L-MT-05-039, Fourth Interval Inservice Inspection Examination Plan. Revision 3
| ML051260121 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/26/2005 |
| From: | Thomas J. Palmisano Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2010-0209, L-MT-05-039 | |
| Download: ML051260121 (613) | |
Text
{{#Wiki_filter:NMuCe Committed to Nudlear Exellence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC APR 2 62005 L-MT-05-039 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Monticello Fourth Interval Inservice Inspection Examination Plan. Revision 3 Enclosed with this letter is Revision 3 to the Monticello Nuclear Generating Plant (MNGP) Fourth Interval Inservice Inspection (ISI) Examination plan. This revision is a comprehensive update and affects all sections of the plan. Therefore, please replace all sections of the plan in their entirety. The superseded pages should be destroyed. This letter makes no new commitments or changes to any existing commitments. homas almisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC 2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
- Fax: 763.295.1454 fl
ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT INSERVICE INSPECTION EXAMINATION PLAN REVISION 3 FOURTH INTERVAL 307 pages follow
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN NMC) NUCLEAR MANAGEMENT COMPANY 700 1st Street HUDSON, WISCONSIN 54106 MONTICELLO NUCLEAR GENERATING PLANT 2807 WEST HIGHWAY 75 MONTICELLO, MINNESOTA 55362 INSERVICE INSPECTION EXAMINATION PLAN REVISION 3 I FOURTH INTERVAL MAY 1, 2003 THROUGH MAY 31, 2012 Prepared By: Richard Deopere Sect ion XI ISI Coordinator Reviewed By: Tom Jones NDE Level III Approved By: [av Potter I Supv, Inspection and Materials Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY ' . - INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN RECORD OF REVISIONS Pa.e:.:. i.. ...- .:K;.,Rev.* Review and Approval ......................... l
;;....... 3 iv .............. ........ 3l 1.1-1 ., I..; '
1.2-1 through 1.2-4, .:.' 3 1.3-1 and 1.3-2 ................ .3 I
'!1.4-1 through -1.4-2-.2 2 1.5-1 through 1.5-71 .............. :.- 2..
2l 1.6-1 through 1.6-4 ............... :. . . 1
-1.7-1 through 1.7-3 . ................... ;.1l -Inspection Schedule (Page, 1 to 326) 1..
an Approval*page. Note: The revision numbers reflect section-speific revisions. Drawings in Section 1.6 retain their own drawing specific revision number. However, the governing revision of all sections is the ISI Plan Revision listed on the Review i Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN RECORD OF REVISIONS (cont'd) Summary of Changes, Plan Revision I Title Page Modified Interval start date to May 1, 2003 and noted Revision 1 Page i Noted Rev. 1 for affected sections Page ii Added page for Summary of Changes, Revision 1 Page 1.2-1 4th Ten Year Interval
- Updated revised 3rd Interval extension dates
- Added discussion regarding overlap of 3rd and 4th Intervals
- Changed 4th Interval start dates Component Selection
- Added requirement for examination of re-used CRD Bolting Page 1.2-2 Code Edition Summary
- Added requirement for examination of re-used CRD Bolting
- Removed reference to NF (Supports). NF not applicable, supports are examined per Subsection IWF
- Modified Appendix Vil Section to reflect latest modification of Appendix VIII implementation per 10CFR50.55a and remove references to specific Supplements and implementation dates Page 1.2-3 Examination Personnel / Procedures
- clarified description of examination personnel and procedure requirements.
- Clarified to reflect additional use of Mandatory Appendix VilI requirements for UT personnel and procedures as modified by 10CFR50.55a dated September 26, 2002, except where relief has been granted.
- Removed reference to Appendix Vil - Supplements.
Page 1.3-1 Removed reference to unpublished Reg. Guide 1.147 Rev. 13 (Draft Reg. Guide 1091) Section 1.4 Modified entire section to remove references to Code Cases listed as approved or conditionally approved in unpublished Draft Reg. Guide 1091, but not found in published Reg. Guide 1.147, Rev. 12. ii Revision 3 3/10/2005 I
-NUCLEAR MANAGEMENT COMPANY. -~. - INSERVICE INSPECTION MONTICELLO 4th INTERVAL ;- .' -EXAMINATION PLAN Summary of Changes, Plan Revision 2 Title Page Modified revision number and revised titles/names Page i Changed Revision Number and pages for affected sections Pages iii & iv Added pages for Summary of Changes, Revision 2 Page 1.2-1
Background:
Format / spacing changes , 4th Ten Year Interval
. Format / spacing changes;'-'
- Changed number of scheduled obutages from Six to Five
- Removed reference to maintenance outages f',. n..............-.4 . K -' -
- IU UULU I8U I~lI i --"Frat a spacing changes'-' -;
T , *, Page 1.2-2 Code Edition Summary Added provisions for implementation of approved ISI Relief Request #7 to use' 2001 Edition o6f Section Xi for Repair/Replacement activities and associated Pressure Testing. NRC exception noted. (see Corrective Action Program OTH020219) Background for Plan / Schedule Development changed intent of scheduling from "subject to allowing meaningful accumulation of service time for new components" to "to the extent practical Page 1.2-3 ISI Plan Overall Description Added RI-ISI to the description of how components are listed in the Plan and Schedule 0 Capitalized Item Number Page 1.2-4 ISI Plan Overall Description (cont'd)
- Added "Rev. B-A" to TR-1 12657 Page 1.3-1 Source Documents
- Added 1995 Edition, 1995 Addenda of Section Xl
- Added 2001 Edition, No Addenda of Section Xl iii Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Summary of Changes, Plan Revision 2 (cont'd) Page 1.3-2 Source Documents (cont'd)
- Added NRC SER for Relief Request #7 Page 1.5-1 Relief Requests
- Added Relief Request No.7 Page 1.5-35 Relief Request No.2 a Added Clarification in title regarding italicized text Page 1.5-48 Relief Request No.3
- added Reference 11, NRC SER Title for Relief Request No.3
- updated Status as approved Page 1.5-53 Relief Request No.5 updated Status as approved and listed NRC SER Title for Relief Request No.5 Page 1.5-56 Relief Request No.6
- added Reference 4, NRC SER Title for Relief Request No.6
- updated Status as approved Page 1.5-57 Relief Request No.7
- added Relief Request No. 7 including NRC exceptions iv Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY. -- INSERVICE INSPECTION MONTICELLO 4th INTERVAL
- 7 EXAMINATION PLAN
'Summary of Changes, Plan Revision 3 Title Page Modified revision number and revised titles/names Page i Changed revision number and pages for affected sections and added note discussing applicability of revision numbers Pages v - viii Added pages for Summary of Changes, Revision 3 Page 1.2-1 4 th Ten-Year Interval
- clarification of 3rd Interval extension and overlap of 3rd and 4th Intervals Component Sele'ction
' Added reference to ASME Section Xl Code Case N-598 applied to per-period percentage requirements Page 1.2-2 Code Edition Summary.
- Class 1 (Quality.Group A), clarified description
. Class 1 CRD Bolting, removed reference to augmented
. program GE SIL. No. 483R2 for examination of B7.80 items.
10CFR50.55a requires'use of 1995 Edition with 1995 Addenda for reused CRD bolting.
' Class 2 (Quality'Group B),' clarified description
. Appen'dix VilI - Mandatory, updated to include subsequent publications of I OCFR50.55a
- Repair/Replacement..., added further restrictions invoked by 10CFR50.55a effective November 1, 2004 Page 1.2-3 Examination Personnel /,Procedures.
. updated to include subsequent'publicatibns of 10CFR50.55a Page 1.3-1 Source Documents
- Changed 1995 Edition, 1995 Addenda of Section Xl to 1995
-Edition, No Addenda
. Updated 10CFR50.55a to current reference in Federal Register
. Updated Reg. Guide 1.147 to Rev.133
. Added EWI-09.04.00 Deleted letters regarding 3r Interval Relief Requests (RR) 8 and 13
- Added Jan. '03 letter regarding further extension of 3rd Interval
- Added Dec. '02 letter requesting NRC review of 4h"-nterval relief requests.included with ISI Plan submittal
;. v Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Summary of Changes, Plan Revision 3 (cont'd) Page 1.3-2 Source Documents (cont'd)
- Added letter for ISI Plan, Rev.2
- Deleted letter regarding 3rd Interval RR 14
- Added cross-reference to 3rd Interval RR 12 ( 4 th Interval RR 2)
- Added NRC SER for RR 3 and 6
- Added NRC SER for RR 5
- Added date to NRC SER for RR 7
- Added NRC SER for RR 8
- Added NRC SER for RR 9 (Fleet RR)
- Added NRC SER for RR 10 (Fleet RR)
- Added NMC Letter to NRC for RR 11 (Fleet RR)
Page 1.4-1 Section Xl Code Cases thru 1.4-6
- Added reference to Rev. 13 of Reg. Guide 1.147
- Added discussion that currently applied Code Cases are underlined
- Completely updated list for Code Cases that are applied to the ISI Plan. Also included Code Cases that would be beneficial if needed on a case by case basis, but have not been implemented for use to date.
Page 1.5-1 Relief Requests thru 1.5-2 0 Added RR 8, 9, 10 and approval dates 0 Added RR 11 submittal (pending approval) 0 Added approval dates to RR 3, 4, 5, 6, 7 0 Clarification for notes regarding RR 1 and 2 Page 1.5-50 Relief Request No.4 thru 1.5-54
- Replaced original submittal with updated final submittal and reference to NRC approval Page 1.5-77 Relief Request No.8 thru 1.5-82
- Added final submittal and reference to NRC approval Page 1.5-83 Relief Request No.9 thru 1.5-107
- Added final submittal and reference to NRC approval vi Revision 3 3/10/2005
- NUCLEAR MANAGEMENT COMPANY, .- INSERVICE INSPECTION MONTICELLO 4th INTERVAL !, k_EXAMINATION PLAN Si of C.vi
. Summanj of Changes, Plan Revision 3 (cont'd)
Page 1.5-108 Relief Request No.10 ... - ..
.!~
I.. . I..~ I. thru 1.5-113 . * . Added final submittal and reference to NRC approval I . . T- - - - - rage 1.5-114 RelieT equeSt NO.11 thru 1.5-118
. Added final submittal . . :. i Page 1.6-1 Boundary and Isometric Drawing Index thru 1.6-4 Updated to show current revision / status ISI Boundary Drawings and ISI Class 1, 2, and.3 Isometric Drawings
- Updated multiple drawings for editorial corrections, piping configuration changes,-and elimination of systems -
Page 1.7-1 Inspection Plan and Table thru 1.7-4
*. Periods, updated period start end dates
- Scheduled Outages, updated wwith current outage schedule
- Scheduled Outages, added Code Case N-598 for per-period percentage requirements
- Note 3, added "to the extent practical"
- Note 4, removed reference to GE SIL 483 and updated with requirements from 10CFR50.55a
- Note 6, added with exam requirements for Code Cat. B-G-2, Item 86.180
- Note 7 p, added further definition
- Note 7 I, added further definition
- Pressure Testing Note A, added details re: restructuring of the Plan and scheduling of Class 1 System Pressure Tests.
. Pressure Testing Note B, added details re:restructuring of the Plan and scheduling of Class 2 System Pressure Tests.
- Pressure Testing Note D, updated from Code Case N-488-1 to N-498-4
- Pressure Testing Note E, previously reserved, applied for Code Case N-522 Pressure Testing Note F, added details regarding restructuring of the Plan and scheduling of Class 2 System Pressure Tests.
NDE Note AA, clarified exam is performed near the end of the Interval. vii Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Summary of Changes, Plan Revision 3 (cont'd) 4 th Interval Plan, Component Examination Schedule
- Updated to reflect current status of examination status
- Updated to reflect inactivation of eliminated systems per Design Change 02Q195 (RPV Head Spray Removal) and 03Q145 (CGCS System Removal)
- Updated to include integrally welded attachments (B-K, C-C, or D-A) which were previously examined under the IWF category, or were exempted from examination in the 3 rd ISI Interval. (see CA 022418, CA 020622, CAP 029634)
- Updated schedule to reflect incorporation of Code Case 598
- Updated schedule for proportional examination of support by system and function (SA 021615, CAP 036901, CA 023866)
- Updated schedule for applied Code Cases (SA 021615, CAP 036901, CA 023866)
- Updated schedule to optimize examination requirements for "multiple" Class 1 and 2 components ( (SA 021615, CAP 036901, CA 023866)
- Updated schedule for items permitting deferral to end of interval (SA 021615, CAP 036901, CA 023866)
- Updated schedule with other miscellaneous changes from SA 021615 and minor self-identified discrepancies.
viii Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN TABLE OF CONTENTS Page Record of Revisions .......................... i Table of Contents. 1.1-1 Introduction .1.2-1 Source Documents. 1.3-1 Section Xl Code Cases. 1.4-1 Requests for Relief. 1.5-1 ISI Boundary/Isometric Drawings. 1.6-1 Inspection Plan and Schedule Tables (Pages 1 to 332) . 1.7-1 1.1-1 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY ' INSERVICE INSPECTION MONTICELLO 4th INTERVAL . EXAMINATION PLAN INTRODUCTION
Background:
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code (hereafter referred to as ASME Section Xl, Section Xl, or the i 'Code), Section XI Inservice Inspection (ISI) Program is prepared and maintained by the Nuclear Mariagement Company (NMC). The Inservice Testing Program (IST) is maintained separately from this program and is submitted under
- separate cover. The Containment Inspection Program, as allowed by 10CFR55a(g)(6)(ii)(B), and the Repair/Replacement Program are maintained separately from this program, and, although they are not submitted, they are available at the plant gite for audit and review.'
4th Ten-Year Interval:' The Monticello 4th Ten-Year Inservice Inspection Interval is slightly less than 120 months due to an extension of the 3rd Interval (Letters to the NRC in May 2002 and January 2003 providing notification of 3rd Interval extension initially through March 8, 2003 (M2002057) and subsequently through May 31, 2003 (L-MT-03-004). The 4th Interval overlapped the 3rd Interval as permitted by IWA-2430(d)(1),(2),(3),jand (4) The 4th Interval start date is May 1, 2003 and end date is May 31, 2012. Five refueling outages are currently scheduled in this time frame. . Component Selection: With the exception of Class 1 and'2'piping welds, components within the examination plan were selected and scheduled using criteria in the 1995 Edition of ASME Section'XI with the 1996 Addenda (Inspection Program B and Code Case N-598) and 10CFR50.55a(g)(6)(ii)(A), except where relief has been requested. Per 10CFR50.55a(b)(2)(xi),-the requirements of IWB-1220 in the 1989 Edition of ASME 'Section XI, "Components Exempt from Examination," shall be used for Class 1 piping instead of the 1995 Edition of ASME Section Xl with 1996 Addenda' Per 10CFR50.55a(b)(2)(xxi)(B) reused CRD Bolting must meet exarmiination requirements for Table IWB-2500-1, Category B-G-2, Item B7.80 of ASME Section' XI 1995 Edition with 1995 Addenda. Selection of Class I and Class 2 piping welds in ASME Categories B-F, B-J, C-F-1 and C-F-2 are based on EPRI Topical Report 112657 Rev. B-A. "Revised Risk Informed Inservice Inspection Evaluation Procedure." The Risk Informed Class 1 and Class 2 application was also conducted in a manner consistent with ASME Code Case N-578 "Risk Informed Requirements for Class 1, 2, and 3 Piping, Method B." The use of the RI-ISI program was approved for use on July 27, 2002. (reference TAC MB3819 and Relief Request #1 for 4th ISI Interval)
1.2-1 Revision 3 1 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN INTRODUCTION (cont'd) Code Edition SummarV: The code editions implemented in the ISI Program can be summarized as follows: Class 1 (Quality Group A) 1995 Edition with 1996 Addenda, Risk-informed Program for Class 1 Piping Category B-F and B-J (Relief #1), 10CFR50.55a(b)(2)(xi) specifies' 989 Edition IWB-1 220 for Class 1 piping exemption requirements Class 1 CRD Bolting (B7.80) 10CFR50.55a(b)(2)(xxi)(B) specifies 1995 Edition for examination requirements of reused CRD Bolting Class 2 (Quality Group B) 1995 Edition with 1996 Addenda, Risk-informed Program for Class 2 Piping Category C-F-1 and C-F-2 (Relief #1) Class 3 (Quality Group C) 1995 Edition with 1996 Addenda MC (Metal Containment) 1992 Edition with 1992 Addenda, Subsection IWE Appendix VIII - Mandatory 1995 Edition with 1996 Addenda as modified by 10CFR50.55a dated September 26, 2002 and subsequently published Final Rules Repair / Replacement and 2001 Edition with No Addenda per ISI Relief associated Pressure Test Request No.7. NRC exception: must use IWA-4540(c) of the 1998 edition in lieu of the 2001 Edition requirement. Additional restrictions for the 2001 Edition include prohibited use of IWA-4340 (10CFR50.55a(b)(2)(xxv) and IWA-2220 (10CFR50.55a(b)(2(xxii) 1.2-2 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY -I INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN INTRODUCTION (cont'd) Backqround for Plan/Schedule'Development: The examination plan and. - schedule was developed from ASME Code'requirements, Risk-Informed
- Methodology, individuial component examination history and plant scheduling needs such as optimizing insulation removal and scaffolding needs. During the 2nd Interval, a substantial number of component'replacements and alterations were made (e.g. the recirculation piping replacement). The intent of the 4th Interval scheduling was to be consistent with the 2nd and 3rd Interval, to the extent practical. For Class 1 (category B-F and B-J) and Class 2 Category C-F-
-1 and C-F-2) Piping Welds examined per the RI-ISI Plan, there may be little schedule correlation with previous IS Intervals. ' - -' -
Examination Personnel I Procedures: Inservice Inspection examination procedures and personnel certifications meet the requirements specified in the 1995 Edition of ASME Section Xl with the 1996 Addenda. Additionally, UT personnel and procedures meet the requirements'of Mandatory Appendix Vil as modified by 10CFR50.55a dated September 26, 2002 and subsequently published Final Rules, except where relief has' been granted. Reporting of Associated Section Xl Programrns The Section Xl Repair and Replacement Program,'System Pressure Tests and Snubber Functional Tests are administered under separate program d6ccimnents. Although these programs are administered separately, the activities required by the Repair and Replacement Program, System Pressure Tests and Snubber Functional Tests are reported in the "Inservice Inspection Summary Report" following each refueling outage. ISI Plan Overall
Description:
The ASME Section Xl Inservice Inspection Program is comprised of six parts: Introduction, Source Documents, Requests for Relief, ISI Boundary Drawings, 1S1 Isometric Drawings, and a table containing the Inservice Inspection Examination Plan and Schedule. The ISI Boundary Drawings outline Quality Group Classifications, (A, B and C). The [SI Isometric Drawings delineate ASME Section Xl components or items that are included in the examination program. The Inservice Inspection Examination Plan and Schedule lists the ASME Section Xi components by Isometric Drawing Number, System, Code or RI-ISI Category, Code or RI-ISI Item, Component Description and Required Examination. The Examination Plan and Schedule identify the ASME Section Xl Item Number listed in Tables IWB-2500-1, IWC-2500-1, IWD-2500-1 and Subsection IWF, and Item Number for Risk Informed Tables as identified in EPRI TR-1 12657, thus identifying the examination method. The examination schedule lists the 1.2-3 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN INTRODUCTION (cont'd) anticipated period and outage for the examination of a given component. The examination schedule is intended to be flexible to allow for deviations in outage length and outage work scope. Therefore, the schedule may be changed, as allowed by the Code, without further notification. Examination distribution was developed in accordance with IWA-2432, Inspection Program B. The examination plan and schedule also contains certain non-code items to be examined, or examinations beyond Section Xl Code requirements. These augmented items include licensee-initiated examinations on NC-7879-6/Tank and NC-ISI-371W-1, W-2, W-3, WA, W-12, W-12A shown in the plan and schedule. These items will be examined to the extent practical in accordance with the Section Xl Code, 1995 Edition with 1996 Addenda, not the RI-ISI Program. Relief requests will not be submitted for these non-code exams if Section Xl Code requirements cannot be met. Non-code exams are also subject to change without prior notification to the NRC. The Monticello Plant was built prior to the implementation of Section Xl Access Requirements. As a result, some components that require examination may not be completely accessible. Welds selected for examination under the Risk Informed Program were selected base on risk ranking, radiation area, and weld accessibility as allowed by EPRI TR-1 12657 Rev. B-A. 1.2-4 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL ¢."' ` EXAMINATION PLAN Source Documents: The following referenced source documents'described and listed below are basis documents used and applicable to the'Monticello 4th Interval ISI Plan. ASME BPV Code'Section Xl, 1992 Edition with'1992 Addenda, Subsection IWE ASME BPV Code Section Xl, 1995 Edition with 1996 Addenda ASME BPV Code Section XI, '1995 Edition with No Addenda - ASME BPV Code Section Xl, 2001 Edition with No Addenda IOCFR50.55a, Industry Codes and Standards (69FR58804) 10CFR-50.55a(g)(6)(ii)(A)(64FR51370) ASME Seiction XI, 1995 Edition with '1996 Addenda, Appendix VlIl Supplements 10CFR-50.55a(g)(6)(ii)(A)(66FR1 6391) ASME Section Xl, 1995 Edition with 1996 Addenda, Appendix VIII Supplement 4 Length Sizing Correction Regulatory Guide 1.147, Rev. 13, Jan 2004 Monticello lnservide Inspection Licensee Control Program,-4 AWI-09.04.00 Monticello ASME Section Xl Inservice Inspection Program, EWI-09.04.00 GE Nuclear Services Information Letter, SIL. No 483R2 "CRD 'Cap Screw Crack Indications,', September 5,1992 ' Generic Letter 88-01 '& NUREG-0313, Rev 2 (IGSCC (M88080A, M88082A) Note: All Monticello'welds meet NUREG-0313, Rev. 2. CategoryA Monticello Notification Letter to NRC, "Notification of Extension of 3rd Ten-Year Inservice Tesiing and Inservice Inspection Intervals," May 30, 2002 Monticello Notification Letter to NRC, 'Change to Inservice Testing Program Plan and Inservice Inspection Examination Plan 10-Year Intervals," January 23, 2003 . - -. Monticello Letter to NRC, "Request for Review and Approval of Relief Requests Associated with Fourth 10-Year Interval Inservice Inspection Examination Plan Submittal," December 6, 2002 1.3-1 - Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Source Documents: (cont'd) Monticello Letter to NRC, "Monticello Fourth Interval Inservice Inspection Examination Plan, Revision 2," September 16, 2004 NRC Letter, UMonticello Nuclear Generating Plant - Risk-informed Inservice Inspection Program (TAC MB3819)," July 24, 2002 (Relief Request #1 for 4th ISI Interval) NRC Letter, "MNGP-Evaluation of Relief Request No. 12 (for the 3rd 10-Year ISI Program Plan," (TAC No. MB0261), July 27, 2001 ( 4 th Interval ISI Relief Request No.2) NRC Letter, "Relief Request Nos. 3 and 6 for the Fourth 10-Year Interval of the Inservice Inspection Examination Plan" (TAC No. MB6896), March 28, 2003 NRC Letter to Nuclear Management Company, "Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 5" (TAC No. MB6956), June 9, 2003 NRC Letter, "Monticello Nuclear Generating Plant - Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 7 (TAC NO. MB6897)," October 3, 2003 NRC Letter, "Monticello Nuclear Generating Plant - One-Time Inservice Inspection Program Plan Relief Request No. 8 For Leak Testing The "B"And "G" Main Steam Safety Relief Valves (TAC No. MB9538)," June 13, 2003 NRC Letter, "Duane Arnold Energy Center, Monticello Nuclear Generating Plant, Prairie Island Nuclear Generating Plant, Units 1 and 2, Kewaunee Nuclear Power Plant, Point Beach Nuclear Plant, Units 1 and 2, Palisades Nuclear Plant Re: Request for Alternatives to American Society of Mechanical Engineers (ASME) Section Xl, Appendix VIII, Supplement 10 (TAC NOS. MC0814, MC0816, MC0820, MC0821, MC0815, MC0818, MC0819 AND MC0817)," February 26, 2004 (MNGP ISI Relief Request No.9) NRC Letter, "Duane Arnold Energy Center and Monticello Nuclear Generating Plant Re: Request for Authorization to Utilize Code Case N-613-1 (TAC Nos. MC2374 and MC2375)," October 6, 2004 (MNGP ISI Relief Request No.10) NMC Letter to NRC, "10 CFR 50.55a Request GR-04-01; Request For Authorization To Utilize Code Case N-661 (L-HU-04-027)," July 28, 2004, (Proposed MNGP ISI Relief Request No.1 1) EPRI Report TR-1 12657, Rev B-A, "Revised Risk-informed Inservice Inspection Evaluation Procedure," December 1999 1.3-2 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY ._"- INSERVICE INSPECTION MONTICELLO 4th INTERVAL ", --'EXAMINATION PLAN Section Xl Code Cases: - .- : The following listed Code Cases are permissible for-use at Monticello during the 4th Interval per Reg. Guide 1.147, Rev. 13. The examination schedule will reflect Code Case implementation on an item or category basis, as applicable. Those that are currently applied are underlined in the listing below.
-Code Case N-307-2 Revised Ultrasonic Examination Volume for
' -Class I Bolting, Table IWB-2500-1,
- 'Examination Category B-G-1, When the
'-Examinations are Conducted from the End of the Bolt or Stud, or from the Center-Drilled
- Hole Code Case N-460 - Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1
.'Code Case N-491-2 Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power. Plants, Section Xl, Division 1 (not used for scheduling - used for evaluation provisions on an as-needed basis)
Code Case N-498-4 Alternative Rules for 10 Year System Hydrostatic Testing for Class 1, 2, and 3 Systems. (Applicable to Class 3, Category D-B only) Condition of Use for . The provisions of IWA-5213, "Test Holding Code Case N498-4 Times," 1989 Edition, are to be used (10 minute uninsulated, 4 hour Insulated)
Code Case N-504-2 . Alternative Rules for Repair of Class 1, 2, and
- - - - -:3 Austenitic Stainless Steel Piping.
I - Code Case'N-513 I Evaluation Criteria for Temporary Acceptance
.. I. .. . . . of Flaws in Class 3 Piping 1.4-1 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Section Xl Code Cases: (cont'd) Condition of Use for 1) Specific safety factors in paragraph 4.0 Code Case N-513 must be satisfied
- 2) Code Case N-513 may not be applied to:
- a. Components other than pipe and tube
- b. Leakage through a gasket
- c. Threaded connections employing nonstructural seal welds for leakage prevention (through seal weld leakage is not a structural flaw; thread integrity must be maintained)
- d. degraded socket welds Code Case N-517-1 Quality Assurance Program Requirements for Owners Condition of Use for The owners quality assurance program that Code Case N-517-1 that is approved under Appendix B to 10 CFR 50 must address the use of this Code Case and any unique QA requirements identified by the Code Case that are not contained in the owner's QA Program description. This would include the activities performed in accordance with this Code Case that are subject to monitoring by the Authorized Nuclear Inspector Code Case N-522 Pressure Testing of Containment Penetration Piping (applies to subset of Class 2 piping only)
Code Case N-526 Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels Code Case N-528-1 Purchase, Exchange, or Transfer of Material Between Nuclear plant Sites 1.4-2 Revision 3 3/10/2005
'NUCLEAR MANAGEMENT COMPANY' -. - ; . INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' 'EXAMINATION PLAN Section Xi Code Cases: (cont'd)
' Condition of Use for -The requirements of 10 CFR Part 21 are to be Code Case N-528-1 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.
Code Case N-532-1 Alternative Requirements to Repair and
'Replacement Documentation Requirements and Inservice Summary Report Preparation
- - and Submission as Required by IWA-4000 and
-;IWA 6000 Condition of Use for The OAR-1 must be submitted to the NRC
'-'Code Case N-532-1 within 90 days of the completion of the refueling outage.
Code Case N-534 Alternative Requirements for Pneumatic Pressure Testing Code Case N-537 Location'of Ultrasonic Depth Sizing Flaws Code Case N-545 Alternative Requirements for. Conduct of Performance Demonstration Detection Test of Reactor Vessel Code Case N-546 .- Alternative Requirements for Qualification of VT-2 Examination Personnel Condition of Use for (1) Qualify examination personnel by test
-'Code Case N-546 to demonstrate knowledge of Section Xl and
, plant specific procedures for VT-2 visual examination.
(2) Re-qualify examination personnel by examination every three years. (3) This Code Case is applicable only to the performance of VT-2 examinations. Code Case N-552 Alternative Methods-Qualification for Nozzle Inside Radius Section from the Outside Surface
- 1.4-3 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Section Xi Code Cases: (cont'd) Condition of Use for To achieve consistency with the 10CFR50.55a Code Case N-552 rule change published September 22, 1999, incorporating Appendix VI II,"Performance Demonstration for Ultrasonic Examination Systems," to Section Xl; add the following to the Specimen requirements: UAt 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 detection criteria, uThe number of false calls must not exceed three." Code Case N-555 Use of Section II,V, and IXCode Cases Code Case N-566-1 Corrective action for leakage Identified at Bolted Connections. (SBLC System only) Code Case N-578* Risk-informed Requirements for Class 1, 2, and 3 Piping, Method B, Section Xl, Division 1 (* Not approved by Reg. Guide 1.147, Rev.13, but referenced by Relief Request #1 on page 1.5-2 for Class 1 and 2 piping welds, Category B-F, B-J, C-F-1, and C-F-2) Code Case N-586 Alternative Additional Examination Requirements for Class 1, 2, and 3 Piping, Components, and Supports 1.4-4 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY M;', - INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Section Xi Code Cases: (cont'd) Condition of Use for,' The engineering evaluations addressed under Code Case N-586,' - .Item (a) and the additional examinations
- addressed under Item (b) shall be performed during this outage. If the additional examinations performed under Item (b) reveal indications exceeding the applicable acceptance criteria of Section Xl, the engineering evaluations and the examinations
."'-. '. shall be further extended to included additional
-- evaluations and 4 examinations at this outage.
Code Case N-592 ASNT Central Certification Program Code Case N-597-1 Requirements for Analytical Evaluation of Pipe
; Wall Thinning Condition of Use for '(lengthy list of conditions for use, see Reg.
Code Case N-597-1 Guide 1.147 for conditions) Code Case N-598 Alternative Requirements to Required
- Percentages of examinations'
- - - (Applie'd to exam categories'in Tables IWB-2412-1,]-WC-2412-1, IWD-2412-1, IWE-2412-1, and IWF-2410-2 with exceptions noted in subparagraph (a))
Code Case N-601 Extent of Frequency of VT-3 Visual Examination for Inservice Inspection of Metal Containments (Applied to IWE Program, approved for use per Relief Request MC-7) Code Case N-606-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique for BWR CRD Housing/Stub tube repairs Condition of Use for A VT-I surface examination, in accordance Code Case N-606-1 with IWA-221 0 must be performed prior to welding to ensure that the surface is free from contaminants, and that the surface is properly contoured so that an acceptable weld can be produced. 1 1.4-5 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Section Xl Code Cases: (cont'd) Code Case N-613* Ultrasonic Examination of Full Penetration Nozzles in Vessels, Exam Cat. B-D, Item No. B3.90, Reactor Nozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c) (* Not approved by Reg. Guide 1.147, Rev.13; approved by Relief Request #10- See Section 1.5) Code Case N-623 Deferral of Inspections of Shell to Flange and Head-to-Flange Welds of a Reactor Vessel Code Case N-624 Successive Inspections Code Case N-638 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique Code Case N-639 Alternative Calibration Block Material Condition of Use for The chemical analysis must be within the Code Case N-639 material specification, and the microstructure (phase and grain shape) must be the same as the material being examined. Code Case N-640 Alternative reference Fracture Toughness for Development of P-T Limit Curves 1.4-6 Revision 3 3/10/2005
..-NUCLEAR MANAGEMENT COMPANY- .'. 'i INSERVICE INSPECTION MONTICELLO 4th INTERVAL I EXAMINATION PLAN
1: --.Requests for Relief Relief Request No. Description : -. i. Rev.
1* Risk Informed Inservice Inspection Plan 0
-(Approved July'24',2002 for 4th Interval)
I Reactor Vessel Circumferential Welds 1 (Approved July 27, 2001 for remainder of current 40-Year Operating License) Appendix Vil Supplement 4 0 (Approved March 28, 2003) Reactor Vessel Stabilizer Brackets / Welds 0 (Approved January 6, 2005) Leakage at Bolted Control Rod Drive 0 (CRD) Housing Connections (Approved June 9, 2003) 0 I Appendix VII Annual Training (Approved March 28, 2003) Use of 2001 Edition for Repair/Replacement 0 Program (Approved October 3, 2003) One-time Relief, Class 1 Pressure Test at 0 Less Than System Operating Pressure, Mechanical Joint (Approved June 13, 2003) Use of Alternative Requirements for Appendix 0 VIII, Supplement 10 as implemented by PDI
- - - '-' I'- (NMC Fleet Relief Request)
(Approved February 26, 2004) ' .
' '- ' 10 Use of Code Case N-613-1 I.
i . . . I0 I I. . . . (NMC Fleet Relief Request) - (Approved October.6, 2004) -
*1.5-1 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Requests for Relief (cont'd) Relief Request No. Description Rev. 11 Use of N-661 0 (NMC Fleet Relief Request) (Proposed, submitted July 28, 2004, not yet approved for use)
- Relief No. 1 was approved for the 4th ISI Interval for implementation on the start date of the 4th ISI Interval.
- Relief No. 2 was approved during the 3 rd ISI Interval and is approved for the remaining time in the current operating license, including the 4th ISI Interval.
It has been revised slightly to correct a weldname nomenclature error and I update commitment statements made in Rev. 0. 1.5-2 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY . INSERVICE INSPECTION MONTICELLO 4th INTERVAL 'v' '-"EXAMINATION PLAN
' Monticello Unit 1 - ISI Relief Request No. I (Rev. 0)
R o.s Ine. .Pla Risk Informed Inservice Inspection Plan System: Various Class: I and 2 Category: B-F Item: ALL B-J .- ;il-
'- 1 _ ALL C-F-1 ALL C-F-2 ALL Alternative Examination Requirements: I!. 'l Monticello has implemented Risk Informed Inservice Inspection program for Class 1 and Class 2 piping welds in accordance with EPRI Topical Report TR-1 12657 Rev. B-A, Final Report, December, 1999.
Basis for Relief: See attached Risk Informed Program Plan Submittal Rev. 0. Status: Approved July 24, 2002. NRC Letter, "Monticello Nuclear Generating Plant-Risk-Informed Inservice Inspection Program (TAC MB3819)"
,i1.5-3 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN RISK-INFORMED INSERVICE INSPECTION PROGRAM PLAN MONTICELLO NUCLEAR GENERATING PLANT - REVISION 0 Table of Contents
- 1. Introduction 1.1 Relation to NRC Regulatory Guides 1.174 and 1.178 1.2 PSA Quality
- 2. Proposed Alternative to Current Inservice Inspection Programs 2.1 ASME Section XI 2.2 Augmented Programs
- 3. Risk-informed ISI Process 3.1 Scope of Program 3.2 Consequence Evaluation 3.3 Failure Potential Assessment 3.4 Risk Characterization 3.5 Element and NDE Selection 3.5.1 Additional Examinations 3.5.2 Program Relief Requests 3.6 Risk Impact Assessment 3.6.1 Quantitative Analysis 3.6.2 Defense-in-Depth
- 4. Implementation and Monitoring Program
- 5. Proposed ISI Program Plan Change
- 6. References/Documentation 1.5-4 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY . INSERVICE INSPECTION MONTICELLO 4th INTERVAL in1U': EXAMINATION PLAN
- 1. INTRODUCTION The Monticello Nuclear Generating Plant (MNGP) is nearing the end of its 3rd Inservice Inspection (ISI) Interval as defined by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Section Xl Code for Inspection Program B. MNGP plans to implement a Risk-Informed'Inservice Inspection (RI-ISI) Program concurrent with the start of the 4th ISI interval, which will begin on June 1, 2002. Pursuant to 10 CFR 50.55a(g)(4)(ii), the applicable ASME Section Xl Code for the 4th ISI interval will be the 1995 Edition through 1996 Addenda. -
The objective of this submittal is to request the use of a risk-informed process for the inservice inspection of Class 1 and 2 piping. The risk-informed inservice inspection (RI-ISI) process used in this submittal is described in Electric Power Research Institute (EPRI) Topical Report (TR) 112657 Rev. B-A "Revised Risk-Informed Inservice Inspection Evaluation Procedure." The RI-ISI application was also conducted in a manner consistent with ASME Code Case N-578 "Risk-Informed Requirements for:Class 1, 2, and 3 Piping,-Method B." 1.1 Relation to NRC Regulatory Guides 1.174 and 1.178 As a risk-informed application, this submittal meets the intent and principles of Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-informed Decisions On Plant-Specific Changes to the Licensing Basis" and Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-informed Decisionmaking Inservice Inspection of Piping." Further information is provided in Section 3.6.2 relative to defense-in-depth. - 1.2 PSA Quality The Monticello Level 1 and Level 2 Probabilistic Safety Assessment (PSA) results that are based on the January .1999 update were used to evaluate the consequences of pipe ruptures for the RI-ISI assessment during power operation. The base PSA Core Damage Frequency (CDF) is 1.5E-5 events per year and the base PSA Large Early Release Frequency (LERF) is 5.5E-7 events per year for the 1999 update. The
--original IPE result was a CDF of 2.6E-5, -which was reported to the NRC in 1992. The PSA model update history is discussed below.
.1.5-5 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN The NRC review of the Monticello Individual Plant Examination (IPE) was issued in May 1994. The Staff Evaluation Report (SER) concluded the following regarding the Monticello IPE:
- The IPE is complete with respect to the information requested in Generic Letter 88-20 and associated Supplement 1;
- The IPE analytical approach is technically sound and capable of identifying plant-specific vulnerabilities;
- Monticello employed a viable means to verify that the IPE models reflect the current plant design and operation at the time of submittal to the NRC;
- The IPE had been peer-reviewed;
- Monticello participated in the IPE process;
- The IPE specifically evaluated the Monticello decay heat removal functions for vulnerabilities;
- Monticello had responded appropriately to the Containment Performance Improvement program recommendations.
There were no areas of improvement to the PSA model that were identified by the NRC in their review of the plant's IPE submittal. The internal events PSA used for the RI-ISI evaluation is based on a more current version of the PSA than the version used for the IPE. The PSA model was updated in 1994, 1995 and 1999. The major differences in the PSA model between the original IPE and the PSA updates through the 1995 update are that the updated model includes the following:
- Addition of a non-safety 480kv diesel generator that can backfeed through emergency bus 15 to supply battery charges;
- Installation of a hard piped vent that provides an additional means for containment heat removal; 1.5-6 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY ' INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' EXAMINATION PLAN
- Improvements to safety relief valve pneumatics (including power supplies);
- Addition of a crosstie for alignment of the diesel fire pump as an additional source of low pressure makeup water;
- Replacement of an instrument air compressor with one that is not dependent on service water;
. More realistic success criteria for service water by changing from 2 of 3 pumps required for success to 1 of 3 pumps required for success;
- Internal floods initiating event frequency and effects were updated.
The 1999 PSA update was performed to incorporate the effects of power
-uprate conditions. -
- .... .. ;: I - -; ;
In 1997, a BWROG PSA Peer Certification Review'was performed on the 1995 update PSA 'model. The overall conclusion was positive and said
-that the Monticello PSA can be effectively used to support applications involving'relative risk significance. The "Facts and Observations" for Monticello have been evaluated, and are being addressed by the Monticello PSA Program. No substantial'changes to the RI-ISI consequence conclusions are anticipated due to planned PSA model revisions to address these "Facts and Observations."
.2. -PROPOSED ALTERNATIVE TO CURRENT ISI PROGRAM REQUIREMENTS 2.1 ASME Section Xl , ASME Section XI Examination Categories B-F, B-J, C-F-I and C-F-2 currently contain the requirements for the nondestructive examination
'(NDE)'of Class 1 and 2 piping components' The alternative RI-ISI
-: ' :program for'piping is described in EPRI TR- 12657. The RI-ISI program will be substituted for the-current program for Class 1 and 2 piping (Examination Categories B-F, B-J,' C-F-1 and C-F-2) in accordance with 10 CFR'50.55a(a)(3)(i) by alternatively providing an acceptable level of quality and safety. Other non-related portions of the ASME Section Xl Code will be unaffected. EPRI TR-1 12657 provides the requirements for
'1.5-7 Revision 3 3110/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN defining the relationship between the RI-ISI program and the remaining unaffected portions of ASME Section Xi. 2.2 Augmented Programs The following augmented inspection programs were considered during the RI-ISI application:
- The augmented inspection program for flow accelerated corrosion (FAC) per Generic Letter 89-08 is relied upon to manage this damage mechanism but is not otherwise affected or changed by the RI-ISI program.
- The augmented inspection program for intergranular stress corrosion cracking (IGSCC) as addressed in NRC Generic Letter 88-01 and NUREG-0313, Rev. 2, have been resolved by Monticello's pipe replacement program wherein all susceptible material was replaced with resistant material. All welds are therefore classified as IGSCC Category "A". In accordance with EPRI TR-1 12657, piping welds identified as Category "A" are considered resistant to IGSCC, and as such are assigned a low failure potential provided no other damage mechanisms are present. Examination criteria for these welds will be in accordance with the RI-ISI process.
- The augmented inspection program for High Energy Line Break (HELB) piping includes 36 Class 1 welds that are classified as ASME Section Xi, Examination Category B-J. Although MNGP is not committed to using the NUREG-0800 Standard Review Plan (SRP),
Sections 3.6.1 and 3.6.2 of the SRP are used as guidance in determining appropriate design and examination requirements for specified high energy piping. The 36 Class 1 welds that require examination in accordance with the HELB augmented inspection program are between the containment penetration and the outboard isolation valve in the main steam, high pressure coolant injection, reactor core isolation cooling, reactor water clean-up, residual heat removal and core spray systems. Independent of the HELB program, the RI-ISI application selected 8 of these 36 HELB welds for examination. The remaining 28 HELB welds will continue to be examined in accordance with the HELB augmented inspection program. 1.5-8 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY, :': - ' INSERVICE INSPECTION MONTICELLO 4th INTERVAL 'iv. "EXAMINATION PLAN
- 3. RISK-INFORMED ISI PROCESS --11;-- - I The process used to develop the RI-ISI program conformed to the methodology described in EPRI TR-112657 and consisted of the following steps: -
- ' Scope Definition
- Consequence Evaluation
- ' Failure Potential Assessment
- Risk Characterization
- Element and NDE Selection
- Risk Impact Assessment
- -Implementation Program
- -Feedback Loop A deviation to the EPRI RI-ISI methodology has been implemented in the failure potential assessment for MNGP. Table 3-16 of EPRI TR-1 12657 contains criteria for assessing the potential for thermal stratification, cycling and striping (TASCS). Key attributes for horizontal or slightly sloped piping greater than 1' nominal pipe size (NPS) include:
1.. . Potential exists for, low flow in a pipe section connected to a' component allowing mixing of hot and cold fluids, or-
- 2. Potential exists for leakage flow past a valve, including in-leakage, out-leakage and cross-leakage allowing mixing of hot and cold fluids, or
- 3. Potential'exists for convective heating in dead-ended pipe sections connected to a source of hot fluid, or 4.': Potential exists for two phase'(steamlwater) flow, or 5. Potential'exists for turbulent penetration into a relatively colder branch pipe connected to header piping containing hotffluid with turbulent flow, AND
- .AT> 501F, ; .. . . . . . -. . :
* , i :. :. .. i: : .
AND .. .. , . . . , , ., , . . . ^ Richardson Number > 4 (this value predicts the potential buoyancy of a
- stratifiedflow) , . . ..
. or
. . ., ... .. r 1.5-9 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN These criteria, based on meeting a high cycle fatigue endurance limit with the actual AT assumed equal to the greatest potential AT for the transient, will identify all locations where stratification is likely to occur, but allows for no assessment of severity. As such, many locations will be identified as subject to TASCS where no significant potential for thermal fatigue exists. The critical attribute missing from the existing methodology that would allow consideration of fatigue severity is a criterion that addresses the potential for fluid cycling. The impact of this additional consideration on the existing TASCS susceptibility criteria is presented below. Turbulent penetration TASCS Turbulent penetration typically occurs in lines connected to piping containing hot flowing fluid. In the case of downward sloping lines that then turn horizontal, significant top-to-bottom cyclic ATs can develop in the horizontal sections if the horizontal section is less than about 25 pipe diameters from the reactor coolant piping. Therefore, TASCS is considered for this configuration. For upward sloping branch lines connected to the hot fluid source that turn horizontal or in horizontal branch lines, natural convective effects combined with effects of turbulence penetration will keep the line filled with hot water. If there is no potential for in-leakage towards the hot fluid source from the outboard end of the line, this will result in a well-mixed fluid condition where significant top-to-bottom ATs will not occur. Therefore TASCS is not considered for these configurations. Even in fairly long lines, where some heat loss from the outside of the piping will tend to occur and some fluid stratification may be present, there is no significant potential for cycling as has been observed for the in-leakage case. The effect of TASCS will not be significant under these conditions and can be neglected. Low flow TASCS In some situations, the transient startup of a system (e.g., RHR suction piping) creates the potential for fluid stratification as flow is established. In cases where no cold fluid source exists, the hot flowing fluid will fairly rapidly displace the cold fluid in stagnant lines, while fluid mixing will occur in the piping further removed from the hot source and stratified conditions will exist only briefly as the line fills with hot fluid. As such, since the situation is transient in nature, it can be assumed that the criteria for thermal transients (TT) will govern. 1.5-10 Revision 3 3/10/2005
-NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO4th'INTERVAL 2 EXAMINATION PLAN Valve leakage TASCS Sometimes a very small leakage flow of hot water can occur outward past a valve into a line that is relatively colder, creating a significant temperature-difference. However,.since this is a generally a "steady-state" phenomenon with no potential for cyclic temperature changes, the effect of TASCS is not significant and can be neglected. Convection heating TASCS
-Similarly, there sometimes exists the potential for heat transfer across a valve'to an isolated section beyond the valve, resulting in fluid
- stratification due to natural convection. However, since there is no potential for'cyclic temperature changes in this case, the effect of TASCS is not significant and can be neglected.-
In summary, these additional considerations for determining the potential for thermal fatigue as a result of the effects of TASCS provide an allowance for the consideration of cycle severity in assessing the potential for TASCS effects. The above criteria has previously been submitted by EPRI for generic approval (Letter dated February 28, 2001, P.J. O'Regan (EPRI) to Dr. B. Sheron (USNRC), "Extension of Risk-informed Inservice Inspection Methodology"). 3.1 Scope of Program 2 :-- The systems included in the RI-ISI program are provided in Table 3.1. The piping and instrumentation'diagrams and additional plant information including the existing plant ISI program, were used to define the Class 1 and 2 piping system boundaries'.-- - 3.2 Consequence Evaluation -: The consequence(s) of pressure boundary failures were evaluated and ranked based on their impact on core damage and containment performance (i.e., isolation,-'bypass and large early release). The impact on these measures due to both direct and indirect effects was considered using the guidance provided in EPRI TR-1 12657. 3.3 Failure Potential Assessment Failure potential estimates were generated utilizing industry failure history, plant specific failure history, and other relevant information.
- 1.5-11 Revisionr 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN These failure estimates were determined using the guidance provided in EPRI TR-1 12657, with the exception of the previously stated deviation. Table 3.3 summarizes the failure potential assessment by system for each degradation mechanism that was identified as potentially operative. 3.4 Risk Characterization In the preceding steps, each run of piping within the scope of the program was evaluated to determine its impact on core damage and containment performance (i.e., isolation, bypass and large, early release) as well as its potential for failure. Given the results of these steps, piping segments are then defined as continuous runs of piping potentially susceptible to the same type(s) of degradation and whose failure will result in similar consequence(s). Segments are then ranked based upon their risk significance as defined in EPRI TR-1 12657. The results of these calculations are presented in Table 3.4. 3.5 Element and NDE Selection In general, EPRI TR-1 12657 requires that 25% of the locations in the high risk region and 10% of the locations in the medium risk region be selected for inspection using appropriate NDE methods tailored to the applicable degradation mechanism. In addition, per Section 3.6.4.2 of EPRI TR-112657, if the percentage of Class 1 piping locations selected for examination falls substantially below 10%, then the basis for selection needs to be investigated. For MNGP, the percentage of Class 1 welds selected per the RI-ISI process is 9.3% (76 of 817 welds), which is not a significant departure from 10%. One additional factor that was considered during the evaluation was that the overall percentage of Class 1 selections included both socket and non-socket welds. Therefore, the percentage of Class 1 selections was 9.3% when both socket and non-socket piping welds were considered. This percentage increases to 13.2% (75 of 567 welds) when considering only those piping welds that are non-socket welded. It should be noted that non-socket welds are subject to volumetric examination, so this percentage does not rely upon welds that are solely subject to a VT-2 visual examination. As stated in TR-1 12657, the existing FAC augmented inspection program provides the means to effectively manage this mechanism. No additional 1.5-12 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY ' .: . INSERVICE INSPECTION MONTICELLO 4th INTERVAL '"-EXAMINATION
-. PLAN credit was taken for any FAC augmented inspection program locations beyond those selected by the RI-ISI process to meet the sampling percentage requirements.
A brief summary is provided below, and the results of the selection are presented in Table 3.5. Section 4 of EPRI TR-1 12657 was used as guidance in determining the examination requirements for these locations. Class I Piping Welds{1)l Class 2 Piping Welds( 21 l All Piping Welds3) l l Total I Selected Total I Selected' Total Selected 1 - .: 817 l . 76 I- 901-. l . - 12 . 1718 l 88 Notes
- 1. Includes all Category B-F and B-J locations.
- 2. Includes all Category C-F-1 and C-F-2 locations.
3.' All in-scope piping components, regardless of risk classification, will continue to receive Code required pressure testing, as part of the current ASME Section Xl program. VT-2 visual examinations are scheduled in accordance with the station's pressure test program that remains unaffected by the RI-ISI program. 3.5.1 Additional Examinations The RI-ISI program in all cases will determine through an
' engineering evaluation the root cause of any unacceptable flaw or relevant'6ondition found during examination. The evaluation will include the applicable service conditions and degradation mechanisms to establish that the element(s) Will still perform their intended safety function during' subsequent operation. Elements not meeting this requirement will be repaired or replaced.
The evaluation will include whether other elements in the segment or additional segments are subject to the same root cause conditions. -Additional examinations will be performed on those elements' with the same'root cause conditions or degradation mechanisms. 'The additional examinations will include high risk significant elements and medium risk significant elements, if needed, up to a number equivalent to the number of elements required to be inspected on the segment or segments during the current outage. If unacceptable flaws or relevant conditions are again found similar to the initial problem, the remaining elements identified as susceptible will be examined. No additional 1.5-13 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN examinations will be performed if there are no additional elements identified as being susceptible to the same root cause conditions. 3.5.2 Program Relief Requests An attempt has been made to select RI-ISI locations for examination such that a minimum of >90% coverage (i.e., Code Case N-460 criteria) is attainable. However, some limitations will not be known until the examination is performed, since some locations may be examined for the first time by the specified techniques. In instances where locations are found at the time of the examination that do not meet the >90% coverage requirement, the process outlined in EPRI TR-1 12657 will be followed. None of the existing MNGP relief requests are being withdrawn due to the RI-ISI application. 3.6 Risk Impact Assessment The RI-ISI program has been conducted in accordance with Regulatory Guide 1.174 and the requirements of EPRI TR-112657, and the risk from implementation of this program is expected to remain neutral or decrease when compared to that estimated from current requirements. This evaluation identified the allocation of segments into High, Medium, and Low risk regions of the EPRI TR-1 12657 and ASME Code Case N-578 risk ranking matrix, and then determined for each of these risk classes what inspection changes are proposed for each of the locations in each segment. The changes include changing the number and location of inspections within the segment and in many cases improving the effectiveness of the inspection to account for the findings of the RI-ISI degradation mechanism assessment. For example, for locations subject to thermal fatigue, examinations will be conducted on an expanded volume and will be focused to enhance the probability of detection (POD) during the inspection process. 3.6.1 Quantitative Analysis Limits are imposed by the EPRI methodology to ensure that the change in risk of implementing the RI-ISI program meets the 1.5-14 Revision 3 3/10/2005
' NUCLEAR MANAGEMENT COMPANY ;1 --".~INSERVICE
- INSPECTION MONTICELLO 4th INTERVAL ' -'EXAMINATION PLAN requirements of Regulatory Guides 1.174 and 1.178. The EPRI criterion requires that the cumulative change in core damage frequency (CDF) and large early release frequency (LERF) be less than 1E-07 and 1E-08 per year.persystem, respectively.
Monticello conducted a risk impact analysis per the requirements of Section 3.7 of EPRI TR-1 12657. The analysis estimates the net change in risk due to the positive and negative influence of adding and removing locations from the inspection program. A risk quantification was performed using the 'Simplified Risk Quantification Method" described in Section 3.7 of EPRI TR-112657. The conditional core damage probability (CCDP) and conditional large early release probability (CLERP) used for high consequence category segments was based on the highest evaluated CCDP (9E-03) and CLERP (9E-03),'whereas, for medium consequence category segments, bounding estimates of CCDP (1E-04) and CLERP (1E-05) were used. The likelihood of pressure boundary failure (PBF)yisdetermined by the presence of ' different degradation mechanisms and the rank is based on the relative failure probability. 'The basic likelihood of PBF for a piping location with no degradation mechanism present is given as x0 and is expected to have a value less than 1E-08. Piping locations identified as medium failure potential have a likelihood of 20xo. In
'addition, the analysis was performited both with and without taking credit for enhanced inspection effectiveness'due to an increased POD from application of the RI-ISI approach. The PBF likelihoods
*and POD values used in the analysis are consistent with those used in the approved RI-ISI pilot' applications at Arkansas Nuclear' One, Unit 2, and Vermont Yankee,"as documented in References 9 and 14 of EPRI TR-112657.
Table 3.6-1 presents a summary of the RI-ISI program versus ASME Section Xl Code requirements and identifies on a per system basis each applicable risk category. The presence of FAC was adjusted for in the performance of the quantitative analysis by excluding its impact on the risk ranking. However, in an effort to be as informative as possible, for those systems where FAC is present, Table 3.6-1 presents the information in such a manner as to depict what the resultant risk categorization is both with and without consideration of FAC. This is accomplished by enclosing the FAC damage mechanism, as well as all other resultant corresponding changes (failure potential rank, risk category and risk rank), in parenthesis. Again, this has only been done for information purposes, and has no impact on the assessment itself. s.1.5-15 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN The use of this approach to depict the impact of degradation mechanisms managed by augmented inspection programs on the risk categorization is consistent with that used in the delta risk assessment for the Arkansas Nuclear One, Unit 2 pilot application. An example is provided below. System Risk Consequence Failure Potential Category Rank' ank DMs Rank In this example if FAC is not considered, the failure potential rank is 'medium' instead of 'high' based on the TASCS and TT damage mechanisms. When a 'medium' failure potential rank is combined with a 'medium' consequence rank, it results in risk category 5 ('medium- risk) being assigned instead of risk cateaory 3 (Vhiah" risk). FW 5 (3) Medium (High) Medium TAScS, (FAC) : Medium (High) In this example if FAC were considered, the failure potential rank would be 'high" instead of 'medium'. If a 'high' failure potential rank were combined with a 'medium' consequence rank, it would result in risk category 3 ('high' risk) being assigned instead of risk category 5 ('medium' risk). Note
- 1. The risk rank is not included in Table 3.6-1 but it is included in Table 5-2.
1.5-16 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY. . ' ', ..INSERVICE INSPECTION MONTICELLO 4th INTERVAL I.-'EXAMINATION PLAN As indicated in the table below, this evaluation has demonstrated
-that unacceptable risk impacts will not occur.from implementation
'of the RI-ISIlprogram, and satisfies the acceptance criteria of
-Regulatory Guide 1.174 and EPRI TR-112657.
Risk Impact Results SysternWl *. : , II DF *-ARiskLERF w/ POD w/ wlo POD. . wl POD w/o POD RPV 9.OOE-1 I 9.00E-1 1 9.00E-11 9.00E-11 RWCU 4.50E-11 .. 4.50E-11 .4.50E-11 4.50E-11 MS 9.90E-10 9.90E-10 . 9.90E-10 9.90E-10 SLC -4.50E-11 -4.50E-11 -4.50E-11 -4.50E-11 RCR .. 6.98E-09 . 6.98E-09 6.98E-09 . 6.98E-09 RCIC -1.38E-10 . -1.10E-10 -9.48E-11 -9.20E-11 RHR -9.71 E-09 -2.13E-09 - 9.72E-09 -2.16E-09 cs .1.22E-09, 1.22E-09 -. 1.22E-09 1.22E-09 HPCI . -6.15E-10 . 2.69E-09 -5.88E-10. 2.66E-09 FW '-6.20E-09 'i 3.90E-09 : -6.17E-09. . 3.91E-09 CCW negligible - negligible , negligible negligible
'CRD negligible'- ' negligible negligible negligible FPEC '-no'change no change no change no change PCAC negligible negligible negligible negligible Torus negligible negligible negligible negligible Total . -7.40E-09 .1.36E-08 . -7.30E-09 1.36E-08
,.Note . '-;. 1N' Sostems are described in Table 3.1.
., I- -I - ,
- , 4 1-i . . r .
1.5-17 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN 3.6.2 Defense-in-Depth The intent of the inspections mandated by ASME Section Xl for piping welds is to identify conditions such as flaws or indications that may be precursors to leaks or ruptures in a system's pressure boundary. Currently, the process for picking inspection locations is based upon structural discontinuity and stress analysis results. As depicted in ASME White Paper 92-01-01 Rev. 1, "Evaluation of Inservice Inspection Requirements for Class 1, Category B-J Pressure Retaining Welds," this method has been ineffective in identifying leaks or failures. EPRI TR-112657 and Code Case N-578 provide a more robust selection process founded on actual service experience with nuclear plant piping failure data. This process has two key independent ingredients, that is, a determination of each location's susceptibility to degradation and secondly, an independent assessment of the consequence of the piping failure. These two ingredients assure defense in depth is maintained. First, by evaluating a location's susceptibility to degradation, the likelihood of finding flaws or indications that may be precursors to leak or ruptures is increased. Secondly, the consequence assessment effort has a single failure criterion. As such, no matter how unlikely a failure scenario is, it is ranked High in the consequence assessment, and at worst Medium in the risk assessment (i.e., Risk Category 4), if as a result of the failure there is no mitigative equipment available to respond to the event. In addition, the consequence assessment takes into account equipment reliability, and less credit is given to less reliable equipment. All locations within the Class 1 and 2 pressure boundaries will continue to receive a system pressure test and visual VT-2 examination as currently required by the Code regardless of its risk classification.
- 4. IMPLEMENTATION AND MONITORING PROGRAM Upon approval of the RI-ISI program, procedures that comply with the guidelines described in EPRI TR-1 12657 will be prepared to implement and monitor the program. The new program will be integrated into the 4th Inservice Inspection Interval. No changes to the Technical Specifications or Updated Final Safety Analysis Report are necessary for program implementation.
1.5-18 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY ". .-AdI NSERVICE INSPECTION MONTICELLO 4th INTERVAL '" t'[ -EXAMINATION PLAN The applicable aspects of the ASME Code not affected by this change will be retained, such as inspection methods, acceptance guidelines, pressure testing, corrective measures, documentation requirements, and quality control requirements. Existing ASME Section Xl program-implementing procedureswill be retained and modified to address the RI-ISI process, as appropriate. The monitoring and corrective action program will contain the following elements: A. Identify J,. B. Characterize C. (1) Evaluate, determine the cause and extent of the condition identified (2) Evaluate, develop a corrective action plan or plans D. Decide ' : - E. Implement F. Monitor .- _ e . -- G. Trend The'RI-ISI program is a living program requiring'feedback of new relevant information to ensure the appropriate identification of high safety significant piping locations. As a minimum, risk ranking of piping segments will be reviewed --and adjusted'on an ASME period basis. In addition, significant changes may require more frequent adjustment as directed by NRC Bulletin or Generic Letter requirements, or by industry and plant specific feedback: S. PROPOSED ISI PROGRAM PLAN CHANGE A comparison between the RI-ISI program and ASME Section Xl Code 1986 Edition program requirements for in-scope piping is provided in Tables 5-1 and 5-2. (Since no examination selections had been made for the 4th interval ISI Program prior to the development on the RI-ISI Program, the 3rd Interval selections were used for comparison purposds. 'The Code of record for the 3rd Interval was'the 1986 Edition of ASME Section Xl.) Table 5-1 provides a summary comparison by risk region;' Table 5-2 provides the same comparison information, but in a more detailed manner by risk category, similar to the format used in Table 3.6-1.-' - ; MNGP is implementing the RI-IS I program at the start of the 1st 'period of its 4th Inspection Interval. As such, 100% of the required RI-ISI program inspections will be completed in the 4th interval. Examinations shall be performed during the
-- 1.5-19 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN interval such that the period examination percentage requirements of ASME Section Xl, paragraphs IWB-2412 and IWC-2412 are met.
- 6. REFERENCES/DOCUMENTATION EPRI TR-1 12657, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," Rev. B-A ASME Code Case N-578, "Risk-informed Requirements for Class 1, 2, and 3 Piping, Method B, Section Xl, Division 1" Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-informed Decisions On Plant-Specific Changes to the Licensing Basis" Regulatory Guide 1.178, "An Approach for Plant-Specific Risk Informed Decisionmaking Inservice Inspection of Piping" Supporting Onsite Documentation Structural Integrity Calculation/File No. NMC-01-301, "Degradation Mechanism Evaluation for Class 1 and 2 Piping Welds at Monticello Nuclear Generating Plant," Revision 1 Structural Integrity Calculation/File No. NMC-01-302, "Risk-Informed Inservice Inspection Consequence Evaluation of Class 1 and 2 Piping for Monticello Nuclear Power Plant," Revision 1 Structural Integrity Calculation/File No. NMC-01-303, "Risk Ranking Summary, Matrix and Report for the Monticello Nuclear Generating Plant," Revision 0 Structural Integrity Calculation/File No. NMC-01 -304, "Risk Impact Analysis for the Monticello Nuclear Generating Plant," Revision 1 Structural Integrity File No. NMC-01-103-4, Record of Conversation No. ROC-002, "Minutes of the Element Selection Meeting for the Risk-informed ISI Project at the Monticello Nuclear Generating Plant," Revision 1, June 21, 2001 MNGP Calculation/File No. CA-01-216, "Monticello Nuclear Generating Plant, Risk-informed Service History Report for Class I and 11Piping Welds, ASME Categories B-F, B-J, C-F-1 and C-F-2," Revision 0 1.5-20 Revision 3 3/10/2005
(c lC C NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
; : ': -Table 3.1
... ; *.. ;System Selection and Segment / Element Definition
-. System Description - - -- -- - Number of Segments Number of Elements RPV-ReactorPressureVessel . - - 19 - 112 RWCU -ReactorWaterClean-Up - - --.- - - 7- - 10 - 85-MS - Main Steam --- .. , ..
- l - - --204 -
SLC-Standby Liquid Control -- -. 3 35 - RCR - Reactor Coolant Recirculation - ..22 - ~ 135 RCIC- Reactor Core Isolation Cooling, -13 - - RHR-Residual Heat Removal - -- - 97 - 476 CS - Core Spray. . .. 36 . . 191 HPCI - High Pressure Coolant Injection 20 . -- .-158 FW- Feedwater - - - -. . . ....-- -37 78 CCW- ComponentCooling Water -----. - ----------- ---- ------ - - --- I I . I CRD - Control Rod Drive.--.. . .. .... o.*. 41 FPEC -Fuel Pool Emergency Cooling . ... . . .. 54 PCAC - Primary Containment and Atmospheric Control .. . . . 8 .- .. 47 Torus-Torus Hard Vent . 1 19 Totals 307 1718 NT . . .. w. s n p o R l . INOTE: TABLE 3.2 was not part of.:.the Risk-informed ISI Program submittal and is intentionally excluded
.. ~~~~~ - ..
from this document. I F.. 1.5-21 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 3.3 Failure Potential Assessment Summary 1 Localized Corrosion Flow Sensitive SystemI Thermal Fatigue Stress Corrosion Cracking TASCS TT IGSCC TGSCC ECSCC PWSCC MIC PIT CC E-C FAC RPV RWCU . . Ms x SLC ._X RCR X RCIC X X RHR X X HPCI X X X X CCW__ CRD . . . - FP E C__ _ _ ___ _ _ _ PCAC . _ Torus Note
- 1. Systems are described in Table 3.1.
