 9/10/2008, ASME Code Case N-729-1 shall be used for future examinations inclusive of the limitations and modifications identified in 1 OCFR50.55a.
E-12 Class 1 Small Bore (License Renewal)
Sampling of small bore piping to perform ultrasonic examination (UT exempt from ASME Code) or destructive testing.
E-13 MRP-146S - Materials Reliability Program Sampling of piping to perform ultrasonic examination on lines that are normally stagnant and non-Management of Thermal Fatigue in isolable.
Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines E-14 MRP-192 Materials Reliability Program Ultrasonic examination of the flow mixing tee and downstream piping Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants RNP-PM-008 Revision 0 Page 75 of 82
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix E (Continued)
Augmented ISI Examination Programs ItemS source ItemIn Actio Respon se N urn b er j
E-1 5 MRP-227 & MRP-228 Reactor Vessel Identification of examinations associated with Augment, E-1 5, future examinations associated with the Aging Management Program (future)
Reactor Vessel Aging Management Program.
E-16 ASME Code Case N-722-1 ASME Code Case N-722-1 shall be used for future examinations inclusive of the limitations and modifications identified in 1 OCFR50.55a.
E-17 ASME Code Case N-770-1 Identification of examinations associated with Augment E-17, via ASME Code Case N-770-1. ASME Section Xl Code Case N-770-1 was endorsed via 10CFR50.55a effective 7/21/2011. These examinations were originally examined under MRP-139 R1 (E-10). Examination elements are contained in ASME Code Case N-770-1 and the additional requirements identified in 10CFR50.55a.
Hot leg nozzles are identified as Item Number "A-2" and cold leg nozzles are identified as Item Number "B" per ASME Code Case N-770-1.
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix F ISI Zone/isometric References CLASS 1 Zone Sheet Zone
- Sheet, Zone Sheet CPL-101 001 CPL-115 020 CPL-127 039 CPL-101A 002 CPL-116 021 CPL-128 040 CPL-101B 003 CPL-116A 022 CPL-129 041 CPL-101C 004 CPL-116B 023 CPL-130 042 CPL-103 005 CPL-117 024 CPL-131 043 CPL-105 006 CPL-117A 025 CPL-132 044 CPL-105A 007 CPL-118 026 CPL-133 045 CPL-105B 008 CPL-118A 027 CPL-134 046 CPL-106 009 CPL-118B 028 CPL-135 047 CPL-107 010 CPL-119 029 CPL-136 048 CPL-107A 011 CPL-120 030 CPL-138 050 CPL-107B 012 CPL-121 031 CPL-140 052 CPL-108 013 CPL-122 032 CPL-141 053 CPL-109 014 CPL-122A 033 CPL-142 054 CPL-110 015 CPL-123 034 CPL-143 055 CPL-111 016 CPL-123A 035 CPL-144 056 CPL-112 017 CPL-124 036 CPL-144A 057 CPL-113 018 CPL-125 037 CPL-114 019 CPL-126 038 4
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix F ISI Zone/Isometric References (Cont'd)
- i*"
CLASS 2 Zone Sheet Zone Sheet Zone Sheet CPL-202 058 CPL-222 085 CPL-245 111 CPL-204 060 CPL-222A 086 CPL-246 112 CPL-205 061 CPL-222B 087 CPL-247 113 CPL-205A 062 CPL-223 088 CPL-248 165 CPL-205B 063 CPL-224 089 CPL-249 166 CPL-206 064 CPL-229 091 CPL-250 113 CPL-212 071 CPL-230 092 CPL-251 206 CPL-213 072 CPL-231 093 CPL-252 207 CPL-214 073 CPL-232 094 CPL-253 208 CPL-215 074 CPL-232A 095 CPL-254 209 CPL-216 075 CPL-233 096 CPL-255 210 CPL-217 076 CPL-234 097 CPL-256 211 CPL-218 077 CPL-234A 098 CPL-257 212 CPL-219 078 CPL-234B 099 CPL-258 213 CPL-219A 079 CPL-239 105 CPL-259 214 CPL-220 080 CPL-240 106 CPL-260 228 CPL-220A 081 CPL-241 107 CPL-261 229 CPL-221 082 CPL-242 108 CPL-262 230 CPL-221A 083 CPL-243 109 CPL-263 231 CPL-221B 084 CPL-244 110 CPL-264 232 CPL-265 233
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix F ISI Zone/Isometric References (Cont'd)
'CLASS 3____
Zone Sheet Zone Sheet Zone
- Sheet, CPL-301 114 CPL-323 134 CPL-331B 147 CPL-302 115 CPL-324J 135 CPL-332 148 CPL-303 116 CPL-324K 175 CPL-333 149 CPL-304 117 CPL-324L 176 CPL-334 150 CPL-305 118 CPL-324M 177 CPL-334A 151 CPL-306 119 CPL-324P 178 CPL-334B 152 CPL-309 122 CPL-324R 179 CPL-335 153 CPL-313 126 CPL-324T 180 CPL-336 154 CPL-313A 127 CPL-324W 181 CPL-341 159 CPL-314 128 CPL-325 139 CPL-342 160 CPL-314A 129 CPL-326 140 CPL-343 161 CPL-315 130 CPL-327 141 CPL-344 162 CPL-316 131 CPL-328 142 CPL-345 163 CPL-322 133 CPL-329 143 CPL-330 144 CPL-331 145 CPL-331A 146 I RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix G Class 1 Acceptance Criteria Examination Acceptance Category Parts Examined Standard B-A Pressure Retaining Welds in Reactor Vessel IWB-351 0 B-B Pressure Retaining Welds in Vessels Other Than IWB-3510 Reactor Vessels B-D Full Penetration Welded Nozzles in Vessels IWB-3512 (Inspection Program B)
B-F Pressure Retaining Dissimilar Metal Welds in Vessel IWB-3514 Nozzles B-G-1 Pressure Retaining Bolting, Greater Than 2 inches in IWB-3515 &
Diameter IWB-3517 B-G-2 Pressure Retaining Bolting, 2 inches and Less in IWB-3517 Diameter B-J Pressure Retaining Welds in Piping IWB-3514 B-K Welded Attachments for Vessels, Piping, Pumps, and IWB-3516 Valves B-L-1 Pressure Retaining Welds in Pump Casings IWB-3518 B-L-2 Pump Casings IWB-3519 B-M-1 Pressure Retaining Welds in Valve Bodies IWB-3518 B-M-2 Valve Bodies IWB-3519 B-N-1 Interior of Reactor Vessel IWB-3520 B-N-2 Welded Core Support Structures and Interior IWB-3520 Attachments to Reactor Vessels B-N-3 Removable Core Support Structures IWB-3520 B-O Pressure Retaining Welds in Control Rod Housings IWB-3523 B-P All Pressure Retaining Components IWB-3522 B-Q Steam Generator Tubing IWB-3521 I RNP-PM-008 Revision 0 1