I r- ` RF 1ion 3 3 2005
C :C C NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 3.4 Number of Segments by Risk Category With and Without Impact of FAC High Risk Region Medium Risk Region Low Risk Region Category 2 Category 3 Category 4 Category 5 Category 6 Category 7 System"') Category I Without With Without With Without With Without With Without With Without With Withuut With 6 6 10 10 3 3 RPV 9 9 1 1 RWCU 5 7 14 14 1 1 MS 2(2) 0 SLC 1 1 2 2 10 10 10 10 2 2 RCR 3(3) 0 2 2 3 6 3 3 2 2 RCIC 3 3 15(4) 0 13 13 5(5) 2 44 59 17 20 RHR 2 2 IN' 0 4 4 4(7) 0 6 7 19 23 CS 2 2 4 4 3 3 11 11 HPCI 21 - 2(90 6 13 1 3 - FW 14(8) 0 14
- * . . ._._.__2_ 2-CCW .
2 2 5 5 CRD . . 10 10 FPEC 8 8 PCAC 1 1 Torus 31 38 21 0 60 69 16 14 111 127 52 59 Total 16 0 Notes
- 1. Systems are described in Table 3.1.
- 2. These two segments become Category 4 after FAC is removed from consideration due to no other damage mechanisms being present.
damage mechanisms.
- 3. These three segments become Category 5 after FAC is removed from consideration due to the presence of other medium failure potential
- 4. These fifteen segments become Category 6 after FAC is removed from consideration due to no other damage mechanisms being present.
1.5-23 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Notes for Table 3.4 (cont'd)
- 5. Of these five segments, three segments become Category 7 after FAC is removed due to no other damage mechanisms being present.
- 6. This one segment becomes Category 6 after FAC is removed due to no other damage mechanisms being present.
- 7. These four segments become Category 7 after FAC is removed due to no other damage mechanisms being present.
- 8. Of these fourteen segments, seven segments become Category 2 after FAC is removed due to the presence of other medium' failure potential damage mechanisms, and seven segments become Category 4 after FAC is removed due to no other damage mechanisms being present.
- 9. These two segments become Category 5 after FAC is removed due to no other damage mechanisms being present.
1( `4 R' 20ion 3 3; 2005
(7 C C, NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Tbe3.5 ..
-. Numiber of Elements Selected for Inspection by Risk Gate gory Excluding Impact of FAG -
* - .High Risk Region' Medium Risk Region -Low Risk Region System1 Category I Ctegory 2Category 3 Category 4 Categor-5'.-'- Categbry 8 - , Category7
*Total Selected .Total Selected .- otal § elected Total Selected Total I Selected Total Selected _TotalI Selected
.RPV- - - 2 383_ 0 8' 0 RWCU 84 .9 .1 0 Ms - 105 ()95 0 4- 0 SLC-_ _ _ _ 8 A1 27- 0 _ _ _
RCR, 10 3 113 12 1 RCIC __ ___ 12- 2, 28 3 12 0, 13 - 0. RHR -- 31 8 ~67- 7- 10 1. 269,. 0 99 0
-Cs.. 2- 1 20" ~- -35 0 14 0 HPCI 8 2 2 -3'-' 33 4 -90 - __
FW 36 138 4() 4 2-CCW_ _ _ _ __ _ _1 -0 - _ _ 10 0 31 0 CRID _ _ _ _ _ __ _ __ FPEC _ _ _ __ _ _ _ _ _ __54 0 PCAC ,.47 0 Torus 19 0 Total 87 24 495 54 75 10 741 0 320 0 Notes
- 1. Systemnsare describedin Table 3.1.
2:' 'One of these eleven welds was selected for examination by both the FAC and RI-ISI Programs. Since FAC was the only damage mechanism identified for this weld, the FAC examination will be credited toward both programs.
- 3. Two of these four welds were selected for examination by both the FAC and RI-ISI Programs. Since FAC was the only damage mechanism Identified for these welds, the'I FAC examinations will be credited toward both programs.
1.5-25 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 3.6-1 Risk Impact Analysis Results Systemil Category Consequence Failure Potential 12 Inspections 133 CDF Impact( 4) LERF IMpacte 4 l Rank DMs Rank Section X1 ) R-IS1 ) Delta w/ POD w/o POD w/ POD w/o POD RPV 4 High None Low 5 3 -2 9.00E-1 1 9.00E-1 1 9.00E-1 1 9.00E-1 1 RPV 6 Medium None Low 4 0 -4 negligible negligible negligible negligible RPV 7 Low None Low 2 0 -2 negligible negligible negligible negligible RPV Total 9.OOE-11 9.OOE-11 9.00E-11 9.00E-11 RWCU 4 High None Low 10 9 -1 4.50E-11 4.50E-11 4.50E-11 4.50E-11 RWCU 7 Low None Low 0 0 0 no change no change no change no change RWCU Total 4.50E-11 4.50E-11 4.50E-11 4.50E-11 MS 4(1) High None(FAC) Low (High) 2 0 -2 9.OOE-11 9.OOE-11 9.OOE-11 9.OOE-11 MS 4 High None Low 30 10 -20 9.OOE-10 9.OOE-10 9.00E-10 9.00E-10 MS 6 Medium None Low 21 0 -21 negligible negligible negligible negligible MS 7 Low None Low 0 0 0 no change no change no change no change MS Total _ 9.90E-10 9.90E-10 9.90E-10 9.90E-10 SLC 4 High None Low 0 1 1 -4.50E-11 -4.50E-1 1 -4.50E-1 1 -4.50E-1 1 SLC 6 Medium None Low 0 0 0 no change no change no change no change SLC Total -4.50E-1 I -4.50E-11 -4.50E-11 -4.60E-11 RCR 2 High CC Medium 10 3 -7 6.30E-09 6.30E-09 6.30E-09 6.30E-09 RCR 4 High None Low 27 12 -15 6.75E-10 6.75E-10 6.75E-10 6.75E-10 RCR 7 Low None Low 0 0 0 no change no change no change no change RCR Total I 6.98E-09 6.98E-09 6.98E-09 6.98E-09
'6 -?
iof 3 1, 12005
C C- -C NUCLEAR MANAGEMENT COMPANY I: INSERVICE INSPECTION MONTICELLO 4th INTERVAL i EXAMINATION PLAN Risk Table 3.6-1 , < .- * -
.,,. .. Risk.Impact Analysis Results ---
~ctgr~
Sytm ConsqeneFailure Potential- Inspections, CDF lpc 1
. LERF Impact"41 RakDs ..- '.
-Rank'_.._ Section R-1l . et . wI POD . loOD I POD. -woPD
,RCIC - 4 .High None -Low 0 .2 -2 -9.OOE-11I- *-9.OOE-11 -9.002-11 -9.00E_1-1T RCIC 5() Medium TT, (FAC) *- Medium (Hg)_ 0 .-1.20E-1 1 no change. -1.20E-12. no chanW RCIC 5Medium -TT . .- Medium - 0 2 - 2 -3.60E-1 1 - -2.002-1 1 --3.60E-12 *-2.00E-12 RCIC- 6 - Medium ...None Low 1 .0 -1 negligible negligible negligible negligible RCIC 7 -Low - -None-- . Low .-0 0 0 no change no change no change no change RCIC Total -- 1.38E-10 -1.10E-10 -9.48E-11 -9.20E-11 RHR 2 High UT Medium 5 8 3 -1.03E-08 -2.70E-09 -1.03E-08 --2.70E-09 RHR .4' 'High None,- Low, 19 -7 12 5.40E-10 5.402-10 5.402-10 5.40E-10 RHR 5,' Medium 'TT, Medium 4 - -- 1 3-3 6.002 3.OOE-1 1 6.0012-13 3.OOE-12 RHR - 6 (3) - Medium -None, (FAC)" Low (High) - -S - - 0 5 -negligible negligible -negligible, negligible RHR 6--- Medium --None- Low .~20 0 -- 0 - negligible . -negligible. negligible -- negligible.
RHR 7 (5) Low - None (FAC) Low (High) I 0- -- 1 negligible -negligible negligible. - -negligible RHR 7 Low, None -Low 8 - -0. .- 8 negligible negligible negligible negligible RHR Total . -9.71 E-09 --2.13E-09 -9.72E-09 -2.16E-09 Cs 2 High cc Medium 2 1 -1 9.00E-10 9.002-10 9.OOE 9.002-10 Cs 4 . High None.. Low . 9 2 , -7 3.15E-10 3.15E-1 0 .3.15E-10 3.15E-10 Cs 6 (3) Medium None (FAC) Low (High) 0 .0 0 no change no change no change -no change Cs 6 Medium None .,. Low.. , 6 0 -6 negligible negligible negligible negligible* Cs 7 (5) Low None (FAC) Low (High) 0 0 0 no change no change no change no change Cs 7 Low None Low '18 0 -18 negligible negligible negligible negligible CS Total '1.22E-09 1.22E-09 1.2E0 1.22E-09 r 1.5-27 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 3.6-1 Risk Impact Analysis Results System°l Category Consequence Failure Potential Inspections CDF Impact'4 ' LERF Impact' 4 ' Rank DMs Rank Section Xl'2' RI-ISI1 3' Delta w/ POD wlo POD w/ POD w/o POD HPCI 2 High TT Medium 5 2 -3 -5.402-10 2.70E-09 -5.40E-10 2.70E-09 HPCI 4 High None Low 2 3 1 -4.50E-11 -4.50E-11 -4.50E-11 -4.50E-11 HPCI 5 Medium TT Medium 7 4 -3 -3.00E-11 3.00E-11 -3.00E-12 3.00E-12 HPCI 6 Medium None Low 7 0 -7 negligible negligible negligible negligible HPCI 6 Low TT Medium 1 0 -1 negligible negligible negligible negligible HPCI Total -6.15E-10 2.69E-09 -5.88E-10 2.66E-09 FW 2 (1) High TASCS, TT, (FAC) Medium (High) 0 1 1 -1.62E-09 -9.OOE-10 -1.62E-09 -9.OOE-10 FW 2 (1) High TASCS, (FAC) Medium (High) 4 1 -3 5.40E-10 2.70E-09 5.40E-10 2.70E-09 FW 2 (1) High TT, (FAC) Medium (High) 2 1 -1 -5.40E-10 9.00E-10 -5.40E-10 9.00E-10 FW 2 High TASCS,TT Medium 0 1 1 -1.62E-09 -9.OOE-10 -1.62E-09 -9.OOE-10 FW 2 High TASCS Medium 6 4 -2 -3.24E-09 1.80E-09 -3.24E-09 1.80E-09 FW 2 High TT Medium 0 0 0 no change no change no change no change FW 2 High CC Medium 2 2 0 no change no change no change no change FW 4 (1) High None(FAC) Low (High) 6 0 -6 2.70E-10 2.70E-10 2.70E-10 2.70E-10 FW 4 High None Low 3 2 -1 4.50E-11 4.50E-11 4.50E-11 4.50E-11 FW 5 (3) Medium TASCS, TT, (FAC) Medium (High) 0 1 1 -1.80E-11 -1.00E-11 -1.802-12 -1.00E-12 FW 5 (3) Medium TASCS, (FAC) Medium (High) 0 0 0 no change no change no change no change FW 5 Medium TASCS Medium 0 1 1 -1.80E-11 -1.002-11 -1.80E-12 -1.OOE-12 FW Total -6.20E-09 3.90E-09 -6.17E-09 3.91 E-09 CCW 7 Low None Low 1 0 -1 negligible negligible negligible negligible CCW Total negligible negligible negligible negligible CRD 6 Medium None Low 10 0 -10 negligible negligible negligible negligible CRD 7 Low None Low 21 0 -21 negligible negligible negligible negligible CRD Total negligible negligible negligible negligible 1F I's R -ion 3 3 2005
C :C NUCLEAR MANAGEMENT COMPANY ' --. -INSERVICE INSPECTION. MONTICELLO 4th INTERVAL, --- .- EXAMINATION PLAN
.-...... Table 3.6-1
- . Risk Impact Analysis Results Consequence FiuePtnalinspections .CDF Impact 4') LERF lmpact 4 System1 Category- ____
3 Rn . 'DMs Rn Sectio l2 Rl-lI Delta' wI POD wlo POD -wiPODl' wto POD
,FPEC 1 6_ Medium _.None -. Low 0 _0 01 no change no change no change no chang.-
FPEC Total no change no change no change no change PCAC 6- Medium -None .Low . .4 -0 -4 negligible negligible negligible .negligible PCAC Total I _______ __ _ __ _ _ __ _ _ __ _ _ __.,-_ __ _ _ _ __ _ _ __ _ _negligible negligible. negligible negligible Torus 6 Medium None Low . 1 .0 -'1 negligible negligible negligible negligible Torus Total -negligible negligible negligible negligible Grand Total -- 7.40E-09 1.36E-08 -7.30E-09 1.36E-08 Notes"',.*.. . 1.- - Systems are described In Table 3.1A--...... ....
- 2. Only, those ASME Section Xi Code inspection locations that received a vlMerc exmnto nadtooa7 sufc xmnation were included in the count. "Inspection, locations previously subjected to a surface examination only were not considered In accordance with Section 3.7.1 of EPRI TR-1 12657.
- 3. 'Risk Categiory 4 (1)'inspection'location's'selected for examination' by both the FAC and RI-SI Programs are not incldded in the count since they do not represent a6dditi6'harF examinations. . . ..
- 4. Per Section 3.7.1 of EPRI TR- 112657, the contribution of low risk categories 6 and 7 need not be considered in assessing the change in risk. Hence, the word 'negligible'is given Inthese cases in lieu of values for CODF and LERF Impact, In those cases where no inspections were being performed previously via Section Xi, and none are planned for Ri-SI purposes, 'no change' is listed instead of 'negligible.'
NOTE: TABLE 4 was~not .part of the Risk-Informed ISI Program submittal and is intentionally excluded from this document. 1.5-29 Revision 3 3110/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 5-1 Inspection Location Selection Comparison Between 1986 ASME Section XI Code and EPRI TR-112657 by Risk Region High Risk Region Medium Risk Region Low Risk Region Systern~" Cd ~)18 Weld Code Categor 1986 Section X1l 21 EPRI TR-112657 Weld 12X( 3 1986 Section X 12 EPRI TR-112657 Weld 1986 Section Xi23 EPRI TR-112657 COUnt Vol/Sur Sur Only RI-ISI Other(3) CoUnt VolISur Sur Only RI-lSI Otherj3) COUnt Vol/Sur Sur Only RI-ISI Other,3) RPV B-F _ 5 3 2 1 . 3 1 2 0 B-J 16 2 3 2 88 5 24 0 RWCU B-F 1 1 0 1 _ B-J 83 9 15 8 1 0 0 0 MS B-J 105 32 1 i4) 1 99 21 21 0 SLC B-F . . . 1 0 1 0 B-J 8 0 3 1 26 0 6 0 RCR B-F 10 10 0 3 2 2 0 0 B-J 111 25 5 12 . 12 0 3 0 RCIC B-J . 14 0 5 0 C-F-2 40 1 0 5 11 1 0 0 B-F 1 1 0 0 2 2 0 0 RHR B-J 30 4 0 8 75 21 0 8 7 4 0 0 C-F-2 __361 30 2 0 B-F 2 2 0 1 CS B-J 20 9 0 2 8 2 0 0 C-F-2 = 161 22 0 0 B-F 2 2 0 0 _ HPCI B-J 6 3 0 2 9 1 0 0 C-F-2 60 9 0 7 81 7 0 0 FW B-J 29 9 0 10 41 8 0 c(5) . C-F-2 7 5 0 0 1 1 0 0 R "ion 3 1( ')
"r3,. 2005
C. C C , 1': _ NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
- Table 5-I (cont'd) - -----
Inspection.Location Selection Comparison Between 1986 ASME Section XI Coe and EPRI TR-112657 by Risk Region, High Risk Region- Medium Risk Region .Low Risk Region 1
/2)Y Wi rytm 1986 Scini 2
'EPRI TR-112657'Wl 1986 Section X 2'EPRI TR-112657- Weld 1986 Section X' EPRI TRA112657
- CutVol/Sur Sur Only RI.ISI Other 3 Con Vol/Su r Sur Only Ri-ISI Other 3 con /VSurSur Only R -i1 te 1
~
CCW C-F-2 18 1 0 C-F-1 31 28 0 0 CRD _ _ _ _ _ C-F-2 _ _ ___ __10 3 0 0 FPEC C-F-2 54 0 0 0 PCAC C-F-2 ____47 4 0 a Torus C-F-2 19 1 0 0 B-F 15 15 0 410 8 2 2: 4 1 3 0 TtlB-J 65 16 0: 20 459 106 27 50 264 33 59 0 C-F-I1_ _ _ _ _ _ 31 28 0 0 C-1F-2 7- 5 01 0 101 11 0, 12 762 69 2 0 Notes 1 . I
- 1. Systemrs are describedin Table 3.1.
- 2. Sinc6 no examination selections had been made for the 4th interval 181 Program prior to the development of the RI-SI Program, the 3rd Interval selections' were used for comparison purposes. The Code of record for the 3rd Interval was the 1986 Edition of ASME Section XI. The Code Categories listed in the table are therefore In accordance with the 1986 Edition of ASME Section XI. . .. ,
- 3. The column labeled 'Other' is generally used to Identify augmented Inspection program locations credited per Section 3.6.5 of EPRI TR-112657. The EPRI methodology allows augmented inspection program locations to be credited if the inspection locations se'lected'strictly for RI-ISI purposes produce substantially less than a 10% sampling of the overall Class 1 weld population. As stated in Section 3.5 of this template, MNGP achieved a 9.2% sampling without relying on augmented Inspection program locations beyond those selected by the RI-ISI process. The MOther' column has been retained in this table solely for uniformity purposes with the other RI-ISI application template submittals.. .. _.
- 4. One of these eleven welds was selected for examination by both the FAC and RI-SI Programs. Since FAC was the only damage mechanism identified for this weld, the FAC examination will be credited toward both programs.
- 5. 'Two of there sixw~elIds were selected for examination by both the FAC and RI-ISI Programs. Since FAC was the only damage mechanism identified for these welds', the FAC examinations Will be credited toward both programs.
1.5-31 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 5-2 Inspection Location Selection Comparison Between 1986 ASME Section XI Code and EPRI TR-112657 by Risk Category Systems Risk Consequence Failure Potential Code Weld 1986 Section Xll2) EPRI TR-112657 Category Rank Rank DMs Rank Category 2 Count Vol/Sur Sur Only RI-ISI Other 31 RPV 4 Medium High None Low B-F 5 3 2 1 B-F 3 1 2 0 RPV 6 Low Medium None Low B-J 80 3 22 0 RPV 7 Low Low None Low B-J 8 2 2 0 B-F 1 1 0 1 RWCU 4 Medium High None Low B- 83 1 8__ ___ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _B-J 83 9 15 8 RWCU 7 Low Low None Low B-J 1 0 0 0 MS 4 (1) Medium (High) High None (FAC) Low (High) B-J 6 2 0 1(4) MS 4 Medium High None Low B-J 99 30 1 10 MS 6 Low Medium None Low B-J 95 21 18 0 MS 7 Low Low None Low B-J 4 0 3 0 SLC 4 Medium High None Low B-J 8 0 3 1 B-F 1 0 1 0 SLC 6 Low Medium None Low ._____ _ B-J 26 0 6 0 RCR 2 High High CC Medium B-F 10 10 0 3 RCR 4 Medium High None Low B-F 2 2 0 0
. B-J 111 25 5 12 RCR 7 Low Low None Low B-J 12 0 3 0 1..'- ' R 'ion 3 3T 2005
C C. NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL "' I EXAMINATION PLAN Table 5-2 (cont'd) Inspection Location Selection Comparison Between 18ASEection Xi Code and EPRI TR-1 12657 by Risk Category .-..
~Risk sytm Consequence .Failure Potential .Ce-Wld1986 Section' Xl( 2) EPRI TR-112657
.. Category - Rank ak -DMs- Rank Caeoy CutVl~rur Only RI-SI . Other-~
RCIC 4 Medium High on-.'Lbw,' C-F-2 1
-RCIC 5 (3) Medium (High) Medium -- TT, (FAC) Medium (High) C-F-2 - 8 I-- 0 _1 RCIC 5 Medium Medium iT Medium C-F-2 20 0 0 -. 2 ___
RCIC 6 Low Medium None LowBJ 5 0 2 0 __ _ __ __ __ __ __ _ _ _ _ _ _ _ _ _ C -F-2 .. -7 1. 0 0. RCIC 7 Low Low None . -. Low",'___ C-2 4 0 0 0 RHR' 2High High ~ TT-Medium- -
- . . BJ 30 4 0 8 __
B2F2 0 0 RHR.Medium HihNone--- Low- -0 7 __ RHR 5 Medium Medium TV Medium B-J 10 4 0 1 RHR 6 (3) Low (High) Medium None (FAC) Low (High) C-F-2 42 5 0 0 ___ RHR 6 Low Medium None Low C-F-2 227 _20- 0 0 RHR 7 (5) Low (Medium) - Low None (FAC) -- Low (High) .C-F-2 10 .1 - 0 0 ___ B-J 7 4 0' 0 RHR 7 LoW" Low None Low CF2 8 Cs 2 ' High High .CC Medium' BF 2 2~ 0 1 Cs 4 Medium High -. None . Low 13-J 20 9 0 2
*Cs 6 (3) Low (High)' Medium ~~ None (FAC) -. Low (High) .C-F-2 4 0 0 0 B-J 8 2 0 0 CS, . -6 Low Medium None Low- __ -
______C-F-2 23 4. 0 0 Cs 7 (5) Low (Medium) Low None (FAC) Low (High) C-F:-2 123 0 0 0O, __ CS 7 Low Low None Low C-F-2 121 18 0 0 1.5-33 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 5-2 (cont'd) Inspection Location Selection Comparison Between 1986 ASME Section XI Code and EPRI TR-112657 by Risk Category systemi"Risk Consequence Failure Potential Code Weld 1986 Section X112) EPRI TR-112657 Category Rank Rank DMs Rank Category(2) Count Vol/Sur Sur Only R-ISIl Other(3) B-F 2 2 0 0 HPCI 2 High High TT Medium B-J 6 3 0 2 HPCI 4 Medium High None Low C-F-2 27 2 0 3 HPCI 5 Medium Medium TT Medium C-F-2 33 7 0 4 HPCI 6 Low Medium None Low C-F-2 81 7 0 0 HPCI 6 Low Low TT Medium B-J 9 1 0 0 FW 2 (1) High (High) High TASCS, TT, (FAC) Medium (High) B-J 1 0 0 1 B-J 1 1 0 1 FW 2 (1) High (High) High TASCS, (FAC) Medium (High) C-F-2 4 3 0 0 B-J 4 1 0 1 FW 2(1) High (High) High TT, (FAC) Medium (High) C-F-2 1 0 0 B-J 2 0 0 1 FW 2 High High TASCS, TT MediumCF2 I 00 B-J 12 5 0 4 FW 2 High High TASCS Medium4 C-F-2 1 0 FW 2 High High TT Medium B-J 1 0 0 0 FW 2 High High CC Medium B-J 8 2 0 2 B-J 18 5 0 2(5) _ FW 4 (1) Medium (High) High None (FAC) Low (High) C-F-2 1 1 0 0 FW 4 Medium High None Low B-J 19 3 0 2 FW 5 (3) Medium (High) Medium TASCS, TT, (FAC) Medium (High) B-J 1 0 0 1 FW 5 (3) Medium (High) Medium TASCS, (FAC) Medium (High) B-J 1 0 0 0 FW 5 Medium Medium TASCS Medium B-J 2 0 0 1 1.1' `4 R '-ion 3 k 3I 2005
C C ( NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Table 5-2 (cont'd) Inspection Location Selection Comparison Between 1986 ASME Section Xl Code and EPRI TR-112657 by Risk Category - ! System~ Risk l Consequence Failure Potential ' - Code Weld 1986 Section Xl12) EPRI TR-112657 Category Rank Rank r DMs -. .-Rank categoiy count VolISur ur Only* RI-ISI Other.3' CCW 7 Low, Low , None Low C-F-2 18 1 O. 0 CRD 6 Low Medium None Low C-F-1 10 10 0 0 C-F-i 21 18 0 0 CRD 7 Low Low None Low C-F-2 10 3 0 0 FPEC 6 .. Low Medium.. None Low C-F-2 54 0 0: 0 PAC-.: 6 .- Low Medium None : - Low . C-F-2 47 4 0 0 Torus - :-- 6 Low . Medium None - Low *- C-F-2 19 1, 0T 0
. . . i , , .; , -, -, -.- ; - ~ i _. ; Ad ; ; . . ;_;
Notesei *- *- e r;a .
- 1. Systems are described In Table 3.1. - - :' 1 -* * ' v , ' ; ;
- 2. Since no examination selections had been made for the4th interval ISI Program prior to the development of the RI-ISI Program, the 3rd Interval selections were used for_
comparison purposes. The Code of record for the 3rd Interval was the 1986 Edition of ASME Section Xi.. The Code Categories listed in the table are therefore in accordance with the 1986 Edition of ASME Section Xl. . . ;
- 3. The column labeled 'Other' is generally used to identify augmented inspection program locations credited per Section 3.6.5 of EPRI TR-1 12657. The EPRI methodology allows augmented inspection program locations to be credited if the inspection locations selected strictly for RI-ISI purposes produce substantially less than a 10% sampling of the overall Classi weld population.' As stated In Section 3.5 of this template, MNGP achieved a 9.2% sampling without relying on augmented inspection program locations beyond those selected by the RI-ISI process. -The 'Other' column has been retained in this table solely for uniformity purposes with the other RI-ISI application template submittals. :
- 4. This one weld was selected for examination by both the FAC and RI-ISI Programs. Since FAC was the only damage mechanism identified for this weld, the FAC examination will be credited toward both programs.-
- 5. These two welds were selected for examination by both the FAC and RI-ISI Programs. Since FAC was the only damage mechanism identified for these welds, the FAC -
examinations will be credited toward both programs. 1.5-35 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Monticello Unit 1 - ISI Relief Request No. 2 (Rev. 1) Reactor Vessel Circumferential Shell Welds (note - italicized text clarifies/ corrects typographicalerrors and omissions or describes actions taken to address implementation) System: Reactor Vessel Class: I Category: B-A Item: B1.11 Reactor Vessel Circumferential Welds: VCBB-4, VCBB-3 and VCBA-2 (errantly named VCBB-2 on Rev.0) Examination Requirements: A September 8, 1992 revision to 10 CFR 50.55a(g)(6)(ii)(A) contains an augmented examination requirement to perform a one time volumetric examination of essentially 100% (>90%) of all circumferential and axial reactor pressure vessel (RPV) shell assembly welds. This rule revokes previously granted relief requests regarding the extent of volumetric examination on circumferential (B1.11) and longitudinal (B1.12) reactor pressure shell vessel welds. 10 CFR 50.55a(g)(6)(ii)(A) requires the augmented examinations to be performed as specified in the ASME Code Section XI (1989 Edition). Monticello requests relief from the inspection of Reactor Vessel Circumferential (B-A) Welds Item B1.11 for the remaining term of the current license for Monticello (during the 4th ISI Interval). Basis For Relief: Monticello reactor vessel circumferential welds were not inspected to the essentially 100% volumetric requirements during the 1st and 2nd ISI inspection intervals. A relief request (RR-01) was granted on the basis of inadequate accessibility and unnecessary radiation exposure during the first two 10 year inspection intervals. Upon submittal of the 3rd Interval ISI Inspection Plan, Rev. 1 (July 29, 1993), continuance for the 1st and 2nd interval relief request (RR-01) was requested. That relief request (RR-01) was denied on the basis of 10 CFR 50.55a(g)(6)(ii)(A), effective September 8,1992, requiring augmented examination for reactor vessel shell assembly welds. On November 10, 1998, the NRC issued Generic Letter 98-05 "BOILING WATER REACTOR LICENSEES USE OF BWRVIP-05 REPORT TO REQUEST RELIEF FROM AUGMENTED EXAMINATION REQUIREMENTS ON REACTOR PRESSURE VESSEL CIRCUMFERENTIAL WELDS." This generic letter permits licensees to request permanent relief from the inservice inspection 1.5-36 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY :. INSERVICE INSPECTION MONTICELLO 4th'INTERVAL i-EXAMINATION PLAN requirements of 10 CFR 50.55a(g)(6) for the volumetric examination of circumferential reactor pressure vessel welds if it can be demonstrated that: (1) at the expiration of the license, the circumferential welds will continue to satisfy the limiting conditional failure' probability for circumferential welds in the staff s July 28,-.1998, safety evaluation, and (2) operator training and procedures limit the frequency of cold over-pressure events to the amount specified in the staffs July 28, 1998; safety evaluation (Reference 1). The following is our evaluation of these two criteria..
- (1) Limiting Conditional Failure Probability The' values established in Attachment 1 were calculated in accordance with the guidelines of RegulatoryGuide 1.99, Revision 2. The chemistry factor for the limiting circumferential weld recorded in Attachment 1 is Monticello:
(manufactured by Chicago Bridge & Iron (CB&I)) plant specific (Reference3). This value is slightly higher than the USNRC's value which utilizes Table 1 of Regulatory Guide 1.99, Revision 2. As a result, the Monticello mean RTNDT value of 46.90 F is slightly higher than the .USNRC's limiting plant specific analysis mean RT'DT value of 44.5° F listed in Reference 5 for the CB&I reference case. -A recent safety evaluation (Referenc6 6) identified a Brunswick Unit '(manufactured by CB&I) mean RTNDT value of 46.50 F which also exceeded the corresponding CB&I mean RTNDTvalue specified in Reference 5. To validate the acceptability of the failure probability in this case, the staff performed calculations using the Brunswick Unit 1 value of 46.50 F. The calculations showed only a small increase in failure&' robability '(6 x 10-7/yr for Brunswick vs. 2 0xi7Iyr for the reference case)>'Since the Monticello mean RTNDT is only slightly higher than the Brunswick Unit 1 mean RTNDT (46.90 F vs. 46.50 F), it is expected that only a small increase in failure probability will result for Monticello. The overall limiting conditional failure probability for circumferential welds across the BWR fleet listed in Reference 5 is 8.17 x 105 /yr (calculated by the staff for the Babcock & Wilcox (B&W) reference case). :This limiting conditional failure probability is based on reactor vessel data that produced a calculated mean RTNDT of 99.80 F (Reference 5). Since the Monticello mean RTNDT (46.90 F) is less than 99.80 F, it follows that the Monticello conditional failure probability will also be less than the limiting failure probability listed in Reference 5.: Attachment 2 provides a plot of mean RTNDT against failure probability using results documented in References 5 and 6. Based on this trend, the conditional failure probability for-Monticello is estimated to be less than 1 x 104 /yr. In conclusion, the above discussion demonstrates that the circumferential welds of the Monticello RPV will continue to satisfy the limiting conditional failure probability listed in Reference 5.
- 1.5-37 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN (2) Training and Procedures The cold pressurization events considered in Reference 1 (i.e., inadvertent injections, condensate injection, CRD injection, loss of RWCU, actual event) were reviewed to identify the critical operator actions that were assumed to occur to mitigate these events. Procedures and training were reviewed to ensure that those critical operator actions would occur with a high degree of certainty so that the low temperature over pressurization (LTOP) event frequency is maintained less than the amount specified in Reference 1 (i.e., 1 x 10-31yr). System design was also considered in this review to assure that the associated systems function as described in Reference 1. Results of our review indicate that in general, procedures, training and system design ensure that the evaluations contained in Reference 1 are valid for Monticello. Following are the detailed results of our review:
- 1. Inadvertent Injections.
The evaluation provided in Reference 1 (paragraph 2.6.1.1) is applicable to Monticello with one exception. The evaluation considered the availability of automatic trips of high pressure injection systems on high water level. Review of Monticello procedures identified that during performance of reactor feedwater pump (RFP) testing during cold shutdown, the high reactor water level trip is bypassed. Measures are taken procedurally to close valves that prevent water from getting to the vessel. Monticello enhanced Operations Procedure B.06.05-05 to further assure the isolation of flow to the vessel.
- 2. Condensate Injection.
The evaluation provided in Reference 1, (paragraph 2.6.1.2) is applicable to Monticello. Operating procedures provide precautions which indicate that reactor water level is to be closely monitored when starting a condensate pump. This aids in assuring that an overfill event which could lead to an LTOP event does not occur. In order to assure that operations personnel understand that an overfill event has the potential to lead to an LTOP event, Monticello enhanced Operations Procedure B.06.05-05 to identify an LTOP event as a potential consequence of an overfill event. Monticello also has high reactor water level and high reactor pressure alarms in the control room that warn operators when high level/pressure limitations are being exceeded which provides further assurance that an LTOP event will not occur due to condensate injection. 1.5-38 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY - ':.,INSERVICE'INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
- 3. CRD Injection.' ' ' >I-'
;V :i,..- ra The evaluation provided in Reference 1, (paragraph 2.6.1.3), is applicable to Monticello. -The evaluation notes that the risk of cold over pressurization due to CRD injection may be higher if a loss of station power were to' occur during reactor vessel pressure testing. Monticello revised vessel pressure testing procedures 0255-20-IIA-l and 0255-20-IIC-1 to provide precautions that ensure proper response to a loss of station power (i.e., RWCU and Recirculation pumps are restored along with restoration of CRD). -
- 4. Loss of Reactor Water Cleanup (RWCU)'
The evaluation provided in Reference 1, (paragraph 2.6.1.4), is applicable to Monticello. Monticello has procedures in place to provide guidance for recovery measures following a scram. In the'event that'a scram occurs that results in a RWCU isolation, procedural guidance is provided which consists of restoring the RWCU system as soon as the cause of the isolation is identified and resetting the reactor scram as soon as possible in order to limit cold water injection into the vessel. Also, procedural guidance is provided for dealing with recirculation loop or vessel stratification so that an excessive amount of cold water is not distributed throughout the reactor vessel during the restart of a tripped recirculation pump(s). - Monticello added a precaution in the Operations Procedure C.4-A for RWCU restoration in order to further inform the operations personnel of the potential of an LTOP event occurring during SCRAM recovery. --
- 5. Actual Event.
General Electric issued RICSIL No. 049, Inadvertent Vessel
- Pressurization, in response to the actual event discussed in Reference 1, (paragraph 2.6.1.5). Our assessment of the RICSIL indicated that the likelihood of a similar event occurring at Monticello is very low.
Procedures require that the reactor vessel remain vented at all times during cold shutdown except as permitted by approved procedures. The reactor vessel pressure test procedure allows the vent valves to be closed
-during cold shutdown. During the pressure test, strict procedural guidance is provided for administratively monitoring vessel pressure and
;: temperature while controlling CRD injection and RWCU.reject in order to assure a smooth, controlled method of increasing or decreasing pressure while vessel temperature is being maintained above the required P-T limits. If reactor pressure exceeds the specified limits, during the test, the
- 1.5-39 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN CRD pump is immediately tripped. In addition to the above mentioned procedural guidance, a requirement is included to perform an "Infrequent Test or Evolution Briefing" with all essential personnel. This briefing details the anticipated testing evolution with special emphasis on conservative decision making, plant safety awareness, lessons learned from similar in-house or industry operating experiences, the importance of open communications, and the process in which the test would be aborted if plant systems responded in an adverse manner. The above evaluations show that system design and procedures, including the proposed enhancements, minimize the probability of LTOP events at Monticello. Our review of training indicated that licensed operator training addresses LTOP events. Initial licensed operator simulator training, for example, includes performance of surveillance tests which ensure pressure-temperature curve compliance during plant heatup and cooldown. Additionally Monticello created Request for Training (RFT) 20012810 to provide training to operations personnel on the specific scenarios and events evaluated in Reference 1, (paragraph 2.6.1.1-5), including the features of system design and procedural controls that prevent such events at Monticello.
== Conclusion:==
The Monticello mean RTNDT value of 46.90 F is less than the mean RTNDT value of 99.80 F corresponding to the B&W limiting reference case. Since the Monticello RTNDT is much less than the limiting RTNDT, the Monticello conditional failure probability will be well below the limiting conditional failure probability of 8.17 x 105 /yr calculated by the Staff for the corresponding B&W reference case. A thorough review of existing procedures, operator training and system design identified improvement opportunities that Monticello has committed to implement. With the recommended enhancements to existing procedures and operator training and with the current design capabilities of the associated systems, the LTOP event frequency is limited to the amount specified in Reference 1, (1 x 103/yr). Based on these evaluations the conditions for requesting relief from the inservice inspection requirements of 10 CFR 50.55a(g)(6)(ii)(A), for the volumetric examination of circumferential reactor pressure vessel welds in accordance with ASME Code Section Xl (1995 Edition with 1996 Addenda), Table IWB-2500-1, Examination Category B-A, Item B1.11, Circumferential Welds, are satisfied. Relief is hereby requested in accordance with 10 CFR 50.55a(a)(3)(1). The proposed alternative examinations provide an adequate level of quality and safety. 1.5-40 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY :INSERVICE INSPECTION MONTICELLO 4th INTERVAL -EXAMINATION PLAN Alternate Examination: As an alternative to the inspection requirements of ASME Code Section Xl (1995 Edition with the 1996 Addenda) Category B-A, Item B1.1 1, 100% volume requirement, we propose that the following examination methodology be used. The alternative examination requested maintains essentially 100% (>90%) examination of reactor vessel longitudinal (axial) shell welds, Code Category B-A, Item B.1.12. Two to three percent of the circumferential RPV shell welds Code Category B-A, Item B1.1 1, Code Category B-A, Item B1.1 1 will be inspected at the intersections of the axial and circumferential welds. This is consistent with the alternate inspection requirements as specified in GL 98-05. This alternative is capable of detecting weld degradation sufficient to insure the integrity of the reactor pressure vessel boundary, and is the same as that described in the NRC SER (Reference 1). Time Period Relief is Requested For: '. ¶ ;! . ' . , i .. , : '-: ;'. . -- ; , , Relief is presently approved by the NRC for the remaining term of the current Monticello license during the 4th 10 year interval. (Reference 7)
References:
- 1. NRC Safety Evaluation Report of Topical Report by the Boiling Water Reactor Vessel and Internals Project: "BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations, BWRVIP-5," (TAC No. M93925), July 28, 1998.
- 2. General Electric Report SASR 87-61, DRF137-0010, 'Revision of Pressure-Temperature Curves to Reflect Improved Beltline Weld Toughness Estimate for the Monticello Nuclear Generating Plant - Rev. 1," December 1987.
- 3. NSP Letter to NRC, Submittal of Report on Reactor Pressure Vessel Specimen Test, December 21, 1998.
- 4. General Electric Report GENE-B313-01796-1, "Reactor Vessel Fracture Toughness Engineering Evaluation - Task 5.4,1 March 13, 1996
-1.5-41 Revision 3
~ - ~ 3/10/2005 l
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
- 5. NRC Safety Evaluation Report of Topical Report by the Boiling Water Reactor Vessel and Internals Project: "Supplement to Final Safety Evaluation of the BWR Vessel and Internals Project BWRVIP-5 Report (TAC No.
MA3395)," March 7, 2000.
- 6. Brunswick Steam Electric Plant, Unit No's 1 and 2 - Safety Evaluation for Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) for Reactor Vessel Circumferential Shell Weld Examinations (TAC No's MA9299 and MA9300).
- 7. NRC Letter, "Monticello Nuclear Generating Plant - Approval of Relief Request Number 12 of the Third 10 Year Inservice Inspection Program,"
(TAC No. MB0261), July 27, 2001. Status: Approved July 27, 2001 for continued use in 4th Interval (...'remainder of current 40-year operating license for the unit'), (See Reference #7 above). 1.5-42 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' . -EXAMINATION PLAN ATTACHMENT I
-Comparison of Monticello RPV Parameters to NRC Limited Plant Specific Parameters
;,~
- Parameter . Monticello Parameters USNRC Limiting Plant Description for the Bounding Specific Analyses Circumferential Weld Parameters SER Table 2.64
--. (Reference 5)
.CB&I B&W Cu, wt% 0.10 (Reference 2) 0.10 0.31 i Ni, wt% 0.99 (Reference 2) 0.99 0.59 CF (Chemistry factor) 138.5 (Reference 3) 134.9 196.7 EOL ID 0.51 (Reference 4) 0.51 0.095 Fluence, x 10'9 n/cm 2 _
ARTNDT, OF 112.5 109.5 79.8 RTNDT (u) OF -65.6 (Reference 2) -65 20 Mean RTNDT, OF 46.9 . 44.5 - 99.8 Conditional Failure <lx104 2x1 ' 8.17x10-5 Probability P(FIE) Attachment 2 _-
;,J.
1.5-43 Revision 3 3/10/2005 I
0 , .0 C 0> ATTACHMENT- 2 Circ. Weld Failure Probability vs Mean RT,40 TTrend Using Limiting CE, CB&l, B&W and Brunswick Data 11.00E+00>
- G
1.0 -1Legend
1 CB&l Limiting Analysis (Ref. 5) - 2 = Brunswick Limiting Analysis (Ref. 6) 0
,1.OOE-02 3 =CE(IP___m_____ys___e-5 IiI 4 =CE (CEOG) Limiting Analysis (Ref'. 5) 5 =B&W Limiting Analysis (Ref. 5) >
1~1.00E-03 0 i.OOE0-04 IL 0 X0 1.OE0 i >5 Monticello Failure Probability vs Mean RTNOT Projected Intersection 0 - 2D1.0-07 CZZ 0 40 46.9 50 60 70 80 90 100 110 0 1C3 0-(.n z K . (
. NUCLEAR MANAGEMENT COMPANY ;) .i-_._'-.' INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' '- EXAMINATION PLAN 1-~`,;r Monticello Unit I - Relief Request No. 3 (Rev. 0)
Appendix Vil Supplement 4
-System/Component(s) For Which Relief Request Will Be Used Code Class: -- : Class 1
Reference:
ASME, Section XI,'Tables IWB-2500-1 (1995 Edition, 1996 Addenda) Examination C:ategory: B-A Item Number:, ' ' 31.1 0, B1.20 'I~
Description:
' Alternative Requirement to Appendix Vlll, Supplement 4 "Quaiification Requirem'ents for the Clad/Base Metal 'Interface of Reactor Vessel" Component Ntirmbers: All
- 1. ......- ....- ,;
Code and 10'CFR 50.55a Requirements:
'10 CFR 50.55a(b(2) was amended on September'22, 1999 to reference Section Xl of the ASME Code through the 1995 Edition with the 1996 Addenda' (64 FR 51370). This amendment provides an implementation schedule for the supplements to Appendix Vil of Section XI to the 1995 Edition with the 1996
'-Addenda., ' ; ' Supplement 4 to'Appendix VIII, Subparagraph 3.2(c) imposes three statistical parameters for depth sizing. The first parameter, 3.2(c)(1), pertains to the slope of a linear regressioni line. The linear regression line is the difference between measured versus'true value plotted along a through-wall thickness. The second parameter, 3.2(c)(2), pertains to the mean deviation of flaw'depth. The third parameter, 3.2(c)(3), pertains to a correlation 66efficient: The Final Rule was amended by Federal Register Notice (66FR16391) dated March 26, 2001: This amendment specified the use of a flaw length sizing tolerance 6riterion'of 0.75 inch Root Mean Square' (RMS) for reactor vessel qualification'to be used in conjunction with the 0 15'inch RMS for depth sizing specified in the Rule in lieu of paragraphi 3.2(a)narid 3.2(b). In the Notice, there
.was no reference to the elimination of the statistical parameters of Paragraph 3.2(c), which were'intended for use with'pariagraphs 3.2(a) and 3.2(b) 'of Appendix VIII,'Supplement 4. The're was no amendment statement included to reflect the use of the RMS error calculations'for depth and length sizing in lieu of Paragraph 3.2(c).
- - 1.5-45 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Basis for Alternative Examination: This relief request was developed using the Electric Power Research Institute (EPRI) Performance Demonstration Initiative (PD1) ASME Section Xl, Appendix Vil Implementation Guideline. It is modeled after the sample request for relief associated with the Supplement 4 published discrepancies: Appendix D, "Sample Request for Relief - Alternative Length Sizing Criteria (Revised)." (Reference 5) The U.S. nuclear utilities created PDI to implement demonstration requirements contained in Appendix Vil. PDI developed a performance demonstration program for qualifying UT techniques. PDI does not use paragraph 3.2(c) for sizing qualifications. The solution for resolving the differences between the PDI program and the Code was for PDI to participate in the development of a Code case that reflected PDI's program. The Code case was presented to ASME for discussion and consensus building. NRC representatives participated in this process. ASME approved the Code Case and published it as Code Case N-622, "Ultrasonic Examination of RPV and Piping, Bolts and Studs, Section Xl, Division 1." (Reference 6) The NRC first approved the use of Code Case N-622 for Florida Power and Light Company's St. Lucie Plant Unit 2 (TAC No. MA5041). (Reference 7) Operating in parallel with the actions of PD1, the Staff incorporated most of Code Case N-622 criteria in the Rule published in the Federal Register, 64 FR 51370 dated September 22, 1999. This amendment requires the implementation of the ASME Code Section Xl, Appendix Vil, Supplement 4, 1995 Edition with the 1996 Addenda. The required implementation date for Supplement 4 was November 22, 2000. Appendix IV to Code Case N-622 contains the proposed alternative sizing criteria which has been authorized by the Staff. However, the sizing parameters printed in the published Rule differed from the sizing parameters implemented by the PDI Program and Code Case N-622. On January 12, 2000, NRC Staff, representatives from the EPRI Nondestructive Examination Center, and representatives from PDI participated in a conference call. The discussion during the conference call included the differences between Supplement 4, "Qualification Requirements for the Clad/Base Metal Interface of Reactor Vessel," to Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," Paragraph 10 CFR 50.55a(b)(2)(xv)(C)(1) in the rule (Federal Register, 64 FR 51370), and the implementation of Supplement 4 by the PDI Program. (Reference 8) 1.5-46 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL :-EXAMINATION PLAN In a public meeting on October 11, 2000 at NRC-,offices in White Flint, MD, the PDI identified the discrepancy between the PDIProgram and statistical, parameters required by Subparagraph 3.2(c). The Staff agreed that the inclusion of the statistical parameters of Paragraph 3.2(c) of Supplement 4 to Appendix VIII was an oversight. The NRC agreed that Paragraph 10 CFR 50.55a(b)(2)(xv)(C)(1) should have excluded Subparagraph 3.2(c) as a requirement. (Reference 9) . . - In Subparagraph 3.2(c), the linear regression line is the difference between measured versus true value plotted along a through-wall thickness. For: Supplement 4 performance demonstrations, a linear regression line of the data is not applicable because the performance demonstrations are performed on test specimens with flaws located in the inner 15% through-wall. The difference between measured versus true value produce a tight grouping of results that resemble a shotgun pattern. The slope of a regression line from such data is extremely sensitive to small variations, thus making the parameter of Subparagraph 3.2(c)(1) a poor and inappropriate acceptance criterion. The value used in the .3.2(c)(2) is too lax with respect to evaluating flaw depths within the inner 15% of wall thickness. Therefore,-Monticello proposes to use the more appropriate criterion of 0.15 inch RMS of 10 CFR 50.55a(b)(2)(xv)(C)(1), that modifies Subparagraph 3.2(a) as the acceptance criteria. Subparagraph 3.2(c)(3) pertains to a correlation coefficient. This value of correlation coefficient is inappropriate for this application since it is based on the linear regression from Subparagraph 3.2(c)(1). The NRC Staff previously approved MNGP use of this Alternative to the Code -and 10 CFR 50.55a on August 22, 2001 (TAC No. MB1833) for use during the 3rd ISI Interval. (Reference-10) - ..Alternative Examination:
;Pursuant to 10 CFR 50.55a(a)(3)(i),' relief is requested to use the-RMS Error calculations in lieu of the statistical parameters of Subparagraph 3.2(c) in Supplement 4 of the 1995 Edition 1996 Addenda of ASME Section Xl Appendix VIII. As discussed above and demonstrated by the PDI, this will provide an acceptable level of quality and safety. -
- . 1.5-47 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Implementation Schedule: This alternative is requested for continued use for the 4th Ten-Year Interval of the Inservice Inspection Program for Monticello.
References:
- 1. ASME Boiler and Pressure Vessel Code, Section Xl, 1995 Edition with 1996 Addenda
- 2. Federal Register, Rules and Regulations, September 22, 1999 (64 FR 51370)
- 3. Federal Register Notice, Industry Codes and Standards, Amended Requirements, March 26, 2001 (66 FR 16391)
- 4. Federal Register, Rules and Regulations, September 26, 2002 (67 FR 60520)
- 5. Performance Demonstration Initiative (PDI), "Guideline for Implementation of Appendix VIII and 10CFR50.55a," Volume One, Programmatic Implementation, Rev. 2, Appendix D, October 14, 2000
- 6. ASME Section Xl Nuclear Code Case N-622, "Ultrasonic Examination of RPV and Piping, Bolts, and Studs"
- 7. NRC Staff letter to Mr. T. F. Plunkett, Florida Power and Light Company, September 23,1999.
- 8. Meeting Summary, Teleconference between NRC and representatives from PDI, D.G. Naujock, Metallurgist, NDE & Metallurgy Section, to Edmund J. Sullivan, Chief NDE & Metallurgy Section, Chemical Engineering Branch, Division of Engineering, U.S. NRC, March 6, 2000.
- 9. NRC Memo, "Summary of Public Meeting Held on October 11, 2000, with PDI Representatives," November 13, 2000
- 10. NRC Letter to Nuclear Management Company, "MNGP - Evaluation of Relief Request No. 13 for the Third 10-Year Interval Inservice Inspection Program," (TAC No. MB1833), August 22, 2001 1.5-48 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY. : - i - INSERVICE INSPECTION MONTICELLO 4th INTERVAL .V EXAMINATION PLAN
- 11. NRC Letter to Nuclear Management Company, "Relief Request Nos. 3 and 6 for the Fourth .10-Year Interval of the Inservice Inspection Examination Plan" (TAC No. MB6896), March 28, 2003 Status:
Approved on March 28, 2003 for use during the 4th Interval. (See Reference 11 above)
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.1.5-49 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Monticello Unit 1 - ISI Relief Request No. 4 (Rev.0) (restructured and resubmitted) Reactor Vessel Stabilizer Bracket Welds ASME CODE COMPONENT AFFECTED Code Class: Class 1 Code Subsection: IWB Code Examination Category: B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves Code Item No.: B10.10 Parts Examined: Pressure Vessels, Welded Attachments Examination Method: Surface Examination Frequency: 1st Interval and each Successive Interval System: Reactor Pressure Vessel (RPV) Component
Description:
RPV Stabilizer Bracket welds to the RPV ISI Summary Number 102650 Component ID: Vsl Stblzr Lugs, (Quantity of 4) Description of Relief: Proposed alternative to the Code examination frequency requirements APPLICABLE CODE EDITION AND ADDENDA American Society of Mechanical Engineers (ASME) Section XI, 1995 Edition with 1996 Addenda is the Code of Record for the 4th ISI Interval. APPLICABLE CODE REQUIREMENT TABLE IWB-2500-1, CATEGORY B-K, ITEM B10.10, INCLUDING NOTE 2 In each Inspection Interval, each welded attachment and each identified occurrence is required to be examined with a surface examination method (described in iWA-2220.) NOTE (2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination. 1.5-50 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY - INSERVICE INSPECTION MONTICELLO 4th INTERVAL i . EXAMINATION PLAN REASON FOR REQUEST Monticello Nuclear Generating Plant (MNGP) is a General Electric Type 3 Boiling Water Reactor. (BWR-3) with a Mark I Containment. The reactor vessel was designed andbuilt to the 1965 Edition of ASME Section il with Summerl 966 Addenda.. Piping systems were designed in accordance with the 1967 Edition of USA Standard (USAS) Code for Pressure Piping B31.1.0. 'Power Piping.' Construction Permit CPPR-31 was issued on June 19,1967 and full commercial operation began on June 30,1971. Plants of this type were designed and erected prior to the examination access requirements of Section XI. The Atomic Energy Commission (AEC) mandated the rules of ASME Section Xl in 1971 for all nuclear plants with construction permits issued after January 1, 1971, and in 1976,- they mandated use of ASME Section Xl for all nuclear plants. 10CFR50.55a(g)(1) states "For a boiling orpressurized water-cooled nuclear power facility whose construction permit was issued before January 1, 1971, components (including supports) must meet the requirements of paragraphs (g)(4) and (g)(5) of this section to the extent practical. U 10CFR50.55a(g)(4) states ".... components (including supports) which are classified as ASME Class 1, 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, -setforth in Section Xl of editions of the ASME Boiler and Pressure Vessel Code and Addenda ..;." [Emphasis Added]. Four RPV stabilizer brackets are attached to the Class I RPV with full - penetration fillet welds at 0°, 900,1800; and 2700 RPV azimuth at an elevation of 994'-2". The RPV stabilizers are connected with flexible couplings to the brackets on the RPV and also to the biological shield wall. The RPV stabilizers, brackets, and their attachment welds are designed to withstand and resist local loads Get reaction forces) and seismic loads while allowing axial and radial movement due to normal thermal growth. The RPV stabilizers brackets do not provide structural support during normal operation. The MNGP RPV has never experienced jet reaction forces or seismic events, therefore the stabilizers, - brackets, and 'attachment welds have not experienced the loads for which they are designed.- The MNGP Mark I primary containment structure, or drywell, is shaped somewhat like an upside-down light bulb. The RPV stabilizer brackets are located in the higher, necked-down elevations of the drywell. This region of the drywell is a very limited access area; it was not designed with the intention of 1.5-51 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN providing access and accommodations normally considered necessary for a general work area. The area around the stabilizers is extremely congested. The vessel stabilizer brackets are surrounded by mirror insulation that is secured by cable hangers and buckles, ventilation ductwork with support bracing, and electrical installations such as thermocouples. All of this equipment must be relocated and restored to provide access to the stabilizers for examination of the welds. Additionally, due to the location of the stabilizer brackets and the lack of a working platform at the stabilizer location a complex scaffold installation is required to provide access to the examination location. The photos and reference drawings, attached to this request, show the physical obstacles imposed by the design and construction of the primary containment, RPV, ventilation ducting, RPV stabilizers, containment supports, and other systems. Combined, these obstacles as described below, create an unusually difficult hardship to overcome to provide access for the examination of the stabilizer bracket attachment welds that are specified by the Code. In the course of scaffold installation and removal, interference removal and restoration, insulation removal and restoration, weld preparation, performance of the examination, and health physics monitoring, personnel would be subjected to significant radiation doses found in the drywell for lengthy durations. Dose survey maps taken from the recent refueling outages at this region of containment indicate dose rates in the general area to be 5 - 140 millirem per hour (mrem/hr). It is reasonable to expect that the contact dose rates at the bracket welds would be similar to those experienced at the nearby feedwater (986'-7" elevation) and main steam nozzles (999'-0" elevation). These dose rates range from 20 - 80 mrem/hr in the general nozzle area and 20 - 800 mrem/hr in contact with the components. NMC estimates indicate that radiation exposure to personnel involved in the activities associated with examination of the four RPV Stabilizer Bracket Welds would result in 21.675 person-rem. In summary, NMC has determined that:
- 1. MNGP is not subject to the access requirements of ASME code as described in 10CFR50.55a(g)(4) due to its age and design.
- 2. Access to the RPV stabilizer brackets is difficult due to their location, interferences, and surrounding equipment.
- 3. Radiological dose rates in the area of the RPV stabilizer brackets is high due to the proximity of the brackets to feedwater and main steam nozzles.
1.5-52 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY -. INSERVICE INSPECTION MONTICELLO 4th INTERVAL 'EXAMINATION PLAN Therefore, pursuant to IOCFR50.55a(a)(3)(ii), NMC has determined that compliance with'the Code requirement would result in hardship or unusual 'difficulty without a compensating increase in quality or safety PROPOSED ALTERNATIVE AND BASIS FOR USE As an alternative to the requirements of the ASME Section Xi Code, Table IWB-2500-1, Category B-K, Item B1 0.10, NMC proposes to perform a surface examination on the stabilizer brackets if local (jet reaction forces) or seismic design loads are experienced. The stabilizer brackets are located in a very limited access area of the drywell which precludes inadvertent damage to be imparted on the brackets such as rigging, climbing, arc strikes, etc. The RPV stabilizer bracket attachment welds have never experienced loads due to jet reaction forces or seismic events. The stabilizer'brackets do not provide support during normal operation. This proposed alternative to the frequency requirements of Table IWB-2500-1, Category B-K, Item BI 0.10 will provide an acceptable level of quality and safety. DURATION OF PROPOSED ALTERNATIVE NMC is requesting relief for the 4th 10-year Interval of the ISI Program for the Monticello Nuclear Generating Plant. PRECEDENTS This relief from the requirements of 10CFR50.55a and alternative to the Code was previously approved for 2nd and 3rd 10-year Intervals of the ISI program at Monticello:
- NRC Letter, "Monticello - Second Ten-Year Inservice Inspection (ISI)
Program," (TAC No. 46510), November 29, 1990, Relief Request No. 51 NRC Letter, "Evaluation of the Third 10-Year Interval Inservice Inspection Program Plan and Associated Requests for Relief for Monticello," (TAC No. M82545), October 18, 1994, Relief Request No. 2 1.5-53 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Status: Approved on January 6, 2005 for use during the 4th Interval, NRC Letter, "Fourth 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 4" (TAC No. MC2222) 1.5-54 Revision 3 3/10/2005
' NUCLEAR MANAGEMENT COMPANY :. INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' EXAMINATION PLAN Monticello Unit IS1 Relief Request No. 5 (Rev. 0) Leakage at Bolted Control Rod Drive (CRD)'Housing Connections SYSTEM: Bolted CRD Housing Joint - 'Class:' Category:.B-P' iI '* :- Item: B15.10 Code Exa'mination-Requirements:- IWA-5250(a)(2):' If leak'age occurs at a bolted connection on other than a
' gaseous system, one of the bolts shall be removed, VT-3 examined, and evaluated in accordance with IWA-31 00.:-
Basis for Relief:- - 10 CFR Part 50, Section 50.55a(a)(3), which'states,: (in part):
'Proposed altern atives to the requirenonts bf paragraphs (c), (d), (e), ('0, (g), and (h) of this section or portions thereof may' be used when...
(ii) Compliance with the specified irq irements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety." The CRD (Control Rod Drive) housings are flan'ged connections beneath' the reactor vessel that are used to secure the 121 CRD mechanisms in position below the vessel. Each of the 121 CRD to" CRD h6using bolted joints utilizes eight bolts,'washers, and nuts to hold the CRD mechanism in position. The joint
^ also utilizes three hollow 'metal O-ringsWto provide a w'atertight seal capable of withstanding full reactor pressure at normal operating temperatures.
The CRD housing joints are VT-2 examined as part of the periodic Reactor
'Pressure Ve'ssel Leakage arnd Hydrostatic' pressure tests. These tests are conducted with the vessel temperature much less'than the design operating temperature. For a typical test, the vessel temperature would be <2120 F, as compared to-a normal operating temperature of about 540 F. It is not unusual for these bolted joints to leak slightly during periodic reactor vessel pressure tests conducted at test temperatures below normal operating temperature.
1.5-55 Revision3 3/10/2005 l
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN This is a condition identified in the original design of the connection by the Architect/Engineer, General Electric (GE). GE developed guidance to permit evaluation of a leaking CRD housing bolted connection over a period of time, while at test pressure, to determine whether the leak will stop once the vessel heats up to normal operating pressure. This leakage evaluation criteria is incorporated into the VT-2 tests for these joints. Compliance with Code Requirement IWA-5250(a)(2) represents a hardship (burden) in the case of the CRD housing bolted joints because:
- 1) Examining the bolting would involve the accumulation of considerable personnel radiation exposure, since the work must be performed in a relatively high dose rate area inside the drywell, immediately below the reactor vessel. Typical shutdown dose rates in the vicinity of the bolting flanges would be on the order of 50 to 100 mr/hr.
- 2) Since the reactor pressure vessel test is critical path item, the additional time needed to depressurize the vessel, remove the bolting, perform the exam, and then re-pressurize the vessel to retest the joint would delay plant startup from an outage by an equivalent amount of time. The cost of such delays is significant, since it is estimated that the cost of extending the duration of an outage is $379,000 per day (including replacement power costs)(this is estimated cost submitted in 1993 (see TAC No.
M82545 referenced in 'Status" section) Compliance with Code requirement IWA-5250(a)(2) would not result in a compensating increase in quality or safety because:
- 1) CRD Housing joint leakage during (relatively) low temperature testing is not unexpected due to the design of the bolted joint. This joint is unusual in that it has hollow metal 0-rings that require the CRD housing bolts to be tightened within a specific torque range in order to function properly at normal operating temperature. Thus, the bolts cannot simply be tightened to stop leakage as might be done for a conventional gasketed joint. As noted previously, GE developed guidance to evaluate any CRD housing leakage to determine if the leakage will persist at normal operating temperature/pressure and should therefore be corrected.
1.5-56 Revision 3 3/10/2005
- 'NUCLEAR'MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th.INTERVAL - EXAMINATION PLAN
*2) Leakage that is found to be acceptable per the guidance is not considered adverse to quality or safety and need not be corrected prior to startup. This type of analysis is consistent with Section Xl.
- 3) Code paragraph IWB-3142 allows analysis of the leakage for acceptability. Performance of the VT-3 bolting examination does not represent a corrective action for the joint leakage and will not reduce the likelihood of joint leakage upon retest. Therefore, the VT-3 bolting examination does not contribute to increased quality
.; . or;safety.
4)' The'b6lts' in the CRD housing connection are periodically examined when the joint is disassembled, per Table IWB-2500-1, Item B7.80 (1995 Edition with no Addenda per 10CFR50.55A Paragraph (b)(2)(xxi)(B)) and Procedure 9309, uChangeout Selected CRD's - Maintenance" and Commitment No. M92076A. Four of the eight bolts on each housing joint were replaced with new bolts in 1991 under Work Control Record (WCR) 91-01909: It was also reported in General Electric SIL 483 that only three uniformly distributed housing bolts are required to support the CRD mechanism. These factors provide a high degree of confidence in the long term safety and integrity of the CRD housing joints. Earlier Section XI code editions invoked by Monticello's 1st and 2nd Ten-Year Inspection Interval Programs did not include the subject examination requirement. During the 3rd Inspection Interval, Relief Request 7 was granted by the NRC in an SER dated October 18,1994. Alternate Examination: Pursuant to 10 CFR 50.55a(a)(3)(ii), the following alternative is proposed. Any leakage found at a CRD housing bolted joint during a periodic pressure test performed at a temperature much less than operating temperature will be evaluated to determine whether it will stop leaking at operating temperature. If this evaluation shows the leak will stop as temperature increases to normal operating temperature, no further action will be taken. The acceptance criteria is based on guidance provided by General Electric and is included in the VT-2 tests for the joint (Note: This criteria was submitted for NRC review during the Request for Relief process previously approved on October 18,1994, therefore it is not included in this submittal). If the leakage is determined to be unacceptable according to the General Electric guidelines and the joint is disassembled to correct the leak, any CRD bolting that is reused will be examined by the VT-1 examination method (10 CFR 50.55a(b)(2)(xxi)(B) dated September 26, 2002).
- 1.5-57 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Upon approval of this Relief Request, MNGP commits to revise the applicable pressure test procedure to perform a VT-1 exam in lieu of a VT-3 exam specified by IWA-5250(a)(2) on all CRD bolting that will be reused when the GE acceptance criteria has been exceeded and disassembly is required to correct the leak. Status: Approved on June 9, 2003 for use during the 4th Interval, NRC Letter to Nuclear Management Company, "Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 5" (TAC No. MB6956) 1.5-58 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY ; I., . '-:INSERVICE INSPECTION MONTICELLO '4th INTERVAL '.' -;,EXAMINATION PLAN Monticello Unit I - ISI Relief Request No. 6 (Rev. 0) Appendix VII Annual Training - System/Component(s)'For Which Relief Will Be Used: 'Code Class: - All ' - -
Reference:
ASME, Section Xl 1995 Edition 1996 Addenda, AppendixVII, VII-4240 Examination Category: 'All Item Number: 'All
Description:
, All NDE Examiners performing ultrasonic volumetric examination in acc6rdance with ASME Section Xl, 1995 Edition 1996 Addenda and Appendix VII, Annual Training., Component Numbers. I 7 All: '.
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Code and 10 CFR 50.55a Requirement:' ASME SectionXil, 1995 Edition, 1996 Addenda, Mandatory Appendix VIl, Paragraph YlI-4240: Supplemental training is required on an annual basis to impart knowledge ,of new 'developments, material failure modes, and any pertinent technical topics as determined by the Emrployer; The extent of this training shall be a minimum of 10 hours per year. A record of attendance and the topics covered during the training shall be maintained; however no examination is required. 10 CFR 50.55a, paragraph (b)(2)(xiv): All personnel qualified for performing ultrasonic examinations in accordance with Appendix Vil shall receive 8 hours of annual hands-on training on specimens that contain cracks. This training must be completed no earlier than 6 months prior to performing ultrasonic examinations at a licensee's facility. Basis For Relief Request: i10 CFR 50.55a was amended in the Federal Register (Volume 64, No. 183 dated September 22, 1999) to require Appendix VII -I Supplements for accelerated implerentatioh in accordan6e'with'ASME Section'XI 1995 Edition, 1996 Addenda.'
; .1.5-59 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Basis For Relief Request (continued): Paragraph 2.4.1.1.1 in the Federal Register (Volume 64, No. 183 dated September 22, 1999) during rule making contained the following statement: "The NRC had determined that this requirement (10 hours of training on an annual basis) was inadequate for two reasons. The first reason was that the. training does not require laboratory work and examination of flawed specimens. Signals can be difficult to interpret and as detailed in the regulatory analysis for this rulemaking, experience and studies indicate that the examiner must practice on a frequent basis to maintain the capability for proper interpretation. The second reason is related to the length of training and its frequency. Studies have shown that an examineres capability begins to diminish within approximately 6 months if skills are not maintained." Thus, the NRC has determined that 10 hours of annual training is not sufficient practice to maintain skills and that annual Ultrasonic training shall be conducted in accordance with 10 CFR 50.55a(b)(2)(xiv) as amended in the Federal Register (Volume 64, No. 183 dated September 22,1999) in lieu of ASME Section Xl, 1995 Edition, 1996 Addenda, Appendix VIl, Subparagraph VII-4240." The latest amendment to 10 CFR 50.55a (Volume 67, No. 187 dated September 26, 2002), paragraph (b)(2)(xiv) further recognizes, and'permits use of, analyzing prerecorded data from material or welds that contain cracks for meeting annual training requirements. However, these provisions apply to those sites implementing use of the 1999 Addenda through the latest Edition and Addenda referenced in paragraph (b)(2) of the Rule; Monticello is using the 1995 Edition with the 1996 Addenda as the Code of Record for the 4th ISI Interval. Alternative Requirement: Pursuant to 10 CFR 50.55a(a)(3)(i), Monticello proposes to use the more rigorous and detailed annual training requirements of 10 CFR 50.55a(b)(2)(xiv) in lieu of annual training requirements Appendix VII, paragraph VII-4240. Therefore, all personnel qualified for performing Ultrasonic examinations in accordance with Appendix Vill - Supplements ASME Section XI, 1995 Edition, 1996 Addenda shall receive 8 hours of annual hands-on training on specimens that contain cracks or by analyzing prerecorded'data from material or welds that contain cracks. This training will be completed no earlier than 6 months prior to performing ultrasonic examinations at the Monticello Nuclear Generating Unit. 1.5-60 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY, ' , . INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' .l"'EXAMINATIONPLAN Justification for Granting Relief: Hi" . S-This relief improves the performance of Appendix Vil - Supplement examinations by requiring NDE examiner performing Appendix Vil examinations to demonstrate proficiency by analyzing specimens that contain cracks or prerecorded ultrasonic data from material or welds that contain cracks prior to performing actual examinations. The proposed alternative will simplify record keeping,'satisfy the needs of maintaining Ultrasonic examiner skills,,and also provides an acceptable level of quality and safety. . A, .. , I~ Implementation Schedule: I The proposed alternative is requested for the 4th Ten-Year Interval of the Inservice Inspection Program for Monticello Nuclear Generating Unit.
References:
- 1. ASME Boiler and Pressure Vessel Code, Section Xi, 1995 Edition with 1996 Addenda
- 2. Federal Register, Rules and Regulations, S-~tember 22,1999 (64 FR:51370)
- 3. Federal Register, Rules and Regulations, September 26, 2002 (67 FR 60520)
- 4. NRC Letter to Nuclear Management Company, "Relief Request Nos. 3 and 6 for the Fourth 10-Year Intervalof the Inservice Inspection Examination Plan" (TAC No. MB6896), March 28, 2003 . '
Status: - Approved on March 28, 2003 for use during the 4thlinterval. (See Reference 4 above) .
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' 1.5-61 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY *INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN: K' Monticello Unit 1 - ISI Relief Request No. 7 (Rev.0) Repair/Replacement, 2001 Edition COMPONENT IDENTIFICATION Code Classes: 1, 2, and 3
References:
IWA, IWB, IWC, IWD, and IWF-4000 (IWX-4000) Examination Category: Not Applicable Item Number: Not Applicable
== Description:== Use of the 2001 Edition of Section Xl to Govern Repair/Replacement Activities and Procedures (IWX-4000). Component Numbers: All Class 1, 2, 3 and. MC. pressure retaining components and their supports. CODE REQUIREMENT IWX-4000 (ASME Section Xl 1995 Edition with the 1996 Addenda, used for Class 1, 2, and 3 components) provides the rules and requirements for repair/replacement activities associated with pressure retaining components and their supports, including appurtenances, subassemblies, parts of a component, core support structures, metal containments and their integral attachments, and metallic portions of Class CC containments and their integral attachments. IWX-4000 (ASME Section Xl 1992 Edition with the 1992 Addenda, used for IWE components) provides the rules and requirements for the repair of pressure retaining components and their supports, including appurtenances, subassemblies, parts of a component, core support structures, metal containments and their integral attachments, and metallic portions of Class CC containments and their integral attachments, by welding, brazing, or metal removal. This article also provides the rules and requirements for the specification and construction of items to be used for replacements and installation of replacement items. 10 CFR 50.55a dated September 6, 1996 required the implementation of Subsections IWE and IWL of the 1992 Edition with the 1992 Addenda. 1.5-62 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY - - -INSERVICE INSPECTION MONTICELLO 4th'INTERVAL , `:,-:EXAMINATION PLAN BASIS FOR RELIEF The 1992 Edition with the 1992 Addenda to Section Xl made several changes to Articles IWX-4000. . Very few of these changeswere technical in nature. - Instead,'the changes-restructured some of the requirements, (ie. Combined IWX-4000 and IWX-7000 into one section) clarified others that were difficult to interpret, and eliminated redundant requirements::-Of the actual technical changes made, these changes either added enhancements to the program or added requirements not applicable to Monticello.>.' Meeting both the 1995 with the 1996 Addenda and the 1992 with the 1992 Addenda of ASME Section Xi would require the maintenance of two separate repair and replacement programs (one for the IWB, IWC, and IWD components per the 1996 Addenda of ASME Section XI and one for the 1992 Addenda for
*the containment vessel). Duplicate records to demonstrate compliance with the 1996 Addenda and the 1992 Addenda would also be required. This duplication of programs and records increases the man-hours necessary to, maintain the Monticello Repair/Replacement Program without providing any increase in quality or safety.
. . . .~
The final rule (Federal RegisterNol. 67, No. 187, dated September 26, 2002) incorporates reference to the 1998 Edition thr6ugh 2000 Addenda. Attached is a reconciliation of the changes made and a comparison of the 2001 Edition to the 2000 Addenda of Section Xl. Each change related to Repair/Replacement Activities is addressed in the attachment to show it will be implemented at Monticello. - I.56 Revision 3 3/10/2005
' NUCLEAR MANAGEMENT COMPANY INSERVICE'INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN K) ALTERNATE EXAMINATION This alternative is requested in accordance with 10CFR 50.55a(a)(3)(ii). Monticello Nuclear Generating Plant will use the 2001 Edition of ASME Section Xl, to govern Repair/Replacement Procedures (IWX-4000) for Class 1,2,3, and MC pressure retaining components and their supports. Using the requirements contained in the 2001 Edition of ASME Section Xl for Repairs/Replacements at the Monticello Nuclear Generating Plant will maintain the safety of the plant. The following table indicates the implementation of the 2001 Edition for Repair/Replacement Activities. Article Topic Bases IWA-1000 Scope and Responsibility 1996 Addenda IWA-2000 Examination and Inspection 1996 Addenda IWA-3000 Acceptance Standards 1996 Addenda IWA4000 Repair/Replacements 2001 Edition IWA-5000 Pressure Tests (Periodic) 1996 Addenda IWA-5000 Pressure Tests (Repair/Replacements) 2001 Edition IWA-6000 Records 2001 Edition IWA-9000 Glossary 2001 Edition IWB-1 000 Scope and Responsibility 1996 Addenda IWB-2000 Examination and Inspection 1996 Addenda IWB-3000 Acceptance Standards 1996 Addenda IWB-5000 Pressure Tests (Periodic) 1996 Addenda IWB-5000 Pressure Tests (Repair/Replacements) 2001 Edition IWC-1000 Scope and Responsibility 1996 Addenda IWC-2000 Examination and Inspection 1996 Addenda IWC-3000 Acceptance Standards 1996 Addenda IWC-5000 Pressure Tests (Periodic) 1996 Addenda IWC-5000 Pressure Tests (Repair/Replacements) 2001 Edition IWD-1000 Scope and Responsibility 1996 Addenda IWD-2000 Examination and Inspection 1996 Addenda IWD-3000 Acceptance Standards 1996 Addenda IWD-5000 Pressure Tests (Periodic) 1996 Addenda IWD-5000 Pressure Tests (Repair/Replacements) 2001 Edition 1.5-64 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY, -; ,:' !... INSERVICE INSPECTION MONTICELLO 4th INTERVAL - :- EXAMINATION PLAN Article * Topic .-. 9 Bases IWE-1 000 Scope and Responsibility 1992 Addenda IWE-2000 Examination and Inspection- . 1992 Addenda IWE-3000 Acceptance'Standards 1992 Addenda IWE-5000 - Pressure Tests (Periodic) v- *AppendixJ IWE-5000 .'Pressure Tests (Repair/Replacements) 2001 Edition w/ Appendix J IWF-1 000- Scope and Responsibilitil,' . 1996 Addenda IWF-2000: Examination and Inspection'. 1996 Addenda IWF-3000 Acceptance Standards 1996 Addenda IWF-5000 Snubber Examinations and ITests 1996 Addenda
. . . 4 .
-APLICABLETIME PEIOD -- - : Relief is requested for the fourth ten-year interval of the Inservice Inspection Program for Monticello Nuclear Generating Plant., -
- I d I - I 1
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. I1.5-65 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY - :INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Certificate of Reconciliation The Certificate of Reconciliation provides the basis for revisions to the Monticello Nuclear Generating Plant's (MNGP) ASME Section XI uRepair/Replacement Program" (4AWI-09.04.03) in order to meet the 2001 Edition of ASME Section Xl. On September 9,1996, the Nuclear Regulatory Commission (NRC) issued a revision to 10 CFR 50.55a, implementing subsections IWE and IWL (IWL "Requirements for Class CC Concrete Components of Light-Water Cooled Plants" is not applicable to the Monticello Nuclear Generating Plan) is not of the 1992 edition, including the 1992 addenda of Section Xl of the ASME Code. This required utilities to develop and implement a program for the examination of containments by September 9, 2001. Additionally, it required implementation of an IWE/IWL repair/replacement program effective September 9,1996. The NMC is updating the MNGP Inservice Inspection (ISI) Program for the fourth ten-year interval to meet the 1995 Edition with the 1996 Addenda. Because of the hardship to maintain two separate Repair/Replacement Programs, this alternative is proposed to allow the use of the 2001 Edition of ASME Section Xl. This reconciliation is completed to provide justification for allowing the use of the 2001 Edition for Class 1, 2, 3 and MC pressure retaining components and their supports. The current revision of 10CFR50.55a requires ASME Section Xl Programs to follow the 1995 Edition as amended by the 1996 Addenda of ASME Section Xl for Class 1, 2, and 3 components and the 1992 Edition as amended by the 1992 Addenda for Class MC components. There are some general issues to discuss prior to delineating the specific changes that have been made to the ASME Section Xl Code (2000 Addenda to 2001 Edition). By performing the reconciliation from the 1992 Addenda, the reconciliation from the 1996 Addenda is covered as well.
- 1) The NRC has reviewed and approved with some exceptions the 1998 Edition through 2000 Addenda of the code. This has been included in the Final Rule (dated September 26, 2002). Those specific exceptions made to the rules for repair/replacement activities are included in the implementation of the 2001 Edition.
- 2) The NMC ISI requirements for MNGP will be based on the 1995 Edition as amended by the 1996 Addenda.
- 3) The Periodic Pressure Testing requirements will be based on the 1995 Edition as amended by the 1996 Addenda. While the pressure testing requirements for repair/replacement activities will be based on the 2001 Edition.
1.5-66 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY .. INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' EXAMINATION PLAN
- 4) The reconciliation attached addresses the changes contained within the IWAm4000 paragraphs. In addition, any significant
- -- @i changes identified within any related requirements are addressed.
Each change'is categorized as' Editorial (E)'-'Those changes that'are of an editorial nature like typographical errors or misspelled words. Technical Significant (TS)- Those changes'that effect the technical. requirements and either reduce or increase'those requirements. These changes are described in more detail as to. their applicabilityto MNGP. Technical (T) - Technical changes that are only used for clarification of an existing requirement. ' Non-significant (TN) -- Those changes that are not technical in nature, but could not be classified as editorial or just a relocation of existing requirements. CISI RELIEF REQUEST NUMBER: No. 7 Certificate of Reconciliation 2001 Edition. IWA-41 10(b) - Revised to insert the words uThermal metal removal" TS
*to clarify that thermal metal removal activities fall (Note 1) within the scope of IWA-4000 IWA-4230 This was added to relocate the requirements of IWA- - TN 4451 uHelical Coil Threaded Inserts". This relocation places these requirements in IWA-4200 'Material" which is appropriate since they deal primarily with helicoil material requirements.
IWA-4400 Retitled to "Welding, Brazing, Metal Removal, and TN Installation". This was retitled specify that metal removal rules apply to all Section XI repair activities. IWA-4410 This was rewritten to make its contents consistent with T the revised title. It is also revised to clarify that mechanical metal removal not associated with defect removal is not within the scope of IWA-4400. IWA-4411 This is a new paragraph titled "Welding and Brazing". T This new paragraph serves to consolidate the requirements applicable only to welding and brazing, and to clarify the distinction between when Construction Code requirements apply and when IWA-4400 requirements apply.
- 1.547 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
'~
ISI RELIEF REQUEST NUMBER: No. 7 Certificate of Reconciliation IWA-4412 This is a new paragraph titled "Defect Removal". This T new paragraph serves to clarify that the requirements of IWA-4420 are mandatory for all defect removal activities, and to direct the user to these requirements. IWA-4413 This is a new paragraph titled "Thermal Metal T Removal". This new paragraph serves to clarify that the requirements of IWA-4461 are mandatory for all thermal metal removal activities, and to direct the user to these requirements. IWA-4420 Revised title to "Defect Removal Requirements". This TN revision makes the title consistent with the changes described below. IWA-4421 Revised to "General Requirements" with the following TN specific changes: i) The second sentence of para. (a) is moved to IWA-4421. ii) The last sentence of para. (a) is dropped, since IWA-4412 now invokes requirements for defect removal and associated NDE. iii) The remainder of the text from IWA-4421(a), (b), and (c) is reorganized and moved to IWA-4411 (a) and (b), except that the final sentence, "A Report of Reconciliation shall be prepared." has been deleted to make this paragraph consistent with the changes made. 1.5-68 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY ; 'i ':INSERVICE _- INSPECTION MONTICELLO 4th INTERVAL 7"EXAMINATION PLAN ISI RELIEF REQUEST NUMBER: No. 7
- - Certificate of Reconciliation IWA-4422 Revised to "Defect Evaluation and Examination". This TN change makes the title consistent with the content changes described for IWA-4422.1. 4 IWA-4421.1 was changed as follows:.
i) Title changed to 'Defect Evaluation"
- ii) The first sentence of IWA-4422.1(a) is deleted. The requirement that the defect removal process comply with 4421 is
-- unneeded, as it is redundant with the new IWA-4421 (a) through (d) riii) .. The third sentence of IWA-4422.1(a) is deleted. This deleted sentence stated, "The component is acceptable for continued service if the resulting section thickness created by the cavity is at least
. ;the minimum required thickness." This sentence is deleted for two reasons:
. - 1) It is redundantwith the proceeding sentence in IWA-4422.1(a) and
- 2) It implies that all defect removal
- operations involve metal removal and creation of a cavityjSeveral repair types do not involve metal removal or
^. r cavity creation.
IWA-4430 This paragraph was deleted. Its contents were TN reworded and relocated to IWA-4411(f). IWA-4450 This was deleted from the Code in its entirety. Use of TN the ASME Code to mandate compliance with manufacturer's recommendations is considered inappropriate and constitutes the basis for deleting this requirement. IWA-4451 This was renumbered as IWA-4134 and is relocated TN accordingly. This relocation is consistent with the contents of IWA-4451, which address installation of helical-coil threaded inserts. The installation of helical-coil threaded inserts does not fall within the scope of IWA-4400. Table IWA- This table was revised to delete reference to P-1 E 4461.1-1 materials. This revision is editorial in nature, and is incorporated to make Table-4461.1 consistent with IWA-4461.1 and 4461.2. The revision for preheat of P-1 materials prior to thermal metal removal was deleted by a prior revision to IWA-4460, but Table IWA-4461.1 was not revised to reflect this revision. 1.5-69 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL - EXAMINATION PLAN ISI RELIEF REQUEST NUMBER: No. 7
- Certificate of Reconciliation IWA-4461.4 Title was revised to "Alternatives to Mechanical TS Processing". This change is necessary to, (Note 1) accommodate a newly added alternative to mechanical processing after thermal metal removal, which is addressed in IWA-4461.4.2. The two alternatives are addressed in new paragraphs IWA-4461.4.1 and IWA-4461.4.2.
IWA-4461.4.1 describes the qualification process whereby thermal metal removal is permitted without subsequent mechanical processing. No changes were made to these requirements other than paragraph renumbering. IWA-4461.4.2 describes the evaluation process where by thermal metal removal is permitted without subsequent mechanical processing. This alternative enables an Owner to perform a documented evaluation to determine whether elimination of mechanical processing is acceptable. A footnote was added to define the term "Mechanical Processing" IWA-4462 This was revised to "Mechanical Defect Removal TN Processes". IWA-4462(a) is replaced with wording that clarifies the applicability of this paragraph to defect removal activities only. - IWA-4500 Title changed to "Examination and Testing" TN 1.5-70 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY . :. II.:: jINSERVICE INSPECTION MONTICELLO 4th INTERVAL _ ,r,,_,-,"< EXAMINATION PLAN
- 1. ISI RELIEF REQUEST NUMBER: No. 7 I. :Certificate of Reconciliation IWA-4520(a) This was revised to add two specific exceptions. TS ii These exceptions are as follows: >- I (Note 1)
.i -
.., IWA-4521(a)(1) was revised to exempt Class 3 base material repairs from volumetric examination when full-i penetration butt welds in the same location do not require volumetric examination.
ii) - IWA-4521(a)(2) was revised to invoke the examination requirements of IWA-4600
- and 4700 in lieu of Construction Code examinations for all repairs using IWA-4600 or 4700. This exception invokes
.. IWA-4600 NDE requirements for all IWA-II X'. -4600 welding, and invokes IWA-4700 NDE r, requirements for IWA-4700 welding. This
; change clarifies that use of IWA-4600 and IWA-4700 welding alternatives and also
. ! . - : . i. mandates use of the associated NDE
;-requirements.
IWA-4600(a) This was revised to delete the words "and TN nondestructive examination requirements". These words are deleted for clarification. The underwater welding alternative requirements of IWA-4660 apply in lieu of Construction Code requirements; however,
;IWA-4660 invokes Construction Code NDE requirements. Since IWA-4660 invokes Construction Code NDE requirements, it is incorrect to state that 4660's requirements are "in lieu of' Construction Code
- . . NDE requirements. -
IWA-4610 -This was revised to "General Requirements for TN
! Temperbead Welding of all Materials" I .' . I
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-; . 1.5-71 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN ISI RELIEF REQUEST NUMBER: No. 7
; Certificate of Reconciliation IWA-4611 IWA-4611.1(a), (b) and (c) were deleted and TS alternative requirements were added. (Note 1) i) The defect removal requirements of 4611.1(a) have been moved to IWA-4421.1. The existing 4611(a), therefore is redundant and is no longer needed.
ii) The IWA-4611.1 (b) requirement that "the original defect shall be removed" has been revised to match what the original intent was by the words "the original defect shall be reduced in size to a level that meets the applicable Construction Code NDE acceptance criteria. The requirement for compliance with Construction Code acceptance criteria was added to IWA-4624.2, 4634.2, 4644.2 and 4654.2. iii) The IWA-4611.1(c) requirements for the Repair/Replacement Program and Plan are redundant with IWA-4150. Deletion of this paragraph eliminates this redundancy. IWA-4611.1(a), (b), and (c)additions are as follows: i) IWA-4611.1 (a) now consists of a reference to IWA-4422.1. Use of this reference enables all defect removal activities to rely on a single set of defect removal requirements, eliminating redundancy and reducing complexity. ii) IWA-4611.1(b) now includes a reference to the NDE requirements applicable to each of the various repair methods authorized by IWA-4600. This reference is needed because each repair method includes its own unique NDE requirements, and these requirements are different from those used for welding and brazing activities that are not within the scope of IWA-4600. i) IWA-461 1.1 (c) now includes a reference to the thermal metal removal requirements of IWA-4413. This reference is needed because the requirements for thermal metal removal apply to all IWA-4600 processes, and because thermal metal removal requirements have been consolidated into IWA-4461, which is referenced by IWA-4413. 1.5-72 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY : INSERVICE INSPECTION MONTICELLO 4th INTERVAL X -'EXAMINATION PLAN
- ISI RELIEF REQUEST NUMBER: No. 7
. __ ; Certificate of Reconciliation IWA-4611 IWA-4611.2(a) was changed as follows: . TS (cont'd) i) In the first line, the word "grinding" is replace (Note 1)
* . -with "Processing". This change is necessary to acknowledge that final grinding is not always required for defect removal. -
. : ii) In the sixth line, "IWA-3000" is replaced with IWB-3500, IWC-3500, or.IWD-3000". This change adds a direct reference to the NDE
... . acceptance criteria tables of IWB and IWC (Note: Since 1WD tables are 'in course of preparation', the IWD-3000 reference invokes permission to use IWB requirements). By
. -. referencing these tables, IWA-4611.2(a) clarifies that the indication may be considered
'reduced to an acceptable level' only when the respective table's acceptance criteria has been met. -,
A new sentence states, uFor supports and
, containment vessels, the provisions of IWA-4422.1(b) may be used." This sentence isadded because ASME Section III Subsections NE and NF do not
;contain surface examination acceptance criteria for base materials, therefore, no criteria exist for these
. exams. IWA-4422.1(b) provides an evaluation alternative for these applications.
IWA-4620 Title was revised to "Temperbead Welding of Similar TN Materials" ._: IWA-4624 - A) -IWA-4624.1 (a) was added to, invoke IWA- TS 4611.2(a), which mandates surface examination (Note 1) prior to welding for all temperbead repairs. This paragraph is added to assure that Section Xl, IWA-3000 acceptance criteria is used for NDE of existing metal.
- B) IWA-4624.2 invokes Construction Code or Section III NDE acceptance criteria on in-processing welding and on the final weld. This assures that all newly installed weld metal complies with Construction Code requirements during installation and at the time of weld completion.
IWA-4630 Title was revised to "Temperbead Welding of TN Dissimilar Materials" IWA-4634 This was revised similar to that discussed in IWA- TS 4624 above. (Note 1)
* . :1.5-73 Revision 3 3/10/2005 1
NUCLEAR MANAGEMENT COMPANY -: INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN ISI RELIEF REQUEST NUMBER: No. 7
-_ Certificate of Reconciliation IWA-4644 This was revised similar to that discussed in IWA- TS 4624 above. (Note 1)
IWA-4654 This was revised similar to that discussed in IWA- TS 4624 above. (Note 1) IWA-4666 This was revised to impose Construction Code NDE TS requirements on completed underwater welds. This (Note 1) paragraph also provides an alternative to these NDE requirements when the underwater environment renders normal NDE practical. K>~ IWA-4711.4 This was revised to clarify the final visual examination TS was to be a VT-1 examination. (Note 1) IWA-4712 This was revised to make its wording consistent with TN IWA-471 1. This change states that use of these requirements is mandatory for Class 1 applications, but use of these requirements in Class 2 and Class 3 applications is also acceptable. IWA-4721.1 This was revised to make its wording consistent with TN IWA-471 1. This change states that use of these requirements is mandatory for Class 1 applications, but use of these requirements in Class 2 and Class 3 applications is also acceptable. - IWA-4131.1(a) The change deleted the word "welded" located in TS before the reference to plugs. (Note 2) IWA-4713 This revision adds new requirements for qualification TS of Class 1 mechanical tube plugs. These (Note 2) requirements represent a compilation of the standards and methods that have been used for twenty years to design, qualify, and install steam generator tube plugs. They have proven to provide safe installation and service for mechanical steam generator tube plugs. These requirements include development and qualification of the plug design and of a Plugging Procedure Specification (PPS), and performance qualification for individuals who install the tube plugs 1.5-74 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY .-,..: -I, .INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN ISI RELIEF REQUEST NUMBER: No. 7 Certificate of Reconciliation` IWA-4132 - This revision deletes the requirement for pressure TS testing and VT-2 visual examination of relief valves (Note 3) rotated from stock and installed by mechanical means. Inthe 1999 Addenda, the requirement to pressure test mechanical joints made in installation of pressure retaining items was deleted from IWA-4540,
-because Own'es operation and mainten'ance '
personnel post-installation inspections are adequate - without an additional Code-reqbired examination.
. Witli the deletion of pressure tests'for mechanical
. . connections, a similar exemption is'warranted for installation of relief valves by mechanical means. The revision also clarifies that no other IWA-4000 - -
requirements apply to rotation of snubber and relief valves, except those of IWA-4132, and clarifies that . use of an ANII is not required. This revision incorporates the provisions of Case N-508-2, "Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing, Section Xl, Division _ _ __ __ _ _ _ _ 1 ." ._ _ _ _ _ NOTE 1. It is important to apply the correct acceptance criteria to each repair/replacement activity completed. As reflected in the Final Rule, the NRC recognizes the difference between the NDE of the Construction Codes and ASME Section Xi. The other changes were made to clarify the rules as they apply to the mechanical removal process and of a non-technical nature with reordering of paragraphs or moving of requirements to different paragraphs. The
- MNGP Repair/Replacement Program incorporates these requirements.
NOTE 2. NMC has determined that it is important to have all special processes qualified and/or demonstrated to verify the application. Because of the elimination of the word "welded," the alternative requirements provided in IWA-4131.1 are no longer applicable to any tube plugging (mechanical or welded). The MNGP Repair/Replacement Program incorporates these provisions. NOTE 3. Since the code no longer requires a VT-2 Examination on installation of mechanical joints, the NMC has determined that the installation of relief* valves rotated from MNGP stock and installed by mechanical means would not require a V-T-2 examination. 1.5-75 Revision 3 3/1012005 I
NUCLEAR MANAGEMENT COMPANY : INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN NRC Limitation / NMC Commitments: The NRC staff requires implementation of paragraph IWA-4540(c) of the 1998 edition in lieu of that of the 2001 edition when implementing the 2001 edition of ASME Code, Section Xl, Article IWX-4000 for repair and replacement activities. The NRC is planning revisions to the Final rule which may have an effect on this Relief Request. NMC has committed to implement the limitations and modifications to the 1998 edition through 2000 addenda of the ASME Code, Section Xl, as stated in 10 CFR 50.55a(b)(2) when implementing the 2001 edition. NMC has further committed to implement any limitations and modifications to the 2001 edition of the ASME Code for its repair and replacement program when the NRC incorporates, by reference, this edition into the regulations.
References:
- 1. NRC Letter to Nuclear Management Company, -Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No.7" (TAC No. MB6897),
October 3, 2003
- 2. NRC Letter to Nuclear Management Company, "Issuance of Corrected Page Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No.7" (TAC No. MB6897), December 31, 2003 Status:
Approved on October 3, 2003 for use during the 4th Interval, (See References 1 and 2 above) 1.5-76 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY* '.' ; ;INSERVICE INSPECTION MONTICELLO4th INTERVAL J. / EXAMINATION PLAN Monticello Unit 1 - ISI Relief Request No. 8 (Rev. 0) One-time Relief, Class I Pressure Test at less than nominal operating pressure. x '. . , '!-.
' COMPONENT IDIENTIFICATION
- _;.- 1 Code Class:' - * ' 1 ' ;4 - ' --
References:
-I -' -' 'IWA-4540(c) . '
- ' IWA-5211 (a) - -- '.
Examination CatE,gory: Not Applicable Item Number:'! ' Not Applicable:----
Description:
-:.System Leakage Pressure Test & accompanying VT-2 Examination at nominal operating pressure following Repair-Replacement activities involving Mechanical Joints.
'Components:'- Main Steam Safety Relief Valve Assemblies
, i ,; .,_ P- . I_., .1
-.1-CODE REQUIREMENTS The 1995 Edition of American Society of Mechanical Engineers (ASME) Section Xl with the 1996 Addenda,'paragraph IWA-5120(a) states: "Items subjected to repair/replacement activities shall be pressure tested when required by IWA-4500.".- i.
Paragraph IWA-4540(c) states:
"Mechanical joints made in installation of pressure retaining items shall be pressure tested in accordance with IWA-521 1 (a)."
Paragraph' IWA-521 1(a) states:
"A'Wsystem leakage test conducted during operation at nominal operating
'pressureor when' pressurized to nominal operating pressure and temperature."
Paragraph IWB-5210(b) states:
"The system pressure tests and visual examinations shall be conducted in accordance with' IWA-5000 and this'Article. The contained fluid in the system shall serve as the pressurizing medium."--
I , , I- I . I i .- I '. t _. . :, _-_- "
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7-'. 1.5-77 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN BASIS FOR RELIEF:' Nuclear Management Company, LLC (NMC) Monticello Nuclear Generating Plant (MNGP) recently completed a refueling outage on May 26, 2003. During the refueling outage, MNGP completed the system leakage test required by American Society of Mechanical Engineers (ASME) Section Xl, Table IWB-2500-1, Category B-P, Item 15.10 and 10 CFR Part 50 Appendix G, Section IV.A.2.d. Following restart of the unit, the "B" and "G" main steam safety relief valve assemblies (SRVs) have indicated leakage, as determined by higher than normal temperatures in their respective discharge tailpipes. MNGP has decided to conduct a planned unit shutdown and enter a maintenance outage to replace the affected SRV assemblies. The SRV assemblies are connected to the main steam piping with a bolted, mechanical joint. Replacing them for maintenance is considered a Repair-Replacement activity under the rules of ASME Section XI, 1995 Edition with the 1996 Addenda which is the current code of record for the 4th 10-Year ISI Interval. Following repair-replacement, a system leakage test is required by IWA-4540(c). The system leakage test at the nominal pressure associated with the reactor at 100% power would be approximately 1000 psig. MNGP has identified three methods for performing the system leakage test on the mechanical joints associated with the repair-replacement activity that meet the requirements identified above. Several conditions associated with such testing represent an imposition on personnel safety, personnel radiation exposure, and challenges to the normal mode and manner of equipment operation. Method No. 1 would perform the pressure test and V1-2 exam during normal startup procedures. During normal startup with normal power ascension, nominal operating pressure of 1000 psig is reached at a reactor power level of approximately 75%. If access to containment were permitted at this power, level, personnel would be exposed to excessive radiation levels, including significant exposure to neutron radiation fields, which is contrary to current station ALARA practices. Establishing the 1000 psig test condition at a more moderate power level (e.g. during plant startup at approximately 7% reactor power) and in the manner needed to address radiation concerns would require altering the normal operational mode of the steam pressure control system. During the performance of plant startup procedures, the electric and mechanical pressure regulator (EPR and MPR) set points are established within their normal 1.5-78 Revision 3 3/10/2005
' NUCLEAR MANAGEMENT COMPANY ', - :-, . INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' ;'i- IEXAMINATION PLAN operational ranges (approximately 918 psig). Their primary function is to regulate the main steam system pressures as sensed near the inlet of the high-pressure turbine..: Reactor pressure control at the nominal .1000 psig is achieved at higher reactor powe'r levels as a function of the pressure control system and the induced differential pressure across the main steam isolation valves and main steam piping. -
While it is technically feasible to manipulate these controls to establish the nominal system pressure of 1000 psig at lower power levels, doing so will affect core reactivity and could challenge plant-safety systems, such as the reactor protection system (RPS). MNGP has not previously operated the EPR and MPR in this manner. Changing the setpoints outside of the normal range of operation for the purpose of performing this test at nominal operating pressure poses*
- several operational challenges. The lack of experience and predictability of setting pressure regulators outside the normal range of operation could
'adversely impact personnel and reactor safety. . v Method No. 2 implements the use of the reactor pressure boundary leakage test which meets the requirements of Table IWB-2500-1; Category B-P, Item 15.10:
the reactor pressure vessel (RPV) is filled with coolant and the steam lines are K2 flooded to provide a water-solid condition. Use of this method would result in multiple operational challenges. During a maintenance outage, pressurization for the test would be provided by decay heat'and the reactor recirculation pumps. To support the pressurization evolution, the normal decay heat removal system, residual heat removal (RHR) shutdown cooling, would be required to be removed from service and isolated from the vessel to be pressurized. This system is not designed towithstand
-pressures greater than185 psig. Thus, the remaining -system available for
'decay heat removal is the reactor water cleanup system (RWCU).
Application of ANSI /ANS-1994 decay heat code results in a significant level of decay heat load. The-ratio of decay heat input versus the heat removal capacity provided by RWCU is approximately 4:1 ..Therefore, the decay heat generated
'by the reactor core will surpass the capacity of RWCU. The heat up rate of the vessel water will cause the temperatures to surpass 2120 F prior to the initiation of the inspections.
Method No. 2 would present several operational challenges. The pressure increase would be obtained by balancing the flow into the vessel, which is provided by the control rod drive (CRD) system, with the flow out of the vessel provided by the RWCU system via the dump flow control valve and flow controller. This is the method used during refueling outages to complete the I'1.5-79 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY' INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN RPV system leakage test. A failure of a non-safety related component, such as the dump valve or flow controller, would cause the interruption of dump flow and would cause the RPV pressure to increase. The RPV pressure would increase until operator action would require the operating CRD pump to be tripped. Due to the amount of decay heat being generated and the RWCU systems heat removal capacity, it is questionable whether the RPV would depressurize and may in fact continue- to pressurize until further operator action would be required to depressurize the RPV. Operator actions may include one or more of the r following: reestablishing RWCU dump flow; if the failure mechanism.was no longer present, opening the main steam line drain valves, SRVs, or head vent line. Any of the last 3 of these actions would probably cause a rapid depressurization transient on the RPV. Extensive valve manipulations, system lineups, and procedural controls are required in order to heat up and pressurize the primary system to establish the necessary test pressure, during plant outage conditions, without the withdrawal of control rods. This test is expected to take approximately 1 day. of outage time, and the additional valve lineups and system reconfigurations necessary to support this test impose an additional challenge to the affected systems. A normal plant startup then occurs, after completion and subsequent recover from the test procedure. Method No. 3 would maintain the RPV at its normal level and use decay heat to produce sufficient steam pressure to conduct the test at nominal operating temperature. At the projected time of shutdown for the maintenance outage, MNGP will have a runtime of approximately three weeks since startup from the Cycle 21 refueling outage. The maintenance of the SRV assemblies is projected to be completed within approximately 50 hours after plant shutdown. While the decay heat load is too high for the water-solid method discussed above, there is not sufficient decay heat available to perform the test within a reasonable time period to support completion of the maintenance outage. Itwould require a minimum of 25 hours to reach the pressure of 1000 psig needed to perform the test required by the Code based upon decay heat projections. Each of the methods discussed above presents a hardship or unusual difficulty to NMC. 1.5-80 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY . INSERVICE INSPECTION MONTICELLO 4th INTERVAL V iEXAMINATION PLAN PROPOSED ALTERNATIVE PROVISIONS Pursuant to 10CFR50.55a(a)(3)(ii), compliance with the required system leakage
'test under IWA-4540(c) would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. =
The NMC proposes to perform a VT-2 examination on the mechanical joints of the SRV assemblies during the normal operational start-up sequence at a minimum of 900 psig following a 10 minute hold time (for uninsulated components) in lieu of the nominal operating pressure associated with 100% reactor power-of approximately 1000 psig. In addition, if there is an unplanned shutdown with a drywell entry before the next refueling outage, another inspection of these bolted connections will be performed to look for any evidence
-of leakage.
Application of this alternative test maintains reasonable levels of personnel safety and reduces the opportunity for the introduction of undesirable operational challenges. While NMC does not expect that leakage will occur, any leakage at the bolted - connection to be related to the differential pressure across the connection. A 10% reduction in test pressure is not expected to result in the arrest of a leak that would occur at nominal operating pressure. In the event that leakage would occur at the mechanical joints at higher pressures associated with 100% reactor power, leakage from these mechanical connections would be detected by the drywell monitoring systems, which include drywell pressure monitoring, the containment atmosphere monitoring system (CAM), and the drywell floor drain sumps. Leakage monitoring is required by Monticello Technical Specifications.,- This alternative method for a system leakage test is particularly applicable for the MNGP maintenance outage, which is of limited scope, and where the only components on the primary system that are being replaced are the main steam "B" and "G" safety relief valve assemblies attached via mechanical connections. The NRC has authorized use of a similar alternative system leakage test method for the Cooper Nuclear Station in 1998 which permitted them to perform a system leakage test at a minimum of 900 psig following replacement of their SRV topworks, a mechanical joint, during a mid-cycle maintenance outage. The approval letter for the Cooper relief request was dated February 26, 1998.
- 1.5-81 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN K) CONCLUSION: In summary, the proposed NMC alternative is to perform the system leakage test and VT-2 examination at 900 psig minimum after a 10 minute hold time in lieu of the pressure testing requirements of the 1995 Edition of ASME Section XI with the 1996 Addenda for mechanical joints following repair-replacement activities. In addition, if there is an unplanned shutdown with a drywell entry before the next refueling outage, another inspection of these bolted connections will be performed to look for any evidence of leakage. Considering the hardship and unusual difficulty in performing the available methods for satisfying the code requirements and the ability to detect leakage in primary containment should it occur, this alternative will provide an acceptable verification of the leak integrity of the mechanical joint without putting the plant in a non-conservative operational condition and without unnecessary radiation exposure and safety challenges to personnel. PERIOD FOR WHICH RELIEF IS REQUESTED NMC requests NRC authorization to perform the proposed alternative test on a K) one-time basis for the system leakage tests following repair/replacement activities on the mechanical joints of SRVs "B" and UG" during the planned maintenance outage. STATUS Approved on June 13, 2003 for use during the 4th Interval, NRC Letter, "Monticello Nuclear Generating Plant - One-Time Inservice Inspection Program Plan Relief Request No. 8 For Leak Testing The UB" And UG' Main Steam Safety Relief Valves" (TAC No. M89538) 1.5-82 Revision 3 3/10/2005
NUCLEAR-MANAGEMENT COMPANY ' INSERVICE INSPECTION MONTICELLO 4th INTERVAL . \t'1.'EXAMINATION PLAN Monticello Unit I - ISI Relief Request No. 9 (Rev. 0) (Fleet Relief Request) Proposed Alternative In Accordance With 10 CFR 50.55a(a)(3)(i) Appendix Vill - Supplement 10 SYSTEM/COMPONENT(S) FOR WHICH RELIEF IS REQUESTED: Pressure Retaining Piping Welds subject to examination using procedures, personnel, and equipment qualified to ASME Section Xi, Appendix Vil, ' Supplement 10 criteria.
'CODE REQUIREMENTS::
The following statements or paragraphs are from ASME Section Xl, Appendix Vill, Supplement 10 and identify the specific requirements that are included in this request for relief. - - Item 1 - Paragraph 1.1 (b) states in part - Pipe diameters within a range of 0.9 to 1.5 times a nominal diameter shall be considered equivalent. Item 2 - Paragraph 1.1 (d) states - All flaws in the specimen set shall be cracks. Item 3 - Paragraph 1.1 (d)(1) states -'At least:50% of -the cracks shall be in austenitic riiaterial. At least 50% of the' cracks in austenitic material shall be contained wholly in weld or buttering material. At least 10% of the cracks shall be in ferritic material. The'remeainder of the cracks'may be in either austenitic or ferritic material.
- Item 4 - Paragraph 1.2(b) states'in part The'nurmber of unflawed grading units shall be at least twice the number of flawed grading 'units.
Item 5 - Paragraph 1.2(c)(1) and 1.3(c) state in part - At least 1/3 of the flaws, rounded to the next higher whole number, shall have depths between 10% and 30% of the nominal pipe wall thickness. Paragraph 1.4(b) distribution table requires 20% of the flaws to have depths between 10% and 30%.
; - 1.5-83 Revision3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Item 6 - Paragraph 2.0 first sentence states - The specimen inside surface and identification shall be concealed from the candidate. Item 7 - Paragraph 2.2(b) states in part - The regions containing a flaw to be sized shall be identified to the candidate. Item 8 - Paragraph 2.2(c) states in part - For a separate length sizing test, the regions of each specimen containing a flaw to be sized shall be identified to the candidate. Item 9 - Paragraph 2.3(a) states - For the depth sizing test, 80% of the flaws shall be sized at a specific location on the surface of the specimen identified to the candidate. Item 10 - Paragraph 2.3(b) states - For the remaining flaws, the regions of each specimen containing a flaw to be sized shall be identified to the candidate. The candidate shall determine the maximum depth of the flaw in each region. Item 11 - Table VIlI-S2-1 provides the false call criteria when the number of unflawed grading units is at least twice the number of flawed grading units. RELIEF REQUESTED Relief is requested to use the following alternative requirements for implementation of Appendix VIII, Supplement 10 requirements. They will be implemented through the Performance Demonstration Initiative (PDI) Program. A copy of the proposed revision to Supplement 10 is attached. It identifies the proposed alternatives and allows them to be viewed in context. It also identifies additional clarifications and enhancements for information. It has been submitted to the ASME Code for consideration and as of September 2002 had been approved by the NDE Subcommittee. BASIS FOR RELIEF Item 1 - The proposed alternative to Paragraph 1.1 (b) states: 1.5-84 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY. -';'. . :INSERVICE INSPECTION MONTICELLO 4th INTERVAL / EXAMINATION PLAN "The specimen set shall include the minimum and maximum pipe diameters and thicknesses for which the examination procedure is applicable. Pipe diameters within 1/2 in. (13 mm) of the nominal diameter shall be considered equivalent. Pipe diameters larger than 24 in. _(610 mm) shall be considered to be flat. When a range of thicknesses is to be examined, a thickness tolerance of +25% is acceptable."! i> Technical Basis'- The change in the minimum pipe diameter tolerance from 0.9 times the diameter to within 1/2 inch of the nominal diameter provides tolerances more in line with industry practice. Though the alternative is less stringent for small pipe diameters they typically have a thinner wall thickness than larger diameter piping.:1A'thinner wall thickness results in shorter sound path distances that reduce the detrimental effects of the curvature. This change maintains consistency between Supplement 10 and the recent revision to Supplement 2. Item 2 - The proposed alternative to Paragraph 111(d) states:
"At least 60% of the flaws shall be cracks, the' remainder shall be alternative flaws. Specimens with IGSCC shall be used when available. Alternative flaws, shall meet the following requirements:
(1) Alternative flaws, if used, shall provide crack-like reflective characteristics and shall only be used when implantation of cracks would produce spurious reflectors that are uncharacteristic of service-induced flaws. (2) Alternative flaw mechanisms shall have a tip width no more than 0.002 in. (.05 mm). Note, to avoid confusion the proposed alternative modifies instances of the term "cracks" or "cracking" to the term uflaws" because of the use of alternative flaw mechanisms."' Technical Basis - As illustrated below, implanting a crack requires excavation of the base material on at least one side of the flaw. While this may be satisfactory for ferritic materials, it does not produce a useable axial flaw in austenitic - materials because the sound beam, which normally passes only through base material, must now travel through weld material on at least one side, producing an unrealistic flaw response. In addition, it is important to preserve the dendritic structure present in field welds that would otherwise be.destroyed by the implantation process. To resolve these issues, the proposed alternative allows the use of up to 40% fabricated flaws as an alternative flaw mechanism under controlled conditions. The fabricated flaws are isostatically compressed which produces ultrasonic reflective characteristics similar to tight cracks. 1.5-85 Revision 3 ' -3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN (t~yationMechanical fatigue crac] in Base material, Item 3 - The proposed alternative to Paragraph 1.1 (d)(1) states: uAt least 80% of the flaws shall be contained wholly in weld or buttering material. At least one and no more than 10% of the flaws shall be in ferritic base material. At least one and no more than 10% of the flaws shall be in austenitic base material." Technical Basis - Under the current Code, as few as 25% of the flaws are contained in austenitic weld or buttering material. Recent experience has indicated that flaws contained within the weld are the likely scenarios. The metallurgical structure of austenitic weld material is ultrasonically more challenging than either ferritic or austenitic base material. The proposed alternative is therefore more challenging than the current Code. Item 4 - The proposed alternative to Paragraph 1.2(b) states: "Personnel performance demonstration detection test sets shall be selected from Table VIII-S10-1. The number of unflawed grading units shall be at least 1-1/2 times the number of flawed grading units." Technical Basis - Table VIII-S10-1 provides a statistically based ratio between the number of unflawed grading units and the number of flawed grading units. The proposed alternative reduces the ratio to 1.5 times. This reduces the number of test samples to a more reasonable number from the human factors perspective. However, the statistical basis used for screening personnel and procedures is still maintained at the same level with competent personnel being successful and less skilled personnel being unsuccessful. The acceptance criteria for the statistical basis are in Table VIII-S10-1. Item 5 - The proposed alternative to the flaw distribution requirements of Paragraph 1.2(c)(1) (detection) and 1.3(c) (length) is to use the Paragraph 1.4(b) (depth) distribution table (see below) for all qualifications. Flaw Depth Minimum (% Wall Thickness)' Number of Flaws 10-30% 20% 31-60% 20% 61-100% 20% 1.5-86 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY :INSERVICE INSPECTION MONTICELLO 4th INTERVAL i :-AMINATION PLAN Technical Basis - The proposed alternative uses the depth sizing distribution for both detection and depth sizing because it provides for a better distribution of flaw sizes within the test set. This distribution allows candidates to perform detection, length, and depth sizing demonstrations simultaneously utilizing the same test set. The requirement that at least 75% of the flaws shall be in the, range of 10 to 60% of wall thickness provides an overall distribution tolerance yet the distribution uncertainty decreases the possibilities for testmanship that would be inherent to a uniform distribution; It must be noted that it is possible to achieve the same distribution utilizing the present requirements, but it is preferable to make the criteria consistent. Item 6 - The proposed alternative to Paragraph 2.0 first sentence states:
"For qualifications from the outside surface, the specimen inside surface and identification shall be concealed from the candidate. When qualifications are performed from the inside surface, the flaw location and specimen identification shall be obscured to maintain a 'blind test".",
I'I Technical Basis'- The current Code requires that the inside surface be concealed from the candidate. This makes qualifications 'conducted from the inside of the pipe (e.g., PWR nozzle to safe end welds) irpractical. The proposed alternative differentiates between ID and OD scanning surfaces, requires that they be conducted separately, and requires that flaws be concealed from the candidate. This is consistent with the recent revision to Supplement 2. Items 7 and 8 The proposed alternatives to Paragraph 2.2(b) and 2.2(c) state:
"... containing a flaw to be sized may be identified to the candidate."
Technical Basis --The current Code requires that the regions of each specimen containing a flaw to be length sized shall be identified to the candidate. The candidate shall determine the length of the flaw in each region (Note, that length and depth sizing use the term "regions" while detection uses the term "grading units" - the two terms define different concepts and are not intended to be equal or interchangeable). To ensure security of the samples, the proposed alternative modifies the first ushall" to a "may" to allow the test administrator the option of not identifying specifically where a flaw is located. This is consistent with the recent revision to Supplement 2.
>1.5-87 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Items 9 and 10 - The proposed alternative to Paragraph 2.3(a) and 2.3(b) state: "... regions of each specimen containing a flaw to be sized may be identified to the candidate." Technical Basis - The current Code requires that a large number of flaws be sized at a specific location: The proposed alternative changes the "shall" to a "may" which modifies this from a specific area to a more generalized region to ensure security of samples. This is consistent with the recent revision to Supplement 2. It also incorporates terminology from length sizing for additional clarity. Item 11 - The proposed alternative modifies the acceptance criteria of Table VIII-S2-1 as follows: TABLE VIII-SZ-1 PERFORMANCE DEMONSTRATION DETECTION TEST ACCEPTANCE CRITERIA Detection Test False Call Test Acceptance Critera Acceptance Criteria I No. of No. of Maximum Flawed Minimum Unflawed Number Grading Detection Grading of False Units Criteria Units Calls 5 10 0 7 16 7 7 12 1 9 7 -lb 2 9 102 10 82- 15 3-2 11 9 2- 17 3 12 9 24- 18 3-3 13 10 2T-20 4-3 14 10 2-21 3 15 11 3e-23 3 16 12 3a- 24 6-4 17 12 34-26 6- 4 18 13 }v 27 4 19 13 3e- 29 7- 4 20 14 40-30 a-5 1.5-88 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Technical Basis - The proposed alternative is identified as new Table VIII-S10-1 above. It was modified to reflect the reduced number of unflawed grading units and allowable false calls. 'As a part of ongoing Code-activities, Pacific Northwest National Laboratory (PNNL) has reviewed the statistical significance of these revisions and offered the revised Table S1 0-1. ' ALTERNATIVE EXAMINATION
- In lieu of the requirements of ASME Section Xl, Appendix VtIII, Supplement 10, the proposed alternative shall be used. The proposed alternative is described in the enclosure.
JUSTIFICATION FOR GRANTING RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), approval is requested to use the proposed alternatives described above in lieu of the ASME Section Xl, Appendix Vil, Supplement 10 requirements. Compliance with'thd proposed alternatives will provide -an acceptable level of quality and safety for examination of the affected welds. IMPLEMENTATION SCHEDULE This technical alternative will be used at Duane Arnold Energy Center; Monticello Nuclear Generating Plant; Point Beach'Nuclear Plant, Units 1 And 2; Prairie Island Nu'c!ear Generating Plant Units 1And 2; Kewaunee Nuclear Power Plant;' and Palisades Nuclear Plant during each plant's present Ten-Year Interval of the Inservice Inspection Program.--(See Attachment 1 for Interval dates.)
,STATUS' Approved on February 26, 2004 for during the 4th Interval, NRC Letter, "Duane Arnold Energy Center, Monticello Nuclear Generating Plant, Prairie Island Nuclear Generating Plant, Units I and 2, Kewaunee Nuclear Power Plant, Point Beach Nuclear Plant, Units 1 and 2, Palisades Nuclear Plant Re: Request for -
Alternatives to American Society of Mechanical Engineers (ASME) Section XI, Appendix VIII, Supplement 10 (TAC NOS. MC0814, MC0816, MC0820, MC0821, MC0815, MC0818, MC0819 AND MC0817)' 1.5-89 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL
- EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Req uiremnent Proposed Change Reasoning 1.0 SCOPE Supplement 10 is applicable to dissimilar A scope statement provides added metal piping welds examined from either clarity regarding the applicable the inside or outside surface, range of each individual Supplement 10 is not applicable to Supplement. The exclusion of piping welds containing supplemental CRC provides consistency corrosion resistant clad (CRC) applied to between Supplement 10 and the mitigate Intergranular Stress Corrosion recent revision to Supplement 2 Cracking (IGSCC). (Reference BC 00-755). Note, an additional change identifying CRC as "in course of preparation" is being processed separately.
1.0 SPECIMEN REQUIREMENTS 2.0 SPECIMEN REQUIREMENTS Renumbered Qualification test specimens shall Qualification test specimens shall meet the No Change meet the requirements listed herein, requirements listed herein, unless a set of unless a set of specimens is specimens is designed to accommodate designed to accommodate specific specific limitations stated in the scope of the limitations stated in the scope of the examination procedure (e.g., pipe size, weld examination procedure (e.g., pipe joint configuration, access limitations). The size, weld joint configuration, access same specimens may be used to limitations). The same specimens demonstrate both detection and sizing may be used to demonstrate both qualification. detection and sizing qualification. . C. R( on 3 3tiu/2005
C C. NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10- QUALIFICATION REQUIREMENTS FOR DISSIMILAR
- METAL PIPING WELDS .
Current Requirement : Proposed Change . . Reasoning. 1.1 General. The specimen set shall 2.1 General. - Renumbered conform to the following The specimen set shall conform to the - requirements. following requirements. (a) The minimum number of flaws in a - New,,changed minimum number of specimen set shall be ten. flaws to 10 so sample set size for detection is consistent with length and depth sizing. (a) Specimens shall have sufficient (b) Specimens shall have sufficient volume Renumbered volume to minimize spurious to minimize spurious reflections that may reflections' that may interfere with the interfere with the interpretation process. interpretation process ,. . . . (b)-The specimen set shall include (c) The-specimen set shall include then Renumbered; metricated, the the minimum and maximum pipe minimumand maximum pipe diameters-and change. in pipe.diameter tolerance diameters and thicknesses for which thicknesses for which the examination provides consistency between, the examination procedure is procedure is applicable.iPipe'diametdrs Supplement 10 and the recent 11 applicable. Pipe diameters within a within 1/2 in. (13 mm) of the nominal revision to Supplement 2 range of 0.9 to 1.5 times a nominal diameter shall be considered equivalent. (Reference BC 00-755)
'diameteir'shall be considered Pipe diameters larger than 24 in; (610 mm) .
equivalent. Pipe diameters larger shall'be considered to be flat. When a than 24 in. shall be considered to be range of thicknesses is to be examined, a flat. When a range of thicknesses is thickness tolerance of +25% is acceptable.- to be examined, a thickness tolerance of +25% is acceptable. 1.5-91 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 1O- QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Proposed Change Reasoning (c) The specimen set shall include (d) The specimen set shall include. Renumbered, changed "condition" examples of the following fabrication examples of the following fabrication to "conditions" condition: conditions: - (1) geometric conditions that (1) geometric and material conditions that Clarification, some of the items normally require discrimination from normally require discrimination from flaws listed relate to material conditions flaws (e.g., counterbore or weld root (e.g., counterbore or weld root conditions, rather than geometric conditions. conditions, cladding, weld buttering, cladding, weld buttering, remnants of Weld repair areas were added as remnants of previous welds, adjacent previous welds, adjacent welds in close a result of recent field welds in close proximity); proximity, weld repair areas; experiences. (2) typical limited scanning surface (2) typical limited scanning surface Differentiates between ID and OD conditions (e.g., diametrical shrink, conditions shall be included as follows: scanning surface limitations. single-side access due to nozzle and (a) for outside surface examination, weld Requires that ID and OD safe end external tapers). crowns; diametrical shrink, single-side qualifications be conducted access due to nozzle and safe end external independently (Note, new tapers, paragraph 2.0 (identical to old (b) for inside surface examination, paragraph 1.0) provides for internal tapers, exposed weld roots, and alternatives when "a set of cladding conditions for inside surface specimens is designed to examinations.. accommodate specific limitations (e) Qualification requirements shall be stated in the scope of the satisfied separately for outside surface examination procedure.").- and inside surface examinations. (' R( on 3 3P u/2005
C C C NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
- -- -SUPPLEMENT 10-7QUALIFICATION REQUIREMENTS FOR DISSIMILAR
._____ . ;METAL PIPING WELDS ::
CurrentRequirement l Proposed Clange Reasoning (d) All flaws in the specimen set shall - Deleted this requirement, because be cracks. new paragraph 2.3 below provides for the use of "alternative flaws" in I.;, lieu of cracks.. .. . (1) At least 50% of the cracks shall 2.2 Flaw Location. Renumbered and re-titled. Flaw be in austenitic material. At least At least 80% of the flaws shall be contained location percentages redistributed 50% of the cracks in austenitic wholly in weld or buttering material. At least because field experience indicates material shall be contained wholly in one and no more than 10% of the flaws that flaws contained in weld or weld or buttering material. At least shall be in ferritic base material. At least buttering material are probable 10% of the cracks shall be in ferritic one and no more than 10% of the flaws and represent the more stringent material. The remainder of the cracks shall be in austenitic base material. ultrasonic detection scenario. may be in either austenitic or ferritic ., ,. ..- r-I.- M .. material.-' - . w
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. I .1 .. I . . I 1.5-93 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Req uiremelint Proposed Change Reasoning (2) At least 50% of the cracks in 2.3 Flaw Type. Renumbered and re-titled. austenitic base material shall be (a) At' least 60% of the flaws shall be Alternative flaws are required for either IGSCC or thermal fatigue cracks, and the remainder shall be placing axial flaws in the HAZ of cracks. At least 50% of the cracks in alternative flaws. Specimens with IGSCC the weld and other areas where ferritic material shall be mechanically shall be used when available. Alternative implantation of a crack produces or thermally induced fatigue cracks. flaws shall meet the following metallurgical conditions that result requirements:**' in an unrealistic ultrasonic (1) Alternative flaws, if used, shall response. This is consistent with provide crack-like reflective the recent revision to Supplement characteristics and shall only be used 2 (Reference BC 00-755). when implantation of cracks would produce spurious reflectors that are The 40%,limit needed t onor alternative te flaws uncharacteristic of service-induced ireent fo up to a flawsrequirement flaws.flw.Mtiae for up to 70% axial (2) Alternative flaws shall have a tip flaws. Metricated
-_ width no more than 0.002 in. (.05 mm).
(3) At least 50% of the cracks shall (b) At least 50% of the flaws shall be Renumbered. Due to inclusion of be coincident with areas described in coincident with areas described in 2.1(d) "alternative flaws",' use of "cracks" (c) above. above. is no longer appropriate. ( 1C4 R( 'on 3 3/10/2005
C
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(-. NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
- SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR. .
-__ - .METAL PIPING WELDS
'Current Requirement Proposed Change Reasoning,
-;- .- 2.4 Flaw Depth. - -
- ;- -- > - (All flaw depths shall be greater than 10% of Moved from old paragraph 1.3(c)
. the nominal pipe wall thickness. Flaw and 1.4 and re-titled. Consistency depths shall exceed the nominal clad between detection and sizing thickness when placed in cladding. Flaws in specimen set requirements (e.g.,
the sample set shall be distributed as 20% vs. 1/3 flaw depth follows: increments, e.g., original paragraph 1.3(c))
. ,Flaw Depth Minimum
-% Wall Thickness) Number of
{; ; ,, , Flaws
.. 10-30% 20%
i.31-60% 20% 61-100% 20% At least 75% of the flaws shall be in the --
- range of 10 to 60% of wall thickness.
1.2 Detection Specimens. The Renumbered and re-titled and specimen set shall include detection - : moved to paragraph 3.1(a). No specimens that meet the following other changes requirements.
, I , , ,: ,: - I , ., 7 ., I . I I - I I . , ,
1.5-95 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSImILAR METAL PIPING WELDS
- Current Requirement Proposed Change Reasoninig (a) Specimens shall be divided into Renumbered to paragraph grading units. Each grading unit shall 3.1 (a)(1). No other changes.
include at least 3 in. of weld length. If a grading unit is designed to be unflawed, at least 1 in. of unflawed material shall exist on either side of the grading unit. The segment of weld length used in one grading unit shall not be used in another grading unit. Grading units need not be uniformly spaced around the pipe specimen. (b) Detection sets shall be selected Moved to new paragraph from Table VIII-S2-1. The number of 3.1 (a)(2). unflawed grading units shall be at least twice the number of flawed grading units. (c) Flawed grading units shall meet Flaw depth requirements moved to the following criteria for flaw depth, new paragraph 2.4, flaw orientation, and type. orientation requirements moved to new paragraph 2.5, flaw type requirements moved to new paragraph 2.3, 'Flaw Type". ( i(- R ion 3 3 01/2005
( C :C, NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS - - Current Requirement Proposed Change Reasoning (1) All flaw depths shall be greater Deleted, for consistency in sample than 10% of the nominal pipe wall sets the depth.'distribution is the thickness. At least 1/3 of the flaws,' . same s for detection and sizing. rounded to the next higher whole number, shall have-depths between 10% and 30% of the nominal-pipe wall thickness. However, flaw depths shall exceed the nominal clad thickness when placed in cladding. At least 1/3 of the flaws, rounded to the next whole number, shall have depths greater than 30% of the;.,-, nominal pipe wall thickness. - - - (2) At least 30% and no more than 2.5 Flaw Orientation. Note, this distribution is applicable 70% of the flaws, rounded to the next (a) For other than sizing specimens at least for detection and depth sizing. higher whble number, shall be ' - 30% and no more than 70% of the flaws, - Paragraph 2.5(b)(1) requires that-oriented axially. The remainder of the rounded to the next higher whole number, all length- sizing flaws be oriented flaws shall be oriented shall be oriented axially. The remainder of circumferentially. circumferentially. the flaws shall be oriented circumferentially.- 1.3 Length Sizing Specimens.-The Renumbered and re-titled and specimren set shall include length - : : moved to new paragraph 3.2 sizing specimens that meet the following requirements. (a) All length sizing flaws shall be Moved, included in new paragraph oriented circumferentially.- ._ 3.2(a) 1.5-97 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10- QUALIFICATION REQUIENIENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Proposed ChIa3nge Reasoning (b)The minimum number of flaws Moved, included in new paragraph shall be ten. 2.1 above (c) All flaw depths shall be greater Moved, included in new paragraph than 10% of the nominal pipe wall 2.4 above after revision for thickness. At least 1/3 of the flaws, consistency with detection rounded to the next higher whole distribution number, shall have depths between 10% and 30% of the nominal pipe wall thickness. However, flaw depth shall exceed the nominal clad thickness when placed in cladding. At least 1/3 of the flaws, rounded to the next whole number, shall have depths greater than 30% of the nominal pipe wall thickness. 1.4 Depth Sizing Specimens. The Moved, included in new, specimen set shall include depth paragraphs 2.1, 2.3, 2.4 sizing specimens that meet the following requirements. ._.._.. (a) The minimum number of flaws Moved, included in new paragraph shall be ten. 2.1: (. 1( 3 ion 3 3i U/2005
( C Cl NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL -EXAMINATION PLAN
. .SUPPLEMENT 10- QUALIFICATION REQUIREMENTS FOR DISSIMILAR ,
- METAL PIPING WELDS Current Requiirement i Proposed Change . Reasoning (b) Flaws in the sample set shall not Moved, potential conflict with old be wholly contained within cladding ,- paragraph 1.2(c)(1); "However, and shall be distributed as follows: -flaw depths shall exceed the J_
and shall be distribd - as f -nominal : clad thickness when
, ,. . * - z; -. - placed in cladding.". Revised for clarity and included in new
._ ._-_--_-_-_-_-_paragraph
_ 2.4 Flaw Depth - - Minimum *. - . -- Moved, included in paragraph 2.4 (% Wall Thickness) Number of .r; .... . for consistent applicability to Flaws -- - : . . -; . - detection and sizing samples. 30% . . , 2-20% - ; : oAd61 -100%->! I 20%; a;. l;, s!. ,,t8'rn a;tv1;"~'t ^a
-sse*?~ .: V The remaining flaws shall be in any........-.
of the above categories. (b) Sizing Specimen sets shall meet the Added for clarity
.following requirements.