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Appendix H Class 2 Acceptance Criteria Exam inatio Pr I Acceptance n Category Parts Exaine Standard C-A Pressure Retaining Welds in Pressure Vessels IWC-3510 C-B Pressure Retaining Nozzle Welds in Vessels IWC-351 1 C-C Welded Attachments for Vessels, Piping, Pumps and IWC-3512 Valves C-D Pressure Retaining Bolting Greater than 2 inches in IWC-3513 Diameter C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel IWC-3514 or High Alloy Piping C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel IWC-3514 Piping C-G Pressure Retaining Welds in Pumps and Valves IWC-3515 C-H All Pressure Retaining Components IWC-3516 Appendix I Class 3 Acceptance Criteria Examination Acceptance Category Parts Examined Standard D-A Welded Attachments for Vessels, Piping, Pumps, and IWD-3000 Valves D-B All Pressure Retaining Components IWD-3000 Appendix J Component Support Acceptance Standards Exami -nation PrsEaieIdAcceptance" CategoryExamined Standard F-A Class 1, 2, 3 and MC Component Supports IWF-341 0 I RNP-PM-008 I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Inservice Inspection Program Revision Summary H. B. Robinson Nuclear Plant Fifth Ten Year Interval ISI Program DRR#: XXXXXX Page Description of Change Reason for Change ALL
- Initial Issue Fifth Ten Year Interval update I RNP-PM-008 I
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United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/12-0023 28 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 FIFTH TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM RELIEF REQUESTS
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-01 Relief Request Number RR-01 Pressurizer Surge Line Nozzle Inner Radius Component(s) for Which Relief is Requested The component applicable to this relief request is the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, pressurizer surge line nozzle inside radius section.
Code Examination Requirements Per the requirements of 10 CFR50.55a(b)(2)(xxi)(A), "The provisions of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items B3.40 and B3.60 (Inspection Program A) and Items B3.120 and B3.140 (Inspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of this section. A visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/I = 0.5),
may be performed instead of an ultrasonic examination."
Requested Relief HBRSEP, Unit No. 2, requests relief from 10CFR50.55a(b)(2)(xxi)(A), regarding visual examination of the pressurizer surge line nozzle inside radius section.
Basis for Requested Relief HBRSEP, Unit No. 2, requests relief in accordance with 10 CFR 50.55a(g)(6)(i) on the basis that performance of the 10CFR50.55a(b)(2)(xxi)(A),-required visual examination of the pressurizer surge line nozzle inside radius section is impractical to perform.
The pressurizer surge line nozzle inside radius section is not accessible for volumetric examination from the exterior of the pressurizer due to interferences associated with the pressurizer heater penetrations (reference sketch, Attachment 1). Examination from the interior of the pressurizer is precluded due to access restrictions caused by the pressurizer retaining basket (Attachment 2). Major design modifications to the pressurizer bottom head, involving significant worker radiation exposures, would be required to establish a configuration that would allow the 10CFR50.55a(b)(2)(xxi)(A) visual examination of the pressurizer surge line nozzle inside radius section. Based on the configurations of the exterior and interior areas surrounding the pressurizer surge line nozzle inside radius section, and the significant modifications that would be required to allow performance of the 10CFR50.55a(b)(2)(xxi)(A) required examinations, HBRSEP, Unit No. 2, has concluded that these 10CFR50.55a(b)(2)(xxi)(A) required examinations are impractical to perform.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-01 Proposed Alternative Examinations No alternative examinations are proposed.
The pressurizer surge line nozzle is examined by VT-2 visual examination during pressure testing each refueling outage in accordance with the ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-P. This Code-required pressure testing provides reasonable assurance of structural integrity.
Request for Relief No. RR-01
- Previously approved during the Third Interval under TAC No. M81310, dated October 19,1992.
Previously approved during the Fourth Interval under TAC No. MB2773, dated September 26, 2002.
Implementation Schedule This relief is requested for and will be implemented in the HBRSEP, Unit No. 2, Fifth Ten-Year Inservice Inspection (ISI) Interval, which begins on July 21, 2012 and ends on February 18, 2022.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-01
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-01 101 22 If kvi l i
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-02 Relief Request Number RR-02 Regenerative Heat Exchanger Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, regenerative heat exchanger circumferential head welds, tube sheet-to-shell weld, nozzle-to-vessel welds, nozzle inside radius section, branch connections, socket welds, and associated supports.
Code Examination Requirements ASME Section Xl, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-B, "Pressure Retaining Welds in Vessels Other Than Reactor Vessels," Item Numbers B2.51, 'Circumferential," and B2.80, "Tubesheet-to-Vessel Welds," require volumetric examination of the regenerative heat exchanger vessel head weld and the tube sheet-to-head weld.
ASME Section Xl, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-D, "Full Penetration Welded Nozzles in Vessels -
Inspection Program B," Item Numbers B3.150, "Nozzle-to-Vessel Welds," and B3.160, "Nozzle Inside Radius Section," require volumetric examination of the regenerative heat exchanger nozzle shell welds and inside radius section.
ASME Section Xl, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-J, "Pressure Retaining Welds in Piping," Item Numbers B9.32, "Branch Pipe Connection Welds Less Than NPS 4," and B9.21, "Circumferential Welds" (less than NPS 4), require surface examination elf the inlet, outlet, and intermediate connecting piping welds between the shell courses.