(1) Length-sizing flaws shall be oriented Moved from old paragraph 1.3(a)
. . circumferentially.
(2) Depth sizing flaws shall be oriented Included for clarity. Previously as in 2.5(a). addressed by omission (i.e., length, but not depth had a s ific exclusionary statement) 1.5-99 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10- QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Propiosed Clhange Reasoning. 2.0 CONDUCT OF 3.0 CONDUCT OF PERFORMANCE Renumbered PERFORMANCE DEMONSTRATION DEMONSTRATION The specimen inside surface and Personnel and procedure performance Differentiate between identification shall be concealed from demonstration tests shall be conducted qualifications conducted from the the candidate. All examinations shall according to the following requirements. outside and inside surface. be completed prior to grading the (a) For qualifications from the outside results and presenting the results to surface, the specimen inside surface and the candidate. Divulgence of identification shall be concealed from the particular specimen results or candidate. When qualifications are candidate viewing of unmasked performed from the inside surface, the specimens after the performance flaw location and specimen identification demonstration is prohibited. shall be obscured to maintain a "blind test". All examinations shall be completed prior to grading the results and presenting the results to the candidate. Divulgence of particular specimen results or candidate viewing of unmasked specimens after the performance demonstration is prohibited.' 2.1 Detection Test. Flawed and 3.1 Detection Qualification. Renumbered, moved text to unflawed grading units shall be paragraph 3.1(a)(3) randomly mixed (a) The specimen set shall include detection Renumbered, moved from old specimens that meet the following paragraph 1.2. requirements. (. 1.( 0- R( on 3 3hKu/2005
c C" ~C NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Proposed Clhange Reasoning
., . . ., (1) Specimens shall be divided into grading Renumbered, moved from old _,
-, a units. paragraph 1.2(a)! Metricated. No (a) Each grading unit shall include at least 3 other changes.
in. (76 mm) of weld length. " -
; -. ,-:-(b)The end of each flaw shall be separated
- ' . from an unflawed grading unit by at least 1 in. (25 mm) of unflawed material. A flaw may be less than 3 in. (76 mm) in length.
(c) The segment of weld length used in one grading unit shall not be used in another grading unit. (d) Grading units need not be uniformly ,;' spaced arourid the pipe'specimen. 1u . o . (2) Personnel performance demonstration Moved from old paragraph 1.2(b). detection test sets shall be selected from Table revised to reflect a change Table VIII-S10-1. The number of unflawed in the minimum sample' set to 10 grading units shall be-at least.1-1/2 times- and the application of equivalent
. . e number of flawed grading units. statistical false call'parameters to
. ,the reduction in unflawed grading units.
Human factors due to large sample size.
,. -,, -, . . (3) Flawed and unflawed grading units shall Moved from old paragraph 2.1 be randomly mixed.
1.5-1 01 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Proposed Change Reasoning (b) Examination equipment and personnel Moved from old paragraph 3.1. are qualified for detection when personnel Modified to reflect the 100% demonstrations satisfy the acceptance detection acceptance criteria of criteria of Table Vil SIO-1 for both detection procedures versus personnel and and false calls. equipment contained in new paragraph 4.0 and the use of 1.5X rather than 2X unflawed grading units contained in new paragraph 3.1(a)(2). Note, the modified table maintains the screening criteria of the original Table Vill-S2-1. 2.2 Length Sizing Test 3.2 Length Sizing Test Renumbered (a) The length sizing test may be (a) Each reported circumferential flaw in Provides consistency between conducted separately or in the detection test shall be length-sized. Supplement 10 and the recent conjunction with the detection test. revision to Supplement 2 (Reference BC 00-755). 1-{. 2 RC' ion 3 3/10/2005
C CC I NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL - ; . . I. , - .. .I - EXAMINATION PLAN
.. , *I SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR
. . _ . .. PIPING WELDS. ..
-:METAL -. -
Current Requirement Proposed Chainge Reasoning (b) When the length sizing test is (b) When the length-sizing test is conducted Change made-to ensure security conducted in coniunction with the in conjunction with the detection test; and of samples,- consistent with the detection test, and less than ten less than ten circumferential flaws are - recent revision to Supplement 2 circumferential flaws are detected, detected, additional -specimens shall be . (Reference BC 00-755). additional' specimens shall be prbvided to the 'candidate su6h thatat least' provided to the candidate such ten flaws are sized. The regionscontaining Note, length and depth sizing use that at least ten flaws are sized. a flaw to be sized may be identified to the the term "regions" while detection The regions containing a flaw to candidate. The candidate shall determine uses the term "grading units". The be sized shall be identified to the the length of the flaw'in each region. two terms define different __________________________concepts and are niot intended to a a no to candidate. The candidate shall ; . c determine the length of the flaw in . be equal or interchangeable. each region. . ; -: (c) For a separate length sizing (c) For a separate length-sizing test, the Change made to ensure security test, the regions of each 'specimen regions of each specimen containing a flaw of samples, consistent with the containing a flaw to be sized shall to be sized may be identified to the recent revision to Supplement 2 be identified to the candidate. The candidate. The candidate shall'determine (Reference BC 00-755). candidate -shall determine the the length of the flaw in each region. length of the flaw in each region.- - - - - (d) Examination procedures, equipment, Moved from old paragraph 3.2(a) and personnel are qualified for length-sizing includes inclusion of "when" as an when the RMS error of the flaw length editorial change. measurements, as compared to the true flaw Metricated.
- a-s *. - , lengths, do not exceed 0.75 in. (19 mm).
23 Depth Sizinq Test 3.3 Depth Sizing Test Renumbered 1.5-1 03 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Proposed Change Reasoning (a) For the depth sizing test, 80% of (a) The depth-sizing test may be Change made to ensure security the flaws shall be sized at a specific conducted separately or in conjunction of samples, consistent with the location on the surface of the with the detection test. For a separate recent revision to Supplement 2 specimen identified to the candidate. depth-sizing test, the regions of each (Reference BC 00-755). specimen containing a flaw to be sized may be identified to the candidate. The candidate shall determine the maximum depth of the flaw in each region. (b) For the remaining flaws, the (b) When the depth-sizing test is Change made to be consistent regions of each specimen containing conducted in conjunction with the with the recent revision to a flaw to be sized.shall be identified detection test, and less than ten flaws Supplement 2 (Reference BC 00-to the candidate. The'candidate, shall are detected,'additional specimens shall 755). determine the maximum depth of the be provided to the candidate such that at flaw in each region. least ten flaws are sized. The regions of Changes made to ensure security each specimen containing a flaw to be sized of samples, consistent.with the may be identified to the candidate. The recent revision to Supplement 2 candidate shall determine the maximum (Reference BC 00-755). depth of the flaw in each region. (c) Examination procedures,'equipment, Moved from old paragraph 3.2(b). and personnel are qualified for depth sizing Metricated. when the RMS error of the flaw depth measurements, as compared to the true flaw depths, do not exceed 0.125 in. (3 mm). ( A4 R(' ion 3 3/10/2005
c C :c NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requirement Proposed Change Reasoning 3.0 ACCEPTANCE CRITERIA Delete as a separate category. Moved to new paragraph detection (3.1) and sizing 3.2 and 3.3 3.1 Detection Acceptance Criteria. Moved to new paragraph 3.1 (b), Examination procedures, equipment, reference changed to Table S10 and personnel are qualified for from S2 because of the change in detection when the results of the the minimum number of flaws and performance demonstration satisfy the reduction in unflawed grading the acceptance criteria of Table VIII- fro'if'2X t -1.5X.
'unit's S2-1 for both detection and false a .,','i, . ---.-.
calls.; . ,. ___________________________________ 3.2 Sizing Acceptance Criteria: '.* Deleted as a separate category.
*1 I- -,- , i 1 ; . .) I.- I I Moved to new paragraph on length 3.2 and depth 3.3 (a) Examination procedures, Moved to new paragraph 3.2(d),
equipment,* and personnel 'are included word "when" as an qualified for length sizing' the RMS . editorial chan'ge. ' error of the flaw length measurements, as compared to the ' true flaw lengths, is less than or' equal to 0.75 inch. I - : - m: - I . I . . - ; - ' - rI ! I I 1.5-1 05 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS Current Requiremienit Proposed Clhanige Reasoning (b) Examination procedures, Moved.to new paragraph 3.3(c) equipment,. and personnel are qualified for depth sizing when the RMS error of the flaw depth measurements,-las compared to the true flaw depths, is less than or equal to 0.125 in. . 14.0 PROCEDURE QUALIFICATION New { 6 R( *on3 3/1 u/2005
C C (7 NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
-SUPPLEMENT 10 - QUALIFICATION REQUIREMENTS FOR DISSIMILAR
-I - METAL PIPING WELDS Current Requiremeit . ; Proposed Chauge Reasoning Procedure qualifications shall include New. Based on experience the following additional requirements. gained in conducting (a)The specimen set shall include the qualifications, the equivalent of 3 equivalent of at least three personnel personnel sets (i.e;, a minimum of performance-demonstration test sets. 30 flaws) is required to provide Successful personnel performance enough flaws to adequately test demonstrations may be combined to the capabilities of the procedure.
satisfy these requirements. Combining successful (b) Detectability of all flaws in the demonstrations allows a variety of procedure qualification test set that are examiners tobe used to qualify within the scope of the procedure shall the procedure. Detectability of be demonstrated. Length'and depth :: each-flaw within the scope of the sizing shall mieet the requirements of procedure is required to ensure an paragraph 3.1, 3.2, and 33 acceptable personnel pass rate. (c) At least one successful personnel The last sentence is equivalent to demonstration shall be performed. the requirements previousfor and is expanding the satisfactory (d) To qualify.;new values of. essential sstial variablesdofg pre
.essential variables of a previously variables, at least one personnel qualification set is required. The - qualified procedure
__ _ :acceptance criteria of 4.0(b) shall be met. 1.5-1 07 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION-MONTICELLO 4th INTERVAL EXAMINATION PLAN ii Monticello Unit 1 - ISI Relief Request No. 10 (Rev. 0) (Fleet Relief Request) Duane Arnold Energy Center Monticello Nuclear Generating Plant
- I I
Alternative to Use Code Case N-61 3-1 i i
- 1. ASME Code Component(s) Affected i Code Class: Class 1
Reference:
ASME, Section Xl I i Examination Category: B-D i Item Number: B3.90 I
== Description:== Reactor Vessel Full Penetration Nozzle-to-Vessel Welds I Component Numbers: See Tables 1 and 2 i
- 2. Applicable Code Edition and Addenda-ASME Section Xl 1989 Edition, no Addenda is applicable to the Duane Arnold Energy Center (DAEC) Inservice Inspection (ISI) Program for the Third Ten-Year Interval. I I
\,_ I ASME Section Xl 1995 Edition, 1996 Addenda is applicable to the Monticello Nuclear Generating Plant (MNGP) ISI Program for the Fourth Ten-Year Interval. i i
3. Applicable Code Requirement
Nuclear Management Company (NMC), LLC is currently required to perform inservice examinations of selected reactor vessel nozzle-to-vessel welds in accordance with the requirements of 10 CFR 50.55a, and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components. Table IWB-2500-1, Examination Category B-D, Item No. B3.90 specifies the examination requirements. Figure IWB-2500-7(b) requires that a minimum volume of material, a distance of tsI2 (one half the reactor vessel shell thickness) adjacent-to the weld, be examined.
4. Reason for Request
The required examination volume for the reactor vessel pressure retaining nozzle-to-vessel welds extends far beyond the weld into the base metal, and is unnecessarily large. This proposed alternative would re-define the examination volume boundary to 1/2 inch of base metal on each side of the widest portion of the weld, removing from examination the base metal that was extensively examined during prior inspections, and is not in the high residual stress region associated with the weld. 1.5-108 Revision 3 3/10/2005
'NUCLEAR MANAGEMENT COMPANY - INSERVICE INSPECTION MONTICELLO 4th INTERVAL -, or:' ECXAMINATION PLAN
- 5. Proposed Altemative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), authorization is requested to use the proposed alternative described in ASME Boiler and Pressure Vessel Code Section Xl Code Case N-61 3-1 in lieu of the ASME Section Xl Table IWB-2500-1 Examination Category B3.90 requirements. Cbnmpliance with the proposed alternative will provide an acceptable level of quality and safety for examination of the affected welds.
In lieu of the tsI2 volume requirement of ASME Section Xl, Figure IWB-2500-7(b), NMC proposes to reduce the examination volume next to the widest part of the weld to one-half (1/2) inch from the weld. This refined examination volume is defined in detail within Code Case N-613-1. NMC will use Code Case N-613-1 for the Reactor Pressure Vessel (RPV) nozzles as shown in Figure 2 of the Code Case. ex-iato--- , The required examination'volume for the RPV nozzleto-vessel welds extends far beyond the weld into the base metal, and is unnecessarily large. This proposed alternative would re-define the examination volume boundary to 1/2 inch of base metal on each side of the widest portion of the weld. This reduction in base metal inspection will not affect the flaw detection capabilities in the weld and heat affected zone. The proposed reduction in exam volume is base metal only. -I The creation of flaws during plant service in the volume excluded from the proposed reduced examination 'is'unlikely because of the low stress in the base 'metal away from the weld. The stresses caused by -welding are concentrated at or near the weld. Cracks, should they initiate, occur in the high-stressed areas of the weld. These high stress areas are contained in the volume that'is'defined by Code Case N-613-1 and are thus subject to examination. During previous examinations, no indications exceeding the allowable limits of the p'reservice or inservice criteria were found in'the reactor vessel nozzle to shell examination volumes including the base metal areas proposed for exclusion from examination in this request. The prior thorough examination of the base metal and the examination of the high-stressed areas of the weld lr6Videian acceptable level of quality and safety.' -6.- Duration of Proposed Alternative , This technical alternative will be used at DAEC during the current Third Ten-Year Interval of the Inservice Inspection Program scheduled to end on November 1, 2005, and at MNGP during the current Fourth Ten-Year. Interval of the Inservice Inspection Program scheduled to end on May 31, 2012. The use of Code Case N-613-1 is requested'until the'NRC publishes the Code Case in a future revision of Regulatory Guide 1.147.--
- -'1.5-109
- - Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN K>s~ STATUS Approved on October 6,-2004 for during the 4th Interval, NRC Letter, 'Duane Arnold Energy Center and Monticello Nuclear Generating Plant Re: Request for Authorization to Utilize Code Case N-613-1 (TAC Nos. MC2374 and MC2375)" I i i t i Table 1 - i DAEC Nozzle-to-Vessel Welds Within Scope of Request- i (NOT INCLUDED IN MNGP ISI PLAN) I i i I iI Ij i i Table 2 I MNGP Nozzle-to-Vessel Welds Within Scope of Request Summary - Weld Nozzle Full Volume Exam Nondestructive Number Identification Configuration Previously Completed to. Examination and Description Extent Achievable (NDE) Method 102652 N-1A NV, Code Case N- Examined in 1994 from UT-0 RPV N-lA 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Suction recordable indications. 102654 N-1B NV, Code Case N- Examined in 2001 from UT-0 RPV N-1 B 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Suction recordable indications. 102656 N-2A NV, Code Case N- Examined in 2001 from UT-0 RPV N-2A 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Riser Inlet recordable indications. . 102658 N-2B NV, Code Case N- Examined in 2001 from - UT-0 RPV N-2B 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Riser Inlet recordable indications. 1.5-110 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY i ,`.§ INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' _ .EXAMINATION PLAN
-Table 2 MNGP Nozzle-to-Vessel Welds Within Scope of Request Summary Weld -Nozzle Full Volume Exam Nondestructive Number Identification.' Configuration Previously Completed to Examination and Description Extent Achievable - (NDE)
Method 102660 N-2C NV, Code Case N- Examined in 2000 from UT-0 RPV N-2C 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Riser Inlet recordable indications. 102662 N-2D NV, Code Case N- Examined in 1994 from UT-0 RPV N-2D' 613-1, RPV shell side only due to UT-45 Nozzle, Recirc' Figure 2 nozzle configuration; no UT-60 Riser Inlet recordable indications. 102664 N-2E NV, Code Case N- Examined in 1994 from UT-0 RPV N-2E 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Riser Inlet recordable indications. -102666 N-2F NV, Code Case N- Examined in 2000 from UT-0 RPV N-2F 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle`configuration; no UT-60 Riser.Inlet" ' ' recordable indications. 102668 - N-2G NV, Code Case N- Examined in 1998 from - UT-0 RPV N-2G 613-1, RPV shell side only due to UT-45 Nozzle, Recirc 'Figure 2 nozzle configuration; no UT-60 Riser Inlet recordable indications. ':' 102670. N-2H NV, Code Case N- Examined in 1998 from UT-0 RPV N-2H i 613-1, RPV shell side only due to UT-45 Nozzle,'Recirc Figure 2 nozzle'configuration; no UT-60 Riser Inlet . recordable indications. 102672 N-2J NV, Code Case N- Examined in 1994 from UT-0 RPV N-2J 613-1, RPV shell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no UT-60 Riser Inlet, recordable indications. 102674 - N-2K NV, Code Case N- Examined in 2001 from UT-0 RPV N-2K ' 613-1, RPVshell side only due to UT-45 Nozzle, Recirc Figure 2 nozzle configuration; no,. UT-60 Riser Inlet' ' ' recordable indications., 102676 N-3A NV, -- Code Case N- Examined in 1994 from - UT-0 RPV. N-3A, Main 613-1,' RPV shell side only due to UT-45 Steam Outlet Figure 2 nozzle configuration; no UT-60 recordable indications. 102678 - N-3B NV, - Code Case N- Examined in 2000 from UT-0 RPV N-3B, Main 613-1, RPVshell side onlydue to UT-45 Steam Outlet"" Figure 2 nozzle configuration; no ' UT-60 recordable indications. ;
-: 1.5-111 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY .. - INSERVICE INSPECTION MONTICELLO 4th INTERVAL - EXAMINATION PLAN V) Table 2 MNGP Nozzle-to-Vessel Welds Within Scope of Request I Summary -Weld Nozzle Full Volume Exam Nondestructive Number Identification Configuration Previously Completed to Examination and Description Extent Achievable (NDE) Method 102680 N-3C NV, Code Case N- Examined in 1998 from UT-0 RPV N-3C, Main 613-1, RPV shell side only due to UT-45 Steam Outlet Figure 2 nozzle configuration; One UT-60 indication was recorded with the 600 scan which required evaluation per ASME Code Section Xl, 1986 Edition with no Addenda and was found to be acceptable. Indication is contained within the reduced volume of Code Case N-613-1, Figure 2.- 102682 N-3D NV, Code Case N- Examined in 2000 from UT-0 RPV N-3D, Main 613-1, RPV shell side only due to UT-45 Steam Outlet Figure 2 nozzle configuration; no UT-60 recordable indications. 102684 N-4A NV, Code Case N- Examined in 1996 from UT-0 RPV N-4A, 613-1, RPV shell side only due to UT-45 Feedwater Inlet Figure 2 nozzle configuration; no UT-60 recordable indications. 102686 N-4B NV, Code Case N- Examined in 1998 from UT-0 RPV N-4B, 613-1, RPV shell side only due to UT-45 Feedwater Inlet Figure 2 nozzle configuration; no UT-60 recordable indications. 102688 N-4C NV, Code Case N- Examined in 1994 from UT-0 RPV N-4C, 613-1, RPV shell side only due to UT-45 Feedwater Inlet Figure 2 nozzle configuration; no UT-60 recordable indications. ' 102690 N-4D NV, Code Case N- Examined in 2000 from UT-0 RPV N-4D, 613-1, RPV'shell side only due to UT-45 Feedwater Inlet Figure 2 nozzle configuration; no UT-60
- recordable indications.
102692 N-5A NV, Code Case N- Examined in 2000 from UT-0 RPV N-5A, Core 613-1, RPV shell side only due to UT-45 Spray Inlet Figure 2 nozzle configuration; no UT-60 recordable indications. 102694 N-5B NV, Code Case N- Examined in 1994 from UT RPV N-5B, Core 613-1, RPV shell side only due to UT-45 Spray Inlet Figure 2 nozzle configuration; no UT-60 recordable indications. 1.5-112 Revision 3 3/10/2005
".'NUCLEAR MANAGEMENT COMPANY ' ' - I - INSERVICE INSPECTION MONTICELLO 4th INTERVAL ml--EXAMINATION PLAN
- .. . . , . - t
- 57' ' ; .
i_ - . ; .Table 2 -:, MNGP Nozzle-to-Vessel Welds Within Scope of Request Summary -- Weld - -- l Nozzle --- Full Volume Exam Nondestructive Number Identification 'Configuration Previously Completed to Examination
-and Description Extent Achievable - (NDE)
Method 102375 N-6A NV, Code Case N- Examined in 1996 from UT-0 RPV N-6A, 613-1, RPV shell side only due to UT-45 Spare (formerly Figure 2 nozzle configuration; no UT-60 Reactor Vessel . recordable indications. - Head Spray) 102377 N-6B NV,. . Code Case N- Examined in 2000 from UT-0 RPV N-6B, 613-1, RPV she'll side only due to UT-45 Spare Figure 2 nozzle configuration; no UT-60
.____;__ _ _ _-_-_ _.recordable indications. '_
102379 N-7 NV, Code Case N- Examined in 1998 from UT-0 RPV N-7,, 613-1, RPV shell sideonly due to UT-45 Reactor Vessel Figure 2 nozzle configuration; no UT-60 Head Vent recordable'indications. ' _'_: i 102696 N-8A NV, Code Case N- Examined in 1994 from UT-0 RPV N-8A, Jet - 613-1, RPV shell side only due to UT-45 Pump Figure 2 nozzle'configuration; no UT-60 i Instrumentation recordable indications. 102698 N-8B NV, - Code Case N- Examined in 2001 from UT-0: RPV N-8B, Jet 613-1, RPV shell side only due to UT-45 Pump Figure 2 nozzle configuration; no UT-60
. Instrumentation . recordable indications.
I 102700 N-9 NV, Code Case N- Examined in 1996 from UT-0 RPV N-9, Spare 613-1, RPV shell side only due to UT-45 (formerly CRD Figure 2 nozzle configuration; no UT-60
. Return) - recordable indications.
102623 N-10 NV, Code Case N- Examined in 2000 from UT-0 RPV N-1 0, 613-1, RPV shell side only due to UT-45 Standby Liquid Figure 2 nozzle configuration; no'" ' UT-60 Control Injection recordable indications. I
,-,I , 4 ! . : " , :_ , ,
. - . ., t . _ . I ,
- . . . . - , i
- -- 1.5-113 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN Monticello Unit I - [SI Relief Request No. 11 (Rev. 0) (Fleet Relief Request) Request For Authorization To Utilize Code Case N-661 10 CFR 50.55a Request GR-04-01 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
- 1. ASME Code Component(s) Affected ASME Section Xl, Class 2 and 3 Carbon Steel Piping for Raw Water Service
- 2. Applicable ASME Section XI Code Edition and Addenda The applicable Codes for Repair/Replacement activities are as follows:
Monticello (2001 Edition) Prairie Island (1998 Edition with the 2000 Addenda) Point Beach (1998 Edition with the 2000 Addenda) Kewaunee (1998 Edition with the 2000 Addenda) Palisades (1989. Edition) Duane Arnold (1992 Edition with the 1992 Addenda)
3. Applicable Code Requirement
ASME Section Xl 1989 Edition IWA-4120(a) requires that repairs be performed in accordance with the Owner's Design. Specification and the original Construction Code of the component or system. IWA-4310 requires that defects be removed or reduced in size in accordance with IWA-4000. ASME Section Xl 1992 Edition with the 1992 Addenda IWA-4170(b) requires that repairs and installation of replacement items shall be performed in accordance with the Owner's Design Specification and the original Construction Code of the component or system. IWA-4310 requires that defects be removed or reduced in size in accordance with IWA-4000. 1.5-114 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY , .j INSERVICE INSPECTION MONTICELLO 4th'INTERVAL iilEXAMINATION PLAN ASME Section Xl 1998 Edition with the 2000 Addenda IWA-4221 (a) requires that items used for repair/replacement activities shall
-: meet the applicable Owner's Requirements.
IWA-4221 (b) requires that an item to be used for repair/replacement activities shall meet the Construction Code specified in accordance with (1),
- (2) or (3) below. . -
'(1) When replacing'an existing item, the newitem shall meet the Construction Code to which the original item was constructed.
(2) When adding a new item to an existing system, the Owner shall specify a Construction Code that is no earlier than the earliest Construction Code used for construction of any originally installed item in that system. (3) When adding a new system, the Owner shall specify a Construction Code that is no earlier than the earliest Construction Code used for other
-systems that perform a similar function; A - --
IWA-4422.1 (a) states that a defect is considered removed when it has been reduced to an acceptable size. . ASME Section XI 2001 Edition i i -IWA-4221 (a) requires that items used for repair/replacement activities shall meet the applicable Owner's Requirements., * ' -- IWA-4221 (b) requires that an item to be used for repair/replacement
'activities shall meet the Construction Code specified in accordance with (1),
(2) or (3) below. (1) When replacing an existing item, the new item shall meet the
-Construction Code to which the original item was constructed.
(2) When adding a new item to an existing system, the Owner shall specify a Construction Code that is no earlierthan the earliest Construction Code used for construction of any originally installed item in that system.
* (3) When adding a new system,. the Owner shall specify a Construction
- Code that is no earlier than the earliest Construction Code used for other
-systems that perform a similar function.- --
IWA-4422.1 (a) states that a defect is considered removed when it has been reduced to an acceptable size. 1.5-115 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
4. Reason for Request
Relief is requested from replacement or weld repair of wall thinning conditions in Class 2 and 3 carbon steel raw water piping systems to the design specification and the original construction code. Such thinning may be the result of various degradation mechanisms such as erosion, corrosion, cavitation and pitting. The use of Code Case N-661 will provide adequate time so that pipe replacement can be planned to reduce impact on system availability including Maintenance Rule applicability and availability of replacement materials.
- 5. Proposed Alternative and Basis for Use NMC proposes to implement the requirements of ASME Code Case N-661 as an alternative under 10 CFR 50.55a(a)(3)(i) for Class 2 and 3 raw water piping systems resulting from degradation mechanisms such as erosion, corrosion, cavitation, or pitting as an alternative to the requirements of the ASME Section Xl code as referenced above. These types of defects are typically identified by small leaks in the piping system or by pre-emptive non-code required examinations performed to monitor the degradation mechanisms. The alternative repair technique described in Code Case N-661 K involves the application of additional weld metal on the exterior of the piping system that restores the wall thickness requirement. This repair technique is utilized whenever engineering evaluation determines that such a repair is suitable for the particular defect or degradation being resolved. Provisions for use of this Code Case will be addressed in the Repair/Replacement Program for each site.
Provisions for implementation of this Code Case will be addressed on a plant specific basis in each site's Repair/Replacement Program. The provisions will require that adjacent'areas be examined to verify that the repair will encompass the entire flawed area and that no other unacceptable degraded locations 'exist within a representative area. This will be dependent on the degradation mechanism present. An evaluation of the degradation will be performed to determine the re-examination schedule to be conducted over the life of the repair. The repair will be considered to have a maximum service life of two fuel cycles unless the re-examinations conducted during each of the two fuel cycles establish the expected life of the repair. Additionally, the following restrictions will be placed on the use of Code Case N-661 to ensure that the use of the Code Case will provide an acceptable alternative pursuant to 10 CFR 50.55a(a)(3)(i): 1.5-116 Revision 3 3/10/2005
- NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL . -'EXAMINATION PLAN (a) if the root cause of the degradation has not been determined, the repair is only acceptable for one cycle,
- (b) weld overlay repair of an area can only be performed once in the same
'location, and - .-...
(c) when through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay e'air is only acceptable until the next refueling outage. . - The basis for use of the repair technique described in Code Case N-661 is that the ASME Code subcommittee for Section Xl determined that this repair technique provides an acceptable alternative to the requirements of IWA-4000 and provides 'an acceptable level of quality and safety. Therefore, the proposed alternative is justified per 10 'CFR 50.55a(a)(3)(i)
. 'Code Case N-661 was approved by the ASME Section Xl Code Committee
- on 'July 23,2002; however, it has not been incorporated into NRC Regulatory Guide 1.147 "Inservice Inspection Code Case Acceptability, ASME Section Xl Division 1." Therefore NMC requests use of the alternative repair technique described via this relief request. A copy of the ASME Section Xl
- Code 'Case N-661 is provided as'Enclosure 2'for reference.
.6. Duration of Proposed Alternative NMC requests authorization of Code Case N-661 to be used for each plant's 10-year ISI interval .(see table below) or until theNRC publishes Code Case N-661 in a future revision of Regulatory Guide 1.147. Upon incorporation into the Regulatory Guide, NMC will review and follow the conditions specified.
All other ASME Code, Section Xl requirements for.which relief was not specifically requested and authorized by the NRC staff will remain applicable
- including third party review by the Authorized Nuclear Inservice Inspector.
- -:. ... .---.. .. , ,-i
* ~ ~~~ I.
1.5-117 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN I> Plant Interval Interval Dates Monticello Nuclear Generating Plant 50-263 Fourth ;05/01/03 - 05/31/12 Prairie Island Nuclear Generating Plant, Units 1 Fourth 12/21/04 - and 2, 50-282 & 50-306 - 12/20/14 Point Beach Nuclear Plant, Units I and 2, 50- Fourth 07/01/02-266 and 50-301 06/30/12 Kewaunee Nuclear Power Plant 50-305 Fourth 06/16/04 -
._ _ 06/16/14 Palisades Nuclear Plant 50-255 Third 05/12/95 -
' 12/12/06 Duane Arnold Energy Center 50-331 Third 11/01/96 -
.11/01/05
- 7. Precedents NMC has determined that the following previous Authorizations to use Code Case N-661 are directly applicable to this Relief Request: I)
(1) Letter from NRC to Southern Nuclear Company, "Edwin I. Hatch Nuclear Plant, Units 1 and 2, Joseph M. Farley Nuclear Power Plant, Units 1 and 2, and Vogtle Electric Generating Plant, Units I and 2 (TAC Nos. MB8959, MB8960, MB8961, MB8962, MB8963, and MB8964)," dated November 21, 2003, ADAMS Accession No. ML033280037. (2) Letter from NRC to TXU Energy, "Coma'nche Peak Steam Electric Station, Units I and 2 - RE: Relief from the. Requirements' of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section Xl, Concerning Relief Requests C-2 and C-7 (TAC Nos. MB7947 and MB7948)," dated February 18, 2004, ADAMS Accession No. ML040490624. STATUS Submitted on July 28, 2004, not yet approved for use, NMC Letter to NRC, "10 CFR 50.55a Request GR-04-01; Request For Authorization To Utilize Code Case N-661(L-HU-04-027)" 1.5-118 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY' :.- ItV~INSERVICE INSPECTION MONTICELLO 4th'INTERVAL ,,,! ;',,'EXAMINATION PLAN. QUALITY GROUP CLASSIFICATION DRAWINGS I (ISI BOUNDARY DWGS) ISO REV SYSTEM I DESCRIPTION BOUNDARY DRAWI NGS 1.5-1 0 ISI Index Key. 1.5-2 3 'Main Steam System I 1.5-3 2- Feedwater System 1.5-4 . . .,, I Reactor Circulation System 1.5-5 3. Reactor Circulation System 1.5-6 3 Residual Heat Removal System Loop A 1.5-7 4'- Residual Heat Removal System Loop B 1.5-8 3 High Pressure Coolant Injection System. (Steam Side),-. 1.5-9 2 High Pressure Coolant Injection System (Water Side) 1.5-10 2- Reactor Core Isolation Cooling (Steam-Side) 1.5-11 2 Reactor Core Isolation Cooling (Water Side) 1.5-12 2 Standby Liquid Control System 1.5-13 t ..
'3'. Primary Containment Atmospheric Control System 1.5-14 2. - -Emergency Diesel Generator Emergency
. I Service Water 1.5-15 2 Emergency Diesel Generator Emergency
'i - ;
Service Water 1.5-16
.. I 2 RHR Service Water .
1.5-17 -3 'Hydraulic Control Unit 1.5-18 2
- Control Rod Drive System (Scram Discharge Piping) -
1.5-19 1 Compressed Air System - .
- 1.5-20 . r-I - k 2 Condensate.Service & Rx Bldg Cooling Water 1.5-21 2 Reactor Water Clean-up & Liquid Radwaste 1.5-22 1 Traversing In-core Probe'System 1.5-23 1 : Excess-Flow Check Valves .
1.5-24 .'-Deleted, system eliminated 1.5-25 ' Deleted, Cm
- . P
.. system eliminated . -
1.5-26 1- .,Primary Containment Sampling Systems 1.5-27 ':1 - .Reactor Vessel Instrumentation 1.6-1 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN ISI ISOMETRIC DRAWINGS ISO # REV SYSTEM / DESCRIPTION CLASS I & 2 DRAWINGS ISI Fig. 0 4 RX Vessel Interior ISI Fig. 1 5 RX Vessel Top Head ISI Fig. 2 4 CRD Location RX Vessel ISI Fig. 3 3 RX Vessel Bottom Head ISI Fig. 4 5 Circ. & Long Reactor Vessel Welds ISI Fig. 5 4 RX Vessel Nozzles ISI Fig. 6 5 Reactor Vessel Bolting ISI 13142-17-A 5 RHR A Suction ISI 13142-17-B 4 HPCI Water ISI-13142-17-C 6 RHR B ISI-13142-18-A 5 RHR B ISI-13142-18-B 5 RHR B Discharge ISI-13142-18-C 3 RHR B Discharge ISI-13142-19-A 5 HPCI Steam Side Discharge ISI-13142-19-B 5 RCIC Steam Discharge ISI-13142-20-A 5 Core Spray A Suction ISI-13142-20-B 5 Core Spray B Suction ISI-13142-20-C - Deleted, system eliminated ISI-13142-26-A 5 Core Spray B Discharge ISI-13142-26-B 5 Core Spray B Discharge ISI-13142-26-C 6 Core Spray B Discharge ISI-13142-26-D 2 Core Spray B Discharge ISI-13142-29-A 3 RX Cooling Water IS-13142-31-A 5 Core Spray B IS1-13142-31-B 4 Core Spray A Discharge ISI-13142-31-C 5 Core Spray A Discharge ISI-13142-31 -D 1 Core Spray A Discharge I ISI-13142-33-A 5 Main Steam A ISI-13142-34-A 5 Main Steam B ISI-13142-35-A 5 Main Steam C ISI-13142-36-A 5 Main Steam D ISI-13142-37-A 4 RHR A Discharge ISI-13142-37-B 5 Containment Spray ISI-13142-37-C 5 RHR A Discharge ISI-13142-37-D 3 Containment Spray (RHR A) ISI-13142-37-E ISI-13142-40-A 1 4 Containment Spray (RHR A) HPCI Water Side Discharge I ISI-13142-40-B 5 HPCI Water Side Discharge 1.6-2 Revision 3 3/10/2005
'; NUCLEAR MANAGEMENT COMPANY.. - ', INSERVICE INSPECTION MONTICELLO 4th INTERVAL .4..:.EXAMINATION PLAN a'JISI ISOMETRIC DRAWINGS ISO # . "REV ' SYSTEM / DESCRIPTION CLASS 1 &2 DRAWINGS (continued) ISI-13142-41-A RCIC'Water Suction ISI-13142-42-A 6 HPCI Steam Side I ISI-13142-43-A *5 - RCIC Steam Side ISI-13142-48-A RHR Service Water ISI-13142-48-B -4, RHR Service Water ISI-13142-49-A 5 RHRA I ISI-13142-51-A RHRA ISI-13142-51-B RHR B ISI-13142-51-C RHRB 5' ISI-13142-51 -D 4 RHRB ' IS 1-13142-52-A Feedwater C &D ISI-13142-53-A Feedwater A & B ISI-13142-62 Fuel Pool Emergency Cooling ISI-13142-67 Fuel Pool Emergency Cooling ISI-16 Jet Pump Instrument Nozzle ISI-19 RX Instrument Nozzles ISI-47 5, RCIC Pump - ISI-48 -RHR Pumps ISI-49 Core Spray Pump Supports
-45 IS I-73880-A 6 RWCU ISI-74209-1-A Recirc. A Drain
.4 ISI-74210-1 -A *'Recirc.B Drain ISI-74215-A Standby Liquid Control ISI-782-A 4 .RX Head Vent. -.
ISI-782-A-A RX Head Vent:, . ISI-786-A Main Steam Condensate Leakoff ISI-7905-32-A .3. .RHR HX A ISI-7905-32-B RHR'HX B IS1-821 -A RX Bottom Head Drain ISI-8292-42-A ...,.:,i - -HPCI Pumps - ISI-8292-48-A HPCI Turbine - ISI-93268-1-A CRD Scram Header A *
- .. 5.3
, ISI-93268-1-B CRD Scram Discharge Header.
IS I-93268-3-A 36 CRD Scram Header B ISI-94699-A 3 Primary Containment &Atmospheric Control IS I-94879-A .3 : Spare Penetration X-47 ISI-94966-A 3. ...Primary Containment &Atmospheric Control ISI-94966-B 3 Containment Air Purge i1.6-3 Revision 3 3/10/2005 I
NUCLEAR MANAGEMENT COMPANY I INSERVICE INSPECTION MONTICELLO 4th INTERVAL - - EXAMINATION PLAN K),
- ISI ISOMETRIC DRAWINGS ISO # REV SYSTEM / DESCRIPTION CLASS 1 & 2 DRAWINGS (continued)
ISI-97003-A - 4 RHR Return Loop A ISI-97003-B 5 RHR A ISI-97004-A 4 RHR Return Loop B ISI-97005-A 5 Recirc. Loop A ISI-97005-B 5 Recirc. Manifold A ISI-97005-C 6 Recirc. Pump A Supports I ISI-97006-A 6 Recirc Loop B ISI-97006-B 5 Recirc. Manifold B ISI-97006-C 7 Recirc. Pump B Supports I ISI-97007-A 4 RX Instrument Nozzle N-1 1B ISI-97008-A 4 RX Instrument Nozzle N-A1A ISI-97027-A 5 RHR Equalizer. ISI-105531-A 3 Standby Gas Treatment & RX Plenum ISI-158074-A 4 Torus Hard Pipe Vent CLASS 3 DRAWINGS ND-ISI-100 2 RHR Service Water ND-ISI-101 2 RHR Service Water ND-ISI-102 I RHR Service Water ND-ISI-103 2 RHR Service Water ND-ISI-104 I RHR Service Water ND-ISI-105 I RHR Service Water ND-ISI-1 06 2 RHR Service Water ND-ISI-107 2 RHR Service Water ND-ISI-108 2 RHR Service Water ND-ISI-109 2 RHR Service Water ND-ISI-110 I RHR Service Water ND-ISI-1 11 3 RHR Service Water ND-ISI-123 2 RHR Service Water ND-ISI-141 Deleted, system eliminated ND-ISI-142 Deleted, system eliminated ND-ISI-144 Deleted, system eliminated ND-ISI-145 Deleted, system eliminated NON-CODE AUGMENTED NC-ISI-37 4 RCIC Feedwater -NC-ISI-51 2 CRD to RWCU 1.6-4 Revision 3 3/10/2005 I
(7 c C IS! INDEX KEY
--- -INDICATES NDE REQUIRED. ASME CODE CLASS I INDICATES NO NDE REQUIRED OR ASME CODE CLASS 2 LORL IOR.. ASME CODE CLASS 3 ASME SAFETY RELATED COMPONENT BUT CANNOT BE CLASSIFIED UNDER REG. GUIDE 1.26 CRITERIA.
ASME NON SAFETY RELATED- C I REF: ,FILE NO: JG? (M&SP)- ISI INDEX KEY. ISI DWN: TJH CHI<D: -V(.APPD: &~to SYSTEM: LINE: I .DWG: 1.5-1 I REV: 0
REACTOR HEAD VENT AIN 7 N-14,N -13 w i [,r I [E-- REACTOR IRV-2-71B RV-2-71G VESSEL RV-2-71H RV-2-71C AO-2-868 AO-2-80B I AO-2-80C AO-2-86C TO TURBiNE I _- -- -N-E- N-3C _ _ _ _ I TO TURBINE STOP VALVE PEN X-7B 9 ~ I FE-2-114B N-3B FE-SIFE-2-114C rI v-PEN X-7C
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SYSTEM: FEEDWATER SYSTEM LINE:. DWG: 1.5-3 IREV 02 I
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- 11 UAVV SYSTEM Z PEI- --- 11-2G X- 41II r - i tdJ-2C -2 I U1-2J I l4-2A -I -I I 41-2K I - 41-lA - - I IRIJ RI1-6I I 44-156-FROMIRH SYTE.SUTIN
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- -- - -ZSYSTEM SItUTDOvlI MO 2-53a~ I.TJE ~ C Md 2-43B MO-2-43A ,Mo *2-53A r - - - -IRECIRCULATIOII I I I REaRCULATollu my -
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. - 4I- -C, /-, ri. I
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-- 'XZo H-58>7 AO-14-13A r 110.
,I.
I I .- . MO-1749 - CS-9-1
. n11i o 1R O-77 Rl* R IRX- -
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P49\b (M&SP)- MONTICELLO IsI DWN: TJH CHI(D: ) APPD: APDt i;--, SYSTEM: CORE SPRAY SYSTEM' LINE: DWGM 1.5-5 IREV: 03
RHR-86 CST-94 CST-118 xP3ENg CST-99 RHR-90-1 TO RHR 74-1 MO-2022 MO-2020 SPRAY_ CST-92I r - TO CROSS TIE FROM CNDS I MO-2029 RHF
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)RUS RING HDR 2 ,71 RHR-7 1 1 1 I _ X-2138 TI (MC)
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...- .--- Ik Irv T- ACCIDENT I RETURN FROM I LJ RV-1992 SAMPLING I I RHRSW-17 RHR POST: ACCIDI ENT P-202C RHR-2-3 RHR-3-3 MO-2002 I RHR-5-1 L SERVICE SAMPLINC 7---6 L WATER Ir I 1 RHR-1-3I _ _ _
P ,7-6 r- -. I ,- 7I I I 1 - \- . / " CV-1994 ; I T ; I RV-1990 t- -RHR-4-1 IJRHR I P -202A RHR-2-1 RHR-3-1 I 'R D} - HX I I I I IRHR-1-1 rH - '
/' _1 __
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-t FROU T-. LJ.
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( c c FROM CONDENSATE CST-98 CST-119 SERVICE WATER . PEN CST-93 X-39A MO-2021 MO-2023 + TO r-------------- T _- -- CONTAINMENT RHR-90-2 RHR-74-2 SPRAY RI . I D~~~~~r~l . . . . ,... I I X-13A T RV-2005R2I-- V~ j- - I--; IO5FI - i MO-2013 MO-2015 T L r-- -. +-t T-, C}?RECIRCULATING
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'I I I .. L--"- JTO CROSS TIE j CST-88 FROM CONDENSATEI MO-40858 I I I .? SERVICE WATER 1-! I I TO I CROSS-TIE I - I ___
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. D 0-2009 1J.I _ I~tn i 1 FE-10-119B j iE-!O-19: RHR-8-2
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/TORUS RING HOR I i_ l;MO-1987X L -
- T -PAS 57-.
PAS 57-4 PA-PAS 59-5 TO POST
.V-. .
CV 1997 bCV-1995 .HR'-1,_. RHR-18-2 ACCIDENT r2 ROM RV-1993 1 ' STORAGE RETURN FROM P-2SAMIN P-202DPOST ACCIDENT RHR-5-2 I MO-2003 RHR-3-4 -. RHR-2-4 r - D } -RHR-1-4 PAS 58-2 I- I I RHR-4-2 RV-1991 I PAS 57-7 HX> RHR-3-2 RHR-2-2 P-202B --- _ -- _ RHR-1-2
.J MO-1989 RV-4282 -
-RHR A REF: NH-36246 IFILE NO:
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DWG: 1.5-7 l REV: 04
MO-2034 MO-2035 FE 3493 PEN X-ll r1 HO-8 HO-7 MO-2036 MAIN STEAM BOOSTER r _ --- A PUMP MAIN PUMP r- TURBINE VALVES PUMP MAINPUMP r- - 1CONTROL STOP
/ / o) 5 HPCI PUMP DRIVE TURBINE l P-209 J- L- T CV-20430-4 HPa-7 1 HPC-60 r IST-2045 PSD (Rwr*E DIU)
L HPCI-59 PCI-7 HPCI-82 HPCI-10 HPCI-9 T HPCI-58 r>< 1 --- [.., - __ ' r- - - _ - - -v _ Y (20 xl6 ) CONDENSER COOLING WATER, RETURN REFER TO HPCI (WATER SIDE) REF: NH-36249 IFILE NO: 1 P5 MONTICELLO ISI DWN: TJH CHKK.i 1 A APPD:_K.PPD: SYSTEM: HP COOLANT INJECTION SYS. (STEAl-'IDE) ( C LINE: IDWG: 1 r R A l I PF\I:- 03
.. . I IIPCI-32 1.10-2063 r -PC--M->1-52-?RnOU CONnDESATE I *:i STORAGE TANK(
.,.I -, . . . I I; r-7- _ 1L _ -II , ...
!r ;
; - - TO COIDEHSATE -- ; lf I I RV2O.64 STORAGE TANK ri I REACTOR VESSEL.U
-0 .11 ;
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, 1.-c I X-9A i" (StEE O) 1PCI-42 II TO CORE SPRAY?-4'1-f%4---- rbj TEST LI - *\ 26E PO 2066 I Tr TOR eS RRGflIJEADen ..
PEN10-2,061 H"PC-31 MO-2Oa2 X-225 REF: NH-36250 IFII F Hn. Ps (M&SP)- MONTICELLO . ISI DWN: TJH - -- CHIKD: f1i APPD: -J'*,- SYSTEM: HP COOLANT INJECTION SYS. (WATER SIDE) LINE: DWG: 1.5-9 I REV: 02
PERI L.. = = =ldN. (SLEEVED)
- jM~ O-2075 ,
IREACTOft' 1- I-- --- [< 1VESSEL I I I I I UAIII STEAM STORlAGE TANI I VROU CCrDN fROIA VACA PUMP REF: I41-1-36251 WFILE NO: (M&SP)- MONTICELLO ISI DWI: TJH -- CHI<D: /\)-APPD:,f?,l,- SYSTEM: RX CORE ISOLATION COOLING (STEAM SIDE) LINE: /... (. DWG: DW :1 1.5-10 5 10- 'K 4: 002
( * -.. -. ..-. - C
/ \
CI- _ REACTOR I
'VESSEL' I I I lI I - I FRO I . s-/ I . RW I *- I FE-13-56
- FW 96-1 Ft 97-1 94- 1 FW 91-1 -DAE
.7 _V _ ^tDAE FL>
PEN I. I,.8, , . .. X-9E i . ,, , ;. _ , REF: NH-36252 l FILE NO: (M&SP)- MONTICELLO ISI DWN: TJH - -- CHKD: -I'/h\-) - APPD. >r, SYSTEM: REACTOR CORE ISOLATIO1N COOLING (WATER SIDE) LINE: - -- I Wvv: 1.5-11 II REV: 02
TO 1ET TAI4K , XP F/ P
~XP-6XP-1-141 FI~O lES TM4 pu ACCULLULAToRI P-11-14A T-204_I XP-7 1
- i
- P-2 X -
sLI-- (Poitiv UlplPmp) IREACIOR I *P4 I KSLI 3H XP-11-14 TP204A XP-24-2 T-204 _- P-2030
... ... 4- lie Dlp.P p REFCNH-36253 lFILE NO S (M&SP)-MONTICELLO ISI
. . ~~~~DWN: TJH- Cl-llD: j}9-AP.W2 SYSTEM: STANDDY LIOUID CONTROL SYSTEM
( __ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ DWG: 1.5-12 - 1 : O
C c C I I I I .
- - - I:
CV-3268( TO STANDBY GA! AND REACTOR BUI Aft AIR PURGE SUPPLY FROM REACTOR BUILDING I . TO STANDBY GAS TREATMENT I. AND REACTOR BUILDING PLENUM I . -. ' :: -2
/ ACUUUM RELIEF
,1I I _. - . SFROM ECONDARY
- AO-2379 CONTAINMENT
- DWV-8-1 VACUUM RELIEF
- - L _L..
- 1 N J--FROM SECONDARY AO-2380 CONTAINMENT CV-2384 NH-36258 NH-46162 AO-4540 NH-94896 NH-94897 REF: NH-1 16629 IFILE NO:
Rupture Disk I%57 MONTICELLO ISI PIPE DWN: BLL CHKD4= i3 APPD: PŽ1w SYSTEM' - SYSTEM: PRI. CONTAIN. ATMOS. CONT. SYS. LINE: DWG: 1.5-13 - REV: 03
's e f ESW-60-1
'TO STORM SEWER STOE1U SEWER ESW-3-2 ESW-1-2 REF: NH-36665 IFILE NO:
IASP (M&sP)- MONTICELLO ISI WATER PUMP DWI'I: TJH CHIKD: 'IMP) APPD:Z,/-r P-lIlA - SYSTEM: EMERG. DIESEL GEN. EMER. SERV. WATER LINE: ( c DWG: 1.5-14 t : 02
, .i . .
c :C..: IC 1. I . .x sw- os-1 ECCS PUMP MOTORS ANO
-VENT U1i1lS
- ,I ECCS PUMP MOTORS AfND VnIT U1I1TS ESW-17 NH-36664 REF: NH-36665 I'
gP? (M&SP)- MONTICELLO; IDWN:.TJH CHII<D:' 11ttil.,' APPD:.. SYSTEM: EMERG. DIESEL GEN. EMER. SERV. WATrER
.t IRRHR SERVICE WATER PUMPS NH-36664 REF: NH-36665 IFILE NO:
I\SP (M&sP)- MONTICELLO IS! DWN: TJH- CH-IKD: 1Ab " APPD:/gciiro SYSTEM: RHR SERVICE WATER LINE: ,,, ( ( DWG: 1.5-1 6 1.5-16 TL. Tt- i: 1: 02
C .C
.: -'C:) . An-
. : l X
io TO FERAU DISCHARCE MEADER
. 1 REF: NH-36245 IFILE NO:
AS (M&SP)-MONTICELLO ISI DWN:-TJH - - - - Cl-II(D: I/\hIA ) APPD:/1, , -- SYSTEM: HYDRAULIC CONTROL UNIT LINE: DWG: . 1.5-17 lREV: 03
1I CVr3-320 CV-35-320
~-i-SCRAM DISCHARCE I I-F-SCRAM DISCHARGE VOLUME II I k-)CV-3-3318 Al--DCV-3-33D REF: NH-36245 IFILE NO: ' .18 REP (M&SP)- MONTICELLO ISI DWN: TJH Cl-ll(D: I,'J APPD:,,r,;w SYSTEM: CONT. ROD DRIVE SYS. (SCRAM DISCII. PIPIING)
LINE: f., (. DWG: 1.5-18 -<. V: 02
- .- - C C II CV-147B X-22 CV-4956 X-2290 J-RINSTRUUIENT I TO DRYWELL, AIR - * -5 9 A-183 I-STRUMENT TO TORUS AIR AI-fi31 AI-630 Al- 2
.1 .
PEN X-21 AS-7S AS-79 AS^39 A
- SERVICE AIR TO DRYELL PEtN PEtI' X-t05-R-G - ' X-34A Al-700 Al-599 - ..Al-584- - Al-708 AI-598 - A_577
-- - 142SUPPLY 4 112 SUPPLY TO RV-2-7103 jg TO RV-2-7tr ACCUUULATOR.
ACCUMULATOR NH-36049-4 NH-36049-10 NH-36049-12 REF: NH-36049-14 19 IFILE NO: 19 hsP (M&SP)- MONTICELLO ISI DWN: CADWorlks CHI<D: ,<7,eŽ,) . --APPD: .. X-SYSTEM: COMPRESSED AIR SYSTEM LINE: DWG: 1.5-19 l REV: 01
PElI X-20 OU-151 DM-152 DM-58A
" .4----j>J--------DEMU. WATER c- I -K~iTO DJRYWELL DEMIN. WATER SYSTEM I
TO COOLING FROU REACTOR BUILODIG WATER PUUP MEAT EXCHANGERS X-24 FROu DRYWEuL 10 DORYEUL COOLERS COOLERS 1H1-36039 REF: NH-36042-2 IFILE NO: 20 Wai (M&SP)- MONTICELLO ISI REACTOR BUILDING COOLING WATER SYSTEM. QWN: TJH CHKD: Alll- APPID: - SYSTEM: DEMIN. WATER SYSTEM & RX BLDG CW LINE: /... S DWG: 1.5-20
/'
1t . /: 02
'C
-:;: I-- .'. -'. ': :-, s
.:.4!. I"
--.1 - - . . .. - -- - ' - ' - - . -c R@-
RC7- ro LAU TO IlPCO 2FROM CLEANUP
.I . . IiEAT EXCIIANGERS l TO Ra RC-1 RC-104 UO~7 LIO-2398 FROM REACT(fhR -- 0 239 - ->I--TO CLEANUP
.RECIRC.' LOOP .13.-~ RECIRC. PUMPS I ~. PENI X-14 FROM REACTORR -- ---- -'
VESSEL DRAIN REACTOR WATER CLEAN-UP SYSTEM PEN AO ; 41A'A0-
; 419 X-t5 FROYDRYWlELRgTO FLOOR DRAIN FLOOR DRAIN SUMP COLECTOR TANK
- PEN AO-2561A AO-2610 Lr W-I it FROMA DRYWELL2 2TO WASTE EOtJIPMEEIT DRAIN COLLECTOR TANK I " . .- . -.-- '.- -I.. NH-36043
. - - "ij 14H-36044 LIQUID RADWASTE -1. REF: NH-36254 IFILE NO:.
' .. I . . .
IINS (M&SP)- MONTICELLO IS! DWN: TJH CHI<D: -RI\ APPD:/2 4r.J-SYSTEM: RX WTR CLEAN-UP. & LIQUID-RADWASTE- - - LINE: I DWG: 1.5-21 I REV: 02
10 :A371I :9Om VI
- 3NIl YGI1SAS 3GOdid 380OO-NI ONIS~J3AWIJ 4Vq~iSAS 1St . 11301illOYI -(dSVi1) C!jCa
- ON 3-11-l I '1JSS~t I I &JOIDV3U I I I I- -I
f <c, - - - -I - -C I I/
,I,,II EXCESS-FL.OW MANUAL CHECK VALVE .
FROM E 4TO PRIMARY i V . RISRUMEIt SYSTEM RACK IWPICAL FOR EXCESS-FLOW CHECK VALVES EXCEPT EXCESS-FLOW CHECK VALVE FOR PENETRATION X-2BF VESSEL HEAD FLANGE I:, ;1 SEALS - i MANUAL EXCESS-FLOW VALVE CHECK VALVE xTO 6 XFV-1 INSTWUUENIT X-8 LI'd RACK EXCESS-FLOW CHECK VALVE FOR PENETRATION X-28F NH-36241 I 1 REF: NH-36242 IFILE NO: 23 I\S? (M&sP)- MONTICELLO :.. . ISI DWN: CADWorks CHI<D: J APPD: ,crft-' SYSTEM: EXCESS-FLOW CHECI( VALVES LINE: DWG: 1.5-23 1 REV: 01
To TO R~tR LOOP A REF: NH--94896 IFILE 10: (M&SP)- MONTICELLO ISI DWN: TJH CHI(D: 141) APPD: f , . l SYSTEM: COMBUSTIBLE GAS CONTROL, DIVISION 1 LINE: ( ~~~(;'G DWG: 1.5-24 152 -i-C ,: 02 1
-9FE-4041 8 .
AO-74238 . : . AO-7422l -T UO-4043fl'z17
- . ~,1 - TO COCS CCc-P2B8:
. DIV I
- T0 . . -CA
.- 40470 . IC-10-2 AO-m74258 AO-74248 PEN X-47. CCC-2-2 w TO PRIIARY PVC-46370 ;HRV-4l21 RV-402C1 .CONTAINMIEIIT 1 ,,,sATOSPIIERIC' COlIIROL CGCC-PID CcC~-l3-2 RWEI SV-40330 .,(MC) CC - - CI9-13-2 'S,Y-40340 alao ' CC -C-1-2 CCC- -2 TO fRna LOOP REF: NH-94897 lFILE NO:3 (M&SP)- MONTICELLO ISI
.... DW:I TJH - CHI<D: ':isth - -APPD:/,.5);.
. . SYSTEM: COMBUSTIBLE GAS CONTROL, DIVISION 11 LINE:
IDWG: 1.5-25 . EV: 02
I TO POST ACCIDENT TO OXYGEN Va A. TORUS TO OXYGEN ANALYZER FROU HYDROGEN-OXYGEN ANALYZERS
}TO HYDROGE11-OXYGEN ANALYZERS NH-46162 NH-91197 REF: NH-96042-1 IIFILE NO: 26 Rsp (M&SP).- MONTICELLO ISI DWN: CADWorks CHI<D: 4K&M-/ APPD: ,.'fi'v SYSTEM: PRIMARY CONTAINMENT SAMPLING SYSTEMS LINE:
( DWG: D G 1.5-26 t 5 2 7i1~Y i; o1
(7 B ----- I I I I DrA'?rD I. - ESSEL I. I I I I .. I I U-119 t--- -, - -- T.
-D
. IlS I
- I I7 I
I112
'I *I I.
- I I,
* * 'ALL OUtWDRIES S90wn ARE QUAUTY GROUP A
_ A REF: NH-36242 IFILE NO: 27 AdSP (M&SP)- MONTICELLO ISI DWN: CADWorks CHIKD: ofJ#'o- APPD: /y.. SYSTEM: REACTOR VESSEL INSTRUMENTATION LINE: DWG: 1.5-27 I REV: ol
(~.. c (7c NOTES: INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (B-N-2) INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (B-N-2) CORE SUPPORT STRUCTURE SP MONTICELLO ISI DWN: BLL CHKD:e7i.J APPD: ftie SYSTEM: RX VESSEL INTERIOR LINE: N/A CRID STUB TUBES ELEVATION VIEW ISI-0 I REV: 04 DWG:
1013 -0 WELD NO WELD W-1 TOP HEAD CIRC WELD W-2 to TOP HEAD MERIDIONAL WELDS W-7 W-8 TOP HEAD-TO-FLANGE WELD 270' j G7 = WELD NO. NX-8290-57 (TOP HEAD) NX-8290-71 (N7 NOZZLE) NX-8290-72 (N6 NOZZLE) 0 = BOLT NO. 157P MONTICELLO ISI DWN: JJP CHKD: pM APPD: as i SYSTEM:-RX VESSEL TOP HEAD - - - LINE: N/A DM = D 'LAR t METAL WELD 180' ( (. DWG: ISI FIG. I ' V: 05 IL :v:
K: C. . . I... I..
. I . . ....... CI NORTH . . , . .
l 180, 51 - 2* 1001 47 'I 101010 010 43 _ 010 010 39 0/ 0 oo10I0I0T _ 35 /0 IOIOIOIO OOIOTOIO . ~w .
- -VESSEL
. I .. ..
31 00 .. -. . t 00 C _C _00CO G -2;70, . _0_000 27 0o-27-90 000010001000 00 ' 23 00. 19- 0 0 0l0CC1OCOlCIOlOC' I 15 00) 01010 Io-o oII A 11 _ 010100001001 07 QIOC0000100 03 0- . . LL o.I 0l
- 0. 0 1 I I I 02 06 10 14 18 *22 26 30 34 38 42 46 50 VIEW LOOKING DOWN REF: NX-7831-471 0)= PERIPHERAL CRD HOUSING 1ISP MONTICELLO ISI CONTROL ROD-DRIVE LOCATION & HOUSING WELD: DWN: MCWI CHKD: RA-0 APPD: 5 SYSTEM: CRD LOCATION. RX VESSEL - - -
(TYPICAL) ,LINE: N/A lDWG: ISI FIG. 2 1[REV: 04
t I-e t STANDBY LIQUID CONTROL RX VESSEL BOTTOM HEAD DRAIN Cont. on ISI-74215-A Cont. on 151-821-A Nis 0. WELD WELD NO. W-1 BOTTOM HEAD DOLLAR PLATE W-2 SEAM WELD BOTTOM HEAD DOLLAR PLATE W-3 TO SIDE PLATES W-4 TO . BOTTOM HEAD SIDE PLATES W-11 MERIDIONAL WELDS 270' 90' W-12 BOTTOM HEAD SKIRT WELD NX-8290 (BOTTOM HEAD) 72 - WELD NO. NX-8290-65 (NIO NOZZLE)' REF: NX-8290-71 (N15 NOZZLE) ISP MONTICELLO ISI DWN: MCWI CHKD: AZd&D APPD: 0;1 SYSTEM: RX VESSEL BOTTOM HEAD - 180- LINE: N/A r 1IDWG: ISI FIG. 3 W ': 03
C. C C FLANGE TO VESSEL RX EL. 52'-5 1/4" TOP HEAD 1001'-10 1/4 - COURSE 4 RX EL 41'-5 11/16" 990'-10 11/16" COURSE 3 RX EL. 30'-6 1/8" 979'-11 1/8' COURSE 2 RX EL; 19'-6 9/16" 959'-11 9/16" li) _ , __ ; . . COURSE 1., N- 1A 5-10 RX EL 8' i, V tCVCBB-1 958'- 0 BOTTOM HEAD TO VESSEL BOTTOM HEAD I I - I-300- 270- 240' 210- 180- 150' 120' 90-. 60- , 30- ..
- 360- 330-REF: NX-931 0-11 PqSP MONTICELLO ISI
- 1. CIRC. & LONG. WELDS ACCESSIBLE THROUGH NOZZLE WINDOWS DWN: BLL CHKD.C 8 APPD: Qm (APPX. LENGTH ACCESSIBLE AS SHOWN) ..
SYSTEM: CIRC & LONG REACTOR VESSEL WELDS
- 2. VL - VESSEL STABILIZER LUG LINE: N/A INTEGRAL ATTACHMENT DWG:
DWG: ISI FIG-4 ISI I REV: 05
N-13. -14 (OFF FLANCE)- RX EL. 52'-5 1/4" TOP HEAD 1001'-10 1/4" of C COURSE 4 03D N-3D 0 0 0 N-3C o N-3D N-3A 0 RX EL. 41-5 11/16- N-`18 N-11A 990'-10 11/16" 00 .0 COURSE 3 N41 0 N-4C N-4B 0 N-4D N-5B 0 O. I N-4D N-5A 0 0 N4 N-9 0 N-4A RX EL. 30'-6 1/8" N-12b 979'-11 1/8'
. N-12A EL. 229'-3 1/2" I . I1 COURSE 2 RX EL. 19'-6 9/16" LCORE REGION 959'-11 9/16" 0 0 0 0 0 0.0 0 0 0 EL. 17'-3 1/2" COURSE 1 0 N-2K N-2J N-2H N-2G N-2F 0 N-2E N-2 N-2C N-2B N-2A N-1A N-1B 0 0 RX EL. 8'-7" N-88 N-BA 958'-0 I I I I I I I 1 I I 360' 330- 300- 270' 240' 210- 180' 150' 120' 90' 60- 30- 0-
°MZZLE WLD SYSTEM NORTH N-IA RCAD-1 Recirc Outlet ISI-97005-A SOU TIH N-ID N-2A RC8D-I RRAD-1 Recirc Outlet ISI-97006-A BOTTOM HEAD Recirc Inlet 151-9 7006-li N-2D RRHD-1 Recirc Inlet I5-97006-8 N-2C RRCD-1 Recirc Inlet 1S-97006-Bi N-2D RRDD-1 Recirc Inlet ISI-97006-0 N-2E RRED-1 Recirc InWet IS-97006-B N-2F RRFD-I Recirc Inlet 151-97005-B N-2G RRGD-1 Recicc Inlet 1S-97005-0 N-2H RRHD-1 Recikc Inlet ISI-97005-U N-2J RRJD-1 Recrc Inlel 1S-97005-0 N-2K RRKD-1 Recirc Inlet ISI-97005-B N-3A MSAD-1 Main Steom 19S-13142-33-A N-3D UMSD-i Main Steam ISI-13142-34-A N-3C USCD-1 Uain Steam ISI-13142-35-A N-3D USDD-1 Mo-mSteam 191-13142-36-A N-9 EL. 986'-O" N-4A FWAD-1 Feedwater 19S-13142-53-A N-40 FWOD-1 Feedwoler ISI-13142-53-A N-4C FWCO-1 Feedwoler ISI-13142-52-A N-4D FWDD-1 Feedwoler 19S-13142-52-A N-5A CSAD-71 Core Spray 151-1.3142-26-A REF:NX-9310-11 N-5D CSSD-1 Core Spray 1S-13142-31-A N-8A JPAD-I Jet Pump Insir. ISI-16 N-8D JPOD-I Jet Pump Instr. 151-16 KS? MONTICELLO N-9 CRAD-1 CRD Return IS FIG. 5 ISI N-IIA VIAE-I Instrumentalion '5'-97008-A N-1113 VIE-1 Instrumentation ISI-97007-A DWN: MCWI CHKD: jWV APPD: N-12A VlCE-1 Instrumentation N-12B VIDE-1 Instrumentation 151-19 191-19 SYSTEM: RX VESSEL NOZZLES N-13 VFAE-I Flange- lo-Noazle ISI FIG. 5 N-14 VfBEv- rlonge-lo-Nazzle ISi FIG. 5 LINE: N/A f DWG: ISI FIG. 5 ::I7 a 04
. _. _.c c... C- .