ASME Section XI, 2007 Edition with 2008 Addenda, Table IWF-2500-1)
Examination Category F-A, 'Supports," Item Number F1.40, "Supports Other Than Piping Supports (Class 1, 2, 3, and MC)," requires VT-3 visual examination of all supports.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-02 Pursuant to 10 CFR 50.55a(a)(3)(ii), the HBRSEP requests relief from the Code-required examination coverage for visual, surface and volumetric examinations of the following components located inside the regenerative heat exchanger room:
Components Required Examination Regenerative heat exchanger vessel and tube sheet Volumetric
-to-head weld Regenerative heat exchanger nozzle and inside Volumetric radius section Regenerative heat exchanger head welds, shell Surface/Volumetric welds, inlet, outlet, and intermediate connecting piping welds between the shell courses:
Regenerative heat exchanger supports other than VT-3 Visual piping supports -
Requested Relief HBRSEP, Unit No. 2, requests relief from ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, Table IWB-2500-1; Examination Category B-B, Item Nos. B2.51 and B2.80,
- Examination Category B-D, Item Nos. B3.150 and B3.160, Examination Category B-J, Item Nos. B9.32 and B9.21,
- Examination Category F-A, Item No. F1.40 Relief is requested for the required surface, volumetric, and VT-3 visual examination of the regenerative heat exchanger vessel head weld, tube sheet-to-shell weld, vessel welds, inlet, outlet, intermediate connecting piping welds, inside radius section, and component supports.
Basis for Requested Relief HBRSEP, Unit No. 2, requests relief in accordance with 10 CFR 50.55a(a)(3)(ii) on the basis that performance of the Code-required examinations associated with the regenerative heat exchanger would result in hardship and unusual difficulty without a compensating increase in the level of quality and safety.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-02 Radiation surveys in the regenerative heat exchanger room identified general area dose rates of 1 to 2 Rem/hour, and heat exchanger contact dose rates of 3 to 4 Rem/hour. As a result, significant worker exposures would result from the preparation for and performance of the Code-required examinations. In order to maintain occupational exposures As Low As Reasonably Achievable (ALARA),
relief from these requirements is being requested. Additionally, the VT-2 visual examination performed each refueling outage during pressure testing provides reasonable assurance of structural integrity. The VT-2 can be accomplished in less time required to perform versus the visual, surface and associated volumetric examinations required by ASME Code.
The drawing of the regenerative heat exchanger provided in Attachment II specifically identifies the applicable welds in conjunction with Attachment I. The welds and supports identified in Attachment s are located inside the regenerative heat exchanger room.
Surface and volumetric examinations may require scaffolding in addition to insulation removal and weld preparation. The asbestos insulation on the regenerative heat exchanger is original insulation and would have to be replaced in its entirety based on the brittleness of the insulation. Surface examination requires a hands-on application in the performance of these examinations.
The time required for VT-2 examination is significantly less than the time required for a surface or volumetric examination. ASME Section Xl, 2007 Edition - 2008 Addenda, IWA-5242(a) states, "Essentially vertical surfaces of insulation need only be examined at the lowest elevation where leakage may be detectable.
Essentially horizontal surfaces of insulation shall be examined at each insulation joint." IWA-5242(b) states, "When examining insulated components, the examination of the surrounding area (including floor areas or equipment surfaces located underneath the component) for evidence of leakage, or other areas to which such leakage may be channeled, shall be required." A VT-2 examination can be performed from a distance in a short period of time, thereby lowering radiation exposure to the examiner.
The total estimated dose associated with performing the ASME Code required examinations of the regenerative heat exchanger is approximately 70 Rem. This is based on approximately 30 Rem estimated for preparation and examination, and 40 Rem for insulation and scaffolding.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-02 There are physical geometric restrictions associated with these components which also cause difficulty in the performance of Code-required examinations, specifically ultrasonics. The nozzle-to-vessel welds and nozzle inside radius sections for the heat exchanger were not designed for ultrasonic examination from the outside diameter. The small diameter of the heat exchanger shell prevents a meaningful ultrasonic examination of these components. The Code-required volumetric examination on the heat exchanger head circumferential welds is limited due to the weld crown, radius of the closure caps, and the nozzles. The Code-required volumetric examination of the tubesheet welds is limited by the weld crown and is obstructed by a support clamp. The clamp must be removed prior to the examination of these welds.
HBRSEP, Unit No. 2, proposes to perform a VT-3 general visual examination of the regenerative heat exchanger, without insulation removal, once each inspection period, as an alternative to the required surface/volumetric and visual examinations.
Proposed Alternative Examinations HBRSEP will perform a VT-3 general visual examination of the Regenerative Heat Exchanger, without insulation removal, once each inspection period, as an alternative examination to the required surface/volumetric and visual examinations.
The regenerative heat exchanger pressure-retaining boundary is examined by VT-2 visual examination during pressure testing that is performed during each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P. This Code-required pressure testing provides reasonable assurance of structural integrity.
Request for Relief No. RR-02
" Previously approved during the Third Interval under TAC No. M81310, dated October 19, 1992.
" Previously approved during the Fourth Interval under TAC No. MB2773, dated September 26, 2002.
Implementation Schedule This relief is requested for and will be implemented in the HBRSEP, Unit No. 2, Fifth Ten-Year Inservice Inspection (ISI) Interval, which begins on July 21, 2012 and ends on February 18, 2022.
H, B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-02 Attachment I Component Component Description ASME ASME Item Required ID Category Number Examination 106/01 Head to Divider Assembly Weld B-B B2.51 Volumetric 106/02 Assembly Divider to Tubesheet Weld B-B B2.80 Volumetric 106/05 Head to Divider Assembly Weld B-B B2.51 Volumetric 106/06 Assembly Divider to Tubesheet Weld B-B B2.80 Volumetric 106/09 Head to Divider Assembly Weld B-B B2.51 Volumetric 106/10 Assembly Divider to Tubesheet Weld B-B B2.80 Volumetric 106/13 Regenerative Heat Exchanger to Nozzle B-D B3.150 Volumetric 106/131R Regenerative Heat Exchanger Nozzle Inner Radius B-D B3.160 Volumetric 106/14 Regenerative Heat Exchanger to Nozzle B-D B3.150 Volumetric 106/141R Regenerative Heat Exchanger Nozzle Inner Radius B-D B3.160 Volumetric 106/15 Regenerative Heat Exchanger to Nozzle B-D B3.150 Volumetric 106/15IR Regenerative Heat Exchanger Nozzle Inner Radius B-D B3.160 Volumetric 106/16 Regenerative Heat Exchanger to Nozzle B-D B3.150 Volumetric 106/161R Regenerative Heat Exchanger Nozzle Inner Radius B-D B3.160 Volumetric 106/17 Regenerative Heat Exchanger to Nozzle B-D B3.150 Volumetric 106/171R Regenerative Heat Exchanger Nozzle Inner Radius B-D B3.160 Volumetric 106/18 Regenerative Heat Exchanger to Nozzle B-D B3.150 Volumetric 106/181R Regenerative Heat Exchanger Nozzle Inner Radius B-D B3.160 Volumetric 123/53 Regenerative Heat Exchanger Nozzle to Pipe B-J B9.21 Surface 123/54 Regenerative Heat Exchanger Nozzle to Pipe B-J B9.21 Surface 123/57 Regenerative Heat Exchanger Nozzle to Pipe B-i B9.21 Surface 123/58 Regenerative Heat Exchanger Nozzle to Pipe B-J B9.21 Surface 123/61 Regenerative Heat Exchanger Nozzle to Pipe B-J B9.21 Surface 123/62 Pipe to Elbow B-J B9.21 Surface 123A/48 Pipe to Elbow B-J B9.21 Surface 123A/50 Regenerative Heat Exchanger Nozzle to Pipe B-i B9.21 Surface 206/A Regenerative Heat Exchanger Support F-A F1.40 VT-3 206/B Regenerative Heat Exchanger Support F-A F1.40 VT-3 206/C Regenerative Heat Exchanger Support F-A F1.40 VT-3 206/D Regenerative Heat Exchanger Support F-A F1.40 VT-3 206/E Regenerative Heat Exchanger Support F-A F1.40 VT-3 206/F Regenerative Heat Exchanger Support F-A F1.40 VT-3
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-02 Attachment II I
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Requests RR-03 Relief Request Number RR-03 Reactor Vessel Bottom Head Peel Segment-To-Disk Circumferential Weld Component(s) for Which Relief is Requested The component applicable to this relief request is the HBRSEP, Unit No. 2, reactor pressure vessel bottom head peel segment-to-disk circumferential weld.
Code Examination Requirements The ASME B&PV Code, Section Xl, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-A, "Pressure Retaining Welds in Reactor Vessel," Item No. B13.21, "Circumferential Head Welds," requires volumetric examination of the accessible length of the reactor pressure vessel bottom head peel segment-to-disk circumferential weld in accordance with Figure No. IWB-2500-3.
Requested Relief HBRSEP, Unit No. 2, requests relief from the ASME B&PV Code, Section Xl, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-A, Item No. B1.21, regarding volumetric examination of the reactor pressure vessel bottom head peel segment-to-disk circumferential weld 7 on the attached ISI Sketch.
Basis for Requested Relief HBRSEP, Unit No. 2, requests relief in accordance with 10 CFR 50.55a(g)(6)(i) on the basis that performance of the Code-required volumetric examination of the reactor pressure vessel bottom head peel segment-to-disk circumferential weld is impractical to perform.
Accessibility for examination of this weld was not provided in the original plant design, which occurred prior to issuance of the Section XI ISI examination requirements. The bottom head peel segment-to-disk weld is completely enclosed within the pattern of Bottom Mounted Instrumentation (BMI) penetrations under the reactor vessel, such that no portion of the weld is accessible for either surface or volumetric examination. There is no existing technology that would provide a meaningful volumetric examination for this configuration. Therefore, this weld is considered inaccessible for volumetric examination due to physical space constraints.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Requests RR-03 Proposed Alternative Examinations No alternative examinations are proposed.
The reactor pressure vessel closure bottom head peel segment-to-disk circumferential weld is examined by VT-2 visual examination during pressure testing each refueling outage in accordance with the ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-P. This Code-required pressure testing provides reasonable assurance of structural integrity.
Implementation Schedule This relief is requested for and will be implemented in the HBRSEP, Unit No. 2, Fifth Ten-Year Inservice Inspection (ISI) Interval, which begins on July 21, 2012 and ends on February 18, 2022
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Requests RR-03 2
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H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Relief Request Number RR-04 Pressure Test Full Boundary Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, Class 1 pressure test boundaries subject to system pressurization at or near the end of the inspection interval in accordance with ASME Section XI, 2007 Edition, 2008 Addenda, ASME Category B-P, Item Number B15.20 and IWB-5222, "Boundaries," subsection (b).
Code Examination Requirements The ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, Category B-P, Item Number B15.20 and IWB-5222(b), which states "The Class 1 pressure retaining boundary which is not pressurized when the system valves are in the position required for normal reactor startup shall be pressurized and examined at or near the end of the inspection interval. This boundary may be tested in its entirety or in portions and testing may be performed during the testing of boundary of IWB-5222(a).
Requested Relief HBRSEP, Unit No. 2, requests relief from the ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, Category B-P, Item B135.20 and IWB-5222(b),
regarding extension of the pressure retaining boundary during system leakage tests conducted at or near the end of the inspection interval to Class 1 pressure retaining components within the system boundary.
Basis for Relief HBRSEP, Unit No. 2, requests relief in accordance with 10CFR50.55a(a)(3)(ii) on the basis that hardship and unusual difficulty exists, without a compensating increase in the level of quality and safety, regarding pressurization of all the Class 1 pressure retaining components within the system boundary.