7" REACTOR VESSEL STUD,- WASHER --& LIGAMENT LOCATION NUT Ii-<" NORTH - 180-1
.. I 1, ~_..' ..
F-WASHER j SET e L5 3/4'1 90-
-S
, i, o0 SOUTH STUD I .I i . k
.,, A+
. . W. . 1. I , ! X I - ___ 1 _.; 1, _ . _. . - . . i ".. - I I I " 1: I I , 1.
* - CTI In
-LIGAMENT BUSHING u . REF: NX-8290-63 6'0 X 7.420" LG IS'P MONTICELLO 1 15/16- ISI DWN: MCWI CHKD: ip APPD: 4jpz.V;'
SYSTEM: REACTOR VESSEL BOLTING ILINE: N/A
.DWG: ISI FIG. 6 REV: 05
TW16-14"-HE A HANGER NO. EA = WELD NO. REF: NX-13142-17 IS'P MONTICELLO . ISI DWN: MCWI CHKD: ranJ13 APPD: Ad) SYSTEM: RHR "A" SUCTION LINE: NOTED IA = INTEGRAI ATTACHMENT (ASME ITEM C3.20)
/1
--- f I DWG: ISI-13142-17-A I-J ': 05 x, \K
- - C A-
_.-,---C C c TW17-14"-HE FROM CONDENSATE STORAGE NORTH NO CONT. (NON-SAFETY) X EL. 910-4" - - A/ , RHR-18-2
-TW15-14"-HE
-TW27-20"-HE
.. . -1 I I EL. 900'-11" I
I EL. 897'-7" tCONT. ON IISI-13142-49A REN REF: NX- 131142-17
= HANGER NO.
I\SP MONTICELLO DWN: BLL CHKD:C1rt4 APPD:
- ( a = WELD NO. -. RHR SUCTION B - SYSTEM: RHR-B SUCTION -- -
IA = INTEGRAL ATTACHMENT (ASME ITEM
NT RHR DISCHARGE B REF: NX-13142-18
= HANGER NO. 1%SP MONTICELLO ISI DWN: MCWI CHKD: , APPD: 05-'
NOTE: H-3 IS NON-EXISTENT. IT WAS REMOVED PER MOD 920520 SYSTEM: RHR B LINE: NOTED
- IA = INTEGR7,A ATTACHMENT (ASME ITEM C3.20) i* DWG: . ISI-13142-18-A . ir /: 05 77K.
.C. MK--
I 1. . ? ", . ISI-13142-18C .I, . ORT I -- S II-RHR "BE HEAT EXCHANGER (E-2008)
*I t I.
I.I . I.
= HANGER NO.
*31L = WELD NO.
CONT. ON ISI-13142-18C TW19-14"-GE P-202D REF: NX-13142-18 P-2028 tS'P MONTICELLO. DWN: MCWI CHKD: (VP -- SYSTEM: RHR 'B" DISCHARGE LINE: TW19-1O"-GE. TW19-14"-GE DWG: ISI-13142-18-B
RHR IBM HEAT EXCHANGER (E-2008) CONT; ON ISI-13142-1BB ( I = HANGER NO. ON
= WELD NO.
REF: NX-13142-18 L ISP MONTICELLO ISI vDWN: MCWI CHKD: 'VUb APPD: 4---. SYSTEM: RHR "B" DISCHARGE - . LINE: TW20-14'-CE. IDWG: ISI-13142-18-C [CV: 03
\I- ,
I( I-.. NT
= HANGER NO.
I is, LCi = WELD NO. Lea MONTICELLO ISI MB8J-34 K 1/ N~ 1 DWN: MCWI CHKD: SLAV APPD:,Pr_, NOTE: 2" DRAIN LINE EXEMPT PER IWC-1222(a). SYSTEM: HPCI STEAM SIDE DISCHARGE TORUS CONN. X-221 LINE: NOTED IA = INTEGRAL ATTACHMENT (ASME ITEM C3.20) (BAY 6) DWG: ISI-13142-1 Q-A I1RFV-I . Iv_____ nc; 1
NORTH EL. 898'-10.75" TORUS PENET. ' X-212 (BAY 12)'- = HANGER NO.
= WELD NO.
'\CONST>/
fcC I-C) ~-C..
.TORJSPENET X-226-B (BAY 14) F,
= HANGER NO.
CORE SPRAY 'A' PUMP P (14-1A) CONT. ON 13142-31C
= WELD NO.
EL. 897'- NSP MONTICELLO ISI DWN: MCWI CHKD: 1i4Y2 APPD:oj, - SYSTEM: CORE SPRAY "A" SUCTION.. LINE: TW10-12"-HE
.D IDWG:
.S G ISI-13142-20-A
- 3 42 2 - IIR REV:
V: 050
/
TORUS NO CONT. 4 QUALITY GROUP D (YELLOW) CORE SPRAY 0B' PUMP P-20)86 (14-1B) CONT. ON ISI-13142-26C
= HANGER NO.
WELD NO. REF: NX-13142-20 KS7 MONTICELLO ISI DWN: MCWI CHKD: Pt..i APPD: 05 SYSTEM: CORE SPRAY "B".SUCTION. LINE: TW6-12"-HE 11 IDWG: ISI-13142-20-B /: 05
1,7C -C Ot NOZZLE .N-5A SEE ISF FIG. 5
) = HANGER NO.
XL*-II---
= WELD NO.
= DOLT NO.
El = VALVE NO. REF: NX-13142-26 I NSP MONTICELLO I DWN: MCWI CHKD:
- SYSTEM: CORE -SPRAY "B" DISi DM = DISSIMILAR METAL WELD LINE: TW7-8"-ED 0 = INACCESSIBLE DWG: ISI-13142-26-A
NORTH BLDG RWC ROOM RED.) CONT. ON ISI 13142-26A E.978:-6"
= HANGER NO.
OS
= WELD NO.
ISP MONTICELLO ISI DWN: BLL CHKD:,YfhJ APPD: SYSTEM: CORE- SPRAY "B" DISCHARGE LINE: TW7-8"-GE : TW7-10"-GE (I ( DWG: DWG ISI-1 1~11313142-26-B 4 -V: 05
(: c C. EL. 927'-10" CONT. ON ISI-1 3142-268 aN.>- NORTH ISI-13142-26D
= HANGER NO.
k,CONS/ = WELD NO. ISI DWN: BLL CHKD: t,) APPD: SYSTEM: CORE SPRAY B DISCHARGE LINE: TW7-10"-GE DWG: ISI-13142 '26-C I REV: 06
NORTH TW8- 8"-GE CONT. ON ISI-13142-51C
= HANGER NO.
Nl = WELD NO. REF: NX- 13142-26 ISP MONTICELLO ISI DWN: BLL CHKD: Cut APPD: R~p SYSTEM: CORE SPRAY "B" DISCHARGE C.... LINE: TW8-8"-HE & TW8-8"-GE DWG: ISI-131 42-26-D ISI-13142-26-D r 7-V: 02
.I _-.. --C .,:. -
I . .
- - FROM RX BLDG NORTH I HEAT EXCHANGERS CW3-8"-HF NO CONT.
TO CW PUMPS (NON-SAFETY) NO CONT. (NON-SAFETY),
. -- Y EL: 935 0 I 9 r8. 6.-
I . -" - , -7, -
-_- 3 EL. 935-O"
. .. .II , '.
-1 .
-Ij' - !.
I .' - - I -\NEL 928' R/;X ,RBCC--79.1,-,'
- I .
TO DRYWELL COOLERS
= HANGER NO.
FROM DRYWELL COOLERS CW4-8"'-HF = WELD NO. CONST.T. NH-36042-2 NX-1 3142-29 REF: NX-13142-38 r\S' MONTICELLO ISI DWN: BLL CHKDij APPD: WT . SYSTEM: RX BLDG COOLING WATER - NOTE: LINE: CW4-8'-HF & CW3-8"-HF LOCATED ABOVE TORUS BAYS 5 & 6 (INBOARD) DWG: ISI-13142-29-A I REV: 03
f -- ' 013 T NOZZLE N-58 SEE ISI FIG. 5
= HANGER NO.
974' Rx Cubicle J- a-1 (elevated room by SBLC - Ladder access by instrument rock) L-~IJ = WELD NO. I GE I CONT. ON ISI-13142-31B EL. 978-6", = BOLT NO.
= VALVE NO.
REF: NX-13142-31
-IGS MONTICELLO ISI DWN: MCWI CHKD: lopi APPD: i5 SYSTEM: CORE SPRAY "A" DISCHARGE DM = DISSIMILAR METAL WELD LINE: TW11-8"-ED
- = INACCFSSIBLE
__ DWG: ISI-13142-31-A r/: 05 K I,
I-C, I .
-C.
EL. 978'-6' CONT. ON 974' Rx Cubicle (elevated room by SOLC - Ladder access by
~-MO -1753 instrument rock)
CSB-CS13J-27
= HANGER NO.
EL. 931-11' CONT. ON 1 ISI-13142-31D . l J = WELD NO. 935.-O" REF. NX- 13142-:-31. 1IS? MONTICELLO ISI DWN: MCWI CHKD: aft APPD: - SYSTEM: CORE-SPRAY " DISCHARGE LINE: TWJI-10"-GE DWG: ISI-13142-31-B REV: 04
hI-... ( NOTE: EXAMS REQUIRED ON HANGERS ONLY. NO EXAMS REQUIRED ON WELDS PER TABLE IWC-2500-1. ITEM NT -
- HANGER NO.
WELD NO. PUMP ROOM CORE SPRAY 'A' PUMP P-20oA REF: NX- 13142- 31 (14-1A) CONT. ON ISI-13142-20A
/ -,-1 \
C
j.c. C.
, NORTH I., I
. I I TORUS . - ; .--
.. . I ,I ROOM-., ,; "-- :.-- '; - ~N, I ... .
. r-{ .. 9.-. >-.
r ' , , _ , : X-210B I . _ _ (TORUS BAY 15)
> = HANGER NO.
L N.
). = WELD NO.
\CONS> f REF:NX-13142-31
-. SP MONTICELLO, - IS1 DWN: BLL CHKD: ;7\ APPD: x3lD
. .... . - SYSTEM: CORE SPRAY "A" DISCHARGE LINE: TW12-8"-HE DWG: ISI-13142-31-D REV: 01
( ( RV-2-71E NO CONT. REACTOR NOZZLE NT N-3A SEE DWG. ISI FIG. 5 IA
= HANGER NO.
= WELD NO.
rON
.Z7J NX-13142-33 0 = BOLT NO.
I NSAJC- NF-36271 NF-36271-1 LIS = VALVE NO.
'INACC CESSIBLE REF: NH-95008-1.2 l
CONT. ON ISP MONTICELLO ISI ISI-786-A DWN: MCWI CHKD: is APPD: 6*92k PS15A-2'-ED SYSTEM: MAIN STEAM A LINE: PS1-18'-ED IA = INTEGCP i ATTACHMENT (ASME ITEM 610.20) _DWG: ISI-13142-33-A K -V: 05
§*
,C.. @ C ORT -
NOZZLE ,' ! iSI'FIG. 5 l fW - 14 \ > ~ d~ CONT. ON ISI-13142-42A QiiiCCi) HANGER NO HPCI (PS1 -8"-ED) CONT. ON ISI-782 HEAD
/' ;
VENT (Vi5-2 -ED)
.DETAIL A, WELD NO.
(3~ - BOLT NO. 2 NO VALVE NO. d ,. , 2 ~ NON-AFTY SAFETY .......
,A02-868y --
ffi . X I iSB'J'4' 28O8j / W-28' \ NX-13142-34
>-- NF-36271 I INACCESSIBLE NF-36271-1 I ,I REF: NH-95008-1.2 I- MrS MONTICELLO ISI NT. ON ISI-786A DWN: MCWI CHKD: 1P.& APPD: h -
(PS1S-2--ED) SYSTEM: MAIN STEAM B . . .... .. A . -. A ..A. T .. . .2 . )... .: .... LINE: PS2-18"-ED IA = INTEGRAL ATTACHMENT (ASME ITEM 810.20) DWG: ISI-13142-34-A I REV: 05
N T CONT. ON ISI-13142-43A (PSi 7-3"-GD) IA
= HANGER L, = WELD NO.
El. GE = BOLT NO. NX-13142-35 - VALVE NO. NF-36271 NF-36271-1 REF: NH-95008-1.2 NOTE: IM5? MONTICELLO W-6 WAS PURPOSLEY REMOVED REVISIONS. DWN: MCWI CHKD: 'I W-6 WAS NON-EXISTENT SYSTEM: MAIN STEAM C IA = INTEGRAL ATTACHMENT (ASME ITEM B10.20) LINE: PS3-18"-ED
* = INACr-' IBLE I F. 151-13142-35-A
\ K. -
i C -C N-13D El. 990'-O.-- 288' .- AZ , W2 ,01
- USoJ-.
.- ~ 7 NO CONT.
; NON SAFETY
- HANGER NO
= WELD 'NO.
w NX-13142-36 0
-ISI = BOLT NO.
= VALVE NO.
NF-36271 NF-36271-1 REF: NH-95008-1,2 S?' MONTICELLO ISI DWN: MCWI CHKD: 1PW APPD:Se-j-e/ SYSTEM: MAIN STEAM D. - . IA = INTEGRAL ATTACHMENT (ASME ITEM 310.20) LINE: PS4-18"-ED
* = INACCESSIBLE DWG: ISI-13142-36-A l REV: 05
f !- . I I EL. 942'-3"
.333- AZ \-
N T TW30-16-DB TW30-1 6-GE I EL. 935'-O" I TORUS ROOM CONT. ON CONT. ON ISI-13142-37B
\TW33-12 -GE Is1I
= HANGER NO.
TW30-14"-GE FE-10-108-A 1 *3L = WELD NO. REF: NX- 13142-37
%SP MONTICELLO iWN: MCWI CHKD:
iYSTEM: RHR "A" DISC INE: NOTED ATTACHMENT (ASME ITEM C3.20) l1"
K:f Kl( I . I .fv-.:
; I -
.ORT IA CONT. ON ISI-13142-48A = HANGER NO.
SW9-8"-GE 11 = WELD NO. 14"x12\ I CONT. ON IREDS ISI-13142-37At -'-\ TW30-14"-GE I em Is'
/C6N T. ON A P P D:
EL. 916'-4" ISI-13142-3 'C
- TW29-147GE W~fl 4/74 ,. - .. -.-. -. - -
SYSTEM: CONTAINMENT..SPRAY. (RHR. A") .. LI NE: .TW33-12"-GE IA = INTEGRAL ATTACHMENT (ASME ITEM C3.20) IA ASM ATACHENT ITM C.20 DWG: 151-13142-37-B I REV: 05
=INTGRA . DW: IS-13 4237- RE:
Ot i- \ HANGER NO. E = WELD NO. CONT. ON t%' MONTICELLO ISI ISI-13142-51A DWN: MCWI CHKD: WBy APPD: aid TW29-14'-GE SYSTEM: RHR 'A" DISCHARGE LINE: TW30-14"-GE /
- 1. _ DWG: _ ISI-13142-37-C --V: 05
c c c NORTH CONT. ON ISI-13142-37B ( I I-CONT. ON ISI-13142-37B
= HANGER NO.
EL. 926'-51/2" X-210B N IC ~ = WELD NO. REF: NX-13142-37 IS? MONTICELLO ISI DWN: BLL CHKDct,) APPD: RkP SYSTEM: CONTAINMENT SPRAY (RHR "A") LINE: TW34-12"-GE & TW34-10"-HE DWG: ISI-13142-37-D I REV: 03
NORTH CONT. ON ISI-13142-37B EL. 953'-2"
= HANGER NO.
= WELD NO.
REF: NX-1 3142-37 ISP MONTICELLO ISI DWN: BLL CHKDC2V7*tX APPD: V SYSTEM: CONTAINMENT SPRAY (RHR "A") t NOTE: LINE: TW33-1O"-GE LOCAT' 'IREACTOR BLDG EL. 935' ABOVE EAST CRD SCRAM & INSTRU T RACKS. DWG: DWG: ISI-13142-37-E ISI- 13142- 37-E T
-( IV: 0011 U:
./I K...
.... s
;I
. - , . I - ------ - - . -
I
.- ,....OR T --
I- . . ' _24 __
- EL. 912-8 MO' 2071 NO CONT. i NON SAFETY
,.- K -
- CONT.:ON --
4 ISI-13142-408- - EL. 915O'--;;. N
= HANGER NO.
I~t
= WELD NO.
REF:NX-13142-40 RS? MONTICELLO ISI DWN: MCWI CHKD: Vf&AD APPD: O4"# SYSTEM: HPCI-WATER SIDE- DISCHARGE LINE: TW3-12"-ED _DWG: ISI-13142-40-A I REV: 04
f - . r I II
. ORT -
ESTEAM CHASE TORUS EL. 931'-0 ROOM
= HANGER NO.
REF: NX-13142-40 IS7 MONTICELLO DWN: MCWI CHKD: RZP APPD:. SYSTEM: HPCI -WATER SIDE DISCHARGE LINE: TW3-12"-ED IA = INTEGf- ATTACHMENT (ASME ITEM C3.20) K I IDWG: ISI-13142-40-B I IK
c c c FROM CONDENSATE STORAGE TANK NO CONT. (NON-SAFETY) NORTH I ; .....---
.I . .
TORUS PE >= HANGER NO. (BAY 12)
= WELD NO.
Kcs> REF: NX-1 3142-41 Ns? MONTICELLO ISI DWN: BLL CHKD: 2X~ APPD: Ed SYSTEM: RCIC WATER SUCTION . LINE: TW5-6"-HE. C17-6"-HE DWG: ISI-13142-41-A i REV: 05
NORTH DRYWELL
-- CONT. ON _,,E.931'-O" ISI-13142-34A U (PS2-18"-ED) l STEAM CHASE TORUS ROOM EL. 905'-6" HPCI STEAM TURBINE S-2017 CONT. ON ISI-8292-48-A <
(STEAM INLET) = HANGER TDAJ-40 0 6..- CO ST
= WELD NO.
= BOLT NO.
ai = VALVE NO. REF: NX-13142-42 I15P MONTICELLO TDAK-33 DWN: BLL CHKD6Z,_L j SYSTEM: HPCI STEAM SIDE DM = DISS'MILAR METAL WELD LINE: PS18-8"-ED IA = INT XLATTACHMENT (ASME ITEM C3.20) DWG: ISI-13142-42-A
I-C -(C
. IORT -
II I- I .. . NO CONT. EXEMPT PER IWC-1221(a)(1)s NPS 4"
- HANGER. NO.
Li WELD NO.
= WELD NO.
T. REF:lNX-13142-43 IS MONTICELLO ISI DWN: MCWI CHKD: bAy) APPD: Of SYSTEM: RCIC STEAM SIDE . . I = NACCE S.., . -. .. LINE: PS17-3"-ED
= INACCESSIBLE DWG: ISI-13142-43-Al REV: 05
I ../ .
..,f '
_ CONT. ON
^ ISI-13142-48B .ORT RCIC ROOM TORUS
- HANGER NO.
= WELD NO.
REF: NX-13142-48 ftSP MONTICELLO ISI DWN: MCWI CHKD: 1'9- APPD:Q0,6 SYSTEM: RHR SERVICE WATER LINE: SW9-8"-GE I- ISI-13142-48-A IA _DWG: e'-V: 04
\l.
r-c NORTR SWARHR SYSTEM RHR SERVICE WATER EL. 931'-.. CONT. ON I .. . . I . . .. .. I I EL HANGER NO. WELD NO. REF: NX- : 3142-48 P~S? MONTICELLO ISI DWN: MCWI CHKD: '12AO) APPD:,Ov,,,,z SYSTEM: RHR SERVICE WATER LINE: SW98-8"-GE IDWG: ISI-13142-48-B REV: 05
CONT. ON ISI-97003-B
- V(REW10-18"--ED)
NORTH y A~~EL94-' EAST 42-67
= HANGER NO.
Is
= WELD NO.
3142-49
I.. C-CST
..; -C .
CONT. ON ISI-13142-37C .ORT i I CONT. ON. ISI-13142-37C EXCHANGER
!. .. , I, ,
I I I.
-- - , , t t t- . - .
I.. . - .: .. . 11 I -
= HANGER NO.
- WELD NO.
I T9 REF: NX-13142-51 rNs? MONTICELLO DWN: MCWI SYSTEM: RHR A LINE. n wr.
( I CONT. ON ISI-13142-51D IRT I~1~ TW23-12"-GE EL. 962-O" TW24-12"GE EL 935'-O0 l HANGER NO.
/--7sF--)
= WELD NO.
nMr MONTICELLO ISI DWN: MCWI CHKD: 1Z-l> APPD: 4A-SYSTEM: RHR B LINE-NOTED IA = INTEGPA. ATTACHMENT (ASME ITEM C3.20) DWG: ISI- 13142-51-0 f KoJ' V: 05 _ ..-K. \1
C c c EL. 962'-O" NORTH I I1 TORUS ROOM 943'- 6" CONT. ON ISI-13142-26D.
= HANGER NO.
I > = WELD NO. EL 929'-6" N I/ REF: NX-1 3142-51 ISP MONTICELLO ISI DWN: BLL CHKBQ'7;LJ APPD: 99b SYSTEM: RHR B LINE: TW24-12"-GE DWG: ISI-13142-51-C I REV: 02
<3
< NORTH H-.H W-1 TO PEN. X-39A EL. 962'-O" EL 964-11 1/2" AZIMUTH 61deg RHR 2
-BIOSHIELD WALL CONT. ON ISI-13142-51B T\1-_6J40IS
( ) = HANGER NO.
= WELD NO.
REF: NX-13142-51 ISP MONTICELLO ISI DWN: BLL CHKD:ce,, J APPD: SYSTEM: RHR B LINE: TW23-10"-GE I DWG: ISI-13142-51-D ciV: 01
- . . I.111.
c (C
... .; -c NO.
DWN: MCWI CHKD: 'QPsj APPD: , _ SYSTEM: FEEDWATER C & D .- - - - . -- - LINE: NOTED IA = INTEGRAL ATTACHMENT (ASME ITEM 810.20) DWG: ISI-13142-52-A I REV: 04
i .'-77!,,,
~ORT NO CONT.
- NON-SAFETY A -
ISP MONTICELLO Is' DWN: MCWI CHKD: P-Js'6 APPD: SYSTEM: FEEDWATER A & B LINE: FW2B-10"-ED & FW2B-14"-ED IA = INTEGP" ATTACHMENT (ASME ITEM 610.20) IDWG: DWG:~ ~
~IS-112-3A0~
ISI-13142-53-A Jr 'V: 05
C C: c. N OR NORH EL 1003'-1' NO CONT. v
,/
i ,. ,
---- . L I. . II
- - .I CONT. ON ISI-13142-18A TW30-14"-GE = HANGER NO.
I
= WELD NO.
REf: - REF: NX-13142 '62 EL 926'-1 ISP MONTICELLO ISI DWN: BLL CHKD:C7, J APPD: Q5i SYSTEM: FUEL POOL EMERGENCY COOLING LINE: FPW12-8"-GE DWG: ISI-13142-62 I REV: 04
NORTH _ NO CONT.
,'\NON SAFETY
= HANGER NO.
G I = WELD NO. REW10-18"-HE REF: NX-13142-67 CONT. ON ISI-13142-49A (.
ICr "
...K ..- .. , - -...
1. I . ....
.,- . .;I DM NBA SEE ISI-FIG. 5 I .- i EL 960'-2' --
60-AZ - . I DM N88 I . SEE ISI-FIG. 5; EL 960'-2"
,. .. I
- 240-AZ I .
= WELD NO.
YK ~sT7 REF: IRSP MONTICELLO ISI DWN: MCWI CHKD: 1J-4A6APPD: d,/- NOTE: LOCATED IN DRYWELL SYSTEM: JET PUMP INSTRUMENT NOZZLE LINE: DM = DISSIMILAR METAL WELD _DWG: ISI-16 l REV: 04
- 1-71-1 NOZZLE 12A SEE ISF-FIG. 5 NOZZLE 12B 1" HALF COUPLING SEE ISI-FIG. 5 NO CONT. EL 984'-7' 220'AZ
= WELD NO.
Vcos2 N12A REF: NF-97010 N128 REF: NF-97009 ISP MONTICELLO ISI DWN: MCWI CHKD: 'as APPD: _o SYSTEM: RX INSTRUMENT NOZZLES . LINE: RLM3-1"-DCA & RLM4-1"-DCA DM = DISSIP" AR METAL WELD . I., A. [DWG: ISI-19 Jr '/: 04 i
I,--( -c.
- TURBINE: .
-:'MANUFACTURER: TERRY STEAM TURBINE CO.
SERIAL NO. 35690 STEAM EXHi NUST MATERIAL: ASTM-A217-60T./ GR. WC-6 NORTH
.HORZ. FLANGE (36 BOLTS)
STEAM EXHAUST * (CONT. ON h 151-13142-19-B)
- " STEAM INLET SUPPORT PEDESTALS
& ANCHOR BOLTING SUPPORT "6B (SUPPORT WA")
VIEW FROM PUMP ENE (LOOKING NORTH) PUMP SUCTION - CONT. ON I ISI-13142-41-A
- DISCHARGE 2 BEARING PEDASTALS SUPPORT "D' & ANCHOR BOLTING (2)
(SUPPORT -C-)
- VIEW FROM PUMP END (LOOKING NORTH) PUMP:
MANUFACTURER: BINGHAM SERIAL NO. 270608 MATERIAL: ASTM-126 / GR. WCB REF: LOOKING DOWN tS'P. MONTICELLO ISt DWN: MCWI CHKD: 'ML) APPD: bar, REACTOR CORE INJECTION COOLANT (RCIC) PUMP & TURBINE SYSTEM: RCIC PUMP & TURBINE
-- RCIC ROOM EL. 896'-O"- - - LINE:
DWG: ISI-47 I REV: 04
MOTOR HOUSING I PIECE CASING ASTM A216 GR.WCB WELD (NO BACKSIDE WELD ON SUPPORT INTEGRAL ATTACHMENT) zJ 2 MOUNTING FEET ASTM A216 GR.WCB 4 BOLTS SIDE VIEW (TYPICAL). RHR PUMPS EL. 896'-O" REF: NX-7905-18
%5P. MONTICELLO ISI SUPPORT NAME PUMP NAME LOCATION DWN: MCWI CHKD: 1R) APPD:
SUPPORT "A: P-202A 1a RHR 'A" ROOM SUPPORT "B" P-202B RHR .B" ROOM SYSTEM: RHR PUMPS SUPPORT "C"* P-202C RHR "A' ROOM LINE: SUPPORT " P-202D RHR "B" ROOM ( K.
,DWG: ISI-48 T1V: 05
. - , -Vc K, ------, -c 1. SUCTION _- CL SIDE VIEW (TYPICAL) CORE SPRAY PUMPS EL. 896'-O" REF: NX-7833-33 ISP MONTICELLO - iSi DWN: MCWI CHKD: '- APPD: SUPPORT NAME .. PUMP NAME LOCATION CQNECSJ . . . . .. .. SYSTEM: CORE SPRAY PUMP SUPPORTS -. SUPPORT 'A - P-208A - ' RHR 'A' ROOM NOZZLE N-5B3 LINE: SUPPORT "0" P-2088 RHR "8" ROOM NOZZLE N-5A IDWG: ISI-49 I REV: 05
RIN ISI-821-A
= HANGER NO.
CONT. ON ISI-97006-A - WELD NO. EL. 953'-11" K2s!2 om NF-73880
, REF: NF-97006 I IsP MONTICELLO I I DWN: MCWI CHPK'D:
DM = DISSIMILAR METAL WELD l I I CvCTCkA.
.J I .J I L IVI. DWAAII I a'. II %J IA = INTEGRAL ATTACHMENT (ASME ITEM B10.20) LINE: REW3-4"-ED/EDD,
- = INACCESSIBLE -
- 1. ISI-73880-A
(
.- (C K... ..: - , " , -C .
-. . NT J>s -* CONT. ON
" ISI-97005-A
". REW13A-28"DCA I "a I Y NO CONT.
NON-SAFETY - ..
"- QXR-7-;1 EL 921-1" CON WELD NO.
0 = BOLT NO. REF: NO-74209-1 RSP MONTICELLO - ISI DWN: MCWI CHKD: Adl APPD: turd SYSTEM: RECIRC. "A" DRAIN. . NOTE: LOCATED IN DRYWELL BELOW RECIRC PUMP P-200A SUCTION LINE LINE: REW28-2"-EC_ DWG: ISI-74209-1-A T REV: 04
I -1 ... ORT 0 REW29-2ED NO CONT. EXEMPT PER IWB-1220(b)(1) e- NPS I' CONT. ON ISI-97006-A
/ REW29-2ECB 2'x2'xl' TEE v CON WELD NO.
0 = BOLT NO. REF: NO- 74210-1 IGS' MONTICELLO ISt DWN: MCWI CHKD: 12&' APPD: J SYSTEM: RECIRC. DB"DRAIN NOTE: LINE: REW29-2"-ECB LOCATED IN nRYWELL BELOW RECIRC PUMP P-200B SUCTION LINE _DWG: ISI-74210-1-A V '1: 05
.. , I I- C c.
- s.
e-c
= HANGER NO.
WELD NO.
= BOLT NO.
Is1 NOTE: t NO CONT. 9I EXEMPT PER IWB-1220(b)(1), NPS.D1! i". ..- EXEMPT PER SYSTEM: STANDBY LIQUID CONTROL D . . = INACCESSIBLE WEL IWC- 1222(a) LINE: DM = DISSIMILAR METAL WELD CH2-1.5 DWG: ISI-74215-A I REV: 06
CONT. ON ISI-782A-A EL. 1004'-7' -p N T
= HANGER NO.
*3IIL = WELD NO.
N>5 MONTICELLO ISI DWN: MCWI CHKD: '1) APPD: , T -V: 03
Cw C ORTI
-N0 1 NO ICONT.
(I" lLINE) HANGER NO. CONT. ON < ISI-782-Av ' WELD NO.
. I - l
- BOLT NO.
REF: FSK-782A - -. IS? MONTICELLO ISI DWN: MCWI CHKD: APPD: By SYSTEM: RX HEAD VENT NOTE: LINE: V15-2'-ED LOCATED ON REFUEL FLOOR DURING REFUELING OUTAGE DWG: isi-782-A-A REV: 04
W-32 772 w-35 DM MSADJ-4 W-26 TJCLA9 NO CONT. NORTH
\SJ MA g J(NON W W< SAFETY)
W- 3 A~ w-W-W- 22 51 1 W-4 3 15 0'Z W3 Co UNS DRYWELL 31 W-W-33 W-43 W-44 DMe W-38 SR-72 3 S J/ DM W-44
-4 m)W i- W- 70B-3
,Si:r S 3 @~~~~
< /_ 0)S \sl5 4 W43 HANGER NO.
W-45 W-484* -4 64 EL. 934'-O" A' i -49=WELD NO. 180A. \ \\'=WELD 0 40 w 5l NO. 41 W-) \ =FSK-786 W- ~REF: NX-1 3142-42 (<a- 1 \5; 43 MONTICELLO ISI W-18J . WC W-52A tDM DWN: MCWI CHKD;-J APPD: NOTE: M SYSTEM: MAIN STEAM CONDENSATE LEAKOV-DM = DISSIE
* = INACCL'.iBLE METAL WELDf.,
( LINE: NOTED k _
= EXEMPT PER IW8-1220(b)(1). 5 NPS 1I DW,: ISI-78(3-A RFV: nfl
c C..' OUTLETI/E 7J REINFORCING PAD I= 35" 0.0. x 1 1/2" T -- 0I
-24" x 16" RED.
(.500"T) SECTION A-A I* 4'-O 5/6' O.D. IA
-HANGER NO.
180-SECTION B-B - . T WELD NO.
,REF: NX-7905-32 MP MONTICELLO ISI 4 -4 3/4' Ol.D. 7/8- T (MIN) DWN: MCWI CHKD: -vJA APPD:.
RHR HEAT EXCHANGER E200A - . SYSTEM: RHR . HX. "A"-. I .- -. IA INTEGRAL ATTACHMENT (ASME ITEM C3.10) LINE: I WG: ISI-7905-32-A REV: 04
PAD 1/2" T 24' x 16" RED. (.500-T) SECTION A-A o0 4'-O 5/6' O.D.- IA IA IA
= HANGER NO.
I'
= WELD NO.
SECTION B-B (5 N) REF: NX-7905-32 KIS? MONTICELLO ISI 4'-4 3/4' O.D . DWN: MCWI CHKD: 'RtL APPD: Ail SYSTEM: RHR HX "B" RHR HEAT EXCHANGER E200B LINE: IA = INTEGP-". ATTACHMENT (ASME ITEM C3.10) k
- t IDWG: ISI-7905 ( -V: 04
- W-59 CONT. ON ISI-73880-A
.A- 47 EL. 962F-C
.INACCESSIBLE I ' '; I-. RPV. , 2 DJ4 A-
'.AJ-5 IW I IW-5
*"' ',, , /O-,.,,
W-57* 7W--3
, tiI I (HOAJ-42 8EL. 961 -4" W-26 ',' '-82(< . I '. IN NO CONTEL. 944 '-4"
--
- l. IIAK-22 ) 1 W
.HOA.J;.-2. -OA-... -- L43 . - -, IO O
_ __ __ __ _ __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DW : I I - 8 1- AR EV 0 AK - \\ REF: FSK-821
,~~~~ IS'P MONTICELLOIS
))
*(DJU DWN: MCWI CHKD: 1%Ž APPD: x'-
. ',' /HOAJ-24. HDAJ-25 )EL. 942'-4" SYSTEM: Rx BOTTOM HEAD DRAIN_
-~~ EL -
L930 2 .~~ LINE: DWG: REW31-2"-ED.1 1R
I4.. NORTH BYRON JACKSON 671-5-1185
- ASTM A216 CR. WCB
- - SHAFT SHAFT E 7 TURBI-NE DISCHARGE NOZZLE SUPPORT A I-lsl (SUPPORT D)
~) WELD NO.
\(IEW LOOKING EAST REF: NX-8292-42 HPCI PUMP ROOM lS MONTICELLO ISI
.DWN: MCWl CH KD: 1~,b APPD:,aA',-
EL. 896'-O" SYSTEM: HPCI PUMPS HIGH PRESSURE COOLANT INJECTION (HPCI) PUMPS LINE: I ____ WG: ISI-8292-42-A -fV:0 K K
C .. C.... C MANUFACTURER: TERRY STEAM TURBINE CO. SERIAL NO. 35932 STEAM INLET (CONT. ON ISI-13142-42-A) I_ STEAM DISCHARGE iL (CONT. ON 161-13142-19-A) STEAM INLET FLANGE BOLTING (16-BOLTS) TURBINE EXHAUST FLANGE BOLTING" STOP VALVE (24-BOLTS)
-- \ X lSUPPORT '
i PEDASTALS(2) N GOVERNOR END PUMP END ( O
\ /EWFROM PUMP END (LOOKING SOUTH)
NX-8292-54 REF: NX-8292-48 HIGH PRESSURE COOLANT INJECTION (HPCI) TURBINE I1SP MONTICELLO ISI HPCI ROOM EL. 896'-O". DWN: MCWI CHKD: jN APPD: ,.- SYSTEM: HPCI TURBINE LINE: DWG: ISI-8292-48-A I REV: OO
3OR NORTH CRD15A-4"-DB CRD1 4A-6"-DB CRD13A-4"-DB IA a = BOLT NO. NF-93268-1 GE )= HANGER NO. NF-93268-4 REF: NX- 13142-77 NSP MONTICELLO ISI (- ~ = WELD NO.
'\, NST DWN: MCWI CHKD:Qf I APPD: Rib NOTE: LOCA7' ON WEST SIDE OF Rx BLDG AT 935' ELEVATION SYSTEM: CRD SCRAM HEADER "A" _
DM = DISSIMILAR METAL WELD LINE: NOTED f IA = INTFGRAI ATTArHMFNT (ASME ITEM C3.20) nwn. Iql - ( ... 1 - A 1 -Pr\/. n-,
NORTH
= HANGER
= WELD NO.
NF-93268-1 = BOLT NO. NF-93268-3 REF: NX-1 3142-77 NSP MONTICELLO Is' F DWN: MCWI CHKD: Jgu APPD: s NOTE: LOG- ON EAST SIDE OF Rx BLDG 0 935' ELEVATION SYSTEM: CRD SCRAM HEADER B" B' DM = DISS IA
, R METAL WELD = INTEGRAL ATTACHMENT (ASME ITEM C3.20)
( LINE: NOTED WG: ISI-93268-3-A
c&. C N T TANK 'A' I I.: . " iI I " t
,:. II
= HANGER NO.
= WELD NO.
*NF-93268-1 (]; D~
CRD-16A-2"CCD NF-93268-3 RX BLDG. (<EST) REF: NF-93268-4 EL. 935'-O IS'P. MONTICELLO ISI DWN: MCWI CHKD: 1ZAb APPD: by./ SYSTEM: CRD SCRAM HEADER DISCHARGE LINE: CRD- 16A-2"CCD & CRD-16D-2"CCD DWG: ISI-93268-1-B IREV: 03
NORTH IA CD3K-47 i i ____
;. CRD1 4B-6" -DB
= HANGER NO.
= WELD NO.
NF-93268-1 = BOLT NO. NF-93268-3 REF: NX- 13142-77
%SP MONTICELLO ISI DWN: MCWI CHKD: 41 APPD:
A RepAi NOTE: LOC T") ON EAST SIDE OF Rx BLDG @ 935' ELEVATION SYSTEM: CRD SCRAM HEADER "B" _ DM = DISSI..- ,R METAL WELD IA = INTEGRAL ATTACHMENT (ASME ITEM C3.20) ( LINE: NOTED DWG: ISI-93268-3-A REV: 06
' . NORTH Cont. Line CP5-18'-HE --
" LAO-2896 EL. 927-9",,-
EL. 927T-9"- - w- 8 DOUBLE STRUT 5R(20"x 8") Torus Pen IS, X-205 ( = HANGER NO. Bay 4 \rE NH-36258 ~= WELD NO. NH-94878 REF: NH-94699 ISP MONTICELLO ISl DWN: BLL CHKD:9 =,J APPD: SYSTEM: PRI. CONT. & ATMOS. CONTROL LINE: CP5-18"-HE DWG: ISI-94699-A REV: 03
NORTH W-5A Drywell Pen I/ a
- X-47 EL. 987'-3" R(6"x4")
Wali H-1 Pen H- 4 W-
\_J X = HANGER NO.
Is' NH-91230 = WELD NO. NH-36258 REF: NH-94879 IS? MONTICELLO ISI DWN: BLL CHKDQ~tJ APPD: Rgt? SYSTEM: SPARE PENETRATION X-47 LINE: CGC1-6"-CB
- = lr -SSIBLE ( DWG: ISI-94879-A ( NV: 03
c C c NORTH
= HANGER NO.
y s"L.tn% iNH-YIJU n An ( ) = WELD NO. NH-94873 WEL NO NH-36258 REF: NH-94966 INS? MONTICELLO ISI DWN: BLL CHKDC:-%J. APPD: SYSTEM: PRI. CONT. & ATMOS. CONTROL NOTE: LINE: CP4-20"-HE & CP3-18"-HE LOCATED ABOVE TORUS BAYS 12 & 13 (ABOVE INBOARD HANDRAIL OF CATWALK) _DWG: ISI-94966-A REV: 03
SOUTH H-i H-24
\ Cont. Line 5 \ __XCPI-18'-HE Drywell Pen / \ - ___-
X- 26 - XAO-2381 3 W- W e Is' L = HANGER NO.
= WELD NO.
NH-36258 REF: NH-94966 15P MONTICELLO ISI DWN: BLL CHKD:cr4-3 APPD: K SYSTEM: CONTAINMENT AIR PURGE LINE: CP1-18"-HE DWG: ISI-94966-B ( 7-V: 03
Ki. -
- lC ,
No. ISI-13142-37A
. -- (TE30-16"-DB) DWN: MCWI CHKD: VJb APPD: 0 SYSTEM: RHR. RETURN LOOP "A" LINE: TW30"-16-DO & DLA & DCA DM - DISSIMILAR METAL WELD DWG: ISI-9 7003-A I REV: 04
f .I I r---------------------- ORT - DETAIL A 1 HANGER NO.
- WELD NO.
NF-97003 0 A, = BOLT NO. NF-74551 = VALVE NO. NF-96201 REF: NX-13142-49
'- - .9 .J MO-2030 IS'P MONTICELLO 151 DWN: MCWI CHKD: p.Aii APPD: -
" CON T. ON *INACCESSIBLE SYSTEM: RHR SUPPLY LOOP "A" ISI-13142-49-A (REW10-W1-HE) LINE: RW-10-18"-ED DM = DISSIM" 'NR METAL WELD
( DWG: ISI-97003-B 05 V -I
lC..... . C ORT
- l R148JR- -
CONT. ON ISI-97006-A ,- (REW130-28"-DCA) -
-I ej'
. I , HANGER NO.
EL. . L- ~li = WELD NO. 0 = BOLT NO.
= VALVE NO.'
NF-74552 REF: NF-97004
- DRYWELL EL 942'-3" I%5S MONTICELLO CONT. ON MO-2015 . WEST SHUT 18- Az I51-13142-18A Y DOWN COOLING DWN: MCWI CHKD:
(TW20-16"-DBE). SYSTEM: RHR RETURN DM = DISSIMILAR METAL WELD . . I INF- TW20l-1r"-nR
- = INACCESSIBLE
(f-bs
'T EL. 96V-11 0' Az
= HANGER NO.
= WELD NO.
ONfi 0 = BOLT NO. El = VALVE NO. NOTE: Mer MONTICELLO ISI LOCATED IN DRYWELL DWN: MCWI CHKD: 1
- B2= BOLTS NUMBERED CLOCKWISE. BOLT (# 1) IN-LINE WITH INLET PIPING. APPD: honW SYSTEM: RECIRC LOOP "A" DM = DISSIMILAR METAL WELD LINE: REW13A-28"-DCA IA = INTEGRAL ATTACHMENT (ASME ITEM 810.20)
DWG: ISI-9 7005-A Y_ /: 05
C C I:. NORTH
.' N N-2K N-2J-IA DM LLJ
= HANGER NO.
>RMIJR3 A CONT.-ON If<
= WELD NO.
ISI-97005-A -J' - NF-96201 REW13A-28"-DCA NX-7831-37-1 HO\ REF: NF-97005 IA 15 MONTICELLO I DWN: BLL CHKD: cr 8APPD: SYSTEM: RECIRC. MANIFOLD "A" DM = DISSIMILAR METAL WELD LINE: REW32-22" IA = INTEGRAL ATTACHMENT (ASME ITEM 810.20)
IA
= HANGER NO.
NF-97005 NF-96201 NX-7831-34 REF: NX-7831-37-3 N5' MONTICELLO ISI PLAN 'A-A' DRYWELL DWN: BLL CHKD.-=:' l! APPD: , PLAN 'B-B' SYSTEM: RECIRC PUMP A SUPPORTS EL. 935'-O" EL. 952'-O" LINE: IA = IN( AL ATTACHMENT (ASME ITEM B10.30) ( DWG: ISI-97005-C I I A
'V: 06
C( CI I-C. deg Az. NT CONT. ON ISI-97006-B CONT. ON N-1B SEE ISI-FIG. 5..' CONT. ON I ISI-73880-Ad 7
- - REW3-4'-VCA .'
- EL 954'-0" ,
SEE IA
- HANGER NO.
= WELD NO.
N IA RCBJR-9 I _ -
- RCBKR-14 H-.206
- IA e - - BOLT NO.
*NF-97006-NF-96202 Flsll = VALVE NO.
REF: NX-7831-37-1 NOTE: N\SP MONTICELLO LOCATED IN DRYWELL DWN: MCWI
- 02= BOLTS NUMBERED CHKD:
CLOCKWISE. BOLT (p 1) IN-LINE WITH INLET PIPING. SYSTEM: RECIRC LOOP DM = DISSIMILAR METAL WELD .INE: REW13[3-213"-DCA IA = INTEGRAL ATTACHMENT (ASME ITEM B10.20) I-
NORTH IA
= HANGER NO.
IA
= WELD NO.
NF-97006 NS ) NF-96202 REF: NX- 7831-37-1 ISi MONTICELLO DWN: BLL CH I SYSTEM: RECIRC Dl'"AILAR METAL WELD DRYWELL LINE: REW32-22" l' !AL ATTACHMENT (ASME ITEM B10.20) DWG: I
C . - . - . c ( . I, - 11,
- 1. NORTH IA
= HANGER NO.
NF-97006 NF-96202 NX-7831-34 REF: NX-7831-37-3 15 MONTICELLO iSI DRYWELL DWN: BLL CHKD: Oya APPD: > PLAN 'A-A' PLAN 'B-B' SYSTEM:. RECIRC .PUMP. B SUPPORTS . .. EL. 935'-O"- - -EL; 952'- 0" - - LINE: IA = INTEGRAL ATTACHMENT (ASME ITEM B10.30) DWG: ISI-97006-C I REV: 07
! .K N T K>
\ \ CONDENSING CHAMBER
\\ CONDENSING CHAMBER
--l)
I-SEE ISI-FIG. 5 I-Z~l 7 = WELD NO. REF: NF-97007 IS? MONTICELLO ISI DWN: MCWI CHKD: fZAV> APPD: 0 NOTE: LOCATED IN DRYWELL SYSTEM: RX INST. NOZZLE N-11B LINE: RLM2- 1 1/2"-DCA DM = DISSIMILAR METAL WELD I _DWG: ISI-97007-A tF-V: 04
Ac: I c: I-..- c I I ., - ,, I i; , He . l, I . 8 B NSING CHAMBER . CONDENSING I .SEE ISI-FIG. 5
- -:. . j DETAIL
(~ J WELD NO. REF: NF-97008 ISP MONTICELLO . ISI DWN: MCWI CHKD: '14b APPD: b NOTE: LOCATED IN DRYWELL SYSTEM: RX INST. NOZZLE N-l A --- - - LINE: RLM1-1/2"-DCA DM-'=' DISSIMILAR METAL WELD
.S DWG;:
UWU ISI-97008-A
- 7 0 -AI I REV:: 040
17':-, EEL
-- Z11I3.- EL !953*-10O
= HANGER NO.
L-l J
- WELD NO.
REF: NF-97027 KS? MONTICELLO IS1 DWN: MCWI CHKD: t(IXjq APPD: ,97-SYSTEM: RHR EQUALIZER NOTE: LINE: TW40-4'-OBA LOCATED IN DRYWELL (, I DWG: ISI-97027-A L ': 05
.C c C NORTH rywell Pen w-1i X-25 IE w-2 i E.988'-6" EL. 985'-O"
- -1
., 1:, .. ;.,
EL. 977-6 1/2"
= HANGER NO.
I NON-SAFETY CV- 2385 = WELD NO.
, NH-91230 N NH-36258
'- ,- REF:NH-105531 IS? MONTICELLO ISI DWN: BLL CHKD.kjj APPD: 9.rP NOTE: - - SYSTEM: STANDBY GAS .TRTMNT & RX PLENUM COMPONENTS BELOW 985' ARE IN RWCU ROOM LINE: CP2-18'-HE
- = INACCESSIBLE DWG: ISI-105531-A I REV: 03
NORTH W-3 EL. 928'-O"
) l w-2I
<<6" Torus Pen w-fio X-240 0-4540 >
W-i I-S I EL. 935'-O" _ q: ( T )= HANGER NO. I I I I I 6 = WELD NO. NH- 36258 \./t~T NH-116629 REF: NH-158074 1%5 MONTICELLO ISI DWN: BLL CHKD:C4tA APPD: RAt' SYSTEM: TORUS HARD PIPE VENT LINE: HPV-8"-HE ( DWG: ISI-158074-A I V: 04
K- ..,........ - -l-(c C-..... I-, .I I ORT
.. i I-
. - I -.
I - . . . : I 1, - I 10-2A, (E200A)
~EL. 20-5 12-I I
. I
- HANGER NO.
REF: NX-13142-16 KS? MONTICELLO . ISI DWN: MCWI . CHKD:
- APPD: ,05r I.
SYSTEM: RHR. SERVICE. WATER - . - NOTE: LINE: SW11-16"-GF LOCATED IN RHR 'A' ROOM DWG: ND-ISI-100 . REV: 02
RHR EBB ROOM TORUS ROOM SW10-16"-GF NT - _EL. 9.23-1O SW10-1 8"-GF CONT ON DWG ND-ISI-102
- HANGER NO.
REF: NX-13142-50 KS? MONTICELLO ISI DWN: MCWI CHKD: fM APPD: OS' SYSTEM: RHR SERVICE WATER NOTE, LINE: AS NOTED LO C ATED~~~~ E C O R B Dl~ A.. DWG: ND-ISI-101 -' V: 02
\i.
C If K II C -c R-T
- CONT -ON ND-ISI-110 RUS ROB
. _. -J I: - :- "
I I',; CONT ON DWG 8 HANGER NO. EL. 897'-3' REF: NX-13142-50 1%S? MONTICELLO . ISI DWN: MCWI CHKD: APPD: A;'O 47-SYSTEM: RHR SERVICE WATER. NOTE: LOCATED IN REACTOR BLDG LINE: Swlo-18"-GF DWG: ND-ISI-102 REV: 01
(7N fin...n EL. 925'-2 7/8-ROOM RHR 'A' ROOM
- HANGER NO.
EL. 925'-2 1/8". REF: NX-13142-93 IS' MONTICELLO ISI DWN: MCWI CHKD: TWPI APPD: one SYSTEM: RHR SERVICE WATER NOTE: LINE: AS NOTED LOCATED l* ')EACTOR BLDG DWG: ND-ISI-ND-ISI-103 103 7-T -V V: 0202-
, I Ic C f :
bs aKT . .- .7 O-RTI-I Il:
... I . I ., II o' I I .
i-:,,.
- HANGER NO.
CONT ON DWG ND-ISI-103 IS' MONTICELLO ISI . DWN: MCWI CHKD: APPD: A - , SYSTEM:- RHR SERVICE-WATER . NOTE: LOCATED IN REACTOR BLDG LINE: SW9-18"-GF IDWG: ND-ISI-104 I REV: 01
/ *x; 0
EL. 944'-3' CONT ON DWG CONT ON DI ND-ISI-104
- HANGER NO.
REF: NX-13142-12 KS? MONTICELLO ISI DWN: MCWI CHKD: i,-!Z APPD: it-SYSTEM: RHR SERVICE WATER NOTE: LOCATED IN TURBINE BLDG. LINE: SW9-18"-GF IL I, /f IDWG: IDWC: ND-ISI-105 NO-ISI- 105 T 7- V: ol01
K I-, .- m-<C . C
, I .. ..-ORT
-CONT ON DOWGO ND-ISI-107 - I
. . I .,
i I - I
- 1, li,I I . - - -- - - . .. " : :
-r_
CONT ON DWGI ND-ISI- 105 -HANGER NO. nrlrl_ ki" 4 . . - . - I ntr-r- IItA - Ilf Y.) - I MrS MONTICELLO ISI DWN:MCwi CH KD: 'PM-0 APPD: o , SYSTEM: RHR SERVICE.-WATER -------I.1 NOTE: ,LINE: sw9-18"-GF LOCATED IN TURBINE BLDG IDWG: ND-ISI-106 -. .4 REV: 02
I.. -* NOR T SW9-1 2"-GF P-109A RHR SERVICE WATER PUMP
- HANGER NO.
IS;> MONTICELLO ISI EL. 925'-3" / CONT ON DWG DWN: MCWI CHKD: tD APPD: , - ND-ISI-106 SYSTEM: RHR SERVICE WATER NOTE: LINE: AS NOTED LOCATED 1P 1' URBINE BLDG If' DWG: ND-ISI-107 T 7 02
c KC.
- I
( IC...t
. I I . : I. . . .. ..t
.. .1. . 1. - - 11- . ORT
- l,
- , .%~
P-109D RHR SERVICE WATER PUMP SW10-12"'-GF P-109W EC RHR rav § SERVICE WATER PUMP SW10-18"-GF LONG t RUN 2 iI
\-EL. 925'-3
= HANGER NO.1 REF: NX-13142-55
I .
, HANGER NO.
REF: NX-13142-92 l%5"P MONTICELLO ISI DWN: MCWI CHKD: ?JZ) APPD: osiv7 ' SYSTEM: RHR SERVICE WATER NOTE: LINE: SW1o-18"-GF LOCATED -' TURBINE BLDG IDWG: ND-ISI-109 ( -'V: 02 C. K.
-C, C
l 4 ' i t EL. 931'-O0 DOOR 125
' - - / I I' I\ CONT ON DWG I ND-ISI-lO9 TURBINE BLDG '; .
CONDENSER ROOM
- HANGER NO.
REF: NX-13142-92 MONTICELLO ISI DWN: MCWI CHKD: T1~t) APPD: 7 SYSTEM: RHR SERVICE WATER NOTE: LOCATED IN TURBINE BLDG LINE: SW10-18"-GF DWG: ND-ISI-11 REV: 01
(:
- ORT NO CONT.
(NON-SAFETY) EL. 939'-9" -- RHR-SW-12 TURBINE BLDG Z CONT. ON ND-ISI-106 CONT. ON ND-ISI-105 CLASS 2 CONT. ON 151-13142-48-B
- HANGER NO.
NlH-91187-1 REF: NX-1 3142-48 IS'p MONTICELLO ISI DWN: MCWI CHKD: VA APPD:,fi SYSTEM: RHR SERVICE WATER NOTE: LINE: SW9-8"-GF LOCATED IIN TURBINE BLDG (FLOOR EL. 931'-O") (. _DWG: ND-ISI-111 *V: 03
1ct (C.... .C NT E5W9-6"-HBD ESW-35 ESW9-3"-HBD ESW9-3"-HBD "1r
- HANGER NO.
REF: NF-93484 NS? MONTICELLO ISt DWN: MCWI CHKD: 1Z APPD: USE NOTE: LOCATED IN TURBINE BLDG (FLOOR EL. 911'-0" ) SYSTEM: RHR SERVICE WATER LINE: AS NOTED
- 3 SUPPORT IS EXEMPT PER IWF-1230 (IWD-1220(o))
DWG: ND-ISI-123 - REV: 02 I
(C .c,
... I--- ___ 1-1 I, NO CONT.
. NON-SAFETY 91-1 FROM FW2A-14'ED PT 'A' FROM FW5-4"ED a< 1 5 FW-94-1 CONT. ON f:..
aI ISI-13142-52A i EL 940'-6' i EL. 939'-O" - STEAM CHASE
' WELD NO.
REF: NX-13142-30 RSP MONTICELLO .IS DWN: MCWI CHKD: 13- APPD: o>c,-, SYSTEM: RCIC FEEDWATER LINE: _DWG: NC-ISI-37 I REV: 04
IABOVE CRD REBUILD AREA l NO CONT. l NO CONT. 3" x 0.438'T i OM4 I 3' x 0.300"T NO CONT. CONTROL ROD DRIVE TO REACTOR WATER CLEANUP = WELD NO. REF:.NX-13142-51 NSP MONTICELLO ISI DWN: MCWI . CHKD: 4'-2l APPD: ,5J SYSTEM: CRD TO RWCU LINE: OM = DISSIII AR METAL WELD K-l DWG: NC-ISI-51 El"02
NUCLEAR MANAGEMENT COMPANY : INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN -INSPECTION PLAN AND SCHEDULE TABLE Periods Period 1 (May 1, 2003 to May 31, 2005) Shortened due to 1 year extension of 3rd Interval Period 2 (June 1, 2005 to May 31, 2009)- Period 3 (June 1, 2009 to May 31, 2012); Scheduled Outaaes
-Interval - Period - Outaqe # - Year; .
4th 1 1 2003 4th 1 2 2005 4th 1 .2007. 4th 2 2 -.2009 4th -3 1 :2011 Above noted outage dates are subject to change during the interval. Inspection percentages are based on periods in accordance with Program B and Code Case N-598, regardless of currently scheduled outage dates. Notes:
- 1. Components may be rescheduled within'the same period.
- 2. Longitudinal welds are examined with the associated circumferential
-welds.-
3.- IWB, IWC, and IWD integral attachment weld examinations for Category B-K, C-C, and D-A items will be scheduled at the same time as the IWF
- component examination, to the extent practical.
- 4. The Code Category B-G-2 Item B7.80 used in the previous ISI Interval Plan for CRD Bolting inspections was removed from the Section Xi 1995 Edition, 1996 Addenda. 10CFR50.55a requires examination of reused
- CRD Bolting to the 1995 Edition. Therefore, Code Category B-G-2 Item B7.80 has been reinstated in the schedule. -
- 5. . The Code Category B-G-2 Item B7.70 valve bolting is only scheduled when a Class 1 valve is required to be disassembled for maintenance or repair. (See Note (2) for Table IWB-2500-1, Categories B-G-2 and B-M-2) 1.7-1 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN
- 6. The Code Category B-G-2 Item B6.180 pump bolting is only scheduled when a Class 1 pump is required to be disassembled for maintenance or repair. (See Note (3) for Table IWB-2500-1, Cat. B-G-2 and Note (2) for Table IWB-2500-1, Cat.B-L-2)
- 7. The letter designations used in the schedule columns are as follows:
s = scheduled to be examined c = examination was completed for Interval (credit is taken) b = multiple examination or re-occurring examination scheduled during interval B = multiple or re-occurring examination was completed p = item is a partially completed examination (further examination expected) e = expanded scope examination E = expanded scope examination was completed a = additional expanded scope examination A = additional expanded scope examination was completed r = item was rescheduled d = item was deferred until later in the Interval h = examination scheduled for successive periods (follow-up exam) H = *examination scheduled for successive periods was completed I = (lower case L) examination was limited (less than code required percentage achievable) Pressure Testing Notes: A. The system leakage tests described by Section Xl Category B-P, Item B15.10, B15.50, B.15.60 and B.15.70 are performed each refueling outage in accordance with Monticello procedures 0255-20-4IC-1 and 0255-20-IIC-2, except for the end of Interval test. The boundary is configured with all valves in the position required for normal reactor operation startup, however the VT-2 boundary extends to the 2nd closed valve. For the ten-year exam at the end of the Interval, 0255-20-IIC-3 is used to configure the boundary instead of 0255-20-IIC-1. For that test, the systems are configured to pressurize all Class 1 pressure retaining components. All Class 1 pressure retaining components, including the Reactor Vessel, piping, pumps, and valves, within the Reactor Coolant Pressure Boundary (RCPB) are included in the examination boundary. Items B15.10, B15.50, B15.60, and B15.70 are all combined into a single summary number in the Plan under Item B15.10 for the RCPB and are 1.7-2 Revision 3 3/10/2005
NUCLEAR'MANAGEMENT COMPANY ,
- INSERVICE INSPECTION MONTICELLO 4th INTERVAL ' . EXAMINATION PLAN not listed nore'hieduled separately. The'CI~ss'1 systems included in these tests are Reactor Vessel (including vent and drain), Reactor Vessel Instrumentation, Reactor Recirculation, Main Steam, Feedwater, Core Spray, Residual Heat Removal, High Pressure Coolant Injection, Reactor Core Isolation Cooling, Standby Liquid Control, Reactor Water Cleanup, Control Rod Drive, and the Excess Flow Check Valves. Boundary Drawings for these systems are 1.5-2, -3, -4, -5, -6, -7, -8, -9, -10, -11, -
12, -17,-21, -23,-27 Record information of examination results is maintained by the Plant.: B. The system leakage tests described by Section Xl, Category C-H, Items C7.10, C7.30, C7.50 and C7.70 are performed in accordance with the Monticello procedure identified under the procedure columns of the Examination and Schedule table. All Class -2 pressure retaining components for Code Item numbers C7.10; C7.30, C7.50, and C7.70, including piping, pumps, valves, and vessels, are included within the examination boundary of the applicable procedure. Therefore, on a-- system basis, the components are all combined into a single summary number in the Plan under Code Item C7.10 for that system and are not listed nor scheduled separately. Record information of examination results is maintained by the Plant. C. (reserved - this note not currently in use) D. See Code Case N-498-4 (System Leakage Test in lieu of System Hydrostatic Test, Applicable to Class'3 only). E. See Code Case N-522 (Testing in accordance with Appendix J Program) F. The system leakage tests described by Section Xi, Category D-B, Items D2.10, D2.20, D2.30, D2.40, D2.50, D2.60, D2.70, and D2.80 are performed in accordance with'the Monticello procedure identified under the procedure columns of the Examination and Schedule table. All Class 3 pressure retaining components for Code'ltem numbers D2.10, D2.30, D2.50, and D2.70, including piping, pumps, valves, and vessels, are included within the examination boundary-of the applicable procedU're. Therefore",'in a system basis, the'compbrnents are all cormbined into a single'summary number in the Plan for the System Leakage Test under Code Item D2.1 0 for that system and areh'6t listed'nor scheduled separately. Likewise, for Code Item numbers D2.20, D2.40, D2.60, and D2.80, they are combined under D2.20 for the System Hydrostatic Test. Record information of examination results is maintained by the Plant.
- '. 1.7-3 Revision 3 3/10/2005
NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION MONTICELLO 4th INTERVAL EXAMINATION PLAN NDE Notes: AA. Reactor Pressure Closure Studs, Item B6.30, will be examined when removed near the end of the Interval. BB. (reserved - this note not currently in use) CC. Dissimilar metal weld. DD. Encapsulated weld. EE. The internal surface visual examination is done during maintenance: Atwood Morrill Globe Valve - Main Steam: VT-3 examination of one valve. FF. The internal-surface visual examination is done during maintenance: Target Rock Relief Valves - Main Steam: VT-3 examination of one valve. GG. The internal surface visual examination is done during maintenance: Anchor Check Valves - Feedwater: VT-3 examination of one valve. HH. The internal surface visual examination is done during maintenance: Anchor Gate Valves - Various Systems: VT-3 examination of one valve in each size. II. The internal surface visual examination is done during maintenance: Chapman Crane Gate Valves - Recirculation System: VT-3 examination of one valve. JJ. Welds in core spray and containment spray were added at the end of the 2nd Interval per EGG-MS-8969. KK. (reserved - this note not currently in use) LL. (reserved - this note not currently in use) MM. Augmented examination for MEB 3-1 as amended by Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements (HELB Superpipe - requires 100% volumetric examination of welds in accordance with ASME Section IWA-2400 requirements once per 10 years). NN. (reserved - this note not currently in use) 1.7-4 Revision 3 3/10/2005
C 4th IInterval ISI Plan (Rev.3) PC Page; I of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 ' Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 2 I 1 4 2 a A I4 . A Class .. Surnrary / ComplD I System r Scope I Method I Procedure Code Case 1 A ISI Fig 4 ISI - - . B-A 102637 B1.1 1 VCBA-2 Circ Weld AUG 1 Reactor Vessel OWN .