Table 1 identifies the Class 1 pressure retaining components that are associated with the requested relief.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 The HBRSEP, Unit No. 2, design of Class 1 vents and drains typically consists of a single isolation valve with a capped end that constitutes the Class 1 system boundary. Many of these valves are not readily accessible due to their physical locations and radiation/contamination levels in the area. Pressurization of these locations for testing would be performed in Mode 3 and would involve opening these single isolation valves to pressurize to the extended Class 1 system pressure test boundary. After performance of the required VT-2 visual examination, these single isolation valves would be closed, isolating a high temperature, pressurized volume of water between the isolation valve and the capped end. This results in an undesirable configuration that would be conducive to pressure lock or the initiation of system leakage from valve packing or capped ends.
In addition, the piping associated with the vents and drains will contain pressurized reactor coolant fluid between the valve and cap. During the subsequent outage, the valve would need to be opened prior to cap removal in order to release the pressurized slug of reactor coolant system fluid contained between the valve and cap, after depressurization of the reactor coolant system to eliminate a safety hazard.
The HBRSEP, Unit No. 2, design also requires substantial effort to extend the Class 1 system boundary where check valves or non-redundant components serve as the first system isolation from the reactor coolant system. Such configurations may require check valve disassembly or other temporary configurations to achieve test pressures at upstream piping and valves. Since the Class 1 system pressure testing is performed in Mode 3, these temporary configurations would conflict with Technical Specification requirements and valve alignments. Establishing and restoring such temporary configurations could also result in an unwarranted increase in worker radiation exposures.
(The following is specific information pertaining to the various pipe segments for which relief has been requested). Small Size Class 1 Vent, Drain, Test and Fill Lines Relief is requested from fully pressurizing piping between the first and second isolation device on small size vent, drain, test, and fill lines. There are twenty-six vent, drain, test and fill lines in the Reactor Coolant System (RCS) ranging in size from 0.75 inch to two inches. The configurations are either two small isolation valves in series, a valve and blind flange, or a valve and cap. In some configurations, the piping between the two vent and drains will tee to a third valve that is also the second isolation boundary. The piping segments provide the design-required double isolation barrier for the reactor coolant pressure boundary. The Code-required leakage test would be performed in MODE 3 at the normal operating pressure of 2235 psig and at a nominal temperature of about 547°F.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Leakage testing of these piping segments at nominal operating pressure in MODE 3 would require the opening of the inboard isolation valve at the normal operating RCS temperature and pressure conditions. In so doing, the design requirement for two primary coolant pressure boundary isolation devices would be violated. Additionally, opening of these valves introduces the potential risk for spills and personnel contamination. For configurations where blind flanges or caps are installed as the isolation device, opening of the inboard valve introduces the possibility of a personnel safety hazard if a flange or cap fails in the presence of inspection personnel.
These piping segments are VT-2 inspected through the entire length as part of the Class 1 system inspection at the conclusion of each refueling outage. The leakage test will not specifically pressurize past the first isolation valve for this inspection. No external or visible leakage will be allowed for a test to be successful. Since this type of test will assure that the combined first and second isolation devices are effective in maintaining the reactor coolant pressure boundary at normal operating temperature and pressure, the increase in safety achieved from the Code-required leakage test is not commensurate with the hardship of performing such testing.
Larger Size Class 1 Piping Segments 14 Inch Residual Heat Removal Motor Operated Valves This piping segment consists of 42 feet of 10 inch piping between Residual Heat Removal (RHR) inlet valves RHR-750 and RHR-751. These valves are interlocked at a required set point of 1474 psig to avoid over-pressurization of the RHR system. The interlock prevents manual opening of the valves from the Control Room with RCS pressure above the set point. There are no test connection points in this segment of the line. This segment was last tested during the Second Ten-Year Inset-vice Inspection interval, with the vessel defueled, as part of the RCS hydrostatic test.
The piping segment is VT-2 inspected through the entire length as part of the Class 1 system inspection at the conclusion of each refueling outage. The proposed system pressure test will not specifically pressurize past the first isolation valve for this inspection. It is possible that the piping becomes pressurized due to minor leakage past the first isolation valve. No external or visible leakage will be allowed for the test to be successful. This test will provide assurance that the combined first and second isolation valves are effective in maintaining the reactor coolant pressure boundary at normal operating temperature and pressure.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Based on the above, extension of the pressure retaining boundary during system leakage tests to Class 1 pressure retaining components within the system boundary represents a hardship and unusual difficulty that does not provide a compensating increase in the level of quality and safety.
Proposed Alternative Examinations The Class 1 system boundary during leakage tests will be maintained in a normal, operational alignment with items identified within Table 1 constituting exceptions to the Code-required boundary of B-P, B15.20. The VT-2 visual examination will extend to the Class 1 boundary during the performance of each system leakage test required by table B-P.
Items within Table 1 will be visually examined for evidence of leakage during system leakage testing without being pressurized.
Request for Relief No. RR-04 Previously approved during the Fourth Interval under TAC No. MB2773, dated September 26, 2002.
Implementation Schedule This relief is requested for and will be implemented in the HBRSEP, Unit No. 2, Fifth Ten-Year Inservice Inspection (ISI) Interval, which begins on July 21, 2012 and ends on February 18, 2022.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Table I Relief Request Number RR-04 Affected Class I Pressure Retaining Components Affected Line or Code Pipe Pipe Sch.
Approx.
Examination Drawing Boundary Exception(s)
Component Class Dia.
Length Category No.
Drain line below PZR safety 5379-Valve RC-545 remains closed to avoid valve RC-551A (pipe piece 0.75 in.
A376 TP316
< 1 ft.
B-P
- 1971, pressurizing downstream Class 1 pipe between RC-545 and RC-SMLS Sch. 160 Sheet 2 piece and valve RC-545A 545A)
Drain line below PZR safety 5379-Valve RC-546 remains closed to avoid valve RC-551B (pipe piece 0.75 in.
A376 TP316 B-P
- 1971, pressurizing downstream Class 1 pipe between RC-546 and RC-SMLS Sch. 160 Sheet 2 piece and valve RC-546A 546A)
Drain line below PRZ safety valve RC-551C (pipe piece A376 TP316 5379-Valve RC-547 remains closed to avoid
<1 0.75 in.
1 ft.
B-P
- 1971, pressurizing downstream Class 1 pipe between RC-547and RC-SMLS Sch. 160 Sheet 2 piece and valve RC-547A 547A)
I Vent valve and blind flange A376 TP316 5379-Valve RC-527C remains closed to 1
0.75 in.
MS1 ft.
B-P
- 1971, avoid pressurizing downstream Class on PZR spray line SMLS Sch. 160 Sheet 2 1 pipe piece and blind flange RCS loop intermediate loop A376 TP316 5379-Valve RC-505A remains closed to "A" drain valve and liquid 1
2 in.
1 ft.
B-P
- 1971, avoid pressurizing downstream Class waste disposal piping SMLS Sch. 160 Sheet 1 1 piping and valve RC-505B A376 TP316 RCS loop intermediate loop 2 in.
A376 Tc3160 7 in.
Valve RC-508A remains closed to "B" drain valve and liquid 1
B-P
- 1971, avoid pressurizing downstream Class waste disposal pipingin.
A376 TP316 Sheet 1 1 piping and valves RC-508B and RC-isos ipng075*in.
542 SMLS Sch. 160 A376 TP316 RCS loop intermediate loop 2 in.
SMLS Sch. 160 8 in.
5379-Valve RC-515A remains closed to 8 in.avoid pressurizing downstream Class "C" drain valve and liquid 1
B-P
- 1971, 1 piping ia n
g downstr e am C
wsedsoapiigA376 TP316 Sheet 1 1 piping and valves RC-515B and RC-waste disposal piping 0.75 in.
SMLS Sch. 160 1 ft.
1 1 601
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Table I (Continued)
Relief Request Number RR-04 Affected Class I Pressure Retaining Components Affected Line or Code Pipe Pipe Sch.
Approx.
Examinatio Drawing Boundary Exception(s)
Component Class Dia.
Length n Category No.
0.75 in.
1 ft.
Valve RC-567 remains closed to avoid RPV head vent valves and SMLS Sch. 160 5379-pressurizing downstream Class 1 1B-P
- 1971, rsuiigdwsra ls piping A376 TP316 Sheet 1 piping and valves RC-572, RC-571, 1 in.
A 1 ft.
RC-569, and RC-570 SMLS Sch. 160 iA376 TP316 Valve CVC-300A remains closed to RC A elinjection dri 1
0.5i.
A7'P1 5 t 3965 avoid pesrzn ontempp valve and blind flange 1
in.
Sheet 1 pressurizing downstream pipe piece and flange RCP "A" seal leakoff vent A376 TP316 5379-685, Valve CVC-30C remains closed to 1
0.75 in.
1
< 1 ft.
B-P S
avoid pressurizing downstream pipe valve and blind flange SMLS Sch. 160 Sheet and a RCP "A" seal weter n
A376 TP316 Valve CVC-307C remains closed to byp6a s
1 0.75 in.
- 1 ft.
B-P 5379-685, avoid pressurizing downstream pipe rn v
eale wan r capa
.SMLS Sch. 160 Sheet 1 piece and cap RCP "B" seal injection drain A376 TP316 5379-685, Valve CVC-30F remains closed to 1
0.75 in.
- 1 ft.
B-P S
avoid pressurizing downstream pipe valve and blind flange SMLS Sch. 160 Sheet I peeadfag piece and flange RCP "B" seal leakoff vent A376 TP316 5379-685, Valve CVC-307 remains closed to 1
0.75 in.
_< 1 ft.
B-P S
avoid pressurizing downstream pipe valve and blind flange SMLS Sch. 160 Sheet piece and a A376 P3165379685,Valve CVC-307E remains closed to RCP "B" seal water byas07 n
MSSch. 160She1 picancp drain valve and cap
<n.1SML.
B-Sheeti1 pressurizing downstream pipe
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Table I (Continued)
Relief Request Number RR-04 Affected Class I Pressure Retaining Components Affected Line or Code Pipe Pipe Sch.
Approx.
Examinatio Drawing Boundary Exception(s)
Component Class Dia.
Length n Category No.
RCP "B" seal water bypass 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-685, Valve CVC-307F remains closed to avoid drain valve and cap SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and cap RCP "C" seal injection drain 1
0.75 in.
A376 TP316
_ 1 ft.
B-P 5379-685, Valve CVC-300G remains closed to avoid valve and blind flange SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and flange RCP "C" seal leakoff vent 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-685, Valve CVC-300J remains closed to avoid valve and blind flange SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and I
flange RCP "C" seal water bypass 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-685, Valve CVC-307C remains closed to avoid drain valve and cap SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and cap Auxiliary spray valve and 1
2 in.
A376 TP316 500 ft.
B-P 5379-685, Valve CVC-311 remains closed to avoid downstream piping SMLS Sch. 160 Sheet 1 pressurizing downstream piping to check valve CVC-313 CVCS letdown drain valve 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-685, Valve CVC-460H remains closed to avoid and downstream cap SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and cap CVCS letdown vent valve and 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-685, Valve CVC-460G remains closed to avoid downstream cap SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and I_
cap CVCS letdown drain valve 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-685, Valve CVC-475 remains closed to avoid and downstream cap SMLS Sch. 160 Sheet 1 pressurizing downstream pipe piece and cap Safety injection loop "1" cold 1
0.75 in.
A376 TP316
_ 1 ft.
B-P 5379-Valve SI-875N remains closed to avoid leg injection vent valve and SMLS Sch. 160
- 1082, pressurizing downstream pipe piece and cap Sheet 4 cap
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Table I (Continued)
Relief Request Number RR-04 Affected Class I Pressure Retaining Components Affected Line or Code Pipe Pipe Sch.
Approx.
Examinatio Drawing Boundary Exception(s)
Component Class Dia.
Length n Category No.
Safety injection loop "2" cold 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-Valve SI-875P remains closed to avoid leg injection vent valve and SMLS Sch. 160
- 1082, pressurizing downstream pipe piece and cap I
Sheet 4 cap Safety injection loop "3" cold 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-Valve SI-875T remains closed to avoid leg injection vent valve and SMLS Sch. 160
- 1082, pressurizing downstream pipe piece and cap Sheet 4 cap Safety injection loop "1" cold 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-Check valve to remain closed to avoid leg injection check valve SMLS Sch. 160
- 1082, disassembly or other temporary SI-875A and upstream piping Sheet 4 configurations required to achieve test 8 in.