.... <. .. ... _.. . .. ~.... . - . -.--- --- -- PRE . ... -.....
B-A 102639 ISI Fig 4 ISI Circ Weld AUG - - ; B1.11 VCBB-3
, OWN - :
1 Reactor Vessel
.. ...PRE -.
B-A 102640 ISI Flg 4 ISI B1.1 1 VCBB-4 Circ Weld @ N4C AUG 1 Reactor Vessel OWN
.PRE. .
PRE ._____ ....-. - B.A 10.-5----5 IsI ' B.A 105005 ISI Fig 4 B.11 VCBB-4 Circ Weld @ N4B AUG' Reactor Vessel OWN : I
.. .. ~PRE -
ISI Fig 4 ISI ' . s B-A 102642 . Long Seam AUG' B1.12 VLAA-1 OWN 1 Reactor Vessel
- .. , . ......-.-. , ~PRE-ISI Fig 4 [SI . -
B-A 102643 B1.12 VLAA-2 Long Seam AUG OWN - ; 1 Reactor Vessel PRE . -. ...- - - .- -.- ISI Fig 4 ISI - - -*- - s B-A 102644 B1.12 VLBA-1 Long Seam AUG OWN ; 1 Reactor Vessel
-- - A . 102645
-PRE B-A , 10245 ISI Fig 4 's5 I . -s -.-
B1.12 VLBA-2 Long Seam AUG I Reactor Vessel OWN PRE - - -'____
^- -
R.A - 4n)CAC I Fi-Ig 4 ISI S B1.12 VLCB Long Seam AUG 1 Reactor Vessel OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 2 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 B-A 102647 lSlFig 4 ISI---- B1.12 VLCB-2 Long Seam AUG - . 1 Reactor Vessel OWN PRE-- .. B-A 102648 ISI Fig 4 ISI -- s - B1.12 VLDB-1 Long Seam AUG I Reactor Vessel OWN PRE - -- --- B-A 102649 ISI Fig 4 ISI -s B1.12 VLDB-2 Long Seam AUG 1 Reactor Vessel OWN PRE - - - - - - - - - - - - B-A 102380 ISI Fig I ISI - s B1.21 W- 1 T.H. Circ. Weld AUG 1 Reactor Vessel OWN PRE B-A 102627 ISI Fig 3 ISI - - s 81.21 W-3 B.H. Circ Weld AUG 1 , Reactor Vessel OWN . PRE . .. . . B-A 102638 ISI/UT/PEI-02.03.15 ISI Fig 4 ISI ob-s - B1.21 VCBB-1 B. Head/Vessel AUG 1 Reactor Vessel OWN PRE B-A 102381 ISI Fig 1 ISI .s . . B1.22 W- 2 T.H. Meridional Weld AUG . 1 Reactor Vessel OWN PRE---- -- B-A 102382 ISI Fig I IS[ . . . . . . s B1.22 W- 3 T.H. Meridional Weld AUG I Reactor Vessel OWN PRE B-A 102383 ISI Fig 1. ISI . . . . s B1.22 W- 4 T.H. Meridional Weld AUG - - - - 1 ,Reactor Vessel OWN . . . . ( PRE PiP'inted 3/4/2005
C'i C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) - Page 3 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I - Period 2 - Period 3 Category, Iso No. i
. I I ItemNO, Comp. Desc.
Class Summary I ComplD I System Scope I Method I Procedure Code Case 1- 2 3
- 4 1- 2.. 3t A 1. -2 3 -4A ISI Fig 1 ISI s B-A 102384 B1.22. W- 5 T.H. Merdional Weld AUG 1 Reactor Vessel OWN -- - - - - - -
B. W-6. T.H. Meridional Weld AUG PRE ISI Fig I ISI s B-A 1023865 B1.22 W- 7 T.H. Meridional Weid AUG 1 Reactor Vessel OWN - - - - ISI Fig 3 ISI .-- s B-A 102625 B1.22 W- 2 B.H. Dollar PilLS.W PRE AUG - - - - OWN
*1. .ReactorVessel ISI Fig 3 ISI - -s s B-A 102628 - - -
W- 2 *W *_ --- B.H. Dollar PiLS. - - AUG PRE - - - - -R - -I -- - - -
-~
B1.22 OWN 1 Reactor Vessel ISI Fig 3 ISI -- . s B-A 102628 B1.22 W-. B.H. Meridional Weld AUG OWN - - . 1 Reactor Vessel ISI Fig 3 ISI - - - . s B-A 102628 B1.22 W- 4 B.H. Meridional Weld AUG PRE .- .- .-. OWN - - - - .- . 1 Reactor Vessel Meridional Weld PRE AUG - -- .- - - - - - - - - - B122 W-6B.H.
. . . OWN ISI - .
I a 1SFig3 Vessel Reactor PRE -_ - -_- -_--_- -_- - - R n A 0-M 4 fl 0 IUlcw 1 ISI Fig 3 [SI s 61.22 W-7 B.H. Meridional Weld AUG 1 Reactor Vessel OWN PRE prlnwfM *1IAr7yfM
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 4 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. itemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method ) Procedure Code Case 1 2 3 4 11 2 34 I 2 3 4 B-A 102632 ISI Fig 3 S B1.22 W- 8 B.H. Meridional Weld AUG . . . . . 1 Reactor Vessel OWN - - - - - - - . PRE - - -. B-A 102633 ISI Fig 3 ISI . . . . . . . . B1.22 W- 9 B.H. Meridional Weld AUG 1 Reactor Vessel OWN - - - - - - - . PRE . . . . . . . . . . . B-A 102634 ISI Fig 3 IS1I - - - - - - - s B1.22 W-10 B.H. Meridional Weld AUG . . . . . . I Reactor Vessel OWN - - - - - . PRE B-A 102635 ISI Fig 3 ISI . . . . . . . . - - B1.22 W-11 B.H. Meridional Weld AUG - - - - - . 1 Reactor Vessel OWN PRE - - - . B-A 102641 ISI/UT/PEI-02.03.15 ISI Fig 4 ISI r d - - - d -
- s 81.30 VCBC-5 Vessel/Flange Weld AUG - - - - - - - .
I Reactor Vessel N-623,N-623,N-623,N-623 OWN - - - - - - - . PRE - - . B-A 102387 ISUMT/PEI-02.02.01 ISI Fig 1 ISI r d r d s- - B1.40 W- 8 ISUUT/PEI-02.03.15 T.H. Flange Weld AUG . 1 Reactor Vessel N-623,N-623,N-623,N-623,N-623 OWN . PRE - - - B-D 102374 ISI Fig I ISI s . . . . . . B3.100 N- 6A IR N- 6A Inner Radius AUG . 1 Reactor Vessel OWN - - - - - - . PRE - . B-D 102376 ISI Fig 1 ISI - - - - - - - - s B3.100 N- 6B IR N- 6B Inner Radius AUG I Reactor Vessel OWN - -. - PRE . . . . . . . . . . B-D B3.100 102378 N-71R: ISI Fig 1 N- 7 Inner Radius ISI
. AUG OWN 5
1 ,Paactor Vessel (' ( PRE
.C-Prin1PrJ'314rXX)5
C 4th IInterval ISI Plan (Rev.3) C Page;5 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) i Period I Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary I ComplD / System.. Scope I Method ! Procedure Comp. Desc.
Code Case I 72 A t 1) I A 1 II A B-D 102622 ISI Fig 3 _ ISI B3.100 N-10IR N-10. Inner Radius AUG 1-- Reactor Vessel OWN
.. ,.- ~~PRE _ _ _ _ _ _
ISI/IUT/PEI-02.03.17 ISI Fig 5 ISI . - s - B-D 102651 B3.100 N- IA IR N- IA Inner Radius AUG - 1 Reactor Vessel OWN -.-
-D n4 nP R E- '-_
O2 n CUt-U 4fl0C'1 I U4oJ - ISI Fig 5 ISI s B3.100 N-1BIR N- 1B Inner Radius AUG 1 Reactor Vessel OWN PRF
. . - II- - 1.
On an ^ e~e. Is[ - - - - S I USu.) lvt-V 151 Fig 5 N- 2A Inner Radius AUG . . . . B3.100 N-2AIR OWN . . . . 1 Reactor Vessel
- I. - PMR -
ISI Fig 5 IsI . s B-D 102657 B3.100 N- 2B IR N- 2B Inner Radius AUG
. . ... .OWN O . . . .
Reactor Vessel B-D 102659 ISI Fig 5 ISI -. -s B3.100 N- 2C IR N- 2C Inner Radius AUG . Reactor Vessel OWN - . B-D 102661 - ISIIUTIPEI-02.03.17 ISI Fig 5 iSI r s B3.100 N- 2D IR N- 2D Inner Radius AUG 1 Reactor Vessel OWN
... ~~PRE- .*
B-D 102663 ISI/UT/PEI-02.03.17 ISI Fig 5 ISI r s B3.100 N- 2E IR N- 2E Inner Radius AUG OWN 1 Reactor Vessel PRE_ - - - - - - O-u - .uzwi1 ISI Fig 5 , . . ISI 5 B3.100 . N- 2F IR ., .. . N- 2F Inner Radius ' AUG 1 Reactor Vessel OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 6 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 1o May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B4D 102667 ISI FigS5SI-s B3.100 N- 2G IR N- 2G Inner Radius AUG 1 Reactor Vessel OWN PRE - B-D 102669 ISI Fig 5 ISI S B3.100 N- 2H IR N- 2H Inner Radius AUG 1 Reactor Vessel OWN . PRE - B-D 102671 ISIUUT/PEI-02.03.17 ISI Fig 5 ISI r s - - B3.100 N- 2J IR N- 2J Inner Radius AUG 1 Reactor Vessel OWN - . PRE B-D 102673 ISI Fig 5 ISI -s - B3.100 N- 2K IR N- 2K Inner Radius AUG - - - - - - . 1 Reactor Vessel OWN . PRE B-D 102675 ISUUT/PEI-02.03.17 ISI Fig 5 ISI r s - - B3.100 N- 3A IR N- 3A Inner Radius AUG
- 1. Reactor Vessel OWN PRE ---
B-D 102677 ISI Fig 5 ISI - .-- -s B3.100 N- 3B IR N- 3B Inner Radius AUG 1 Reactor Vessel OWN PRE - B-D 102679 ISI Fig 5 ISI -- s - - - B3.100 N- 3C IR N- 3C Inner Radius AUG . 1 Reactor Vessel OWN . PRE--. B-D 102681 ISI Fig 5 ISI-. . B3.100 N- 3D IR N- 3D Inner Radius AUG - - - - . 1 Reactor Vessel OWN PRE - - . B-D 102683 ISI Fig 5 ISI s B3.100 . - N-4AIR N- 4A Inner Radius AUG 1 Reactor Vessel OWN PRE
- C.-
Printed 3/4/2005
C Monticello Nuclear Generating Plant C" 4th Interval ISI Plan (Rev.3) C Page -7 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method ! Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-D 102685 ISI Fig 5 ISI B3.100 N- 4B IR N- 4B Inner Radius AUG I Reactor Vessel OWN :
, .............: - >.- . , .PRE _ .. _..
B-D 102687 ISIIUTIPEI-02.03.17 ISI Fig5 ISI r s - - 83.100 N-4CIR N- 4C Inner Radius AUG - - - -- 1 Reactor Vessel OWN - ' _ _ .'~---- --- PRE -..- ___._. B-D 102689 ISI Fig 5 lSI . - - - B3.100 N- 4D IR N- 4D Inner Radius AUG
- 1. Reactor Vessel OWN
- - PRE.
B-D 102691 [SI Fig 5 ISI s - B3,100 N-5A IR N- 5A Inner Radius AUG Reactor Vessel OWN
-.
- PRE . .... - .. . .. .
B-D 102693,,, ISINUT/PEI-02.03.17 [SI Fig 5 ISI r s - - B3.100 N- SBIR N-SBInnerRadius AUG . Reactor Vessel OW - - - :- -- -- -- B-D 102695 ISIIUT/PEI-02.03.17 ISI Fig 5 ISI r s - - B3.100 N- 8A IR N- 8A nner Radius AUG . 1 Reactor Vessel OWN - :
. ... . . . . .. ." . . . .PRE -
B-D 102697 ISI Fig 5 ISI -s -- --- B3.100 N-8BIR N-8B Inner Radius AUG Reactor Vessel OWN -
.... PRE B-0 102699 : -SI Fig 5 ISI s B3.100 N-91R N- 9 Inner Radius AUG 1 Reactor Vessel OWN -
-PRE - - - - - - - - - - - -
. ISI Fig I, . ISI s - - - -
0 B-D . 102375 , .... B3.90 ' N- 6A NV . ., . ... NozlefHead Weld AUG - '7. " .. ' N-613-1 OWN . . . . 1 Reactor Vessel PRE . . . . Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 8 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope / Method / Procedure Code Case I 2 3 4 11 2 3 4 1 2 3 4 B-D 102377 ISI Fig 1- IS s B3.90 N- 6B NV N- 6B Noz/Head Weld AUG . . . . . . . . 1 Reactor Vessel N-613-1 OWN - ..- PRE - - - - - - - - -- B-D 102379 [SI Fig I IS1 - - s- . . B3.90 N-7NV N- 7 Noz/Head Weld AUG . 1 Reactor Vessel N-613-1 OWN - - - - - - - . PRE .- ... ........ B-D 102623 ISI Fig 3 ISI . . . . . . . . s B3.90 N-10NV N-10 Noz/VslWeld AUG - - - - - - - - . 1 Reactor Vessel N-613-1 OWN - - - - - - - . PRE-- - - - a a o B- 102652 ISIIUTIPEI-02.03.17 ISI Fig 5 IS1 r s - - B3.90 N-1ANV N-1A VsVNoz Weld AUG - .... 1 Reactor Vessel N-613-1,N-613-1 OWN PRE B-D 102654 ISI Fig 5 IS1 - - - - - .s - . B3.90 N- 1B NV N- I B VslUNoz Weld AUG - - - - - - - . I Reactor Vessel N-613-1 OWN - - .- ... PRE .- B-D 102656 ISI Fig 5 ISI - - - - - -s - . B3.90 N- 2A NV N- 2A Noz/Vsl Weld AUG - - - - 1 Reactor Vessel N-613-1 OWN - - - - - - - . PRE - - - - - - - - - B-D 102658 ISI Fig 5 ISI . . . . s B3.90 N- 2B NV N- 2B Noz / Vsl Weld AUG . . . . . . 1 Reactor Vessel N-613-1 OWN - - . PRE - - - - - . - . B-D 102660 ISI Fig 5 IS1I- . --. - s B3.90 N- 2C NV N- 2C Noz/Vsl Weld AUG . . . . . . . . I Reactor Vessel N-613-1 OWN - - - - . - PRE - - - - . - - B-D 102662 ISUUT/PEI-02.03.17 ISI Fig 5 IS1 r 5 83.90 N- 2D NV N- 2D Noz/Vsl Weld AUG 1 Reactor Vessel N-613-1,N-613-1 OWN PRE Printed 3/4/2005
C. Monticello Nuclear Generating Plant C, 4th Interval ISI Plan (Rev.3) C. Page .;9 of 332
.ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
IPeriod I Perloi 12 Period 3 Category, Iso No. I ItemNO, I I.Comp. . Desc. Class - -Summary I ComplO I System - Scope / Method I Procedure. . -- Code Case- I1.2 .3 4 .1- 2 -3 4 1.,2 3.-4 B.D 102664 . SfIUT/PEI-02.03.17 ISI Fig 5 S r s - - - - - - - - - - 83.90 N- 2E NV N- 2E Noz/Vsl Weld AUG - - - - - - - - - - - - 1Reactor Vessel . -N-613-1.N-613-1 OWN- - - - - - - - - - -
. --. PRE - - - - -- -
B-D 102666 ISI Fig I.SI ---- - -s 83.90 N- 2F NV N- 2F NozIVsl Weld AUG - - - - - - - -
- 1. Reactor Vessel N-613-1 OWN - - - - - - - - - - -
.P..".-.- P-E----- -.-.--.---
B-D 102668 [SI Fig 5 ISI-S - - - - - - B3.90 N- 2G NV N- 2G NozIVsI Weld AUG - - - - - - - - - - - - 1I Reactor Vessel N-613-1 OWN - - - - - - - - - - - -
.. ... .. - PRE '
B.D 102670 lSl Fig 5 [SI.I 5 - B3.90 N- 2H NV N- 2H NozlVsl Weld AUG I Reactor Vessel... . N-61 3-1 OWN PRE B-D 102672 ISIIUTJPEI-02.03.17 ISI Flg 5 [IS r s - - - - - - - - - - 83.90 N- 2J NV N- 2J1 Noz/Vsl Weld AUG . . . 1 Reactor Vessel N-61 3.1 N-61 3-1 OWN - - - - - - - - - - - -
-PRE' B-D 102674 .I SIFig 5 ISI--- - -s - -
83.90 N- 2K NV N- 2K NozIVsI Weld AUG - - - - - - - - - - - 1 Reactor Vessel N-61 3.1 OWN - - - - - - - - - - - - PRE -- * -- 8-D 102676 ISIIUTIPEI-02.03.17 151Fig 5 ISI . r s - - - - - - - - - - B3.90 N- 3A NV N- 3A VsIVNoz Weld AUG - - - - - 1 Reactor Vessel N-613-1,N-613-1 OWN - - - - - - - - - - - -
-.... PRE 8-0 102678 ! SI Fig SI 1 - -s- ----
83.90 . N- 38 NV N- 38 VsllNoz Weld AUG - - - - - - - - - - - - IReactor Vessel N-613-1 OWN - -. '- - -.- PRE - - - - - - - - - - - - 8-0,, 102680.-,- 1 -ISI Fig 5 [SI 5 83.90 . N- 3C NV.~ r. ~ -N- 3C Noz/VsI Weld AUG 1Reactor Vessel N.613-1 OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 10 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-D 102682 ISI Fig S . ISI- . s B3.90 N- 3D NV N- 3D VsUINoz Weld AUG - . 1 Reactor Vessel N-613-1 OWN PRE B-D 102684 ISI Fig 5 ISI s - - B3.90 N- 4A NV N- 4A Noz/Vsl Weld AUG 1 Reactor Vessel N-613-1 OWN PRE - B-D 102686 ISI Fig 5 .ISI . .- s B3.90 N- 4B NV N- 4B Noz/Vsl Weld AUG - - . 1 Reactor Vessel N-613-1 OWN PRE - - . B-D 102688 ISI/UT/PEI-02.03.17 ISI Fig 5 ISI r S - - B3.90 N- 4C NV N- 4C Noz/Vsl Weld AUG . . . . 1 Reactor Vessel N-613-1,N-613-1 OWN - - - . PRE -. B-D 102690 ISI Fig 5 ISI - - - - - s B3.90 N- 4D NV N- 4D Noz/Vsl Weld AUG - - . 1 Reactor Vessel N-613-1 OWN PRE - - -- -- - - B-D 102692 ISI Fig 5 ISI . . -s . B3.90 N- 5A NV N- SA Noz/Vsl Weld AUG . - 1 Reactor Vessel N-613-1 OWN - - - - . PRE B-D 102694 ISI/UT/PEI-02.03.17 ISI Fig S ISI r s - - B3.90 N- 5B NV N- 5B Noz/Vsl Weld AUG - . 1 Reactor Vessel N-613-1,N-613-1 OWN PRE- ---- - - - B-D 102696 ISI/UT/PEI-02.03.17 ISI Fig S ISI r s . - B3.90 N- 8A NV N- BA Noz/Vsl Weld AUG - - - - . V 1 Reactor Vessel N-613-1,N-613-1 OWN - PRE B-D . 102698 . ISI Fig S . ISI B3.90 N- 8B NV N- 8B VsVNoz Weld AUG 1 P4ctor Vessel NC'4-1 OWN PRE p - - -oo
C- C Monticello Nuclear Generating Plant 4th Intl erval ISI Plan (Rev.3) Page 11 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 , Period 3 Category, Iso No. ItemNO, Comp. Desc. A 2 I A .Class - Summiary I ComplD I System ....- Scope / Method / Procedure = Code Case 1 2 3 A I 2 A I B-D 102700 ISI Fig 5 B3.90 N- 9 NV N- 9 Ves/Noz Weld AUG 1- Reactor Vessel N-613-1 OWN .
.PRE B-G.1 102710 ISI Fig 6 ISI r d - r d s -
B6.10 Nuts 64 RPV Nuts AUG .-
.1 Reactor Vessel .- , .,,,. OWN
-.. - PRE-B-G-1 101971 ISIIUT/PEI-02.03.06 ISI-97005 A ISI r s - .
B6.180 B-2 RC Pump A Studs, Nuts AUG . 1 Recirculation A N-307-2,N-307-2 OWN PRE - B--1 102076 ISI-97006-A ISI r r t - B6.180 B-2 . . RC Pump B Studs, Nuts AUG . 1 - Recirculation B - *, N-307-2,N-307-2,N-307-2 OWN .
~~PRE----~-
B-G-1 101992 ISIIVTIPEI-02.05.01 ISI-97005-A s5s - - - - - - - - - - B6.190 P200-A Flange Surface AUG
.1.-.. Recirculatlon A .. - . , . , OWN
.-. ~ PRE- -- -*-- -~.. .
B-G-1 107184 ISI-97006-A ISI tt-- - - B6.190 P200-B Flange Surface AUG . 1 Recirculatlon B OWN
.~PRE-B-G-1 102711 - ISI// ISIFig6 ISI . r d - - r d - . s B6.20 Studs . 64 RPV Studs, In-Place AUG
. Reactor Vessel N-307-2,N-307-2,N-307-2,N-307-2,N-307-2 OWN
.- 1 1 . .. PRE . - ..
102712 ISI Fig 6 ISI r r r r s B-G-1 B6.30 Studs 64 RPV Studs, Removed AUG . 1 Reactor Vessel N-307-2.N-307-2,N-307-2,N-307-2,N-307-2 OWN PRE D- l '1 IV48tW 'I'.: , I . .' ..
' . ., .. ...' .. ISIFlg -* , . ISI r d rd - S B6.40 . -Threads in Flange. . .Threads in Flange . AUG OWN : . .
1 Reactor Vessel PRE Printed 314t2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 12 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD / System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 411 2 3 4 B-G.1 102708 ISI Fig6 ISI r d r d s - B6.50 Bushings 64 Bushings AUG I Reactor Vessel OWN PRE - B-G-1 102713 ISI Fig 6 ISI r d r d s-B6.50 Washers 64 Washers AUG - 1 Reactor Vessel OWN PRE - B-G-2 102373. ISWT/PEI-02.05.01 ISI Fig 1 ISI r s . - B7.10 B- I N-6B Flange Bolts AUG 1 Top Head OWN PRE B-G-2 100395 PSI/VT/PEI-02.05.01 ISI-FIG.1 IS1- - - - - - - - - s - B7.50 B-2 PSINT/PEI-02.05.01 Flange Bolts AUG 1 Rx Ves Head Cooling AUG/PTIPEI-02.01.01 OWN PRE p B-G-2 100566 ISINiT/PEI-02.05.01 ISI-13142-33-A ISI c 57.50 B-1 Flange Bolts @ W-12 AUG Main Steam A OWN PRE - - -- B4G.2 100567 ISI-13142-33-A ISI - ss - B7.50 B-2 Flange Bolts @ W-14 AUG
- 1. Main Steam A OWN PRE B-G-2 100568 ISIITIPEI-02.05.01 ISI-13142-33-A ISI c -
B7.50 B-3 Flange Bolts @ W-16 AUG 1 Main Steam A OWN PRE ----. . B-G-2 100569 IS1I 13142-33-A IS1 -s - - :- B7.50 B-4 Flange Bolts @ W-18 AUG I Main Steam A OWN -. PRE B-G-2 100570: ISI-13142-33-A [SI - S - - B7.50 .B5 Flange Bolts @ W-20 AUG 1 Main Steam A OWN PRE I prinit-d V4Ir~XJO
C C (7 Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 13 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May.31, 2012) Period I Period 2 Period 3 Category, -I - Iso No. Comp. Desc. .
- ItemNO, Class -- Summary I ComplD I System - Scope I Method I Procedure Code Case .11 2 3 . 4 11:'2 3 :'~4 1 2 3 4.
B-G-2 100571 ISI-13142-33-A ISI s B7.50 B-6 Flange Bolts @ W-22 AUG 1 Main Steam A -
- OWN
. . . - PRE . . . . . ...
B-G-2 100621 ISINT/PEI-02.05.01 ISI-13142-34-A ISI . C c B7.50 B- I . Flange Bolts @ W-13 AUG 1 Main Steam B OWN ! .- PRE - - - -- B-G-2 100622 r PSINT/PEI-02.05.01 ISI-13142-34-A ISI - s - B7.50 B-2 Flange Bolts @ W-1 5 AUG I Main Steam B OWN PRE - b . . . . . - B-G.2 100623 ISN/VTPEI-02.05.01 ISI-13142-34-A ISI c - . -- B7.50 B-3 PSINT/PEI-02.05.01 Flange Bolts W-16 AUG I Main Steam B OWN E. . ... . B4-2 100674 ISI-13142-35-A ISI - -. s - - B7.50 B-3 - Flange Bolts @ W-16,. AUG . - Main Steam C OWN . ...---------
-PE-
~PRE" _ _ _ _ _ _
B-0.2 100675 ISIIVT/PEI-02.05.01 ISI-13142-35-A ISI . - c - B7.50 B- 4 Flange Bolts @ W-18. AUG 1 Main Steam C OWN .
.. . PRE - - - - - - - - - - -
B4--2 100676 ISI/VT/PEI-02.05.01 ISI-13142-35-A ISI C - B7.50 B-5
- Flange Bolts @ W-14 AUG 1 Main Steam C OWN ---
. - - PRE . - .
B-G-2 100725 ISI/VT/PEI-02.05.01 ISI-13142-36-A ISI C - B7.50 B- 1 Flange Bolts @ W-13 AUG 1 Main Steam D OWN :- - PRE - - . B4--2 100726 . .I .ISI-13142-36-A - IS! 5 1 ; FlangeBoits§W-15 AUG B7.50 B- 2 1 Main Steam D OWN PRE Prjin.4 1P.M);
Monticello Nuclear Generating Plant 4th Interval Plan Schedule (Rev.3) Page 14 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-G-2 100727 ~ isI/VTIPEI-02.05.01 ISI-13142-36-A ISI c 7 =-_ B7.50 B- 3 Flange Bolts @ W-17 AUG - - -
-1 Main Steam D OWN -
PRE - B-G.2 100728 ISI-13142-36-A ISI- s B7.50 B- 4 Flange Bolts @ W-19 AUG .1 Main Steam D OWN PRE -* -- B-G-2 100729 IS1-13142-36-A [SI --.- B7.50 B- 5 Flange Bolts @W-21 AUG 1 Main Steam D OWN PRE B-G-2 100730 ISI-13142-36-A ISI -- - s B7.50 B-6 Flange Bolts @ W-23 AUG 1 Main Steam D OWN PRE B-G-2 101392 ISI-74209-1A ISI -- -- s .B7.50 B- 1 Flange Bolts AUG 1 Recirc A Drain Une OWN PRE B-G-2 i.101408. ISI-74210-1A ISI- - s B7.50 B- I Flange Bolts AUG 1 Recirc B Drain Line OWN PRE - - B-G-2 101491 PSI/VT/PEI-02.05.01 ISI-782A-A IS1 - - - s B7.50 B- 1 Flange Bolts AUG 1 Head Vent OWN PRE c-- B-G-2 101492 PSI/VTIPEI-02.05.01 ISI-782A-A ISI r s - B7.50 B- 2 ISI/VT/PEI-02.05.01 Flange Bolts AUG . . . . 1 Head Vent ISI/MTIPEI-02.02.01 OWN PRE c - B-G-2 101616 ISI-821A ISI B7.50 B-I Flange Bolts AUG 1 Bottom Head Drain OWN II. PRE Prin'ed 3'4/2005
CI..C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Pae15 of 332
'ASME Section XI (1995 Edition, 1996 Addenda) (May 1,2003 toMay 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. 1 I ItemNO, -Comp. Desc. Scope/I Method/I Procedure .. -- ,.Code Case 1 22 A I I AlIl I A Iiass -II Summary I ComplD I System -' -- -- 10185 ISI-97003-A I[- B-G.2 Flange Bolts W 11 AUG - - - - - - - - - - - - B7.50 B-3 jRHR RetumnAOW
. - .. ~--.PRE " * -
181--- - -s - 8-G.2 101851 .ISI-97003-A Flange Bolts W 22 AUG - - - - - - - - - - - - B7.50 B.4 -. 1 RHR RetumnA .OWN PRE - .~. [sil,, S - 87.50 8-2 Flange Bolts § W-9 AUG 1 _: RHR Suction A OWN ISI-97003-B 18 ,s - B-G-2 101892 Flange Bolts W- 14 AUG - - - - - - - - - - - - B7.50 8. 3
¶ RHR Suction A . , .OWN 18-97004-A ISI 181-s - - - - - -
B-G-2 101930 Flange Bolts AUG - - - - - - - - 87.50 8-3
..-. ~OWN - - - - - - - - - - -
RHR RetumnB PRE '_--~,--,:. - _ . IS1-97004-A I 18--- - - - s - B-G-2 101931 . Bolts AUG - - - - - - - - - - - - B 50 B4Flange - - - 1 RHR RetumnB -OWN PRE - . -. I81-97005-A I18-- .- - B-G-2 101972 Flange Bolts W-17 AUG - - - - - - 87.50 8- 3 OWN - - - - - - - - - - - - I1 Recirculatlon A PRE ----. . . . .- ISINVTIPEI-02.05.01 ISI-97006-A 181 C - - - - - - - - - - - 8-G-2 . 102077 Flange Bolts'~ W-1 6 AUG - - - - - - - - - - - - B7.50 B-3 OWN - ----. - 1 Recirculation B
-PRE
[Si - - - - Valve Bolts ,. I AUG . . . . B7.70 B- 1 I;. OWN - - - - 1 Core Spray 8 PRE I - - - - Printed 314=205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 16 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary / ComplD I System Scope I Method I Procedure Comp. Desc.
Code Case C o.Cs . ....... ... .... --------......
- 1. 2 It A 1. I2 1 A n n A B-G.2 100425 ISI-13142-26-A ISI B7.70 B-2 Valve Bolts AUG - - - - - - - .
1 Core Spray B OWN PRE - . --.- .- - - B-G-2 100426 ISI-13142-26-A ISI . . . . . . . . . B7.70 B-3 Valve Bolts AUG - - - - - - - . 1 Core Spray B OWN . . . . . . . . . PRE 100492 ISI-13142-31-A ISI . . . . . . . . B-G 2 B7.70 B- 1 Valve Bolts AUG - - - - - - - - . 1 Core Spray A OWN PRE - - - -. ISI-13142-31-A ISI . . . . . . . . . . . . B-G.2 100493 87.70 B-2 Valve Bolts AUG - - - - - - - . 1 Core Spray A OWN . PRE . . . . ... . . . . . B-G-2 100494 ISI-13142-31-A ISI . B7.70 B-3 Valve Bolts AUG Core Spray A P OWN - - - . PRE ... . . . . . .. . ... . -. 100572 ISWNT/PEI-02.05.01 ISI-13142-33-A ISI c - . B-G-2 B7.70 B-7 PSIIVT/PEI-02.05.01 Valve Bolts AUG 1 Main Steam A ISUNT/PEI-W2.05.01 OWN PRE p- - . B-G-2 100573 ISI-13142-33-A ISI . . . . . B7.70 8- 8 Valve Bolts AUG 1 Main Steam A OWN . . . PRE B-G.2 100574 ISI-13142-33-A ISi . . . . . . . . _ B7.70 B-9 Valve Bolts AUG - . - ... OWN . . . . . . . . . . 1 Main Steam A PRE . . . . . . . . . . . B-G-2 .in ,71007 n eAe tI//;~~nn r;Quv 11FrQjuK.ua.wl .. Ib1-1314Z-A .' 1SI 87.70 B-10 .Valve Bolts AUG 1 ("- Steam A OWN PRE p - - - I. (v., Pfinta'd 1V412005
C C C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 17 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 . Period 3 Category, Iso No. . ItemNO, Comp. Desc. I A i4 3 A 1 s- , A Class - Summary / ComplD / System -- -- Scope I Method / Procedure Code Case.. I . ISI-13142-34-A ISI - . B-G.2 100624 B7.70 B- 4 Valve Bolts @ W-26 AUG Main Steam B OWN I B-G.2 100625
~~~~~PRE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
B-G2 100625 ISI-13142-34-A ISI . AUG -. B7.70 B. S Valve Bolts
. OWN 1 .. Main Steam B -
B-G.2 100626 PSINT/PEI-02.05.01 ISI-13142-34-A ISI-B7.70 B-6 PSI/VTiPEI-02.05.01 Valve Bolts AUG 7 1 Main Steam B * , -- -
-. . - - - p- b' 'PRE-.-
B-G-2 100629 PSINT/PEI-02.05.01 ISI-13142-34-A ISt B7.70 B-7 PSINTIPEI-02.05.01 Valve Bolts AUG 1 Main Steam B , - , OWN
. PRE Pb: : -.- -
B-G-2 100672 - ISI/VT/PEI-02.05.01 ISI-13142-35-A ISI . - s B-,1 Valve Bolts AUG B7.70
- - OWN - .,
1 Main Steam C .
.-.- .. ,--PRE -
ISINT/PEI-02.05.01 ISI-13142-35-A ISI c - : B-G.2 100673 PSINT/PEI-02.05.01 Valve Bolts AUG . B7.70 B- 2 1 Main Steam C : OWN PRE' c' ISI-13142-35-A ISI . . . B-G-2 100677 . B7.70 B-6 Valve Bolts AUG 1, Main Steam C *-. - . OWN
-- - - - ' \ '- . , - -- -- ~ 'PRE - ^
B-G-2 . 100679 ISI-13142-35-A ISI B7.70 , B7 Valve Bolts AUG OWN - - - - - . 1 Main Steam C PRE
. . .^ .q^4. A B.G.2 1.n.7.^1-;
4 ; -. .. IS1 B-7 ' Valve Bolts ,r AUG B7.70 1 Main Steam D OWN PRE Prinfa ~4trfl)nc 11
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 18 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case _1 2 3 .4 11 2 3 4 1 2 3 4 B-G-2 100732 ISI-13142-36-A ISI B7.70 B- 8 Valve Bolts AUG 1 Main Steam D OWN PRE -- B-G-2 100733 ISI-13142-36-A ISI B7.70 B- 9 Valve Bolts AUG 1 Main Steam D OWN PRE '- -' - - -- - B-G-2 100734 ISI-13142-36-A ISI B7.70 B-10 Valve Bolts AUG 1 MainSteam D OWN PRE B-G-2 100973 ISI-13142-42-A ISI B7.70 B- 1 Valve Bolts AUG 1 HPCI Steam OWN PRE B-G-2 100974 PSIVTIPEI-02.05.01 ISI-13142-42-A ISI - s - . B7.70 B- 2 PSINT/PEI-02.05.01 Valve Bolts AUG 1 HPCI Steam PSWVT/PEI-02.05.01 OWN ISIVT/PEI-02.05.01 PRE c b B-G.2 101191 IS1-13142-52-A ISI B7.70 B- 1 Valve Bolts AUG 1 Feedwater OWN PRE - - - - B-G-2 101192 ISI-13142-52-A ISI B7.70 B- 2 Valve Bolts AUG 1 Feedwater OWN PRE . B-G-2 101193 ISI-13142-52-A ISI t - B7.70 B- 3 Valve Bolts AUG 1 Feedwater OWN , PRE B-G-2,. - 101246' ISI-13142-53-A lSI B7.70 B- 1 Valve Bolts AUG I Feedwater OWN QI PRE Printed 3/4/2005
C C C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 19 of 332
. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May. 31, 2012)..
Period 1 Pert od 2 Period 3 Category, Iso No.' ItemNO, Comp. Desc. - Class Sumnmary / ComplD I Systerm .
- Scope / Method / Procedure'- - Code Case .- - --- : -iI 2 A I 2 3It A 1 -- A1'
-All ___
B-G.2 101247 ISI-13142-53-A ISI B7.70 B. 2 Valve Bolts AUG
- i. ,Feedwater OWN PRE B-G.2 101248 ISI-13142-53-A ISP B7.70 B- 3 Valve Bolts AUG OWN PRE B-G 2 101848 ISI-97003-A ISI B7.70 B- 1 Valve Bolts AUG 1 . . RHR Return A OWN PRE -;
B-G-2 101849 ISIN/TIPEI-02.05.01 ISI-97003-A ISI c B7.70 B. 2 Valve Bolts AUG 1, -, RHRReturnA ,,OWN PRE B-G-2 101852 ISI-97003-A ISI B7.70 6- 5 Valve Bolts AUG 1 : , RHR Retum-A , , ,OWN PRE - : B-G-2 101890 ISI-97003-B ISI - . B7.70 B- I Valve Bolts AUG - - - . 1, RHR Suction A OWN - : PRE B-G-2 101893 ISI-97003-B ISI : B7.70 B-4 Valve Bolts AUG RHR Suction A OWN PRE - - - - - - - - - B-G-2 101894 ISI-97003-B [SI B7.70 B-5 Valve Bolts AUG 1 RHR Suction A OWN - - : PRE Ri-G2 . initwR -.. - rtt/D n eD..mS ISI s
-lauv I PEl-04.05.0 I B7.70 B-I ; Valve Bolts I. I AUG 1 RHR Return B OWN PRE Prinf-d IF-Itrrn;
- Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 20 of 332 ASME Section Xl (1995 Edition, 1996 Addenda). (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-G-2 101929 ISI-97004-A ISI - - - - - - - - - - - - B7.70 B- 2 Valve Bolts AUG . . . . . . . 1 RHR Return B OWN PRE . . . . . . . . B-G-2 101932 iSI-97004-A ISI - - - - - - - - - - - - B7.70 B- 5 Valve Bolts AUG . . . . . . . . 11 RHR Return B OWN - - - - - - - - . PRE - - - - - - - - - - - - B-G-2 101970 ISI-97005-A IS1 . . . . . . . . . . . B7.70 B- 1 Valve Bolts AUG 1 Recirculation A OWN - - - . PRE . B-G-2 101973 ISI-97005-A ISI - - - - . B7.70 B- 4 Valve Bolts AUG 1 Recirculation A OWN - . PRE B-G-2 102075 1..97006-A .1 . B7.70 B- 1 Bolts AUG
- 1. Recirculation B. OWN -
PRE B-G-2 102078 ISI-97006-A ISI B7.70 B- 4 Bolts AUG - . 1 Recirculation B OWN PRE - - - - - . B-G-2 102392 ISI Fig 2 ISI B7.80 02-23B CRD Housing Bolts AUG 1 CRD Housings OWN PRE . . . . . . . . B-G-2 102395 ISI Fig 2 IS1 - - - - - - - - - - - B7.80 02-27B CRD Housing Bolts AUG 1 CRD Housings OWN - PRE B-G-2 - 102398 ISI Fig 2 IS1 B7.80 02-31 B CRD Housing Bolts AUG 1 r ) Housings OWN ( PRE pri,~-e -i';~nnq
.C Monticello Nuclear Generating Plant 4th Interval ISt Plan (Rev.3) Page 21 of 332 ASMVE Section Xi ( 9 Edition, 1996 Addenda) __(May 1, 2003 to May 31, 201 2)
Period 1 Period 2 Period 3 Category, Iso No. iternNO, Comp. Desc. A Clas - Summriary I CompiD I System --- - Scope I Method I Procedure - . . Code Case. I7 II A 4 ') *I A 4 *1) '1 Siig B-G.2 102401 . CRD Housing Bolts AUG - - - - - - - - - - - - 87.80 06.1158 OWN - - - - - - - - - - - - 1CRD Housings PRE'-- - -- - - - - ' - - -- " - IS ilg 2 I11 , - - - - -- B-G-2 102404 CR0 Housing Bolts AUG- - - - - - - - - - - - - 87.80 06-198 1CRD Housings-OW
..... .PRE IZI F-ig z 151 87.80 06.23B CRD Housing Bolts AUG CRD Housings OWN. I-
- "'" - ,- n mr rnQ I- - - -I- .
8-G-2 102408 ISI Fig 2 is' 87.80 06-27B CRD Housing Bolts AUG 1 CR0 Housings OWN ISI Fig 2 S- - - - - - - - - - - - 8-G.2 102412 Housing Bolts AUG - - - - - - - - - - - - B780 0631BCR0 W
- 1. CR0 Housings .
OW - -. - - - - - - ISI Fig 2 PRE --. - B-G-2 102415 CR0 Housing Bolts AUG . . . . . . . . . . . . 87.80 06-358 OWN - - - - - - - - - - - - 1I CRD Housings
~~~PRE -. ~ .
IS1Fig 2 ISI - - - - - - B-G-2 102418 CR0 Housing Bolts AUG . . . . . . . . . . . . 87.80 06-39B - - - OWN - - - - - - - - - I . CR0 Housings 8-G-2 . 102421 ISl Fig 2 .~isi CR0 Housing Bolts AUG . . . . . . . . . . . . 87.80 10.11B OWN 1 6 R0 Housings PR E . . . . . . . . . . . . R 7 . .. r A A '
- 1. . I. I . .: I I Is' 87.80 : 10-I.158--: .I . i- .rCR0 Housing Bolts AUG 1 CR0 Housings OWN PRE Printed X!42005
Monticello. Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 22 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Scope I Method I Procedure Code Case I 2 3 A I I A A I 3 It A Summary / ComplD I System B-G-2 102425 ISI Fig 2 ISI . . . . . . . . . . . B7.80 10-19B CRD Housing Bolts AUG - - - - - - - . 1 CRD Housings OWN . PRE . B-G-2 102426 PSIVT/PEI-02.05.01 ISI Fig 2 ISI - - - - - - - - - - . B7.80 10-23B PSINTIPEI-02.05.01 CRD Housing Bolts AUG - - - - - - - - . 1 CRD Housings OWN - - - - - - - - . PRE c b B-G.2 102427 ISI Fig 2 ISI . . . . . . . . . B7.80 10-27B CRD Housing Bolts AUG . . . . . . . . 1 CRD Housings OWN - - - - - - - - . PRE . . . . . . . .. . . . B-G-2 102428 PSVNTIPEI-02.05.01 ISI Fig 2 ISR E B7.80 10-31B CRD Housing Bolts AUG . . . . . . . 1 CRD Housings OWN - - - - - - - . PRE c - . B-G-2 102429 ISI Fig 2 ISI . . . . . . . B7.80 10-35B CRD Housing Bolts AUG - - - - - - - - . 1 CRD Housings OWN - - - - - - - - . PRE B-G-2 102432 ISI Fig 2 ISI - - - - - - - - - - . B7.80 10-39B CRD Housing Bolts AUG . . . . . . . . . 1 CRD Housings OWN - - - - . PRE - - - - - - - -- -.- B-G-2 102435 ISI Fig 2 ISI E - - - - - - - . B7.80 10-43B CRD Housing Bolts AUG . . . . . . . . . I CRD Housings OWN PRE .- ... - . .. B-G.2 102438 ISI Fig 2 ISI - - - - - - - - - - . B7.80 14-07B CRD Housing Bolts AUG - - . 1 CRD Housings OWN - - - - - - - .- PRE
-- - '^ . . . .
B-G-2 102441 -. ISI rig Z lSi B7.80 14-11B - CRD Housing Bolts AUG - tl - - (nD Housings OWN - - - (.
/7-PRE I',- -
PrinfM wnnnr
C. C C P Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 23 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) - . (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 2 3 A A 2 i A Class Summary / ComplD / System ' - Scope I Method I Procedure Code Case 1 1 I 3 1 B-G-2 102442 ISI Fig 2 IS, 87.80 14-15B CRD Housing Bolts AUG 1 - CRD Housings OWN
,~ , . .. . --- ------- ' PRE _----.
B4G.2 102443 ISI Fig 2 ISI,- B7.80 14-19B CRD Housing Boils AUG CRD Housings , OWN 1 ,: - - - -- - -- - - .. R-
. ~~~~~~~~~~~~~-
.~PRE B4G-2 102444 ISi F 2 S B7.80 14-238 CRD Housing Bots AUG 1 CRD Housings OWN
,,,,....--------PRE' ..-- - - - -
B4--2 102445 ISi Fig 2 ISI B7.80 14-27B CRD Housing Bolts AUG 1 CRD Housings - OWN PRE - . :.-:-- - - B4--2 102446 PSI/VT/PEI-02.05.01 ISI Fig 2 ISi. . B7.80 14-31B CRD Housing Bolts AUG - _
, - OWN . -
1 CRD Housings
.~PRE ~
B4--2 102447 ISI Fig 2 ISI B7.80 14-35B CRD Housing Bolts AUG 1 CRD Housings OWN
... .... -- - -- ~-~- ' ' 'PRE-:
B4--2 102448 ISI Fig 2 ISI B7.80 14-39B CRD Housing Bolts AUG 1 CRD Housings OWN PRE' -- B4--2 102451 ISI Fig 2 ISI _ B7.80 . 14-43B CRD Housing Bolts AUG 1 CRD Housings OWN PRE . R~~~n. )ACA ,,,. s, :. :ISIIFlg 2 [IS . . . .
.., .I , CRD Housing Bols AUG - - - -
B7.80 1447B CRD Housings OWN . . . . 1 PRE - - - - MrTnl-t -)1flntnr,
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 24 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-G-2 102457 ISI Fig 2 IS1 07.80 18-07B CRD Housing Bolts AUG 1 CRD Housings OWN PRE - B-G-2 102458 ISI Fig 2 IS1 . . . B7.80 18-11B CRD Housing Bolts AUG 1 CRD Housings OWN PRE -- B-G-2 102459 PSIVTIPEI-02.05.01 ISI Fig 2 ISI B7.80 18-15B CRD Housing Bolts AUG 1 CRD Housings OWN PRE c B-G-2 102460 PSINT/PEI-02.05.01 ISI Fig 2 ISI - . 87.80 18-19B CRD Housing Bolts AUG 1 CRD Housings OWN PRE C - B-G2 102461 iSI Fig 2 ISI 87.80 18-23B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B.-G2 102462 ISI Fig 2 ISI - - - . 87.80 18-27B CRD Housing Bolts AUG I - CRD Housings OWN PRE . B-G-2 102463 ISI Fig 2 IS1 B7.80 18-31B CRD Housing Bolts AUG 1 CRD Housings OWN PRE 8-G-2 102464 ISI Fig 2 ISI B7.80 18-35B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B-G62 102465 PSINTiPEI-02.05.01 ISI Fig 2 ISI 87.80 18-39B CRD Housing Bolts AUG C... t CRD Housings OWN PRE (,. Printed 3/412005
C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 25 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) . .. (May 1,2003 to May 31, 2012) Period 1 Period 2 Period 3 I Category, Iso No. - I ItemNO, Comp. Desc. Scope/ Method I Procedure ' . Code Case - -- - 1 3 -A 1 -**2--3 A I.1 2 A-Class -Surnmiry/Compil/System-ISI Fig 2 ISI . . . . . . . . . . . B-G-2 102466 CRD Housing Bolts AUG - - - - . B7.80 18^43B 1,, , CROD Housings . ,, .-. -OWN PRE . . . . . . , ISi Fig 2 ISI : . - - - - - - - - - - - B-G.2 102469 CRD Housing Bolts AUG . . . . . . . . . . . .. B7.80 18-47B OWN - - - - - - - - - - 1 - CRD Housings .- PRE . . . . . . . . B-G.2 102472 ISI Fig 2 ISI . 22-03B CRD Housing Bolts AUG - - - - _ B7.80 1, . CRD Housings._, , ,.OWN ., PRE . . . . . . . . . . ISI Fig 2 ISI - - - - . B-G.2 102475 B7.80 22-07B CRD Housing Bons AUG - - - - - - - . 1 CRDHousings. OWN PRE . . . . . . . . ISI Fig 2 IS1 . - - - - - - - - - - - - B-G42 102476 CRD Housing Bolts AUG . . . . . . . . . . . . B7.80 22-11B. OWN 1 CRDHousings PRE . . . . . . . -, PSINT/PEI-02.05.01 ISI Fig 2 ISI - - - - - - . B-G-2 102477 CRD Housing Bolts AUG . . . . . . . . B7.80 22-15B I CRD Housings OWN - - - - - - - . PRE C - - - - - - - - - . ISI Fig 2 ISI: . . . . . . . . . . . B-G-2 102478 87.80 22-19B CRD Housing Bolts AUG - - - - - . 1 CRD Housings . .O ON . PRE . . . B-G-2 102479 ISI Fig2. ISi . CRD Housing Bolts AUG - - - - - - - - . B7.80 22-23B OWN -. . :- . . 1 CRD Housings PRE - - - - - - - - - - - - Iusou.. - : ISIgFg2 .: ISV B7.80 22-27B ; - - I ,~i I;;- CRD Housing Bolts . AUG 1 CRD Housings OWN PRE prinfor 1140r)nrs
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 26 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.
. a A Class- Summary / ComplD I System Scope I Method I Procedure Code Case 1. 'A B-G-2 102481 PSIVT/PEI-02.05.01 ISI Fig 2 ISI - .
B7.80 22-31B CRD Housing Bolts AUG OWN 1 CRD Housings PRE c - - - BG-2 102482 ISI Fig 2 ISR . B7.80 22-35B CRD Housing Bolts AUG 1- CRD Housings OWN PRE - B-G-2 102483 ISI Fig 2 ISI B7.80 22-39B CRD Housing Bolts AUG I CRD Housings OWN PRE - - - - - - - - - - - - ISI Fig 2 ISI . . . . . . B-G-2 102484 B7.80 22-43B CRD Housing Bolts AUG 1 CRD Housings OWN B-G-2 102487 ISI Fig 2 ISP 87.80 22478 CRD Housing Bolts AUG 1 CRD Housings OWN B-G2 102490 ISI Fig 2 PSI B7.80 22-51B CRD Housing Bolts AUG 1 CRD Housings OWN PRE - .. _- B-G-2 102493 ISI Fig 2 ISP 87.80 26038 CRD Housing Bolts AUG I CRD Housings OWN B-G-2 102494 ISI Fig 2 -P--RE B7.80 26-07B CRD Housing Bolts AUG I CRD Housings OWN B-G2 102495 AAE
*a rig z ISI 87.80 26-118 CRD Housing Bolts AUG 1 (r,0) Housings
,. OWN PRE Printorl 1V4'IOO5
C 'C Page 27 of 332 Monticello Nuclear Generating Plant 4th Interval IS1 Pian (Rev.3) ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I *. Period 2 . Period 3 Category, iso No. itemNO, Comp. Desc. Code Case 1 23 4 1 23 4 1 23 4 tll~ae- .- 'ornmarvn I flnmnin tI ysttm . Scope I Method I Procedure. B-G-2 102496 SFi2 S - - - - - - - - - - - - - 878 618CRD Housing Bolts AUG - - - - - - 1CR D HousingsOW - - - - - - - - - - - -
. ~ ,
. . . .... ... . . . .. . ~ . -.- PR E - - - - -
B-G.2 102497 ISI Fig 2 151 -. 87.80 26.1 98 CRD Housing Bolts AUG7 CRD Housings OW
- - -. ~ ~ -'--- PRE . -- .-
B.G.2 102498 -ISI Fig 2 1St . - 87.80 26-23B CRD Housing Bolts AUG - - - - - - - - - - - - 1CRD HousingsOW
- . II .M . . . M I - - . M . M r IM I . - . l PR E B-G-2 102499 ISI Fig 2 1St 878 628CRD Housing Boits AUG - - - - - - - - - - - -
1 CRD HousingsOW - - - - - - - - - - - -
.7.. ..-- PRE_ _ _
B-G-2 102500 PSINTI/PEI-02.05.01 1SI Fig 2 1St 878 638CRD Housing Bolts AUG 87.80 26.358 CR Huin Bls U OWN 1- CRD Housings7
.. ., .PRE e -- -- t B-G.2 102502 ISI Fig2 181 . - -
B7.80 26.398 CRD Housing Bolts AUG - - - - - - - - - - - - OWN - - - - - - - - - - - - 1CRD Housings BG2IS[ Fig 2 ISt 878 648CRD Housing Bolts AUG - - - - - - - - - - - -
¶CRD Housings OWN -7 PRE -
OW - - - - - - - - 1 CRD Housings B-G.2 102504 - : ... .I : - . .. ~I1 . . . . ICRD Housing Bolts . AUG - - - - 87.80 26-47B8 - -., OWN - - - - 1 CRD Housings PRE - - - - Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 28 of 332
.. ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 22 A I 2 3 4 2 3 A Class Summary I ComplD I System Scope I Method / Procedure Code Case B-G-2 102507. ISI Fig 2 ISI . B7.80 26-51B CRD Housing Bolts AUG .
- 1. CRD Housings OWN B-G-2 102510 ISI Fig 2 [SIE-B7.80 30-03B CRD Housing Bolts AUG 1 CRD Housings OWN
- PRE BG-2 102513 ISI Fig 2 IsI .
B7.80 30-07B CRD Housing Bolts AUG 1 - CRD Housings OWN PRE . . . ... . . . . . . B-G-2 102514 ISI Fig 2 ISR . B7.80 30-11 B CRD Housing Bolts AUG CRD Housings OWN PRE . . . D~r2_3 4 M 4 .. IU -~ JI ISI Fig 2 ISI B7.80 30-15B CRD Housing Bolts AUG 1 CRDHousings OWN DOC F
.- :- - - -I- - - -I
-B -G-2 102516l . . 11ir1g z Is' B7.80 30-19B CRD Housing Bolts AUG
- 1. CRD Housings OWN DDF B-G.2 102517 ISI Fig 2 ISI 30-238 CRD Housing Bolts AUG - .
B7.80 OWN : 1 CRD Housings PRE B-G.2 102518 PSINTIPEI-02.05.01 ISI Fig 2 IS ... B7.80 30-31B CRD Housing Bolts AUG 1 CRD Housings OWN PRE c - B-G. ISI F-Ig 2 IS' B7.80 30-358. CRD Housing Bolts AUG .. . . 1 CRD Housings OWN PRE Printlri.14Q0M5
C C Monticello Nuclear Generating Plant 4th Interval 151 Plan (Rev.3) Page 29 of 332 ASMVE Section XI. (1995 Edition, .1996 Addenda) .. _'.~(May 1, 2003 to May 31, 2012) Period I - Period 2 Period 3 Category, -i so No. IternNO, Comp. Desc.
-- Scope I Method I Procedure.-- - Code Case I. 2.-3, 4 1. 2 3 4 1-2 4 Class - '-Summary!I CompiD I System -
ISI Fig 2 S . . . . . . . . . . . . B-G-2 102520 CR0 Housing Bolts AUG - - - - - - - - - - - - B7.80 30-39B I ; CRD Housings . -OWN PRE B-G-2 102521 ISI Fig 2 isI CRD Housing Bolts AUG - - - - - - - - - - - B7.80 30-43B I RDHousings. .OWN E* ISI Fig 2 151 - - - - - B-G-2 102524 CRD Housing Bolts AUG - - - - - - - - - - - - B7.80 30-47B J1.1. -.. ,-CRDHousi.ngs .. -OWN PRE SI Fig 2 151 - - - - - - 8.G-2 102527 ' CRD Housing Bolts AUG - - - - - - - - - - - - 87.80 30-518B I RDOHousings ...... PRE . -. - .--- -. - - 102530 ISI Fig 2 isi . . . . . .. B-G-2 CR0 Housing Bolts AUG - - - - - - - - - - - - 87.80 3.4-07B 1 CRD Housings
- -OWN
--.. . ,.. .. ~~P R E - ~ - - * -~
8-0.2 102531 151 Fig 2 ISI . - 87.80 34-118 CR0 Housing Bolts AUG 1 CRD HousingsOW _..... . ~~~PRE~ '* - . . B-G-2 102532 ISI Fig 2 ISI CR0 Housing Bolts AUG - - - - - - - - - - - - 87.80 34-15B ICR0 Housings OWN
-PRE - - - - - - - - - - - -
B-G-2 102533 ISI Fig 2 ISI CR0 Housing Bolts AUG - - - - - - - - - - - - 87.80 34-1 98 1 CR0 Housings OWN PRE - - - - - - - - - - - - - I I . -1I1 Fig 2 , 'si - - - - B-G.2 102534, , B7.80 . 34-238 '" : .1. , Ii CR0 Housing Bolts AUG OWN - - - - ICR0 Housings PRE - - - - Printod VIMOM5~
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 30 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. tlemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method / Procedure Code Case 1 2 3 4 1 23 4 I1 2 3 4. B-G-2 102535 ISI Fig 2 ISI B7.80 34-27B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B-G-2 102536 ISI Fig 2 ISI B7.80 34-31 B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B-G-2 102537 ISI Fig 2 ISI B7.80 34-358 CRD Housing Bolts AUG 1 CRD Housings OWN PRE B-G.2 102538 ISI Fig 2 ISI B7.80 34-39B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B8--2 102541 ISI Fig 2 ISI B7.80 34-43B CRD Housing Bolts AUG I CRD Housings OWN PRE - - . B-G-2 102544 ISI Fig 2 [SI - - - - - - - - - - B7.80 34-47B CRD Housing Bolts AUG . 1 CRD Housings OWN PRE - - B-G2 102547 ISI Fig 2 ISI - . B7.80 38-07B CRD Housing Bolts AUG 1 CRD Housings OWN PRE . . . . .. B-G-2 102550 ISI Fig 2 . ISI - . 87.80 38-11 B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B--2 102551 ISI Fig 2 . Is' B7.80 1 38-15B CRD Housings CRD Housing Bolts AUG OWN (- PRE
-CJ Printed 31412005
C C Ca Page 31 of 332
- Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3)
-ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
... ~~~~ . 1. . ... ._. . .. I _ ....._
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.
.. Scope I Method I Procedure Code Case 123 4 1 2 3 4 1 2 3 4 Class - - Summary I ComplD / System -
ISI Fig 2 ISI - . B-G.2 102552 B7.80 38-19B CRD Housing Bolls AUG 1 CRD Housings OWN B-G-2 102553 ISI Fig 2 I5 B7.80 38-23B CRD Housing Bolts AUG . 1 CRD Housings OWN
- --- --- -PRE----.-. -. .. .. . ..
.. .. .~ ... . _ . .. - - . .--- .- - - - -.-.--
B-G-2 102554 ISI Fig 2 ISI B7.80 38-27B CRD Housing Bolts AUG I. - CRD Housings OWN
... . -- - - - - I- -- - - - PRE B-G-2 102555 PSINTIPEI-02.05.01 ISI Fig 2 ISI ,
B7.80 38-31 B CRD Housing Bolts AUG CRD Housings OWN z . I
-- PRE c 102556 .SIFig 2 ISi 7 B-G-2 -
B7.80 38-35B CRD Housing Bolts AUG 1 CRD Housings ... OWN
. .E . . .-... -..-- - ..--. . . -
B8G-2 102557 ISI Fig 2 ISI - - - - - - - - - - - - 87.80 38-39B CRD Housing Bolts AUG 1 CRD Housings OWN PRE -- B-G-2 102563 - ISI Fig 2 ISI -- B7.80 38-47B CRD Housing Bolts AUG . 1 CRD Housings OWN PRE - ISI Fig 2 ISI . - : 8-G-2 102566 B7.80 42-11B CRD Housing Bolts AUG I CRD Housings OWN PRE . B-62 102569 . * , - I ISI Fig 2. ; ISI B7.80 42-15B8 CRD Housing Bolts., AUG CRD Housings OWN I PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 32 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class - Summary I ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 11 2 3 4 1 2 3 4 B-G-2 102570 ISI Fig 2 ISI B7.80 42-19B CRD Housing Bolts AUG 1 CRD Housings OWN PRE . . . . . . . . . . B4-G2 102571 ISI Fig 2 IS1 B7.80 42-23B CRD Housing Bolts AUG 1 CRD Housings OWN PRE-B-G-2 102572 ISI Fig 2 ISI 87.80 42-27B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B-G.2 102573 ISI Fig 2 ISI B7.80 42-31 B CRD Housing Bolts AUG I CRD Housings OWN PRE B4--2 102574. ISI Fig 2 ISI B7.80 42-35B CRD Housing Bolts AUG I CRD Housings OWN PRE B4G-2 102577 ISI Fig 2 IsI B7.80 42-39B CRD Housing Bolts AUG 1 CRD Housings OWN PRE . JB4-2 102580 [SI Fig 2 ISI . B7.80 42-43B CRD Housing Bolts AUG 1 CRD Housings OWN PRE B-G-2 102583 ISI Fig 2 ISI B7.80 46-15B CRD Housing Bolts AUG 1 CRD Housings OWN PRE ISI Fig 2 Is' B4G-2 87.80 1025868. 46-19B CRD Housing Bolts AUG 1 CRD Housings OWN
. (1 PRE
-C --
Printed 3/4/2005
(. C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 33 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
- Period I Period 2 Period 3 Category, Iso No.
ItemNO, Comp. Desc. Code Case I1 2 3 1 3 A 1 2 A Class Summary I CompID I System Scope I Method I Procedure 4 2 B-G-2 102589 ISI Fig 2 ISI 87.80 46-23B CRD Housing Bolts AUG - _ 1 CRD Housings OWN PRE B-G-2., ,_,,,102590. IS Fig 2 s ISI - .--- 87.80 46-27B CRD Housing Bolts AUG I CRD Housings OWN . PRE . - 1-G-2 102593 ISI Fig 2 -ISI -
- 46-31BB . . . CRD Housing Bolts AUG :
B7.80 .. 1 CRD Housings OWN PRE BG-2 102596 [SI Fig 2 ISI B7.80 46-35B CRD Housing Bolts AUG
- OWN , ... .. .
I CRD Housings PRE . . . . . . . . . . B-G-2 102599 ,ISI Fig 2 [SI B7'.80' 46-39B CRD Housing Bolts AUG 1 CRD Housings , - - OWN OWN - - . PRE BG02 102602 ISI Fig 2 ISI. B7.80 50-23B CRD Housing Bolts AUG 1 CRD Housings OWN
....-- .- - ---- - -- PRE - - - .-- -
B-G-2 102605 ISI Flg 2 II . .. B7.80 50-27B CRD Housing Bolts AUG 1 CRD Housings OWN PRE - B-G-2 102608 ISI Fig 2 ISI B7.80 50-31 B CRD Housing Bolts AUG I CR0 Housings OWN - . PRE . I. 1ISIFig2, ISI . . . . DiJL IQ IU-I
.- -,, ,. - .. , -, ,,- . CRD Housing Bolts, AUG . . . .
B7.80 30-27B OWN . . . . I CRD Housings PRE . . . . Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 34 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 I 2 3 4 B-G42 102715 ISI Fig 2 ISI B7.80 38-438 CRD Housing Bolts AUG
- 1. CRD Housings OWN PRE - . . . . . .
B-K 102636 ISI Fig 3 ISI .- s B10.10 W-12 B.H. to Skirt Weld AUG I Reactor Vessel OWN PRE B-K 102650 ISI/VT/PEI-02.05.02 ISI Fig 4 IS1 r s - - B10.10 Vsl Stbizr Lug @ 0 deg. Stblz Lug @0 deg / RR4 - One time Visual AUG 1 Reactor Vessel OWN PRE B-K 106105 ISINT/PEI-02.05.02 ISI Fig 4 IS1 - s B10.10 Vsl Stblzr Lug @ 90 deg. Stblz Lug @ 90 deg / RR4 - One time Visual AUG 1 Reactor Vessel OWN PRE B-K 106106 ISI/VT/PEI-02.05.02 ISI Fig 4 IS1 - S Stbkz Lug @180 deg / RR4 - One time B10.10 Vsl Stblzr Lug @ 180 deg. Visual AUG 1 Reactor Vessel OWN PRE B-K 106107 ISIVT/PEI-02.05.02 ISI Fig 4 ISI - S Stbkz Lug @270 deg / RR4 - One time B10.10 Vsl Stblzr Lug @ 270 deg. Visual AUG 1 Reactor Vessel OWN PRE B-K 100576 ISUMTIPEI-02.02.01 ISI-13142-33-A . IS1- c . . . . . . B10.20 H- I Dbl Spring /4 Lugs AUG 1 Main Steam A OWN PRE B-K 100584 ISI-1 31 42-33-A IS' - - B10.20 H-8 ! ." Dbl Spring /4 Lugs AUG I Main Steam A OWN K PRE Printed 3/4/2005
C- C 4th Interval ISI Plan (Rev.3) Page 35 of 332
. Monticello Nuclear Generating Plant ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period I Period 2 ; Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 2 3 A 1 23 A 1 2 A A Class ., Summary I ComplD I System Scope I Method I Procedure Code Case B-K 100630 ISI-13142-34-A IS B10.20 H-1 Dbl Spring 4 Lugs AUG OWN - - -
- 1. Main Steam B
... PRE- .