A376 TP316 3 ft.
pressures at upstream piping and valves SMLS Sch. 120 SI-873F, SI-850B, SI-876A, SI-875H, 10 in.
A376 TP316 62 ft.
SI-875D, and SI-875M SMLS Sch. 140 Safety injection loop "2" cold 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-Check valve to remain closed to avoid leg injection check valve SMLS Sch. 160
- 1082, disassembly or other temporary SI-875B and upstream piping Sheet 4 configurations required to achieve test 8 in.
A376 TP316 5 ft.
pressures at upstream piping and valves SMLS Sch. 120 SI-875S, SI-873E, SI-876E, SI-876B, 10 in.
A376 TP316 52 ft.
SI-875J, SI-850D, and SI-875E SMLS Sch. 140 Safety injection loop "3" cold 1
0.75 in.
A376 TP316
< 1 ft.
B-P 5379-Check valve to remain closed to avoid leg injection check valve SMLS Sch. 160
- 1082, disassembly or other temporary SI-875C and upstream piping Sheet 4 configurations required to achieve test 8 in.
A376 TP316 8 ft.
pressures at upstream piping and valves SMLS Sch. 120 SI-875R, SI-873D, SI-875L, SI-850F, 10 in.
A376 TP316 63 ft.
SI-876C, and SI-875F SMLS Sch. 140
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-04 Table I (Continued)
Relief Request Number RR-04 Affected Class I Pressure Retaining Components Affected Line or Code Pipe Pipe Sch.
Approx.
Examinatio Drawing Boundary Exception(s)
Component Class Dia.
Length n Category No.
Safety injection loop "2" hot 1
2 in.
A376 TP316 92 ft.
B-P 5379-Check valve to remain closed to avoid leg injection check valve SI-SMLS Sch. 160
- 1082, disassembly or other temporary 874B and upstream piping Sheet 4 configurations required to achieve test pressures at upstream piping and valves SI-874C and SI-866B Safety injection loop "3" hot 1
2 in.
A376 TP316 44 ft.
B-P 5379-Check valve to remain closed to avoid leg injection check valve SI-SMLS Sch. 160
- 1082, disassembly or other temporary 874A and upstream piping Sheet 4 configurations required to achieve test pressures at upstream piping and valves SI-874D and SI-866A Residual heat removal 1
14 in.
A376 TP316 42 ft.
B-P 5379-Valve RHR-750 to remain closed to motor-operated valve RHR-SMLS Sch. 140
- 1484, avoid pressuring downstream piping 750 and common suction Sheet 1 and valve RHR-751, which would piping result in single valve isolation between hydrostatic test boundary and decay heat removal system
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-05 Relief Request RR-05 Borated Bolted Connections Component(s) for Which Relief is Requested The components applicable to this relief request are HBRSEP, Unit No. 2, Class 1, 2, and 3 pressure retaining bolting.
Code Examination Requirements The ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, IWA-5250, "Corrective Action," requires that if leakage If leakage occurs at a bolted connection in a system borated for the purpose of controlling reactivity, one of the bolts shall be removed, VT-3 examined, and evaluated in accordance with IWA-3100. The bolt selected shall be the one closest to the source of leakage. When the removed bolt has evidence of degradation, all remaining bolting in the connection shall be removed, VT-3 examined, and evaluated in accordance with IWA-3100.
Requested Relief HBRSEP, Unit No. 2, requests relief from the ASME B&PV Code,Section XI, 2007 Edition with 2008 Addenda, IWA-5250, regarding the actions to be taken when leakage occurs at a bolted connection in a system borated for the purpose of controlling reactivity, during the conduct of a system pressure test. Specifically, removal and examination of one bolt closest to the source of leakage would be by VT-1 visual examination in lieu of the Code-required VT-3 visual examination. Additional relief is requested from the requirement to remove any bolting if the source of the leakage can be confirmed by visual inspection, to have not come into contact with the bolting.
Basis for Relief HBRSEP, Unit No. 2, requests relief to perform the Proposed Alternative Examinations pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternatives provide an acceptable level of quality and safety.
The use of a VT-1 visual examination in lieu of the Code-required VT-3 visual examination will provide a comparable level of quality and safety. The ASME B&PV Code, Section Xl, references the VT-1 visual examination for pressure retaining bolting. Guidance for performing VT-1 visual examinations of bolting are already incorporated within examination procedures and are considered more stringent than those associated with the VT-3 visual examination.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-05 Leakage may be confirmed by visual inspection, to have not come into contact with the bolting by direct methods and pursuant to confirmation that the borated effluent has not come into contact with the subject bolt, the bolting degradation may be assessed to be acceptable. Furthermore, the licensee invokes a Boric Acid Program (EGR-NGGC-0207).
The purpose of this procedure is to establish the requirements for minimizing the effects of boric acid corrosion on PWR structures, systems, and components (SSCs). It provides instructions for the inspection, reporting, evaluation and corrective actions required when boric acid residue is found. It also provides guidance for evaluating components which have been found to have wastage caused by boric acid corrosion.
The Proposed Alternative Examinations described below will provide an acceptable level of quality and safety when compared with the Code-required examinations.
This relief request specifically identifies the actions that are necessary to address bolted connection removal required by IWA-5250 of the ASME Code. The Code requires removal of a bolt, closest to the source of the leakage, when leakage occurs at a bolted connection, and prescribes the actions necessary if degradation is identified. The Code does not specifically address the actions necessary to stop leakage at a bolted connection, since such leakage may have a variety of sources. Plant processes (procedures) are in place to address the leakage source, such as generation of a corrective maintenance work order for leakage or evidence of leakage and employ the evaluation elements of the Boric Acid Program. This relief request is not directed at relief from correcting leakage sources, but is intended to address the actions necessary to address leakage identified at bolted connections, and required actions to be performed at the bolted connection, as required by IWA-5250, "Corrective Action."