O . ..-. ... ISI-13142-34-A IS1 . . . . B-K 100634 H-5 Dbl Spring 4 Lugs AUG B10.20 OWN - . 1 Main Steam B R-K-... t-- - . - PRE - _. _.._. n~Ie innnai biS-1n14Zg14LgA Is' B10.20 H- I Dbl Spring / 4 LUgs AUG 1, Main Steam C OWN PFF= B-K 100685 ISI-13142-35-A ISi Dbl Spring /4 Lugs AUG - . - - . B10.20 H-5 Main Steam C OWN
- PRE- ..
- ISI-1 3142-36-A ISI B-K 100735 . .
Dbl Spring /4 Lugs AUG . . . . . : 810.20 H-1 - -
. OWN 1 Main Steam D PRE...
Si B-K 100742 .ISI-13142-36-A Dbl Spring / 4 Lugs AUG - - . B10.20 H-7 OWN - . 1 Main Steam D PR P -- --- - - - - - ISI/MTIPEI-02.02.01 ISI-13142-52-A ISs . . . . B-K 101197. DbiSpring /4 Lugs AUG . . ; 810.20 H-3 OWN - - - - ; 1 Feedwater PRE - ........--- ....-PE.... M ..... 5. . . .. ISI-13142-52-A ISI . B-K 101203 810.20 H-8 DblSpring/4Lugs AUG OWN - .... 1 Feedwater PRE . RKe D-tX . 4n1Osn r4 IUIV14 1, I . - ,. ,, Sp151-ri14Z-L3-Aug IS! 810.20 H-3 Dbl Spring / 4 Lugs AUG i 1! 1 Feedwater OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant -4th Interval ISI Plan (Rev.3) Page 36 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003'to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 4 ft A 4 . . I Class Summary I ComplD I System Scope I Method I Procedure Code Case 4
) I A 1 4.
I l I I 4
- 1. _ - C e B-K 101256 ISI-13142-53-A ISI s B10.20 H-8 DbI Spring /4 Lugs AUG - - - - - .
1 Feedwater OWN - - .- ... B-K 101363 ISI-73880PAR IS B10.20 H- 3 Dbi Spring /4 Lugs AUG - - - - - - - . 1 Reactor Wtr Cleanup OWN - - - - - - - . PR . . . . . .. .. B-K 101976 ISI-9700REA ISI,E B10.20 H-O2 DbI Spring /4 Lugs AUG - - - - - . 1 Recirculation A OWN - - - - - . B-K 101981 ISI-97005-A PsR[E - B10.20 H-5 Clevis / Lugs / Constant-Support AUG - - - - - - - . 1 Recirculation A OWN - - - . B-K 101983 ISI-97005-A IPsRl E B10.20 H-6 Clevis /Lugs Constant-Support AUG - - . - . - .. 1 Recirculation A OWN - - - - .- - - -
- PRE . . .. . . . .
ISI-97005-A ISI . . . . . . . . . . . . B-K 101984 1 H-7 Double Spring AUG - - - - - -.-.. ... 810.20 1 Recirculation A OWN - - - - .- - - -
-PRE -- - - - - - - - - - - - .-
101986 ISI-97005-A ISP - - - - - - - - - - - - B-K B10.20 H-8 Snubber /SLugs AUG - .- - t Recirculation A Snubber / Ls OWN A B- 099PRE B-K 101989 ISUPT/PEI-02.01.01 ISI-97005-A ISI C B10.20 H-10 DbI Spring 14 Lugs AUG . . . . . . . . 1 Recirculation A OWN - - - - - . - . _ _ _ PRE . . . . . . . . ... . . I IbI-97W5uu-B ISI B10.20 H- 2 Snubber / Lugs AUG 1 Recirc Manifold A OWN PRE Printed 314'2005
C I- Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3) I Page 37 of 332
.,ASME Section XI (1995 Edition, 1996 Addenda) (May 1,20031to May 31, 2012) I Period I !Pert Dd 2 Period 3 Category, Iso No.
Comp. Desc.
- ItemNO, Class Summary I CompiD I System Scope I Method I Procedure Code Case 1 2 3 41 1 2 3 411 2 34 B-K 102023 ISI-97005-B s- - - - - - - - - - - -
810.20 H-6 Spring ILugs AUG - 1 Recirc Manifold A OWN - -
.. ~...PRE B-K 102028 ISI-97005-B 181 - - - - -
10.20 H-1Il Springl Lugs AUG - - - - - - - - - - - - 1 Recirc Manifold A OWN B-K 102029 ISIII ISI-97005-B IS! r-s - - - 810.20 H-1 2 Snubber/ILugs AUG - - - - - - - - 1 Recirc Manifold A OWN - - - - - - - - -
... PR E - - - - - - - - - - - - - -
B-K 102081 ISl/PTIPE1I-02.01.01 ISI-97006-A ISI C - - - - - - - - - - - B10.20 H- 3 Dbl Spring 14 LugsAU 1I - Recirculation B. OWN - - - - - - - - - - - - OR E - -- -- - - - - -. - -R - - B-K 102082 -ISI-97006-A ISI 810.20 H-5 Clevis ILugs IConstant-Support AUG' 1Recirculation B OWN -- -
~PRE_
B-K 102087 ISI-97006-A I181 - -- 10.20 H- 6 Clevis ILugs IConstant-Support AUG' - IRecirculation 13 OWN - B-K 102089 ISI-97006-A isI 610.20 HI-7 Dbl SpringI Lugs AUG 1 Recirculation B OWN . . . . . . . . . . . .
- .. .- PRE - - - - - - - - - - - -
B-K 102090 8-97006-A ISI.. is[ B13 O.20 H-B8 Snubber/ Lugs AUG . . . . . . . . . . . . I Recircutatlon B OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - B-K,. ~102093 - ISI-97006-A ISI 10.20 H-10b Dbl Spring- AUG I Recirculation B OWN PRE Printed 314r2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 38 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method i Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-K 102125 ISI-97006-B ISI B10.20 H-2 Snubber / Lugs AUG 1 Recirc Manifold B OWN PRE B-K 102127 ISI-97006-B ISI B10.20 H-5 Spring / Lugs AUG 1 Recirc Manifold B OWN PRE B-K 102136 ISI-97006-B ISI B10.20 H-10 Spring / Lugs AUG 1 Recirc Manifold B OWN PRE B-K 102138 ISI-97006-B ISI Bl0.20 H-12 Snubber AUG 1 Recirc Manifold B OWN PRE B-K 107644 ISI-97004-A IS' Bl10.: 20 H-1 Variable / Slide AUG 1 RHR Return B OWN PRE
- A I~
B-K 107645 ISI-97003-A [SI B10.20 H- I Variable Spring AUG
- 1. RHR Return A OWN PRE B-K 107646 ISI-97003-A ISI B10.20 H-2 Variable Spring AUG - .
1 RHR Return A OWN - . PRE B-K 107647 ISI-97003-B ISI 7 B10.20 H- 5 Variable Slide AUG . . . . . . 1 RHR Suction A OWN - - - . PRE - - B-K 107660 ISI-13142-42-A ISI B10.20 H-I Variable Spring AUG 1 IHIPCI Steam OWN ( PRE Printed 314/2005
C 4th Interval ISI Plan (Rev.3)
- C Page 39 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I A I A 14 *1 A Class Summary I ComplD / System Scope I Method I Procedure Code Case. 1 2 I I ., 107661,. ISI-1314243-A IS B-K . B10.20 H- 1 Variable Spring AUG : 1 RCIC Steam OWN - .
.. - . - . -~~..~~PRE B-K 107662 - ISI-13142-33-A IS1 810.20 H-4 Varible / Spring AUG OWN
- 1. . Main Steam A
----- . . .. PRE - - - . - - - - .-
,, ISI-13142-36-A ISI - - - - - .
B-K 107663 Variable / Spring AUG - - ::; B10.20 H-4 OWN - : 1 Main Steam D
.. .. . PRE . = ..
B-K 107665 ISI-13142-52-A ISI Variable / Spring AUG ; 810.20 H-2
, .. . OWN I . Feedwater
- -:- PRE - -- .....
107666, ISI-13142-53-A IS - - - - B-K B10.20 H-2 Variable/ Spring , AUG 1 , Feedwater , OWN _..............._--.--RE --.--... ISI-13142-26-A ISI . B-K 107667 Restraint Slide AUG : B10.20 H-2 OWN ; 1 .. Core Spray B
- . - PRE .
B-K 102063 ISI-97005-C ISI B10.30 H- 1 Rod/Clevis Grip/Lugs/Constant-Support AUG 1 Recirc Pump A OWN .
. --. PRE- -. ,.- ., ..--
ISI-97005-C ISI . . . . . . . B-K 102064 Rod/Clevis Grip/Lugs/Constant-Support AUG - - . B10.30 H- 2 OWN - . I Recirc Pump A PRE - .
^ .^ _
DR.K 1vR I UVUQ . eiooln IsUPI
.n dC. Grlp-l . sn.U1 sSp.,
t,,.- o ISI - S -
'1\ .
. , * ,, , ,. Rod/Clevis Grip[Lugs/Constant-upr AUG - - - -
810.30 , -H- 3 1 Recirc Pump A OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 40 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. . Class Summary I CompiD I System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 11 2 3 4 B-K 102172 ISI-97006-C ISI ------ -- - - -- B10.30 H- I Rod/Clevis Grip/Lugs/Constant-Support AUG 1 Recirc Pump B OWN PRE B-K 102173 ISI-97006-C ISI B10.30 H- 2 Rod/Clevis Grip/Lugs/Constant-Support AUG i Recirc Pump B OWN
.....- .- PRE *--..
B-K 102174 ISI-97006-C 151 B10.30 H-3 Rod/Clevis Grip/LugslConstant-Support AUG 1 Recirc Pump B OWN PRE B-L-2 102099 PSINr/PEI-02.05.02 ISI-97006-A ISI . B12.20 P200-B PSIIVT/PEI-02.05.04 Pump Casing Internal Surfaces AUG 1 Recirculation B OWN PRE c b B-L-2 107183 PSINT/PEI-02.05.02 ISI-97005-A ISi - S - - . B12.20 P200-A ISWTIPEI-02.05.04 Pump Casing Internal Surfaces AUG 1 Recirculation A PSINTIPEI-02.05.04 OWN PRE c b -- B-M-2 100431 ISI-13142-26-A ISI B12.50 V- I Valve Int Surfaces AUG 1 Core Spray B OWN PRE B-M-2 100432 ISI-13142-26-A ISI 812.50 V- 2 Valve Int Surfaces AUG 1 Core Spray B OWN PRE B-M-2 100433 ISI-13142-26-A ISI . . . B12.50 V- 3 Valve Int Surfaces AUG 1 Core Spray B OWN PRE B-M-2 100497 ISI-13142-31 -A ISI B12.50 V- 1I Valve Int Surfaces AUG 1 Core Spray A OWN ( PRE (- Printed 3/4/2005
C I.~Monticello Nuclear Generating Plant C 4th Interval ISt Plan (Rev.3)
-C Page 41 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period I - Period 2 . Period 3 Category, Iso No. IternNO, Comp. Desc. Class Summary/IComplOIDSystem- I ScopelI Method I Procedure Code Case 1 2 3 4. I., 2. 3 4 1 2. 3 4 100498 ISI-13142-31-A s - - - - - - - - - - - B-M-2 .ISINT/PEI-02.05.04 612.50 V-2 Valve Int Surfaces AUG - - - - - - - - - - - - Spray A OWN - - - - - - - - - - - - 1Core PRE B.M.2 100499 ISI-13142-31-A 151 . - B12.50 V- 3 Valve Int Surfaces AUG - - - - - - - - - -
- 1. Cbre Spray A OWN - - - - - - - - - - - -
B-M-2 100585 ISI-1 3142-33-A ISI , 812.50 V-i1 Valve Int Surfaces AUG I.- Main Steam A OWN
-. -PRE _: -- m " --
6 6 6 ISI-13 142-33-A ISI . . . . B-M.2 100588 - Valve Int Surfaces AUG - - - - 612.50 V- 2 Main Steam A OWN . . . . 1 .- 1... PRE -; '-Z , -;., - ,- 100587 ISINVTIPEI-02.05.04 ISI-13142-33-A ISt C - - - - - - - - - - - B-M-2 B12.50 V- 3 Valve mnt Surfaces AUG - - - - - - - - - - - - OWN - - - - - - - - - - - Main Steam A . B-M-2 100588 .ISI-1 31 42-33-A ISI. --. 612.50 V-4 Valve Int Surfaces AUG - - - - - - - - - - - - 1- Main Steam A OWN - - - - - - - - - - - - PRE '- . . - .. - - 100635 PSIIVTIISI-VT-3.0 ISI-1 3142-34-A ISl c - - - - - - - - - - - B.M-2 612.50 V- I ISI/VTIPEI-02.05.04 Valve Int Surfaces AUG . . . . . . . . . . . . IMain Steam B PSINVTIPEI-02.05.04 OWN - - - - - - - - - - - - PRE p s-B-M-2 100638 ISIIVTIPEI-02.05.04 ISI-13142-34-A IS1 C - - - - - - - - - - 812.50 V- 2 Valve Int Surfaces AUG - - - - - - - - - - - - 1 Main Steam B OWN-- -- PRE B-M-2 :100637 .I I I IS-13142-3.4-A -- 'SI 612.50 V- 3 Valve Int Surfaces AUG IMain Steam 6 OWN PRE Printed 3I4r200S
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 42 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class - Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-M-2 100638 ISI-13142-34-A ISI . B12.50 V- 4 Valve Int Surfaces AUG 1 Main Steam B OWN PRE B-M-2 100687 ISI-13142-35-A IS1 B12.50 V- I Valve Int Surfaces AUG 1 Main Steam C OWN
.. - - - PRE .- - - -
B.M-2 100688 ISI-13142-35-A IS . B12.50 V- 2 Vaive Int Surfaces AUG 1 Main Steam C OWN PRE - B-M-2 100689 PSWIVTIISI-VT-3.0 ISI-13142-35-A ISI - s B12.50 V- 3 ISINT/PEI-02.05.04 Valve Int Surfaces AUG 1 Main Steam C OWN PRE p B-M-2 100690 ISIIVT/PEI-02.05.04 ISI-13142-35-A ISI c B12.50 V- 4 PSINT/PEI-02.05.04 Valve Int Surfaces AUG 1 Main Steam C OWN PRE p--. B-M-2 100743 ISI-13142-36-A ISI B12.50 V- I Valve tnt Surfaces AUG 1 Main Steam D OWN PRE B-M-2 100744 ISI-13142-36-A ISI B12.50 V- 2 Valve Int Surfaces AUG 1 Main Steam D OWN PRE B-M-2 100745 ISI-13142-36-A ISI B12.50 V- 3 Valve Int Surfaces AUG 1 Main Steam D OWN PRE _ _ . .00746. ISI-13142-36-A ISI B-M-2 - 100746 B12.50 V-4 Valve Int Surfaces AUG 1 P'-in Steam D OWN PRE Printod V140nnr)
C I IC g 4 Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) -. Page 43 of 332 -:. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) , 4 Period I - Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Summary I CompID I System
- -- .lass . -- -- Scope I Method ! Procedure.- -. Code Case . .....- ..... 12 3 4 1. 2 .3 4 1 2 3. 4 B.M.2 100991 ISI-13142-42-A ISI -
B12.50 V.1 Valve nt Surfaces AUG 1 HPCI Steam OWN
........-.-- PRE B-M-2 100992 . ISI/VTIPEI-02.05.04 ISI-13142-42-A ISI . s B12.50 V- 2 Valve Int Surfaces AUG 1 HPCI Steam . ; - - - --
.-. ~ ~ PRE . -
B.M-2 101204 ISINT/PEI-02.05.04 ISI-13142-52-A ISI - s B12.50 V- 2 PSINT/PEI-02.05.04 Valve Int Surfaces AUG 1 Feedwater ISI/VT/PEI-02.05.04 OWN PRE....... -, -. - *- PR B-M-2 101205 ISI-13142-52-A ISI B12.50 V- 1 Valve Int Surfaces AUG 1 Feedwaler OWN
... PRE -
B.M.2 .101206 . ISINT/PEI-02.05.04 ISI-13142-52-A IS1 - c - B12.50 V- 3 Valve lnt Surfaces AUG 1 Feedwater OWN - -
.PRE - - -_-;
B-M-2 101257 ISI-13142-53-A ISI.- B12.50 V- 1 Valve Int Surfaces AUG 1 Feedwater OWN PRE' B.M.2 101258 ISINT/PEI-02.05.04 ISI-13142-53-A ISI - s B12.50 V- 2 Valve Int Surfaces AUG 1 Feedwater OWN PRE - - - B-M-2 101259 ISI-13142-53-A ISI B12.50 V- 3 Valve Int Surfaces AUG 1 Feedwater OWN - PRE B-M-2 101857 ISI-97003-A
- e. !ec - ISI B12.50 V-1 . .alve Int Surfaces AUG OWN - - - -
1 RHR Return A PRE - - - - Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 44 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case . 1 2 3 4 1 2 3 4 11 2 3 4 B-M-2 101858 ISIJVTIPEI-02.05.04 ISI-97003-A IS_ C B12.50 V- 2 Valve Int Surfaces AUG - . 1 RHR Return A OWN PRE B-M-2 101859 ISI-97003-A ISI - - - - - - - . B12.50 V- 3 Valve Int Surfaces AUG 1 RHR Return A OWN - - - - - - - . PRE - - - - - B-M-2 101900 15-97003-B ISI B12.50 V- I Valve Int Surfaces AUG 1 RHR Suction A OWN PRE B-M-2 101901 ISI-97003-B ISI B12.50 V- 2 Valve Int Surfaces AUG 1 RHR Suction A OWN PRE B-M-2 101902 ISI-97003-B IS' B12.50 V-3 Valve Int Surfaces AUG 1- RHR Suction A OWN PRE B-M-2 101937 ISIVTIPEI-02.05.04 ISI-97004-A ISI S B12.50 V-1 Valve Int Surfaces AUG 1 RHR Return B OWN PRE B-M-2 101938 ISI-97004-A ISI B12.50 V- 2 Valve Int Surfaces AUG 1 RHR Return B OWN PRE B-M-2 101939 ISI-97004-A ISI B12.50 V- 3 Valve Int Surfaces AUG 1 RHR Return B OWN - PRE B-M-2 101993 ISI-97005-A [SI B12.50 V- I Valve Int Surfaces AUG 1 ,P^ircuation A Q OWN PRE Printed 31412005
C 4th Interval ISI Plan (Rev.3) C Page 45 of 332 Monticello Nuclear Generating Plant ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I - Period 2 Period 3 Category, lso No. .- -'-- - ItemNO, Comp. Desc. Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 Class Summary I CompiD I System B-M-2 101994 ISI-97005-A ISI . B12.50 . V-2.. , Valve Internals AUG - - 1 Recirculation A OWN PRE - 102100 ISI-97006A ISI: - - . B-M-2 B12.50 I Valve Int Surfaces AUG I Recirculation B OWN PRE - - - - - B-M.2 102101 ISI-97006-A [ISI' B12.50 .V-2 , Valve Int Surfaces AUG I Recirculation B OWN PRE --- ISINT/PEI-02.05.05 ISI Fig 0 ISRI b - b s B-N-1 102716 813.10 'C'IA -. lsTop Guide (areas made access., fuel cell 13.0' CA ISlli vacated).' AUG- - . Reactor Vessel ISIIY . OWN --.. - PRE ISIlfT/PEI-02.05.05 ISI Fig 0 ' :-Si I-b - b - - - b s B-N.1 102718
,,ISi/ ' Shroud Shelf 0-1 8O deg AUG Bi3.10,,_ ..C-3A, Reactor Vessel ISI// OWN --- ------ ---
PRE : ISINT/PEI-02.05.05 ISI Fig 0 IS1 b - - - b s B-N-1 102719 Surveillance Sample Holder & Bracket @ 30 B13.10 C-4A IS4/, deg AUG ISI// OWN - - - - ' Reactor Vessel PRE --- ISINT/PEI-02.05.05 ISI FigO IS1. - b - - b s, B-N-1 102723 Stm Dryer Holddown Bracket @ 45 deg (in ISU/ Closure Head) AUG - -
- B13.10 C-B8A 1 Reactor Vessel ISI/ OWN -
A PRE -- - - - - - RPREl U-N.- I A luzt 4u4 AIWIvIFI-UW.U5.U 151 Fig 0 lS1 - b - - b - - -- -.
- . Steam Dryer Support Bracket @ 45 deg. AUG - - - - . . .
B13.10 ..-. C-9A . - , . *- , . ISI//. . .
- ISII// :; ' . OWN . . . . - - -
1 . . Reactor Vessel - . PRE - - - - I - - - I Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 46 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Summary I ComplD / System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 411 2 3 4 Class B-N-1 102728 ISWTIPEI-02.05.05 ISI Fig 0 ISI - b b s . . B13.10 C-10 ISI// Reactor Closure Head Interior AUG - - - - - - - . 1 Reactor Vessel ISI/I OWN - - - - - . -.- PRE - - - - B-N-1 107678 ISINTIPEI-02.05.05 ISI Fig 0 ISI - b - - - b s Surveillance Sample Holder & Bracket @ 210 B13.10 C- 4B ISIN/VrPEI-02.05.05 deg AUG - - - - - - - . 1 Reactor Vessel ISWVT/PEI-02.05.05 OWN - - . PRE . . . . . . . . B-N-1 107679 ISINTIPEI42.05.05 ISI Fig 0 ISI - b - - - b s Surveillance Sample Holder & Bracket @ 300 B13.10 C- 4C ISINT/PEI-02.05.05 deg AUG - - . 1 Reactor Vessel ISINT/PEI-02.05.05 OWN - - - - - - - . PRE - - - - - - - - - . -. B-N-1 107690 ISINT/PEI-02.05.05 ISI Fig 0 ISI - b - b s -s B13.t0 C- 3B IS111 Shroud Shelf 180-360 deg AUG - - - - - - - . I Reactor Vessel ISI// OWN . PRE - - - - - - - - - - . B-N-1 107696 ISINT/PEI-02.05.05 ISI Fig 0 ISI - b - - - b s - B13.10 C- 1C...ISU/ Guide Rod Bracket @ 175 deg AUG - - - - - - - . 1 Reactor Vessel ISIII OWN - - - - - - . PRE - - - - . B-N-1 107697 ISINT/PEI-02.05.05 ISI Fig 0 ISI - b - b s -- B13.10 -C-11D ISI/I Guide Rod Bracket 355 deg AUG . 1 Reactor Vessel ISI/I OWN PRE - - - - - - . B-N-1 107723 ISINTIPEI-02.05.05 ISI Fig 0 ISI - b - - - b s Stm Dryer Holddown Bracket @ 135 deg (in B13.10 C- 8B ISIII Closure Head) AUG . . 1 Reactor Vessel ISIWI OWN - - . PRE ISI Fig 0 ISI S ..... B-N-1 107724 ISINT/PEI-02.05.05 Stm Dryer Holddown Bracket @ 225 deg (in B13.10 . C- 8C lSI// Closure Head) AUG OWN 1 Reactor Vessel IS11l PRE . . . .
, (1. Printed 3/4/2005
C C C. Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 47 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1
- Period 2 . Period 3 Category, Iso No.'
ItemNO, .. I- -... Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 I 2 3 -4 B-N-1 107725 . ISINVT/PEI-02.05.05 ISI Fig 0 ISI - b b s - Stm Dryer Holddown Bracket @ 315 deg (in B13.10 C- 8D . ISII/ Closure Head) - AUG 1 Reactor Vessel .ISI// ........ .... .OWN .- PRE 107730 ISINT/PEI-02.05.05 ISI Fig 0 ISI - b - b s - B-N-1. ISII/ Steam Dryer Support Bracket @135deg: AUG - -_ B13.10 C-9B 1 Reactor Vessel - ISI//- . . . .OWN- - PRE B-N-1 107731 ISINTIPEI-02.05.05 ISI Fig 0ISI - b - - - b s B13.10 C- 9C ISI// Steam Dryer Support Bracket @ 225 deg. AUG 1 Reactor Vessel . . - . OWN - PRE B-N-1 107732 ISINT/PEI-02.05.05 ISI Fig 0 ISI - b - b s - - 813.10 C-9D ISI/. Steam Dryer Support Bracket@ 315 deg. AUG 1-Ractor Vessel v--- -... S/----; _ ..... _-R >_..:.OWN_.-,- PRE B-N-1 107737 ISIIVT/PEI-02.05.05 ISI Fig 0 ISI - b b b - - s - - - Incore Dry Tubes (if made accessible during B13.10 C-1I IS11/ RFO) AUG 1 Reactor Vessel
- ISI .. OWN . . . . ... . .
ISIII PRE B-N-I 107738 ISINT/PEI-02.05.05 ISI Fig 0 ISI B b b b - - b - Core Plate (areas made access., fuel cell . 813.10 C-12A ISII/ vacated) AUG
. - - - - . . OWN O - -
1 Reactor Vessel ./ .. ISII/.
- PRE . .
ISI Fig 0 ISI s 102717 ISI/VT/PEI-02.05.05 . .
'Jet Pump Pair 1/2 Riser Support Pads /
813.20 C- 2A Welds AUG 1 Reactor Vessel OWN
- . .. . - I ! . . I . ... . ' . . .
. . . . . .I.
PRE Prinfal 114tnn;
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 48 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method / Procedure Code Case 1 2 3 4 1 2 3 '4 1 2 3 4 B-N-2 107681 ISINT/PEI-02.05.05 ISI Fig 0 ISI- . s Jet Pump Pair 3/4 Riser Support Pads / B13.20 C- 2B Welds AUG 1 Reactor Vessel . . . OWN - - - . . PRE B-N-2 107682 ISINT/PEI-02.05.05 ISI Fig 0 ISI.s - Jet Pump Pair 5/6 Riser Support Pads I B13.20 C- 2C Welds AUG 1 - -.- Reactor Vessel OWN . . PRE B-N.-2 107683 ISINT/PEI-02.05.05 ISI Fig 0 IS- . s Jet Pump Pair 7/8 Riser Support Pads / B13.20 C- 2D Welds AUG . 1 Reactor Vessel OWN PRE B-N-2 107684 ISI/VT/PEI-02.05.05 ISI Fig 0 [SI - - -s Jet Pump Pair 9/10 Riser Support Pads / B13.20 C- 2E Welds AUG 1 Reactor Vessel OWN PRE B-N-2 107685 ISINT/PEI-02.05.05 ISI Fig 0 ISI . s - -. Jet Pump Pair 11/12 Riser Support Pads / B13.20 C- 2F Welds AUG 1 - Reactor Vessel - OWN PRE B-N-2 107686 ISINTIPEI-02.05.05 ISI Fig 0 ISI.. s - - Jet Pump Pair 13/14 Riser Support Pads / B13.20 C- 2G Welds AUG 1 . Reactor Vessel OWN PRE - - - - - - - - - - - - B-N-2 107687 ISINT/PEI-02.05.05 ISI Fig O ISI s - - - Jet Pump Pair 15/16 Riser Support Pads / B13.20 C- 2H Welds AUG Reactor Vessel OWN PRE ( Printed 3/4/2005
C.- C PC Page 49 of 332 Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 . Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 B-N-2 107688 ISINT/PEI-02.05.05 ISI Fig 0 [SI s
. -. ~- Jet Pump Pair 17/18 Riser Support Pads /-
B13.20 C-2J. Welds AUG . I Reactor Vessel OWN PRE B-N-2 107689 ISINT/PEI-02.05.05 ISI Fig 0 IS1 s --- Jet Pump Pair 19120 Riser Support Pads /-- - B13.20 C-2K .. Welds AUG 1 Reactor Vessel OWN PRE 107693 ISI/VT/PEI-02.05.05 ISI Fig 0 ISI . . . s - B-N-2 Surveillance Sample Holder Lower Weld @ . .. ... . B13.20 C-4D - 30 deg AUG 1.. Reactor Vessel OWN . PRE . B-N.2 107694 . ISINVT/PEI-02.05.05 ISI FigO - -1S- -- - - - s - Surveillance Sample Holder Lower Weld @ B13.20 C-4E 210 deg AUG
- OWN : : . :
- 1. Reactor Vessel
..-.. ~ RE B-N-2 107695 ISINT/PEI-02.05.05 ISI Fig 0 ISI-s .s Surveillance Sample Holder Lower Weld @ . .
B13.20 C- 4F 300 deg . AUG . .n. . .1 Reactor.Vessel OWN
.. -.. PRE-----
B-N-2 107698 ISINT/PEI-02.05.05 ISI Fig 0 ISI- s B13.20 C-1E Guide Rod Bracket Weld 175 deg AUG 1 Reactor Vessel OWN
.. PRE B-N-2 107699 ISINT/PEI-02.05.05 - ISI Fig 0 ISI s B13.20 C- IF Guide Rod Bracket Weld @ 355 deg AUG I Reactor Vessel OWN PRE
. . , . . I. -.; . ... . . . .. .. A. .
. I I . .1 . ' .. .. .. . . ..
... : t, . ,
?.. , .
Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 50 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary / ComplD / System Scope / Method I Procedure Code Case 1 23 4 1 23 4 1 23 4 B-N-2 102720 ISIVT/PEI-02.05.05 ISI Fig 0 ISI - s B13.30 C-5A Core Spray Sparger Bracket Weld 30 deg. AUG 1 Reactor Vessel OWN - - . PRE - - - - - . B-N-2 102721 ISINT/PEI-02.05.05 ISI Fig 0 ISI- . . . . . . . B13.30 C- 6A FW Sparger Bracket Welds @ 0 deg AUG I Reactor Vessel OWN
- PRE B-N-2 107691 ISINT/PEI-02.05.05 ISI Fig 0 ISI -- -- s ---
B13.30 C- 3C Shroud Shelf H-9 Weld 0-180 deg AUG 1 Reactor Vessel OWN PRE B-N-2 107692 ISINT/PEI-02.05.05 ISI Fig 0 ISI -- -- s --- B13.30 C- 3D Shroud Shelf H-9 Weld 180 360 deg AUG 1 Reactor Vessel OWN PRE B-N-2 107700 ISINT/PEI-02.05.05 ISI Fig 0 ISI - s Core Spray Sparger Bracket Weld @ 150 B13.30 C- 5B deg. AUG I Reactor Vessel OWN PRE B-N-2 107701 ISVVTIPEI-02.05.05 ISI Fig 0 ISI - S Core Spray Sparger Bracket Weld @ 210 B13.30 C- 5C deg. AUG 1 Reactor Vessel OWN PRE B-N-2 107702 ISINTIPEI-02.05.05 ISI Fig 0 ISI - S Core Spray Sparger Bracket Weld @ 330 B13.30 C- 5D deg. AUG 1 Reactor Vessel OWN PRE B-N-2 107703 ISINr/PEI-02.05.05 ISI Fig 0 ISI S B13.30 C-6B FW Sparger Bracket Welds @ 90 deg AUG 1 Reactor Vessel OWN t - -32 PRE ( Printed 3/4/2005
Cr Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3) Page 51 of 332
. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Code Case 1 2 3 A I 2 A A I I A A Class Summary I ComplD I System Scope I Method I Procedure B-N-2 107704 . ISINVT/PEI-02.05.05 ISI Fig 0 ISI s- . 813.30 C- 6C FW Sparger Bracket Welds @ 180 deg AUG .
- 1. Reactor Vessel OWN
........ . . .....---. PRE -. . . ; .
B-N-2 107705 ISINTIPEI-02.05.05 ISI Fig 0 IS --- -s B13.30 C- 6D FW Sparger Bracket Welds @ 270 deg AUG - ; 1 Reactor Vessel OWN ...
... PRE . -
B-N-2 107706 ISIWTtPEI-02.05.05 ISI Fig 0 ISI -- - s C- 7B Shroud Support Leg Weld @ 10 deg AUG - : B13.30 1 Reactor Vessel OWN
. .. . *. PRE B-N-2 107707 ISINT/PEI-02.05.05 ISI Fig 0 ISI -- -
813.30 C- 7C Shroud Support Leg Weld @ 30 deg AUG 1 Reactor Vessel OWN
... PRE B-N-2 107708 . ISI/T/PEI-02.05.05 ISI Fig 0 [SI - .
B13.30 C-7D Shroud Support Leg Weld @ 60deg AUG : . . 1 Reactor Vessel OWN . _.. .... -.-.- PRE._ _- B-2 107709 ISINVT/PEI-02.05.05 ISI Fig 0 ISI-. . 813.30 C- 7E Shroud Support Leg Weld @ 90 deg AUG 1 Reactor Vessel OWN ; .
._PRE..- -- - - - -
B-N-2 107710 ISINT/PEI-02.05.05 ISI Fig 0 ISI- s B13.30 C-7F Shroud Support Leg Weld @120 deg AUG 1 Reactor Vessel OWN P P. . .- -. - - - - - - - B-N-2 107711 ISINT/PEIW2.05.05 ISI [ Fig 0 ISI -- --- s B1i.30 C-7G Shroud Support Leg Weld@ 150 deg AUG . . 1 Reactor Vessel OWN . PRE RwN I ISI Fig 0 [St s B13.30 C-7H . . Shroud Support Leg Weld @ 170 deg AUG 1 Reactor Vessel OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 52 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 . Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B-N-2 107713 ISINT/PEI-02.05.05 ISI Fig 0 ISI s - 813.30 C- 7J Shroud Support Leg Weld @ 190 deg AUG 1 Reactor Vessel OWN PRE B-N-2 107714 ISINT/PEI-02.05.05 ISI Fig 0 IS - - s B13.30 C- 7K Shroud Support Leg Weld @ 210 deg AUG 1 Reactor Vessel OWN PRE B-N-2 107715 ISIVT/PEI-02.05.05 ISI Fig 0 ISI-- -s B13.30 C- 7L Shroud Support Leg Weld @ 240 deg AUG 1 Reactor Vessel OWN
- PRE B-N-2 107716 ISINTIPEI-02.05.05 ISI Fig 0 ISI-- -s B13.30 C- 7M Shroud Support Leg Weld @ 270 deg AUG 1 Reactor Vessel OWN PRE B-N.2 107717 ISIVT/PEI-02.05.05 [SI Fig 0 ISI- s B13.30 C- 7N Shroud Support Leg Weld @ 300 deg AUG 1 Reactor Vessel OWN B13.30 C- 7P Shroud Support Leg Weld @330 deg AUG 1 Reactor Vessel OWN PRE B-N-2 107719 . ISIVTIPEI-02.05.05 ISI Fig 0 ISI- - s -
B13.30 C- 7Q Shroud Support Leg Weld @350 deg AUG 1 Reactor Vessel OWN PRE B-N-2 107720 ISWVTIPEI-02.05.05 ISI Fig 0 ISI s - - - Surveillance Sample Holder Upper Weld @ B13.30 C- 4G 30 deg AUG 1 Reactor Vessel OWN PRE (. (. Printed 3/4/2005
C C 4th Interval 151 Plan (Rev.3) C Page 53 of 332 Monticello Nuclear Generating Plant .t ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 200310o May 31, 2012) IPeriod I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary!I ComnpiD I System Scope I Method!I Procedure Code Case 1 23 4 1 23 4 1 2 34 B.N2 107721 ISINVTIPEI-02.05.05 151Fig 0[S Surveillance Sample Holder Upper Weld ~- 21 0deg AUG - - - - - - - - - - - - 813.30 C- 4H OWN - - - - - - - - - - - - 1 Reactor Vessel PRE - - - - - - - - - - - -
-107722.- -- ISINVTIPEI-02.05.05.-ISI Fig 0 - - - 151 -- .s R.N.2 Surveillance Sample Holder Upper Weld -
300 deg AUG - - - - - - - B13.30 C- 4. 1 Reac'tor Vessel .OWN PRE 0OI'd- tit II o4 Ibliv I IIt1U/LU t.U!3 ISI Filg 0 'Is S - - - Stm Dryer Holddown Bid Weld ~ 45 deg fin 813.30 C- BE Closure Hd) AUG 1 Reactor Vessel OWN PRF 13-N-2 107727 ISINVT/PEI-02.05.05 151FigO0 ISI-S-- Stm Dryer Holddown Bkt Weld 135 deg (in Closure Hd) . - AUG - - - - - - - - - - - - 813.30 C-O8F OWN - - - - - - - - - - - - 1- Reactoir Vessel - PRE -__ -_ -_ -_ - _-_ __-_ _ _-_ _- [SINVT/PEI-02.05.05 ISI FigO0 ISI' ----- s-- B.N-2 107728 Stm Dryer Hoiddown Bid Weld 225 deg (inClosure Hd) .AUG - - - - - - - - - - - - 5 13.30 C-86G Reactor Vessel OWN --- 1.. ISINVTIPEI-02.05.05 ISI Fig 0 ISI--s -- ------ B-N-2 107729 Sim Dryer Holddown BIdk Weld 31 5 deg (in Closure Hd) AUG - - - - - - - - - - - - 813.30 C-O8H
'. Reactor Vessel OWN PRE - - - - - - - - - - -
tS-N-Z luf[33 ISVNT/PEI-02.05.05 ISI Fig.0- [Si 5- - - Steam Dryer Support Bracket Weld @ 45 13.30 C- 9E deg. AUG 1 Reactor Vessel OWN PRE Printed 314r20O5
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 54 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 11 2 3 4 1 2 3 4 B-N-2 107734 ISINVT/PEI-02.05.05 ISI Fig 0 IS--s s -- Steam Dryer Support Bracket Weld @ 135 B13.30 C- 9F deg. AUG 1 Reactor Vessel OWN - . PRE B-N-2 107735 ISI/VT/PEI-02.05.05 ISI Fig 0 ISI- . s - Steam Dryer Support Bracket Weld @ 225 B13.30 C- 9G deg. AUG - . 1 - Reactor Vessel OWN PRE B-N-2 107736 ISI/VT/PEI-02.05.05 ISI Fig 0 [SI . . .s Steam Dryer Support Bracket Weld @ 315 B13.30 C- 9H deg. AUG - . 1 Reactor Vessel OWN PRE . B-N-2 107740 ISI/VT/PEI-02.05.05 ISI Fig 0 IS1 - S B13.30 C-13 Bottom Head Drain Weld AUG . 1 Reactor Vessel OWN PRE - . B-N-2 107741 IStNTIPEI-02.05.05 ISI Fig 0 ISI - - s B13.30 C-14 Bottom Head CRD Stub Tubes AUG 1 Reactor Vessel OWN . PRE B N 107742 - ISt/T/PEI-02.05.05 ISI Fig 0 - -I. B13.30 C-15 Bottom Head CRD HousinglStub Tubes AUG 1 Reactor Vessel OWN . PRE . B-N-2 107743 ISUVT/PEI-02.05.05 ISI Fig 0 IS1 - s B13.30 C-16 Bottom Head Incore Housing AUG - 1 Reactor Vessel OWN . PRE - . B-N-2 102722 ISI/VT/PEI-02.05.05 ISI Fig 0 ISI 5 B13.40 C- 7A Shroud Support Legs AUG 1 Reactor Vessel OWN PRE (., ( Printpi 3/4/00M
C Monticello Nuclear Generating Plant C 4th Interval 151 Plan (Rev.3) Page 55 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May' 31, 2012) I IPeriod 1I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.. Class Summary I CompiD I System Scope I Method I Procedure Code Case 1 23 4 I 23 4 1 2 34 B.N.2 107680 ISINVTIPEI-02.05.05 ISI Fig 0 ISI-S - 813.40 C-lIB Top Guide AUG ............ 1Reactor Vessel OWN
.- - --..... PRE.-
B..N-2 107739 ISINVTIPEI.02.05.05 ISI Fig 0 151 B b-- b b -- s Core Plate (areas made access., fuel cell B13.40 C-I12B ISiII vacated)' AUG . . . . . . . . . . . . IReactor Vessel ..... -WN --. -.--.. 15111 PRE B-N-2 107744 ISINVTIPEI-02.05.05 [SI FigO0 ISI B b-- b b- - Fuel Support Cast. (areas made access., fuel - - - B13.40 C-17A IS1ll cell vacated) AUG 1 - . -"Re'actor Vessel, OWN ISI"/ PRE B-N-2 107745 ISIIVTIPEI-02.05.05 ISI Fig 0 - .. 15-1[S B b - - b b - - s - - Peripheral Fuel Spt (areas made access, fuel B813.40 - C-17B.I-- --- celivacated) - ~ - . .AUG - - * .. 1 Reactor Vessel ISIII. OWN - - - - - - - - - - - ISI!!- PRE . . . . . . . . . . . . B-N-2 107746 ISINTI1PEI-02.05.05 ISI Fig 0 ISi B b - - b b - - s - -
,.. ~ ~~~-.CtrlRod Guide Tube-nt (when access, fuelI .- -
B13.40 C.18 15I/I cell vacated) AUG - -- - - - - - - IReactor Vessel iSiII OWN B---. 1777ISIIVTIPEI-02.05.05 ISI Fig . . .IS[ ... B13.40 C- 3E Shroud Shelf 0-1 80 deg AUG - - - - - - - - - - - - 1 Reactor Vessel OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - B-N.2 .-. 107748 . .. .ISIIVT/PEI-02.05.03 . - ISI FigO.. ISI .... - s - B13.40 C-3F *..Shroud Shelf 180-360 deg AUG - - - - - - - - - - - - 1I Reactor Vessel , . .. OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - 8.0 102390 ISI Fig 2 151 Bi14.10 02-23 (Lower) CR D Housing Weld AUG I CRD Housings OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 56 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 It -1 A 4 I . 4 *s S Code Case e Class - Summary I CompID I System Scope I Method / Procedure B-0 102391 ISI Fig 2. SI B14.10 02-23 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN PRE . . . . . . . . . . . . B40 1023937 IS Fig 2 -sR S B14.10 02-27 (Lower) CRD Housing Weld AUG . 1 CRD Housings OWN .
-PRE .. . . . . . . . . .
B-0 102394 ISI Fig2 ISI - s - B14.10 02-27 (Upper) CRD Housing Weld AUG . . . 1 CRD Housings OWN PRE . B-0 102396 ISI Fig 2 Is -- S - - - B14.10 02-31 (Lower) CRD Housing Weld AUG . I CRD Housings OWN PRE B-0 102397 ISI Fig 2 ISI . . s - - - B14.10 02-31 (Upper) CRD Housing Weld AUG 1* CRD Housings OWN - - . PRE - - - - - - - - - - - - B-0 102399 ISI Fig 2 ISP . . B14.10 0-15 (Lower) CRD Housing Weld AUG - - - - - - . 1 CRD Housings OWN - - - . PRE - - - - - - - - - - - - B-0 102400 ISI Fig 2 ISP B14.10 06-15 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN PRE - - - - - - - - - - - - B-0 102416 ISI Fig 2 ISI B14.10 06-39 (Lower) CRD Housing Weld AUG 1 CRD Housings OWN PRE . 10241i7 .. B4n ISI F-ig 2 ISI B14.10 06-39 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN PRE C. - Printed 3/4/2005
C C 'C
,'Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev;3) ' Page 57 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012) ...
Period 1 . Period 2 Period 3 Category, Iso No. ItemNO, : Comp. Desc. I 1 - 1-i A 7 ' A Class Summary / ComplD I System . Scope'/ Methvd I Procedure Code Case - 7 "It~ -A 4 B-0 102419 ISl Fig 2 ISI B14.10 10-11 (Lower) CRD Housing Weld AUG
. . .... OWN
- 1. CRRHousings ......
PRE . 102420 ISI Fig 2 ISI B-0 CRD Housing Weld AUG B14.10 10-11 (Upper)
........ .... OWN 1 -- CRD Housings PRE 102433 ISI Fig 2 ISI B-0 CRD Housing Weld AUG B14.10 10-43 (Lower)
- 1. . . CRD Housings . OWN PRE 102434 ISI Fig 2 ISI B-0 10-43 (Upper) CRD Housing Weld AUG .
B14.10
. . ... .. OWN
.1 ... CRD Housings.._... PRE - - - - - - - - ISI Fig 2 ISI : __ -_-____ B-0 102436 CRD Housing Weld AUG . . b14.10 i4-07 (Lower) _.. .. OWN i . _CFDHousings .. . . PRE ._ B4 102437 ISI Fig 2 ISI - B14.10 14-07 (Upper) CRD Housing Weld AUG
.. OWN
.1 . CRD Housings . ....... PRE -_ B-4 102452 ISI Fig 2 ISI B14.10 14-47 (Lower) CRD Housing Weld AUG OWN -.------ 1 CRD Housings PRE - - - - - - - - - - - 102453 ISI Fig 2 ISI B-0 B14.i0 14-47 (Upper) CRD Housing Weld AUG OWN -, - : - - . - -- - - -, - 1 CRD Housings PRE A B~4 10270 lI9 B14.10 22-03 (Lower) *. CRD Housing Weld AUG 1 CRD Housings OWN PRE I-Prinf*~rt V402O9
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 58 of 332 ASME Section XI. (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 *4 B4 102471 ISI Fig 2 ISI . . B14.10 22-03 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN . PRE B40 102488 ISI Fig 2 ISI . B14.10 22-51 (Lower) CRD Housing Weld AUG 1 . CRD Housings OWN PRE B-0 102489 ISI Fig 2 ISI B14.10 22-51 (Upper) CRD Housing Weld AUG 1 CRD Housings. OWN - - - - - - . PRE - - - - - - - - _ B-0 102491 ISI Fig 2 ISI - - - - - - - - - - - 814.10 26-03 (Lower) CRD Housing Weld AUG I CRD Housings OWN PRE - - - - - - - - - - - - B-0 102492 ISI Fig 2 ISI - - - - - - . B14.10 26-03 (Upper) CRD Housing Weld AUG - - - - - - - - . 1 . CRD Housings_ OWN PRE - - - - - - - - - - - - B4 102505 ISI Fig 2 ISI - - . B14.10 26-51 (Lower) CRD Housing Weld AUG . . . . . . . . . 1 CRD Housings OWN - . PRE B4 102506 ISI Fig 2 ISI - B14.10 26-51 (Upper) CRD Housing Weld AUG . . . . . . . . . 1 CRD Housings OWN . PRE - - - - - - - - - - - - 80 102508 ISi Fig 2 IiSI . B14.10 30-03 (Lower) CRD Housing Weld AUG 1 CRD Housings OWN PRE - - - - - - - - - - . B-0 102509 ISI Fig 2 ISI 814.10 30.03 (Upper) CRD Housing Weld AUG 1 'n) Housings OWN p . . . .fl PRE (
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 59 of 332 ASME Section Xl .(1995 Edition,,1996 Addenda) (May 1, 2003 to May 31, 2012) Period I I Period 2 Period 3 Category, . Iso No.
- ItemNO, Class - Summary W I ComplD / System ----- Scope I Method I Procedure.
Comp. Desc.
- - - Code Case --- - -- -- .. - - . - .. - 1 3, A 1. 2_i. A 1 2 3t A ISI Fig 2 ISI , . . . . . . .
B-0 102525 30-51 (Lower) CRD Housing Weld AUG - - - . B14.10 OWN - . I - CRD Housings PR E ._ _ _. _ _. . _. _ . ._._. ._._ B-O 102526 ISI Fig 2 ISI - 614.10 30-51 (Upper) CRD Housing Weld AUG
. - OWN - - - .
1 CRD Housings - - - . .- -- .... - - -- - - -. . - RE- - - - -: PRE ISI Fig 2 ISI - . B-0 102545 B14.10 38-07 (Lower) CRD Housing Weld AUG - - - - . 1 CRD Housings OWN PRE - : - -: 102546 ISI Fig 2 ISI . . B-0 B14.10 38-07 (Upper) CRD Housing Weld AUG
.CRD Housings .. -,,, .* . ...... . - , OWN l
PRE - - - - -. - .- - - - - ISI Fig 2 ISI - - - - - . B-0 102561 B14.10 38-47(Lower) CRD Housing Weld AUG - ..-
.OWN 1' CRD Housings 102562 ISI Fig 2 ISI - _
38-47 (Upper) CRD Housing Weld AUG . B14.10 OWN OWN 1 CRD Housings - . -- - ORE - - B-0 102564 ISI Fig 2 ISI CRD Housing Weld AUG . . B14.10 42-11 (Lower) 1 CRD Housings OWN PRE B-0 102565 ISI Fig 2 ISI B14.10 42-11 (Upper) CRD Housing Weld AUG OWN-- . . . . I CRD Housings PRE - =
' - I U& J rI I ' . . : :. .- 1 - ; : - , ISIl-igZ . ;: .:, lSI D-V B14.10 : 42-43 (Lower) .. . -. !. . ,.. . CRD Housing Weld . AUG 1 CRD Housings OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 60 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class - - Summary I ComplD I System Scope I Method I Procedure .Code Case.. 1. 2 3 4 1 2 3 4 11 2 3 4 B-0 102579 ISI Fig 2 ISI . . . . . . . . . . B14.10 42-43 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN - - - - . PRE - - . B-0 102581 ISI Fig 2 ISI . B14.10 46-15 (Lower) CRD Housing Weld AUG 1 CRD Housings OWN - - - - - - - - - - - PRE - B-0 102582 ISI Fig 2 IS1 - - - - - - - - - - . B14.10 46-15 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN - - . PRE . B-0 102597 ISI Fig 2 ISI B14.10 46-39 (Lower) CRD Housing Weld AUG 1 CRD Housings OWN PRE B-0 102598 ISI Fig 2 [SI B14.10 46-39 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN - . PRE - 80 102600 ISI Fig 2 IS1. s B14.10 50-23 (Lower) CRD Housing Weld AUG 1 CRD Housings OWN - - - - - - - . PRE - 80 102601 ISI Fig 2 IS1I. . . . . s . B14.10 50-23 (Upper) CRD Housing Weld AUG - - - - - . 1 CRD Housings OWN - - - . PRE .. B-0 102603 ISI Fig 2 ISI B14.10 50-27 (Lower) CRD Housing Weld AUG . . V 1 CRD Housings OWN - .- PRE . . . B-0 102604 - ISI Fig 2 iSI B14.10 50-27 (Upper) ICRD Housing Weld AUG 1 (fli) Housings OWN P . . .(~ PRE (.
C C 4th Interval ISI Plan (Rev.3) Page 61 of 332 Monticello Nuclear Generating Plant ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
. . I . .. -. ... .II I . . I I.
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Scope I Method / Procedure Code Case 1 2 3 A I I A A 1 I I A Class - Summary / CompID / System B-O 102606 ISI Fig 2 ISI B14.10 50-31 (Lower) CRD Housing Weld AUG 1 CRD Housings OWN PRE - ---- B-O 102607 -, -ISI Fig 2 ISI B14.10 50-31 (Upper) CRD Housing Weld AUG 1 CRD Housings OWN _-
-R-B-P 107055 ISINT/0255-20-llC-2 1.5-2 Boundary ISI B b - b b - - s B15.10 Reactor Coolant Pressure Boundary ISINT/0255-20-llC-2 System Leakage Pressure Test AUG .
1* Reactor Coolant Pressure Boundary OWN . PRE -. C-A 101600 - ISI/UTIPEI-02.03.01 ISI-7905-32A ISI r s . - C1.10 W- I Top Flange to Shell AUG 2 RHR Heat Exchanger A . OWN
....-.------- PRE --- .
101601 ISIIUTIPEI-02.03.01 ISI-7905-32A [Si . . . . . . s - C-A .. . W-2 Lower Flange/Shell AUG . C1.10 2 RHR Heat Exchanger A . . . . OWN W . .
.* -, ---- PRE . .--. .- *..
C-A 101611 - ISI-7905-32B ISI C1.10 W- 1 Top Flange to Shell AUG
- 2. RHR Heat Exchanger B OWN
. . .. PRE
- ISI-7905-32B ISI - .
C-A 101612 C1.10 W- 2 Lower Flange/Shell AUG 2 RHR Heat Exchanger B OWN
. . .PRE- . --
101602 - : S.IS-7905-32A ISI - s C-A C1.20 W- 3 Lower Head/Flange AUG - . 2 RHR Heat Exchanger A OWN PRE - A - -_ - -_ _ , _- - I UMlOUJ I .: .- -. : I I ImIr . .. . ISI-7905-32A ISI s C1.20 W-4 Lower Head Circ Weld AUG 2 RHR Heat Exchanger A OWN PRE -I-Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 62 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 C-A 101613 ISI-7905-32B ISI C1.20 W- 3 Lower Head/Flange AUG . . . . . . . 2 RHR Heat Exchanger B OWN PRE - - - - . - - - - - - C-A 101614 ISI-7905-32B IS1 - - - - - - - - - - - - C1.20 W- 4 Lower Head Circ Weld AUG - - - - - - - . 2 RHR Heat Exchanger B OWN - - - - - - - - . PRE - - - - - - - - - - - C-B 101594 ISUMT/PEI-02.02.01 ISI-7905-32A ISI r s - - - - - - - -.... C2.31 N- 1 Shell-Pad-Noz AUG - - - - - . 2 RHR Heat Exchanger A OWN - - . PRE - - -, ,- -_. C-B 101595 ISIIMTIPEI-02.02.01 ISI-7905-32A ISI r r - - - C2.31 N-2 Shell-Pad-Noz AUG - - - - - - - . 2 RHR Heat Exchanger A OWN PRE . . . . . . C-B 101604 ISI-7905-32B IS1 C2.31 N-11 Shell-Pad-Noz AUG - - - - - - - . 2 RHR Heat Exchanger B OWN - - - . PRE - '. C-B 101605 ISI-7905-32B ISI 62.31 N-2 Shell-Pad-Noz AUG 2 RHR Heat Exchanger B OWN PRE C-C 101596 ISI-7905-32A ISI - - - - - . C3.10 Support A Support A,E200A, 0' AUG . . . . . . . . . 2 RHR Heat Exchanger A OWN - - - . PRE . . . . . . . . . . C-C 101597 ISI-7905-32A IS1 - - - - - - - - - . C3.10 Support B Support BE200A 180 AUG . . . . . . . . . 2 RHR Heat Exchanger A OWN - - - - - . PRE C-C . 101598 : ISUMT/PEI-02.02.01 ISI-7905-32A 1S1 s - - C3.10 Support C,. . . . . Support C,E200A 315' AUG . . 3.2.0 2 RHR Heat Exchanger A OWN .. . PRE (. Printed 3/4/2005
C Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3) C Page 63 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class -
- Summary I ComplD I System . .- .Scope I Method I Procedure .... Code Case' -.. .1. .2 3 4 1. 2..3 4 1 2 3 4 C-C 101606 ISI-7905-32B ISI C3.10 Support A Support A.E200B 0 AUG - - -
2 RHR Heat Exchanger B OWN - C-C 101607 ISI-7905-32B ISI . . . . - - - C3.10 Support B Support BE2008 180' AUG - - - - . . . OWN - - - 2 RHR Heat Exchanger B . . . ..
- - - - --j
' ' '- ' PRE-'-
C-C 101609 ISI-7905-32B IS.- C3.10 Support C Support CE200B 315 AUG 2 RHR Heat Exchanger B OWN
.RE. . . E C-C 100060 ISI-13142-17-A IS C3.20 H- 5 Dbl Spr I Half Clamp AUG 2 RHR Suction A OWN
.... * -.- -^-. PRE' C-C 100062 ISI-13142-17-A . -ISI - -
C3.20 H- 6 Dbl Spr I Half Clamp AUG 2 RHR Suction A OWN
~PRE - - - ' .
C-C 100133 ISI-13142-17-C IS1 .. s ----- C3.20 H- 6 Dbl Spr I Half Clamp AUG 2 RHR Suction B OWN C-C 100135 ISI-13142-17-C ISI ' C3.20 H-8 Dbl Spr I Half Clamp AUG 2 RHR Suction B -. OWN
- PRE PR~- - - - -
C-C 100136 ISI-13142-17-C ISI C3.20 H- 9 Dbl Strut I 8 Lugs AUG 2 RHR Suction B OWN-- - PRE - - .
. I - 1. ISI/MT[PEI-02.02.01 ISII TIPE-02.2.o ISI-13142-18-A ISI c C-C . - 100179 . -
C3.20. H-9 -. - DblSpring /4Lugs ;' AUG 2 RHR Discharge B OWN PRE Prinled 3t4t2005
Monticello Nuclear Generating Plant 4th Interval 1S1 Plan (Rev.3) Page 64 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 t1 May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary / CompiD JSystem Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 C-C 100265 ISI-13142-19-A iSI C3.20 H- 3 Dbl Spring /4 Lugs AUG 2 HPCI Steam Disch OWN PRE C-C 100270 ISI/MTiPEI-02.02.01 ISI-13142-19-A ISI-s C3.20 H- 7 Dbl Spring 14 Lugs AUG 2 HPCI Steam Disch OWN PRE C-C 100788 ISI-13142-37-A ISI C3.20 H- 7 Dbl Spring / 4 Lugs AUG 2 RHR Discharge A OWN PRE C-C 100814 ISI-13142-37-B ISI C3.20 H- 2 Strut /8 Lugs AUG 2 Containment Spray OWN PRE C-C 100815 ISI/MT/PEI-02.02.01 ISI-13142-37-B ISI - - - - S C3.20 H- 3 Strut 18 Lugs AUG 2 Containment Spray OWN PRE C-C 100818 ISI-13142-37-B ISI C3.20 H-5 Snubber/Lugs AUG 2 Containment Spray OWN PRE C-C 100820 ISI-13142-37-B ISI C3.20 H-6 Dbl Spr/Clamp&Saddle AUG 2 Containment Spray OWN PRE C-C 100821 ISI-13142-37-B ISI C3.20 H- 7 Dbl Spring / 4 Lugs AUG 2 Containment Spray OWN-PRE 100917 C-C, 100917 .ISIIMT/PEI-02.02.01 ISI-13142-40-B IS' r s C3.20 H- 6 Dbl Strut / 4 Lugs AUG 2 V'-CI Water Side Dsch OWN C PRE Prinfcwl V%4/7flO'
Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3) ( Page 65 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 . Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case- ' 1 2 3 A 1 2 3 AI 2 3 A 100978 ISI-13142-42-A . . C-C Dbl Spring /4 Lugs AUG - - - - - - - . C3.20 H- 3 OWN - - - - 2 HPCI Steam
.- ~~PRE _ _ _
C-C 101167 ISI-13142-51-B ISI Dbl Spring /4 Lugs AUG - - - - - - - - - ; 03.20 H- 2 OWN : : . . . . : . . . ; 2 Containment Spray
... PRE. . .
C-C 101721 . ISI-93268-1A iS! - . - ... Tank Support AUG - I - - - - ; C3.20 H-20 CRD Scram Header A OWN - - . 2
.;- ---- -- PRE P. .... .
is i' ^4 C4fl lUl ISI-93268-3A is1 C3.20 H-7 Restraint /4 Lugs AUG 2 CRD Scram Header B OWN
...... . Docl ISi-93268-3A Is - - .- - - - .
C-C 101815 C3.20 H-14 Tank Support AUG OWN 2 CRD Scram Header B
................. PRE ISI-13142-67 ISI - - ....
C-C 106979 C3.20 H-6 Restraint Hanger AUG - - .- - : OWN 2 Fuel Pool Emergency Cooling
~...-..*PRE 107608 ISI-13142-17-A iSI CC Slide Pipe AUG - - - - - - - .
C3.20 H- 3 OWN . . . . . . . . 2 RHR Suction A
- PRE C-C 107609 ISI-13142-17-A iS. . .
Slide AUG - - . C3.20 H- 8
-OWN 2 RHR Suction A PRE - - - -
(Id, . 10t10wrlinA.4bA._ I-v . t iSI . . .. .
.. '. , I .. . . . . ...
C3.20 H- 9 Slide . , I -. AUG
,, I I. ', I I RHR Suction A OWN - -.-.-.
2 PRE - -.-.-. Printed 314/2u05
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 66 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Scope I Method / Procedure Code Case 1 2 3 A I 2 a A I 2 A A Class Summary I CompID I System 0
------------- ~~~~ -- - ----- . .......
C-C 10761 ISI-13142-17-B ISI . . . . . . . C3.20 H-3 Restraint AUG - - - . 2 HPCI Water Side Sctn OWN PRE . . C-C 107612 ISI-13142-40-B IIs C3.20 H-10' Variable Spring AUG . . . . 2 HPCI Water Side Dsch OWN PRE . CC 107613 ISI-13142-20-B IS1 C3.20 H- 1 Variable AUG 2 Core Spray B OWN - - . PRE - . C-C 107614 ISI-13142-20-B ISI - - . C3.20 H- 2 Slide Hanger AUG - . 2 Core Spray B OWN - . PRE . ... . . . . . . . . C-C 107615 ISI-13142-20-B ISI . . . . . C3.20 H- 4 Variable I Support AUG 2 Core Spray B OWN . C-C107616 - - PRE-. . . C-C 107616 ISI/MTiPEI-02.02.01 ISI-13142-20-B iSI . . s . . C3.20 H- 5 Variable / Support AUG . 2 Core Spray B OWN .
.PRE . . ... . . . . . . . .
C-C 107617 ISI-13142-20-A ISIs - - C3.20 H- 1 Variable Spr / Slide AUG 2 Core Spray A OWN - . C-C 107618 ISI/MT/PEI-02.02.01 ISI-13142-20-A IPsRl E s C3.20 H- 2 Slide AUG - . 2 Core Spray A OWN - - . PRE - - . - . - f C . In7rinq... IRI-H3142-2O-A lSI C3.20_ H-4 Variable Spr/Slide AUG . .. 2 Core Spray A OWN IC PRE Printed 3/412005
C C I C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 67 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 ' Period 3 - Category, . Iso No. ItemNO, .. Comp. Desc. Class - -- Summary / ComplDI System -. - Scope / Method I Procedure .. -Code - Case - .... _._.. - . .. -- .. . 1 .-2 3 . 4 .1 .2. 3 4 1 .2 3.4 C-C 107620 ISI-13142-51-A ISI . C3.20 H- 2 Restraint Hanger AUG . . . . . . . 2 RHR A OWN - - - .
-. . .-....-......---. PRE- . ' . .
C-C 107621 ISI-13142-51-A ISI . . . . . . . . . . . C3.20 H- 4 Restraint Hanger AUG . . . . . . . . 2 RHR A -- . OWN -. - - - - - - - -
.......... ...-. .. .. v ...------ --------- - ~'~~ PE
- -;-E C-C 107622 ISI-13142-51-A ISI C3.20 H-6 Restraint Hanger AUG
- 2. RHR A OWN PRE C-C 107623 ISI-13142-51-A ISI - .
C3.20 H- 7 Restraint Hanger AUG . 2 RHR A . - OWN - - - - - - - -
- ..- *-PRE C-C 107624 ISI-13142-37-C ISI - - - - - - - .