Proposed Alternative Examinations If leakage is identified and in contact with a bolted connection in a system borated for the purpose of controlling reactivity during the conduct of a system pressure test, the following actions will be taken:
- 1. The bolt in contact with the source of leakage will be removed and a VT-1 visual examination performed. The condition will be evaluated in accordance with IWA-3100. When the removed bolt shows evidence of degradation, the remaining bolting will be removed, a VT-1 visual examination performed, and the condition will be evaluated in accordance with IWA-3100.
Implementation Schedule This relief is requested for and will be implemented in the HBRSEP, Unit No. 2, Fifth Ten-Year Inservice Inspection (ISI) Interval, which begins on July 21, 2012 and ends on February 18, 2022.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-06 Relief Request No RR-06 Surface Examination of Reactor Vessel Dissimilar Metal Welds Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, reactor pressure vessel (RPV) nozzle-to-safe end welds on each loop on the reactor vessel inlet and outlet piping. These are dissimilar metal welds on the hot and cold leg piping of each reactor coolant system loop, i.e., RPV inlet and outlet piping. The affected welds are uniquely identified as follows:
Weld Identification Number Location CPL-107/1DM Hot Leg "A" CPL-107/14DM Cold Leg "A" CPL-1 07A/1 DM Hot Leg "B" CPL-107A/14DM Cold Leg "B" CPL-1 07B/1 DM Hot Leg "C" CPL-107B/14DM Cold Leg "C" Code Examination Requirements The ASME B&PV Code, Section Xl, 2007 Edition with 2008 Addenda, Table IWB-2500-1, Examination Category B-F, "Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles," Item No. B5.10, requires volumetric and surface examination of RPV nozzle-to-safe end welds in accordance with Figure No.
Requested Relief HBRSEP, Unit No. 2, requests relief from the ASME B&PV Code,Section XI, 1995 Edition with 1996 Addenda, Table IWB-2500-1, Examination Category B-F, Item No. B5.10, regarding surface examination RPV nozzle-to-safe end welds.
Basis for Relief HBRSEP, Unit No. 2, requests relief in accordance with 10 CFR 50.55a(a)(3)(ii) on the basis that hardship and unusual difficulty exists, without a compensating increase in the level of quality and safety, regarding performance of the Code-required surface examination of the RPV nozzle-to-safe end welds.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-06 Examination of the RPV nozzle-to-safe end welds was not considered as part of the original plant design, which occurred prior to issuance of Section XI ISI requirements. Access to the affected welds from the refueling cavity is significantly limited. Additionally, due to the configuration of the RPV nozzles as they penetrate the biological shield wall, the weld area accessible for the Code-required examinations is approximately the top one-third of the weld outside diameter.
Significant personnel hazards are associated with examinations of the RPV nozzle-to-safe end welds that are not commensurate with the benefits gained from performing such examinations. Access to the affected welds from the refueling cavity involves entry into an area that is physically confining with elevated ambient temperatures. These ambient conditions, combined with the required use of personnel protective equipment, create the potential for heat stress and exhaustion. Detailed dose assessments have concluded that performance of the Code-required examinations is not consistent with the principal of "As Low As Reasonably Achievable" (ALARA). For example, with an assumed area dose rate of 600 mRem/hour, worker exposure for surface examination of the six affected welds is estimated at approximately 7.5 Rem.
Previous examination history supports the Proposed Alternative Examinations in lieu of the Code-required surface examinations. A surface examination was performed in the Second 10-Year Interval on the accessible portions and identified no indications. For the Third 10-Year Interval, relief was granted from performing the surface examination. A VT-2 examination was performed from the refueling floor through the access hatch. The dissimilar metal welds, as well as the safe end-to-pipe welds, were examined at the conclusion of the Third 10-Year Interval for the ASME Code-required volume. Two indications were identified in the hot leg "B" safe end on the nozzle side, and one indication was identified in the cold leg "C" nozzle side.
The dissimilar metal welds, as well as the safe end-to-pipe welds, were examined volumetrically at the conclusion of the Third Ten-Year Interval for the ASME Code-required volume. Two volumetric indications were identified in the hot let "B" safe end on the nozzle side, and one indication was identified in the cold leg "C" nozzle side. These three volumetric indications were evaluated in accordance with Code requirements and found to be acceptable.
H. B. Robinson Steam Electric Plant, Unit No. 2 Fifth Ten-Year Interval Relief Request RR-06 During the Fourth Ten Year Interval, the dissimilar metal welds were examined under MRP-139 in refueling outage twenty five utilizing volumetric phased array technique. Volumetric indications were identified in all three hot leg dissimilar metal welds and the "B" loop on the cold leg and were validated as NOT ID connected by eddy current testing. Successive examinations are scheduled to be performed during refueling outage twenty seven, which is the last outage of the Fourth Ten Year Interval with mitigation planned in refueling outage twenty eight, which is the first refueling outage of the Fifth Ten Year Interval.
Proposed Alternative Examinations Ultrasonic examinations will be conducted from the inside diameter of the RPV nozzle and will include the Code-required weld volume, i.e., lower one-third, as well as the heat-affected zone. These examinations will be performed as required by ASME Section XI Code during the Fifth Ten Year Interval.
In addition, these welds are being examined, as required by 10CFR50.55a 50.55a(g)(6)(ii)(F), which states, "Licensees of existing, operating pressurized-water reactors as of July 21, 2011 shall implement the requirements of ASME Code Case N-770-1, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (g)(6)(ii)(F)(1 0) of this section, by the first refueling outage after August 22, 2011,".
As an alternative to the Code-required surface examination, a VT-2 visual examination will be conducted in accordance with the ASME Code, Section Xl, 2007 Edition with 2008 Addenda, IWA-5242, "Insulated Components."
Request for Relief No. RR-06 Previously approved during the Fourth Interval under TAC No. MB2773, dated September 26, 2002.
Implementation Schedule This relief is requested for and will be implemented in the HBRSEP, Unit No. 2, Fifth Ten-Year ISI Interval, which begins on July 21, 2012.