C3.20 H-3 .Variable SprIng AUG .2 RHR Discharge A OWN
- .- ,- -PRE- -
C-C 107625 ISI-13142-37-A . ISI .... ..... . . . C3.20 H- 4 DbI Spring I Clamp AUG . 2: RHR Discharge A OWN - - - . PRE C-C 107626 . ISI-13142-37-B ISI, C3.20 H- I Variable Spring AUG 2 Containment Spray OWN PRE" -.. - . . - C-C 107627 ISI-13142-37-B ISI - - - C3.20- H- 4 Variable Spring AUG . . . . . . . 2 Containment Spray OWN PRE . . . . . . . . . C-C : 107628 . ISI-13142-26-C -. I ISI C3.20 H-i . ~ .!.- . Restraint Hanger , AUG 2 CORE SPRAY B OWN PRE now.,gf,4, ns,,"nnn';
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 68 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Code Case 14 2 -1 A A A e I e e . Class Summary I ComplD / System Scope I Method I Procedure C-C 107629 ISI-13142-26-C ISI C3.20 H- 6 Restraint Hanger AUG 2 Core Spray B Discharge OWN . . . . PRE . _._. . ._ . .___. . CC 107630 .ISI-13142-26-C IS1 . . . . . C3.20 H-9 Restraint Hanger AUG 2 Core Spray BDischarge OWN - - - - - CPRE CIC 107631 ISI-13142-26-B ISI . C3.20 H- 2 Restraint Hanger AUG 2 CORE SPRAY B OWN PRE . . CC 107632 ISI-13142-18-B ISI C3.20 H- 1 Variable Slide AUG 2 RHR Discharge B OWN PRE C-C 107633 ISI-13142-18-A IS1 . . C3.20 H- 5 Dbl Spr/U-BItUSaddle AUG 2 RHR Discharge B OWN . . . . . . . PRE _-_- -- C..C10734 C.C 107634 ISI-13142-1 8-A ISI . C3.20 H-6 Dbl Spr/U-BltSaddle AUG . . . 2 RHR Discharge B OWN PRE' . CC 107635 ISI-13142-18-A ISI . . . C3.20 H- 8 Dbl Spr/U-BIt/Saddle AUG 2 RHR Discharge B OWN - - . C.C1 0 7 6 3 8- PRE - . C-C 107636 ISI-13142-37-D ISI C3.20 H- i Restraint Hanger AUG 2 RHR A OWN . PRE . . . Cr- C ir10763 Isl-n1H142-3a-ne is1 C3.20 *H-2 Restraint Hanger AUG 2 RHR A OWN ( PRE Prinled 314/2005
C .- C C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 69 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012)
- .Period I Period 2 Period 3 Category, . so No. I iternNO, ~'I.'Camp. 1Desc.I Class - - Surmmary/ICompID/ISystem. .. Scope! Method/IProcedure,- _.-.. Codecase.,;;- . ,_ - 1..I..1 I 2- 3-4 I 2 3 4 I 1 23 4 C-C 107638 ISI-1 3142-31-B S' C3.20 H-i B Restraint Hanger -AUG - - - - - - - - - - - -
2 Core Spray A Discharge OWN - - - - - - - - - - - - PRE, -~ C-C 107639 ISi-131 42-26-B ISi, , - C3.20 H- 4 Restraint Hanger AUG - - - - - - - - - - - - 2 , ~ CORE SPRAY B ... .OWN - - - - - - - - - - - 7
.- ~ . ... ,.-....PRE -.-. -
C-C 107640 ISI-13142-51-D ISI,- C3.20 H- I Restraint Hanger AUG 2 -; RHR B OWN
- . .1..
. . i. . - --- , PRE C-C 107641 ISI-1 3142-'51-D ISI C3.20 H- 2 Restraint IH langer AUG 2 : RHR B - OWN
.. .. - - ~ - - -- PRE '
C-C 107642 ISI-13142-51-C IS!. -, C3.20 H-I1 Restraint Hanger AUG - - - - - - - - - - - - 2- RHR B . -OWN - - - - - - - - - - --
...-.-. ~~~~~PR E - - - - - - .-- -
C-C 107643 ISI-13142-1 8-A ISI C3.20 H-1Il Seismic Restraint AUG . . . . . . . . . . . . 2: RHR Discharge B . OWN - - - - - - - - - - - -
.. .. -PR E - - - - -
C-C 107648 ISI-13142-31-C .IS! C3.20 H- 1 Restraint Hanger AUG- - - - - - - - - - 2 Core Spray A Discharge.. . .- .. OWN7 7
-PRE - - - - -
C-C 107649 ..- ISI-1 3142-49-A IS! C3.20 . H- 2 Dbi Spring I Tee AUG . . . . . . . . . . . . 2 RHR Suction A OWN I- - - - - - - - - PRE - - - - - - - - - - - - C-C . -107650 - 1 -.. . : f'1- . I--'--'SI-13142-17-C %.~ Is' C3.20 ,H-4 - - , : - - :' !: !. , ;Slide , ,. 1,2 .. .. AUG 2 RHR Suction B OWN PRE Printl#I 114*O5
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 70 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class. - - Summary I ComplD I System Scope I Method I Procedure Code Case 1 2. 3 4 1 2 34 1 2 3 4 C-C 107651.. ISI-13142-17-C 1St C3.20 H- 2 Slide AUG 2 RHR Suction B OWN PRE - - C-C 107652 ISI-13142-17-C ISI C3.20 H- 3 Slide AUG 2 RHR Suction B OWN PRE C-C 107653 ISI-13142-62 ISI C3.20 H- 5 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN
- PRE C-C 107654 ISI-13142-62 ISI C3.20 H- 4 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN PRE C-C 107656 ISI-13142-37-D ISI C3.20 H-3 Double Snubber AUG
- 2. RHR A OWN
- ... PRE 1.
4 1. C-C 107657 ISI-13142-51-C ISI C3.20 H-5 Seismic Snubber AUG 2 RHR B OWN PRE C-C 107658 ISI-13142-51-A ISI C3.20 H- 1 Snubber I Dbl Strut AUG 2 RHR A OWN PRE C-C 107659 ISI-13142-37-C ISI C3.20 H- 4 Dbl Strut I Snubber AUG 2 RHR Discharge A OWN L.. PRE C-C 107664 : ISI-13142-19-B ISI C3.20 H-2, . Restraint Hanger AUG 2 RCIC Steam Discharge OWN C PRE Printed 3/4/2005
C C 4th Interval ISI Plan (Rev.3) Page 71 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. A 3 A Class .-.. Summary I ComplD I System . . Scope! Method / Procedure Code Case 1 2 3 A 1 2 A I I C-C 107668 ISI-13142-40-A [SI H-14 Seismic Restraint AUG C3.20 2 HPCI Water Side Dsch OWN
~PRE _ _ _
C-C 107669 .ISI-13142-17-B [SI Restraint AUG C3.20 H- 4
. . OWN 2 HPCI Water Side Sctn ..
PRE- ------- _ 107670 ISI-13142-40-B 1S1 C-C C3.20 H-3 Seismic Restraint AUG 2 - HPCI Water Side Dsch OWN PRE - _.... C-C 1 0l7R71n Is[ C3.20 H-5 Restraint Hanger AUG
- 2. RCIC Steam Discharge OWN
.. ^ . . . . .. . . . ... . ..... ... ......
... I .. -.-. DOM..
ISI-13142-31-C IS C-C 107672 H-i. Seismic Restraint AUG C3.20
. OWN - - - .
2- Core Spray A Discharge ISI-13142-48-A . ISI C-C 107673 Restraint Hanger AUG - : C3.20 H- 4 . 2 - RHR SERVICE WATER OWN C- .ISI-13142-67 064- ISI.
.. .. s -- * - Restraint-- ;- Hanger-: ---- -- AUG..;
PRE - . .. . .. . C3.20 H- 1 2 Fuel Pool Emergency Cooling .... . OWN ISI-13142-67 ISI C-C 107675 Restraint Hanger AUG C3.20 H- 2 OWN . . 7 ... .. . 2C C Fuel Pool Emergency Cooling 1067 IS-134-6 _.P PRE Eu 1.1Ww - , .- . .. , I , I .- - eStrIn-t H1a42-ne lS1 C3.20 . ; H- 5 .- - . 1.
- Restraint Hanger . AUG 2 Fuel Pool Emergency Cooling OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 72 of 332
- ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope / Method / Procedure Code Case 1 2 3 4 I 2 3 4 I 2 3 4 C-C 107677 151-13142-67 IS1 C3.20 H- 9 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN PRE C-C 102745- IS148 ISI C3.30 RHR Support C Pump Support AUG 2 RHR Pumps OWN PRE.- C-C 102747 ISI-48 ISI C3.30 RHR Support D Pump Support AUG 2 RHR Pumps OWN PRE C-C 102751 ISI-48 ISI s C3.30 RHR Support A Pump Support AUG 2 RHR Pumps OWN PRE . C-C 102752 ISI-48 ISI C3.30 RHR Support B Pump Support AUG
- 2. RHR Pumps OWN PRE, C-C 102753 ISUMTIISI-MT-2 ISI-49 ISI r r - - s C3.30 Support, Pump A Pump Support AUG 2 Core Spray Pumps OWN PRE .
C-C 102754 ISI-49 ISI . . . . . . . C3.30 Support, Pump B Pump Support AUG
- 2. Core Spray Pumps OWN - - - - - .
PRE . . . . . . .. C-H 100003 ISUVT/0255-02-llC-1 1.5-12 Boundary ISI b - - - b - s C7.10 SBLC ISVVT/0255-02-llC-2 System Leakage Pressure Test AUG 2 SBLC OWN - . PRE C-H7 100008,. I 5ISVTI0255-034llC-1 . 1.5-5 Boundary ISI B b Pns 25 C7.t0 . Core Spray System Loop A System Leakage Pressure Test AUG
; . ,7 2 Core Spray Loop A OWN
( PRE Printed 3/4/2005
C ,C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 73 6f 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 C-H 100010 ISINT/0255-04-11C-2 1.5-7 Boundary ISI - b b s C7.10 RHR System Loop B System Leakage Pressure Test AUG - - - - - . 2 RHR Loop B . OWN - - - - -
...... PRE - -
C-H 100013 ISINT/0255-04-IIC-1 1.5-6 Boundary ISI b - b . . s C7.10 RHR System Loop A System Leakage Pressure Test AUG . . . . 2 RHR Loop A ;OWN O -. .- .- - - - .
.. .... PE_-.
C-H 100023 ISINT/0255-06-IIC-1 1.5-8 Boundary ISI s C7.10 HPCI System Leakage Pressure Test AUG 2 HPCI OWN PRE C-H 100025 -ISINT/0255-IIC-1 1.5-10 Boundary ISI - b . . - b s C7.10 RCIC System Leakage Pressure Test AUG - - - - - . 2 . RCIC* OWN - - - - - . PRE-. - C-H 100037 ISINVT10255-12-IIC-1 1.5-3 Boundary . !SI - b - - b - s - C7.10 Feedwater System System Leakage Pressure Test AUG - - - - . 2 Feedwater A ; . OWN - - - - - - - - :
~~PRE--...
C-H 100038 -ISINT10255-12-IIC-2 1.5-3 Boundary ISI - b - - - b * - s C7.10 Feedwater System System Leakage Pressure Test AUG - - - - . 2 Feedwater B OWN
-- PRE . -
C-H 100044 ISINT/0255-16-lIC-1 1.5-21 Boundary ISI b b s 7 C7.10 Drywell Floor Drain System Leakage Pressure Test AUG - - 2 Drywell Floor Drain OWN
- PRE--
C-H 100046 151NT10255-16-1C-2 1.5-21 Boundary ISI b b - C7.10 Drywell EQT Drain System Leakage Pressure Test AUG 2 Drywell EQT Drain OWN PRE C-H 106300 .I I 1.5-13 Boundary. ISI It t t - - t C7.10 iri. Containment Vac. Relief ; I System Leakage Pressure Test AUG - -.. 2 Pri. Containment Vac. Relief N-522.N-522,N-522,N-522 OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 74 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary / ComplD I System Scope -
I --Method / Procedure Comp. Desc. Code Case 1. 23 I A 1.4S
- 7
-2 1 A 1 4
- t. .I It S.
f A C-H 106400 1.5-13 Boundary ISI - t t - t C7.10 Pri. Containment Air Purge Supply System Leakage Pressure Test AUG 2 Pri. Containment Air Purge Supply N-522.N-522.N-522.N-522 OWN - - - - - . PRE . - - . -. - - - - - C-H 106500 1.5-13 Boundary ISt
- t - - t t - - t C7.10 Torus Air Purge Supply System Leakage Pressure Test AUG Torus Air Purge Supply N-522,N-522,N-5z2,N-522 OWN 2
..-- - -- - -- - -R- - ...-
.- 2,-52N52,2 PRE --- -
OW -. C-H 106601 1.5-13 Boundary IS1 t - t t - t C7.10 PCAC System Leakage Pressure Test AUG - . 2 PCAC N-522,N-522,N-522,N-522 OWN C-H 106700 1.5-13 Boundary ISP R t - - t t - C7.10 Standby Gas Treatment System Leakage Pressure Test AUG 2 Standby Gas Treatment N-522,N-522,N-522,N-522 OWN PRE 1.5-13 Boundary IS1 t t - t t - C7.10 Torus HPV System Leakage Pressure Test AUG 2 Torus HPV N-522,N-522,N-522,N-522 OWN _ . . DDI:
-1n7lA lIQ11V r -, - -rrn_ ISI -b b s C. H -.- VI IuVzDU-L%.-z 1.b-17 Boundary C7.10 CRDH System Leakage Pressure Test AUG 2 CRDH OWN C-H 107140 1.5-19 Boundary ISI - t t t t C7.10 Compressed Air System System Leakage Pressure Test AUG . ....
2 Compressed Air N-522,N-522,N-522,N-522 OWN PRE . . . . . . . . .. . . C-H 107144 1.5-20 Boundary ISI . t - - t t - - t C7.10 Demin Water System System Leakage Pressure Test AUG - - - - - - - . 2 Demin Water Sytem N-522,N-522,N-522,N-522 OWN PR C-H 10n7l14 1. 0 boundary lSI t t t - . t - - C7.10 RBCCW System Leakage Pressure Test AUG P I n . 2 RBC RBCCW N-522,N-522,N-522,N-522 OWN PRE
. (.
Printed 3/4/2005
C' Monticello Nuclear Generating Plant C 4th Interval ISI Pl~an (Rev.3) I i - I . I , Pag e 75 of 332 I ASME Section XI, (1995 Edition, 1996 Addenda) I (Mayl1,2003 to May 31,2012) i - Period I Period 2 .Period 3 Category, I. Iso No., ItemNO,I .I! I Comp. Desc.
- Scope I Method I Procedure .,. __ .1.1 2 3 4 I 2 3 A 1 7 ft A Class ,--Summary/IComptoIDSystemn "-- -Code Case _ - _
C-H 107156 ISINVT/0255-20-IIC-2 1.5-21 Boundary[Sb---bs C7.10 RWCU System Leakage Pressure Test AUG ------------ 107164 1.5-22 Boundary [Si . - It It It - - t - - C.H C7.10 Tranversing In-Core Probe System System Leakage Pressure Test AUG ------------ 2 Tranviersing In-Core Probe System -N-522.N-522,N-522.N-522 OWN ------------ PRE Boundary 1SF . t - - t t - - t C- 0121.5-23 C7.1 0 Excess-Flow Check Valves System Leakage Pressure Test AUG ------------ 2 Excess-Flow Check Valves N-522,N-522,N-522,N-522 OWN ---------- PRE - -- - - - - - - - C-H 107176 1.5-26 Boundary ISI - t - - t t - t - - - C7.10 PC Sample System System Leakage Pressure Test AUG ------------ 2-: Primary Containment Sample System N-522,N-522,N-522,N-522 OWN ------------
.R ' '-_ . . .. "
107607. I15lNT10255-03-IIC-2 1.5-5 Boundary ISI B - - -b s--- C-H C7.10 Core Spray System Loop B System Leakage Pressure Test AUG ............ 2 Core Spray Loop B OWN ----
'PRE -
D-A 102756 nd-IsI-101 181 - - - - - SS-562 Dbi Strut I Snubber AUG - - - - - - - - - - - - 01.20 OWN . . . . . . . . . . . .
- 3. RHR Service Water PRE - -~* - - . - - - -
D-A 102757 nd-ist-101 181 - - - - - Stanchion - - - - - - - - - - - - 01.20 SWH-43 .AUG OWN - - - - - - - - - - - - 3 RHR Service Water
,.-PRE . . - - - - - - -
D-A 102758 nd-IsI.102 [SI Seismic Restraint AUG . . . . . . . . . . . . 01.20 ~- SR-79 3 RHR Service Water OWN - . - - .- - -.-.- - f ft.. . f )7 .. PRE - - - - -- - - - - - - na-Isi-1 ui ISI D1.20 -,:SWH-304.-, ... I.Double Spring. AUG 3 RHR Service Water OWN PRE Printed 3/41205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 76 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Class *- Summary I ComplD I System Scope / Method I Procedure Code Case .1 .2 3 4 1 2. 3 4 1 2 3 4 D-A 102760 -nd-isi-103 I1St - - - - -- D1.20 SR-459 Seismic Restraint AUG 3 RHR Service Water ,. OWN PRE' - - - D-A 102761 nd-isi-106 ISI D1.20 SR-457 Anchor AUG 3 RHR Service Water OWN
' ' . PRE D-A 102762- nd-isi-107 ISI D1.20 SR-105 Stanchion AUG 3 RHR Service Water OWN PRE D-A 102763 ISIIVTIISI-VT-1.0 nd-isi-107 ISI D1.20 SWH-72A Stanchion AUG - .
3 RHR Service Water OWN PRE D-A 102764. . nd-isi-107 ISI D1.20 SWH-72B. Stanchion AUG - ...- 3 RHR Service Water OWN
* ~PRE-D-A 102765 -S1iNT/lSl-Vr-1.o nd-isi-108 . IS-S D1.20 IS-SWH-65 Stanchion AUG 3 RHR Service Water OWN PRE D-A 102766 nd-isi-108 ISI D1.20 IS-SWH-66 Stanchion AUG 3 RHR Service Water OWN PRE .
D-A . 102767 ISINTIPEI-02.05.01 nd-isi-108 ISI c r . - D1.20 SR-106 Stanchion AUG 3 RHR Service Water OWN PRE D-A . 102768 - I nd-isi-1 09 lS1 D1.20 SR-458 : Anchor. AUG 3 F-Q Service Water OWN I9. PRE PrintnM 1'A!I)OA'
C C '. I
- C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) ' . Page 77 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. . ItemNO, Comp. Desc. Class . Summary I ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 D-A 102769 nd-isi-111 IS . D1.20 SR-88 Stanchion AUG 3 RHR Service Water OWN PRE - . D-B 100021 1.5-16 Boundary ISI - b - s D2.10 RHR SW Div. I System Leakage Pressure Test AUG 3.- RHR SWA . . . OWN
,3 SW A ..- -- -- -- - - -- ---OWN-- - - -PR - ----
.PRE D-B 100022 1.5-16 Boundary IS1 - b - - - s D2.10 RHR SW Div. ll System Leakage Pressure Test AUG 3 RHR SW B OWN
... . _. -- PRE..
D-B 100031 1.5-14 Boundary ISI - B - - - s D2.10 EDG-ESW A Div 1 System Leakage Pressure Test AUG 3 EDG-ESW A . . . ; OWN
.......... . < .. .. --.- . -- - -- - ---- -- ----- ---- PRE- - -.....
D-B 100032 - 1.5-15 Boundary ISI - b - - - s D2.10 EDG-ESW B Div. lI System Leakage Pressure Test AUG - 3.- EDG-ESW B . .. OWN
..-.--.. P RE.. . ,
D-B 100033 1.5-14 Boundary ISI - b - - - s D2.10 ESW A Div. I System Leakage Pressure Test AUG 3 ESW A OWN
. . . .. .- - - --- - -- - - -PRE-- . ; .
D-B 100034 1.5-15 Boundary IS1 - b - - s D2.10 ESW B Div. ll System Leakage Pressure Test AUG 3 ESW B OWN PRE - D-B 107102 1.5-8 Boundary ISI - b - s - - D2.10 HPCI System Leakage Pressure Test AUG 3 HPCI OWN PRE D-B . 107111 I.. .1.5-10 Boundary. .: ISI s D2.10 RCIC - System Leakage Pressure Test AUG 3 RCIC OWN PRE Printed 3/4t2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 78 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class - Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 D-B 100017 ISWVT/0255-05-IIC-1 1.5-16 Boundary IS- s D2.20 RHR SW Div. I Hydrostatic Pressure Test AUG 3 RHR SW A N-498-4 OWN PRE - - -- . . D-B 100020 ISINT/0255-05-IIC-2 1.5-16 Boundary ISI - . . s D2.20 RHR SW Div. II Hydrostatic Pressure Test AUG 3 RHR SW B N4984 OWN PRE D-B 100027 .ISVVT10255-11-IIC-3-1 1.5-14 Boundary ISI .. . .s D2.20 EDG-ESW Div. I A ISINT10255-1 1-llC-3-2 Hydrostatic Pressure Test AUG 3 EDG-ESW A N-498-4 OWN PRE D-B 100028 ISINVT10255-11-llC4-1 1.5-15 Boundary ISI s- - - s D2.20 EDG-ESW B Div. II ISVVT/0255-1 1-IIC-4-2 Hydrostatic Pressure Test AUG 3 EDG-ESW B N-498-4,N-498-4 OWN PRE D-B 100029. ISWNT/0255-11-IIC-1 1.5-14 Boundary ISI -- - -s D2.20 ESW A Div. I Hydrostatic Pressure Test AUG 3 ESW A N4984 OWN PRE- . .. .. D-B 100030 ISWT10255-11-IIC-2 1.5-15 Boundary IS1I-s -s D2.20 ESW B Div. II Hydrostatic Pressure Test AUG 3 ESW B N-498-4 OWN PRE - .. - .... D-B 107597, ISVNT/0255-06-IIC-1 1.5-8 Boundary ISI .. .s D2.20 HPCI Hydrostatic Pressure Test AUG 3 HPCI N-498-4 OWN PRE D-B 107598 ISINVT10255-08-11C-1 1.5-10 Boundary ISI s D2.20 RCIC Hydrostatic Pressure Test AUG 3 RCIC N4984 OWN PRE F-A 100427 ISWVTiPEI-02.05.02 ISI-131 42-26-A ISI 5 F1 .10a H- I Restraint I Clamp AUG 1 Core Spray B OWN PRE . (. Printed 3/4/2005
C C Monticello Nuclear Generating Plant 4th Interval IS1 Plan (Rev.3) Page 79 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) . .,,, (May 1,2003 to May 31, 2012) Period I PeriodI2 Period 3 Category, iso No. 1temNO, Comp. Desc. 2 It A i A Class .Summary I CompiD I System Scope I Method I Procedure Code Case I A I ', t1 4 -1 ISt-i131 42-26-A S - - - - - - - - - - - - F.A 100428 Restraint Slide AUG F1.10a H-2 OWN - - - - - - - - - - - -
- 1. Core Spray B SI-73880-A I1 - - - - - -
F.A 101361 .. Restraint AUG - - - - - - - - - - - - n 1a H-2Box
.1ReactorWtr Cleanup .
- ,..~~~~PRE-..
101420 ISI-74215A IS1 F-A - - - Box Restraint AUG - - - - - - - - - F1.1lOa H-I W Standby Liquid Cntrl
-- PRE - -.
I1 - - - - - F-A 101421 -ISI-74215A Box Restraint AUG - - - - - - - - - - - - F1.10a H-2 1Standby Liquid CntrlOW PRE-SNIE-02.05.02 II725 S -- F-A 101422 . Restraint AUG. . . . . . . . . . . FIla H3Box OWN. 1, ta.ndby Liquid Cntrl
.. ~...--.-
PRE -- ISI-74215A ISI F-A 101423 Restraint AUG - - - - - - - - - - - - H 4Box 1 . Standby Liquid Cntrl OWN - - - - - PRE - -- ISI-782A I1St - - - - -- F-A 101460 - Hanger AUG' F1.10a H-i1 OWN . . . . . . . . . . . . 1 . Head Vent 101461 ISI.782A ISI - S - - . - F-A .ISINVr/PEI-02.05.02 Hanger AUG - - - - - - - - - - - -
,F1.10a H-2 OWN - - - - - - - - - - - -
Head Vent PRE - - - - - - - - - - - -
- iI .JsUz I I I *IiiIAb/irtf-uzAuRUZ 1 . 1S!-756A
- . ,, . 'SI H F1 .10Oa .H-i Box Support -, AUG I MS Condensate Lkoff OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISt Plan (Rev.3) Page 80 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003.to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 11 2 3 411 2 3 4 F-A 101521 ISI-786A I1 - - - - - - Fl.10a H-2 Box Support AUG 1 MS Condensate Ikofi OWN PRE . .. F-A 101522 ISINT/PEI-02.05.02 ISI-786A IS1 - s - F1.10a H- 3 Unear Support AUG 1 MS Condensate Lkoff OWN
*- -PRE-- -.. .
F-A 101523 ISI-786A ISI F1.10a H-4 Box Support AUG I MS Condensate Ikoff OWN PRE---- F-A 101618 ISINTIPEI-02.05.02 ISI-821A ISI- - s F1.10a H- 2 Box Restraint AUG I Bottom Head Drain OWN PRE F-A 101620 ISI-821A IS1 F1.10a H-4 Box Restraint AUG I Bottom Head Drain OWN PRE F-A 101621 ISI-821A ISI F1.10a H- 5 Box Restraint AUG Bottom Head Drain OWN . PRE - F-A 101622 ISI-821A ISI F1.10a H-6 Box Restraint AUG 1 Bottom Head Drain OWN PRE . . . . F-A 101974 : ISI-97005-A ISI F1.10a H- I Seismic Restraint AUG i Recirculation A OWN PRE F-A 101980 ISIVTIPEI-02.05.02 ISI-97005-A [Si F1.10a H-4 Seismic Restraint AUG . s . . 1 Recirculation A C OWN PRE Printed 3/41200
C . C C Page 81 of 332 Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) ASMVE Section Xi (1995 Edition, 1996 Addenda) (May 1, 200310o May 31, 2012) IPeriod I . Period 2 Period 3 Category, Iso No.
- IternNO, Class . -. Summary I CompiD I System Scope!I Method I Procedure. . - ..
Comp. Desc. Code Case 1.2_ 3..4I1 3 4 I 2 3 4. F-A 101988 ISI/VT/P EI-02.05.02 ISI.97005-A S E - - - - - - - - - - - F1.10a H-9 Seismic Restraint AUG - - - - - - - - - - - - 1 Recirculation A OWN - - - - - - - - - - - - PRE - - - . . F-A 101991 SIS!NT/PEI-02.05.02 ISI-97005-A ISI . E ----------- F1.l0a H-12 Seismic Restraint AUG - - - - - 1 Recirculation A OWN - - - - - - - - - - - - PRE - .. ~ . F-A 102018 ISI/Vr/PEI-02.05.02 ISl.97005-B 1St- - - - - -s-F1.10a H.1I Restraint AUG' 1 Recirc Manifold A OWN - - - - - - - - - - - - PRE' F-A 102020 ,ISI-97005-B [SI . - F1.10a H.3 Restraint AUG - - - - - - - - - - - - Recirc Manifold A OWN - - - - - - - - - - - -
... PRE '
F-A 102021 .. ;ISINTI/PEI-02.05.02 ISI-97005-B ISI.-. - --- - - - -s - - - F1.10a H.4 Restraint AUG--- . . - IRecirc Manifold A -OWN - - - - - - - - - - - - F.A 102022 ISI-97005-B [St. . - F1.10a H.5 Restraint AUG - - - - - - - - - - - - Recirc Manifold A OWN - - - - - - - - - - - -
.. PRE - -.
F-A 102024 ISI5-97005-B 151 - - - - - F1.10a H-7 Restraint AUG - - - - - - - - - - - - 1Recirc Manifold A OWN - - - - - - - - - - - - 00 P-B15 RE F-A 102025IS970B s F1.10a .. H-8 Res'traint AUG - - - - - - - - - - - - 1 Recirc Manifold A OWN - - - PRE - - - - - - - - - - - - F-A - 102026 ,I .,: ISI-97005-B3, .. 'SI F1.10a H , - . .: - Restraint ,, .- AUG I Recirc Manifold A OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 82 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Class Summary I ComplD I System Scope I Method I Procedure Comp. Desc. Code Case 1 2 3 4 1. 2 3 411 2 3 4 F-A 102027 . ISINT/PEI-02.05.02 ISI-97005-B IS[ - - - - s F1.10a H-10 Restraint AUG 1 Recirc Manifold A OWN PRE - . ... F-A 102030 ISI-97005-B lSI F1.10a H-13 Restraint AUG 1 Recirc Manifold A OWN PRE - I ~i F-A 102079 ISI-97006-A ISI F1.10a H- I Restraint AUG 1 Recirculation B OWN PRE F-A 102085 ISJVTIPEI-02.05.02 ISI-97006-A IS1 C r - - - - - . F1.10a H-4 Restraint AUG . . . I Recirculation B OWN . PRE - - - . F-A 102092 ISI-97006-A IS1 F1.10a H-9 Restraint AUG 1 Recirculation B OWN PRE .. 4 F-A 102098 ISI-97006-A ISI F1.10a H-12 Restraint AUG 1 Recirculation B OWN PRE F-A 102124 ISI-97006-B ISI . F1.10a H- I Restraint AUG
- 1 Recirc Manifold B OWN .
PRE - F-A 102130 ISI-97006-B IS1 FI.1Oa H-4 Restraint AUG 1 Recirc Manifold B OWN -- PRE F-A . 102131 ISI-97006-B ISI F1.10a H-3 Restraint AUG 1 Pacirc Manifold B OWN (. PRE Printer] 31417005
C. C C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 83 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) - (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class -- Summary I ComplD I System - - - Scope /Method / Procedure --- Code Case 1. 2 .3 4 1 2 3 4 1 2 3 4 F-A 102132 ISI/T/PEI-02.05.02 ISI-97006-B ISI - - - - - . F1.10a H- 6 Restraint AUG - - - - - - . 1 Recirc Manifold B ..... . OWN -.- - - - -.- -- - PRE F-A 102133 - - ISI-97006-B ISI - . F1.10a H- 7 Restraint AUG . . . . . . . I Recirc Manifold B OWN - - - - - - - . PRE . . . . . ._. . . F-A 102134 ISI-97006-B iSI . . . . F1.10a H- 8 Restraint AUG 1' Recirc Manifold B OWN PRE - - - . F.A 102135 ISI-97006-B ISI - - - - . F1.10a H-9 Restraint AUG Recirc Manifold B OWN - - .
. PR - - - - - - - - . ----
PR...; F-A 102137 ISI-97006-B ISi - - - - - - . F1.10a H-1 I Restraint AUG - -.. - 1 Recirc Manifold B : ' OWN - - - - - - . . ... PRE . . . . . . . . . . F-A 102139 ISINT/PEI-02.05.02 ISI-97006-B ISI-- . -. .- F1.10a H-13 Restraint . AUG . 1 Recirc Manifold B - OWN . ............. PRE . F-A 105019 ISI-782A ISI . . . . . . F1.10a H-5 Hanger AUG - . 1 Head Vent - OWN PRE . F-A 105020 ISINT/PEI-02.05.02 ISI-782A ISI - - - - s F1.10a H-SA Hanger AUG . 1 Head Vent OWN -:,- - - - - * -- - - - - - PRE . . . . . . . . . . . . 105021 . *... .: - . - -ISI-782A- 'SI - - - - F-A . . F1.10a H- 7 ; : . I: ~' Hanger - ; AUG OWN - - - - 1 Head Vent PRE . . . . Printorl V'15fW)
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 84 of 332 ASME S.cti.on Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary I CompiD I System Scope I Method / Procedure Comp. Desc.
Code Case - I I 2 3 A 1 2 q A 1. 12 -1 A F-A 105023 PSINT/PEI-02.05.02 ISI-782A-A ISI F1.10a H- I PSINT/PEI402.05.02 Hanger AUG 1 Head Vent OWN - - - . PRE H h - - F-A 105025 PSIIVT/PEI-02.05.02 ISI-782A-A ISI F1.10a H-3 PSINT/PEI-02.05.02 Hanger AUG . 1 Head Vent OWN . PRE H h - F-A 105052. ISI-821A ISI . F1.10a H- 9 Suppor AUG 1 Bottom Head Drain OWN PRE - F-A 100578 ISI-13142-33-A ISIR . F1.10b H-2 Snubber / Clamp AUG 1 Main Steam A OWN PRE F-A 100579 PSINTIPEI-02.05.02 ISI-13142-33-A ISI , F1.10b H- 3 Snubber / Clamp AUG 1 Main Steam A OWN PRE c - - - -. - - F-A 100582 PSIVr/PEI-02.05.02 ISI-13142-33-A ISI - - - - s F1.10b H-6 ISINT/PEI-02.05.02 Snubber / Clamp AUG 1 Main Steam A ISINTIPEI-02.05.02 OWN PRE - b . F-A 100583 ISI-13142-33-A ISI - - - . F1.10b H- 7 Snubber / Clamp AUG . 1 Main Steam A OWN . PRE F-A 100631 ISI F1.10b H-2 Snubber Clamp AUG . I Main Steam B OWN PRE no ICn- -I - qs.- _ FA 100632A'; OCIAM1001 I;u llrcl-U I .Ux IS' F1.10b H- 3 Snubber / Clamp AUG i,1 Min Steam B OWN (o,.. (I. PRE H PA,#4'/A.
C: C7 EC Monticello Nuclear Generating Plant 4th Interval ISI'Plan (Rev.3) Page 85 of 332
- ASME Section Xi (1995 Edition, 1996 Addenda) .. . ._ (May 1, 2003 to May 31, 2012) ._ .-. . .- . -
Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / Systemr Scope I Method I Procedure - - Code Case 1 3 4 1 2 3 4 1 2 3 4-F-A 100682 PSIIVTIPEI-02.05.02 ISI-13142-35-A ISI; F1.10b H- 2 Snubber I Clamp AUG . MaInSteam C.. .. . . OWN PRE - - F-A 100683 . ISINT/PEI-02.05.02 ISI-13142-35-A ISI - s F1.10b H-3 PSINT/PEI-02.05.02 Snubber / Clamp AUG
- 1. Main Steam C_ _ O, - - - - - - - - - - -
PRE . - - - - - F-A 100737 PSINTIPEI-02.05.02 ISI-13142-36-A ISI Fi.1ob H-2 Snubber / Clamp AUG 1 Main Steam D OWN PRE c - - -.- - - --- - -- F-A 100740 PSINVTIPEI-02.05.02 ISI-13142-36-A [S I . . . . F1.10b H- 5 Snubber / Clamp AUG . . . . .1 . Main Steam D OWN PRE F-A 100741- PSIN/PEI-02.05.02 ISI-13142-36-A ISI-: - - FiAlOb H-6 ISINT/PEI-02.05.02 Snubber/Clamp AUG 1 ... . Main Steam D . OWN PRE H- -.-- . - F-A 101042 ISI-13142-43-A ISI - F1.10b H-2 Strut Clamp AUG .1 .CI Steam OWN F-A 101198 ISI-13142-52-A ISI F1.10b H- 4 Snubber Clamp AUG 1 Feedwater OWN
- - -- - - PRE.
-- -. - -RE F-A- 101201 ISI-13142-52-A ISI F1.10b H-7 Snubber / Clamp AUG 1 Feedwater OWN - * -' - .-
PRE F-A 101253 ISINVTIPEI-02.05.02 ISI:13142-53-A: IsI F1.10b H-5 PSI/Vr[PEI-02.05.02 Snubber / Clamp . AUG 1 Feedwater OWN PRE b - Prinn1d /-rn n1;m
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 86 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 2 3t 4 1.2.I ' I. I 3 A Class Summary I ComplD I System Scope I Method I Procedure Code Case-F-A 101255 ISI-13142-53-A ISI . F1.10b H-7 Snubber I Clamp AUG 1 Feedwater OWN PRE -. - F-A 101855 PSINT/PEI-02.05.02 ISI-97003-A PSI F1.10b H-3 PSINT/PEI-02.05.02 Snubber Clamp AUG . 1 RHR Return A PSUVTIPEI-02.05.02 OWN PSINTIPEI-02.05.02 PRE c b - - F-A 101856 ISI-97003-A ISI F1.10b H-4 Snubberl Clamp AUG 1 RHR Return A OWN PRE - - - - - - - - - - - - F-A 101896 PSIVT/PEI-02.05.02 ISI-97003-B ISI F1.lOb H-2 PSWVTIPEI-02.05.02 Snubber l Clamp . AUG 1 RHR Suction A OWN PRE -s F-A 101897 PSINT/PEI-02.05.02 ISI-97003-B ISI F1.10b H-3 PSINT/PEI-02.05.02 Snubber / Clamp AUG . 1 RHR Suction A, OWN PRE . F-A 101935 ISI-97004-A ISI - . F1.10b H-3 Snubber/Clamp AUG 1 RHR Return B OWN . PRE . ... F-A 101936 ISINT/PEI-02.05.02 ISI-97004-A ISI s F1.10b H-4 Snubber l Clamp AUG 1 RHR Return B OWN PRE' F-A 102195 ISI-97027-A ISI F1.10b H-2 Snubber I Clamp AUG 1 RHR Equalizer OWN PRE ISv DlrE.1-02.05,0
- ISI-97027-A ISI . S -
F1.10b H-3 Snubber I Clamp AUG I P'-R Equalizer OWN (h. (1b PRE Printad 11412005
C 4th Interval 151 Plan (Rev.3) 87 of 332 Monticello Nuclear Generating Plant -Page
'ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) I I
Period I - Period 2 Period 3 Category, Iso No. IternNO, Comp. Desc. 4 I 'I A 1 4 11 I A Class Summary ICompiD I System - - Scopi I Method/IProcedure -- Code Case I I I A ISI-821AAs - F-A 105051' Strut/IClamp AUG - - - - - - - - - - - - F1.10b H-8 1Bottom Head DrainOW ISI-97005-A PRE - - - - - F-A 107528 PSI/VTIPEI-02.05.02 Snubber Lugs, AUG - - - - - - - - - - - - F1.10b H-8 ISINVrIPEI-02.05.02 Recirculation A W-- 1 ..- ISI-97005-8 ISI F-A 107530 Snubber/ILugs AUG - - - - - - - - - - - - F1.10b H-2 OWN - - - - - - - - - - - -
- 1. Recirc Manifold A ..
F- 053PRE ISI-97005-8 ISI H - - - - - - - - - - - F-053ISINTI/PEI-02.05.02 Snubber ILugs AUG - - - - - - - - - - - - F1.10b H-12 1 Recirc Manifold A.- .OWN
..- PRE '-- - - - - - - - - - - --
ISI-97006-A is[ . .s. .-. .-. .- F-A 107547 'PSINVTIPEI-02.05.02 Snubber Lugs AUG - - - - - - - - - - - - F1.10b H-8 isuvT/PEI-02.05.02 I Recircufation B '44 ~ ~OWN - - - - - - - - - - - - 107549 PSINVTIPEI-02.05.02 ISI-97006-8 [Si F-A Snubber /Lugs AUG - - - - - - - - - - - - F1.10b H-2 OWN - - - - - - - - - - - -
- 1. Recirc Manifold B lSl-97006-B t S1S - - - - --
F-A 107552 .PSINTI/PEI-02.05.02 PSINTI/PEI-02.05.02 Snubber AUG - - - - - F1.10b H-12 1 eicManifold B. *OW PRE c- --- - - - -- -. -- ISI-13142-31-A 151 - F-A . 100495 Springl/Clamp AUG - - - - - - - - - - - - F1.10c H-i OWN , - - - -- - ICore Spray A PRE - - - - - - - - - - -
- fflO ,'~rtr , n . . .--
Is' S F1.l0c7 .: H-2 .. .I Spring I Clamp , . AUG 1 Core Spray A OWN PRE Printed 3/4/2005
- Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 88 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary i ComplD I System Scope I Method / Procedure Code Case 1. 2 3 4 1 2 3 4 1 2 3 4 F-A 100580 ISINTIPEI-02.05.02 ISI-13142-33-A 151 - r s F1.10c H-4 Variable t Spring AUG 1 Main Steam A OWN PRE . F-A 100581 ISI-13142-33-A ISI . F1.10c H- 5 Spring /Clamp AUG . 1 Main Steam A OWN
.~~~~R . .. . . .... . . .. .. ... . ... .
PRE- - F-A 100633 iSi-13142-34-A [SI - . F1.10c H- 4 Spring / Clamp AUG 1 Main Steam B OWN PRE - . F-A 100684 ISINTIPEI-02.05.02 ISI-13142-35-A ISI - s - - F1.10c H-4 Spring / Clamp AUG 1 Main Steam C OWN PRE . F-A 100738 ISI-13142-36-A ISI , . F1.10c H-3 Spring Clamp AUG . 1 Main Steam D OWN - . PRE - - F-A 100739 ISI-13142-36-A ISI . . . . , F1.10c H-4 Variable / Spring AUG 1 Main Steam D OWN - . PRE F-A 100975 ISI-13142-42-A ISI F1.10c H- I Variable Spring AUG 1 HPCI Steam OWN PRE F-A 101041 PSVNT/PEI-02.05.02 ISI-13142-43-A ISI F1.10c H- 1 Variable Spring AUG 1 RCIC Steam OWN PRE H - - . F-A 101194 ! ISI-13142-52-A ISI F1.10c H-1 Spring I Clamp AUG 1 ( dwater OWN (. I. PRE - I Print-i I!A.')Mr,
C C IC Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) : .Page 89 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) P . I . 2 Period I Pelo Period 3 Category, Iso No. ItemNO, Comp. Desc. I Method I Procedure. Code Case 19 2) I AI 1 2 'I A4 4 t 1 A Class -- Summary I ComplD / System .Scope 101196 ISI-13142-52-A ISI F-A H-2 Variable I Spring AUG F1.10c
- . OWN 1 Feedwater F-A 101199 ISI-13142-52-A ISI H-5 SpringlClamp;.. AUG I F1.10c 1 Feedwater -- - - -WN
.. PRE- -
ISiIVT/PE42.05.02 ISI-13142-52-A ISI- - s - - F-A 101200 F1.10c H-6 Spring Clamp AUG 1 Feedwaier OWN
- . PRE -
F-A 101249 ISI-13142-53-A isI F1.10c H-1 Spring . AUG 1 . Feedwater OWN
-*--PRE ---
F-A10-250 .- F-A 101250 ISI-13142-53-A sl- . F1.10c H- 2 Variable/ Spring AUG .. 1 Feedwater ,-. OWN
. - ... ------- P-. _.. ;
F-A 101252 ISI-13142-53-A ISI F1.10c H-4 Spring / Clamp AUG 1 Feedwater F 101254-PRE --- F-A 101254 ~ ISI-13142-53-A ISI F1.10c H-6 Spring Clamp AUG 1 Feedwater OWN 101360 ISI-73880-A ISI F-A F1.10c H- 1 Spring / Clamp AUG pOWN -. 1 Reactor Wtr Cleanup
. . . . . PfR.7 . . .P
. .
- L*. IbI-OZI 1M ,. ISI F1.A0c H-1 .. - , 1*. Clamp .-.. ; AUG
.1I Bottom Head Drain OWN PRE Printorl ve41700n
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 90 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class - Summary I ComplD I System Scope I Method I Procedure Code Case - 1 23 4 1 2 34 1 2 3 4 F-A 101619 ISI-821A - - - - - F1.10c H- 3 Clamp AUG 1 Bottom Head Drain OWN - - - - - . PRE . - .- . - F-A 101623 ISIVTIPEI-02.05.02 ISI-821A ISI-5 s F1.10c H-7 Clamp AUG I Bottom Head Drain OWN - - - - . PRE . . .. - - F-A 101853 ISI-97003-A .... F1.10c H- I Variable Spring AUG 1 RHR Return A OWN PRE F-A 101854 ISI-97003-A [Si - - - - - - - - - - - - F1.10c H-2 Variable Spring AUG 1 RHR Return A OWN PRE F-A 101895 ISI-97003-B 151 - - - - - F1.10c H-1 Variable Spr Clamp AUG 1 RHR Suction A OWN PRE - - F-A 101898 ISI-97003-B ISI . . . . . . . F1.10c H-4 Variable Slide/Clamp AUG - - . 1 RHR Suction A OWN - - . - - - .- PRE F-A 101899 ISI-97003-B ISI, . . . . . . . . . . . F1.10c H-5 Variable Slide AUG - - - - - - - . 1 RHR Suction A OWN - - - - - . PRE - - . - - . F-A 101933 ISI-97004-A ISI . . . . F1.10c H-1 Variable / Slide AUG - .... 1 RHR Return B OWN 14. PRE - - - - - . F-A 101934- - . ISINT/PEI-02.05.02 . ISI-97004-A, IsI S F1.10c . H-2 ,Variable/Slide/Clamp AUG : --- 1 RHR Return B OWN c PRE P /-n- - Printed 3/4/2005 0
( C Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3) . PC Page 91 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class . Summary I ComplD I System . . . Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 101975, ISINT/PEI-02.05.02 ISI-97005-A ISI C F1.10c H-1I Sway Brace . AUG 1 Recirculation A . .- OWN
-..-.-. .......... ....------ PRE.-
F-A 101978 . ISI-97005-A ISI . F1.10c H- 3 Sway Brace AUG
- 1. Recirculation A OWN
..- --PRE-F-A 102080 ISI-97006-A ISI 7 F1.10c H-2 Sway Brace AUG 1 Recirculation B OWN PRE --
F-A 102096 ISI-97006-A IS1 F1.10c H-1I Sway Brace AUG 1 Recirculation B OWN
. .. - - --- PR E - -
F-A 102194- .r ISI-97027-A ISI, F1.10c H-I Spring/Clamp AUG
- RHR Equalizer ,7 OWN ON 7.
PE- R-- -P -. . F-A 102197 . ISI/VT/PEI-02.05.02 ISI-97027-A ISI-s F1.10c H-4 Spring / Clamp AUG 1 RHR Equalizer OWN
* - PRE F-A 105022 ISINT/PEI-02.05.02 ISI-782A [SI - - - -
F1.10c H-17 Spring/ Clamp AUG 1 . Head Vent OWN
... . .. -PRE F-A 105024 PSIIVr/PEI-02.05.02 - ISI-782A-A ISI F1.1 0c H- 2 PSINT/PEI-02.05.02 Spring I Clamp AUG I Head Vent OWN PRE H h F-A - - : 107511, . ISiNTI/PEI-02.05.02 . ISI-131
- b. S .42-33-A i . Lu gs. ISI C -
F1.10c _ H-1 . .I Dbl Spring / 4 Lugs, AUG I. " , . . .. 1 Main Steam A OWN PRE Printed 3/4/2005
Monticello-Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 92 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class.. Summary / ComplD / System Scope / Method / Procedure Code Case 1 2 3 A I 2 .3 A I 2 3 A F-A 107512 ISI-13142-33-A ISI F1.10c H-8 Dbl Spring 4 Lugs AUG 1 Main Steam A OWN PRE . . F-A 107513 ISINT/PEI-02.05.02 ISI-13142-34-A ISI c - _ F1.1Oc H-1 Dbl Spring /4 Lugs AUG 1 Main Steam B OWN
-PRE- - -
F-A 107514. ISI-13142-34-A ISI - F1.10c H-5 Obi Spring 14 Lugs AUG - . Main Steam B OWN . F-A 107515 ISI-13142-35-A IPR -E_______-__ F1.10c H-I Dbl Spring /4 Lugs AUG - . 1 Main Steam C OWN - . PRE . F-A 107516 PSIVT/PEI-02.05.02 ISI-13142-35-A ISI F1.10c H- 5 Dbl Spring / 4 Lugs AUG 1 Main Steam C OWN - . PRE c F-A 107517 ISI-13142-36-A ISI . F1.10c H-I Dbl Spring 4 Lugs AUG . . . 1 Main Steam D OWN F-A 107518* ISI-13142-36-A E IPSR1 F1.10c H- 7 Dbl Spring / 4 Lugs AUG . 1 Main Steam D OWN . PRE F-A 107519 ISIiT/PEI-02.05.02 IS1-13142-52-A ISI - r- s - . F`1.10c H-3 Dbl Spring / 4 Lugs AUG - . 1 Feedwater OWN PRE EA 47E~fl ISI-13142-52-A 1SI - - - - a -'* IUI.ISIJ: H-B.' Dbl Spring /4 Lugs AUG - - - - F1.10c. OWN .C .- - . 1 rdae PRE C Prin4e,-1 '2 14 rMr,
C C C Monticello Nuclear Generating Plant 4th Interval ISI Plan. (Rev.3) ' Page 93 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2
- Period 3 Category, Iso No.
ltemNO, Comp. Desc. Scope I Method I Procedure Code Case 1 2 3 4 I 2 3 4 l 1 2 3 4 Class Summary I ComplD I System F-A 107521 ISI-13142-53-A ISI . F1.10c H-3 Dbl Spring l 4 Lugs AUG 1 Feedwater OWN
. .PRE - - - -
F-A 107522 ISINT/PEI-02.05.02 ISI-13142-53-A IS1 s Dbl Spring 4 Lugs AUG : F1.10c H-8 1 Feedwater OWN
........ . ........ . . . .. -.. .... .._ .. _........ ___PRE F-A 107523 ISINTIPEI-02.05.02 ISI-73880-A ISI . . . . s H-3 Dbl Spring / 4 Lugs AUG - .
F1.10c 1 Reactor Wtr Cleanup OWN - - ;
.. .... . PRE -.
F-A 107524 ISINT/PEI-02.05.02 ISI-97005-A [Si E - . F1.10c H-2 Dbl Spring l4 Lugs AUG - . 1 Recirculation A OWN
. PRE F-A 107525 ISI-97005-A ISI .
F1.10c H- 5 . Clevis I Lugs l Constant-Support AUG.
. OWN : : . : ;
1 Recirculation A .
~~PRE.-,
ISINVT/PEI-02.05.02 ISI-97005-A ISI c . : : ; ; F-A 107526 H-6 Clevis / Lugs / Constant-Support AUG - - ; F1.10c 1 Recirculation A OWN
.............................. PRE..
ISINT/PEI-02.05.02 ISI-97005-A IS1 E - - ; F-A 107527 F1.10c H-7 Double Spring AUG . 1 Recirculation A OWN - : PRE ISINTIPEI-02.05.02 .. ISI-97005-A IS1 c r - - - - . F-A 107529 F1.10c H-10 Dbl Spring /4 Lugs AUG - . 1 Recirculation A OWN PRE F-A. 107531 . . ISI-97005-B IS' F1.10c H-6 Spring I Lugs . AUG 1 Recirc Manifold A OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 94 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 ISI F.A 107532 ISI-97005-B F1.10c H-11 Spring / Lugs AUG . . . . . . . . I Recirc Manifold A OWN - .
.. PRE - - - - - .- - - - -
F-A 107543 ISINT/PEI-02.05.02 ISI-97006-A ISI c . . . . . . . . . F1.10oc H-3 Dbl Spring / 4 Lugs AUG 1 Recirculation B OWN - - - - - - - - . F-A 107544 ISI-97006-A ISI . . . . . . . . . . F1.10c H-5 Clevis / Lugs Constant-Support AUG 1 Recirculation B OWN PRE F-A 107545 ISI-97006-A ISI . . . . . . . . F1.10c H-6 Clevis / Lugs I Constant-Support AUG 1 Recirculation B OWN - . PRE - - - - - . F-A 107546 ISIVTIPEI-02.05.02 ISI-97006-A ISI c F1.10c H-7 Dbl Spring/ Lugs AUG I Recirculation B OWN - - - - - - - - . PRE - - - . F-A 107548 ISINT/PEI-02.05.02 ISI-97006-A ISI E - - - - - - - - - . F1.10c H-10 Dbl Spring AUG - - - - - - - - . 1 Recirculation B OWN . PRE - - - - - - - - F-A 107550 ISI-97006-B ISI - - - - F1.10c H-5 Spring/Lugs AUG . . . . . . . . . . . . 1 Recirc Manifold B OWN . PRE - - - . F-A 107551 ISI-97006-B ISI .- . F1.10c H-10 Spring / Lugs AUG . . . . . . I Recirc Manifold B OWN - - - - - . PRE . . . . . . . . .. F-A .100098 . ISI-13142-17-B IS! s F1.20a . H-I Rod /Clevis. AUG - - - -0
... t . .- -- - - -
2 HPCI Water Side Sctn OWN C PRE Printed 3/412005
C Monticello Nuclear Generating Plant ASME Section XI (1995 Edition, 1996 Addenda) 4th Interval 1St Plan (Rev.3) (May 1,20031to May 31, 2012) AC Page 95 of 332 Period 1 Period 2 :Period 3 Category, Iso No. ItemNO, Cormp. Desc.
. Scope I Method I Procedure . Code Case 1 23 4 1 23 4 1 2 3 A Class. -. Sunmiary I CompiD I System F-A 100100 151-314217-RestraintAU - - - - - - - - - - - -
F1.20a H.3
- 2. HPCI Water Side SctnOW ISI.13142-17-B 1 - - - - - - - - - -
F-A 100101 F1.20a H-4 Restraint OWN ---------- - - 2 .. HPCI Water Side Sctn 100169 ISI-13142-1 8-A IS1 F-A Box Restraint AUG - - - - - - - - - - - - F1.20a H- 2 OWN - - - - - - - - - - - - 2, RHR Discharge B PRE - - - - - - - - -- - ISI-13142-18-A ISI - --- - --- s - - - F-A 100171 . Box Restraint AUG - - - - - - - - - - - - F1.20a H-4 OWN - - - - - - - - - - - - 2.RHR Discharge B
.~PRE -
F-A 100176 ., - .ISI-13142-18-A ISI Seismic Restraint AUG - - - - - - - - - - - F1.20a H-l I 2 .. RHR~ Discharge B 8W
-,. -- R - 7 ..-. - - - - - -
-~O .
ISI-1 31 42-20-B I11 - - - - -- F-A 100364 Variable / Support AUG - - - - - - - - - - -- - F1.20a H-4 OWN - - - - - - - - - - - - 2 Core Spray B PRE ISI-13142-20-B IS1 - - - - s - - - - - - - F-A 100365 Variable I Support AUG - - - - - - - - - - - - F1.20a H-s5 OWN - - - - - - - - - - - - 2 Core Spray B PRE- -- - - - - - - - - 100876 ISI-1 31 42-40-A ISI F-A Box Restraint AUG - - - - - - - - - - - - F1.20a,.. H. 2 OWN - - - - - - - - - - - - 2 HPCI Water Side Dsch PRE - - - - - - - - - - - - 1U d(. I .. ISI-1 31 42-40-A Is' F1.20a .. H- 3 ,. Rod/IClamp AUG 2 HPCI Water Side Dsch OWN PRE Print~d 314r205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 96 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 100880 ISI-1314240-A IS . . . . . . . . . F 1.20a H- 6 Rod / Clamp AUG - - - - - - - . 2 HPCI Water Side Dsch OWN - - - - - - - - . PRE -- - - -- --- F-A 100881 ISI-13142-40-A ISI . . . . . . . . . . . F1.20a H-7 Rod /Clamp AUG - - - - - - - . 2 HPCI Water Side Dsch OWN - - - - - - - . PRE . - . . ... ... . ISI-13142.40-A iSI F-A 100883 F1.20a H-9 Rod / Clamp AUG 2 HPCI Water Side Dsch OWN PRE F-A 100884 ISI-13142-40-A ISI - - - - . FI.20a H-10 Rod / Clamp AUG - - - - - - - . 2 HPCI Water Side Dsch OWN - . PRE - - - - - - - - - - . F-A 100885 ISINT/PEI-02.05.02 ISI-13142-40-A ISI C - - - - - - - - - . F1.20a H-1I Rod / Clamp AUG - - - . 2 HPCI Water Side Dsch OWN - - - - - - - . PRE . F-A 100886 ISI-13142-40-A ISI . . . . . . F1.20a H-12 Rod / Clamp AUG - - - - - . 2 HPCI Water Side Dsch OWN - - - - - - - . PRE - - - -. - .. - - - . F-A 100888 ISI-13142-40-A ISI - - - - - - - - -- - . F1.20a H-14 Seismic Restraint AUG - - - - - - - - . 2 HPCI Water Side Dsch OWN - - . PRE . . . . . . . . . . . . F-A 100912 ISI-13142-40-B I . . . . . . . . . . . F1.20a H- I Rod / Clamp AUG - . 2 HPCI Water Side Dsch OWN - - - - - - - - . PRE - - . F-A 100914 ISI-1314240-B . ISI . . . . F1.20a H- 3 Seismic Restraint AUG 2 HPCI Water Side Dsch OWN PRE (.-. (. Printed 3/4/2005
C C 4th Interval ISI Plan (Rev.3) C Page 97 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I I 3 A I 2 3 A 1 2) 1 A Class .. . .. Summary / ComplD I System ... _ Scope I Method I Procedure Code Case ISINT/PEI-02.05.02 ISI-13142-40-B IS E s F-A 100916 .. F1.20a H-5 PSINT/PEI-02.05.02 Box Restraint AUG 2 HPCI Water Side Dsch OWN
~---~PRE F-A 100986 ISI-13142-42-A ISI F1.20a H-10 Rod/Clamp AUG 2 HPCI Steam OWN F-A 100988 ISI-13142-42-A [SI FI.20a H-12 Box Restraint AUG
- 2. HPCI Steam OWN PRE .
F-A 101708 - ISI-93268-4A ISI FI.20a H-7 Box Restraint AUG 2 CRD Scram HeaderA OWN
-. ,--.~ - - - -.. ,.. -. PRE - .-. -.- _....
F-A 101711 .;; . ISI-93268-1A ISI -- Fi.20a H-10 Restraint, AUG 2 CRD Scram Header A OWN . . F-A 101712 ISINT/PEI-02.05.02 ISI-93268-1A ISI c F1.20a H-1I Rod / Clamp AUG 2 CRD Scram Header A OWN
-- PRE---..-
ISI-93268-3A ISI . F-A 101802 . F1.20a H- 5 Box Restraint AUG 2 CRD Scram Header B OWN PRE F-A 101803 ISI-93268-3A ISI F1.20a H-6 Rod / Clamp AUG 2 CRD Scram Header B OWN PRE .
- -' . .. , u .
lW; i ' , : .,. . . Ib -V3Zbt-JA IsI F1.20a H-8 - . .- - . .; Box Restraint. ; AUG 2 CRD Scram Header B OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 98 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. S A n . 4 e e Class Summary / ComplD I System Scone I Method I .Procedure Code Case 4 n . e J 4 I F-A 101812 IS1-93268-3A ISI - - - - - - - - - - . F1.20a H-13 Box Restraint AUG - - - - - . 2 CRD Scram Header B OWN - - - . PRE . . . . . .- - - - - --- F- 1 F-A 106811 ISI-13142-19-B ISI - - - - - - - . F1.20a H-2 Restraint Hanger AUG 2 RCIC Steam Discharge OWN - - - - - - - PRE-F-A 106812 ISI-13142-19-B ISI . . . . . . . . F1.20a H- 3 Restraint Hanger AUG 2 RCIC Steam Discharge OWN - - - - . F- PRE - - - - - - - . F-A 10i813 ISI-13142-19-B ISI - - - - - - - - . F1.20a H- 4 Restraint Hanger AUG - - - - - - - . 2 RCIC Steam Discharge OWN PRE - - - - - - - F-A 106814 ISINTIPEI-02.05.02 ISI-13142-19-B IS1 - - - - - - - - s - . F1.20a H- 5 Restraint Hanger AUG 2 RCIC Steam Discharge OWN - - - - - - - - . F- 085PRE - - F-A 106815 ISI-13142-19-B 15 F1.20a H- 6 Restraint Hanger AUG - - . 2 RCIC Steam Discharge OWN - - - - - - - - . PRE . . . . . . . -. . .... . F-A 106821 ISI-13142-26-B ISR - - - - - - - - F1.20a H-2 Restraint Hanger AUG - - - - - - - . 2 CORE SPRAY B OWN - - - - - - - - - - . PRE - - - - - - - - - - . F-A 106822 ISI-13142-26-B ISI . . . . . . . . . . . . F1.20a H- 3 SEISMIC RESTRAINT HANGER AUG - - - . 2 CORE SPRAY B OWN - - - - - - - - - - . PRE - - - - - - - F-A F1.20a
^R.^^^
10623l
- H-4, . .
ReS Itrant a Restraint Hanger ISI AUG
. -~~
2 CORE SPRAY B OWN ( PRE Printed 34/42005
C C Monticello Nuclear Generating Plant 4th Interval ISI Plan. (Rev.3) Pasle 99 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Peio I Peio . .2 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 2 3 A I 2 A A 1. 2 3 A Class Summary I ComplD I System Scope I Method I Procedure Code Case ISI-13142-26-B ISI F-A 106824 . . - F1.20a H-5 SEISMIC RESTRAINT HANGER AUG 2 CORESPRAYB OWN
.. . PRE - .. . . -
ISI-13142-26-B ISI s F-A 106825 . RESTRAINT HANGER TWH-121 AUG ; F1.20a H-6 OWN 2 CORE SPRAY B
- . .. .. ..__-- PRE--- .. - -.- :.
F-A 106826 . ISI-13142-26-B IS1 F1.20a H-7 SEISMIC RESTRAINT SR-646 AUG 2 CORE SPRAY B OWN F-A 106827 - ; . ISI-13142-26-B ISI FI.20a H- 8 RESTRAINT HANGER TWH-102 AUG . 2.. CORE SPRAY B OWN PRE, - F-A 106830 ISI-13142-26-C ISI F1.20a H- I Restraint Hanger AUG
.WN : : : : : :
2 CORE SPRAYB
- - . . . . ,.-.... .... ...-.iPRE -.... .-.. -_-
F-A 106831 ISI-13142-26-C ISI F1.20a H-2 Seismic Restraint AUG 2 Core Spray B Discharge OWN
. PRE .
F-A 106832 ISINTIPEI-02.05.02 ISI-13142-26-C ISI c r . - F1.20a H- 3 Restraint Hanger AUG Core Spray B Discharge OWN - . 2 PRE- - F-A 106833 - ISI-13142-26-C ISI F1.20a H-4 Seismic Restraint AUG . 2 Core Spray B Discharge OWN PRE
.a I r1-M 1nn I uoj- . .ISI-13142-26-C . ISI F1.20a H 5 . - : SEISMIC RESTRAINT SR-647 AUG 2 Core Spray B Discharge OWN PRE Printed 3M42005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 100 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. lb A I A I 4 ., e j Class . Summary I ComplD / System Scone I Method I Procedure Cnde Case 4 I4_ & j 1 A a 4 F-A 106I35 ISI-13142-26-C ISI F1.20a H- 6 Restraint Hanger AUG 2 Core Spray B Discharge OWN PRE -_-_-_-_-_- _-_-_-_-_- F-A 106836 ISINT/PEI-02.05.02 ISI-13142-26-C ISI c r - - F1.20a H-7 Seismic Restraint AUG 2 Core Spray B Discharge OWN PRE - - - - - F-A 106837 ISI-13142-26-C ISI- - F1.20a H- 8 Seismic Restraint AUG 2 Core Spray B Discharge OWN F-A 106838 ISI-13142-26-C ISI -- F1.20a H-9 Restraint Hanger AUG 2 Core Spray B Discharge OWN F-A106 47PRE F-A 106H47 ISI-13142-26-D [Si E F1.20a H- I Restraint Hanger AUG 2 Core Spray B Discharge OWN F- 080PRE 106850 ISI-13142-31-B ISI E s F-A F1.20a H-1A Seismic Restraint AUG 2 Core Spray A Discharge OWN F- 08!PRE isi - - F-A 106851 ISI-13142-31-B F1.20a H-1B Restraint Hanger AUG 2 Core Spray A Discharge OWN PRE . . . . . . . . . . . F-A 106852 ISI-13142-31-B ISI F1.20a H-1C Restraint Hanger AUG 2 Core Spray A Discharge OWN ___ _ _A_ PRE F-A 106RE3
-4_,,
1s1-1 R14z-s1-ta lSI Seismic Restraint AUG F1.20a 2 H-1D Core Spray A Discharge OWN PRE (. rC Printed 3/4/2005 2
C. C 4th Interval ISI Plan (Rev.3) C Page 101 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary I ComplD I System Scope I Method I Procedure Comp. Desc.
Code Case I1 2 3 4 ~1I2 3 A4 1 2 It A F-A 106854 . . ISI-13142-31-B ISI F1.20a H-1 E Restraint Hanger AUG 2 Core Spray A Discharge OWN F-A 106860 . ISI-13142-31-C ISI F1.20a H-i . Restraint Hanger AUG 2 Core Spray A Discharge OWN PRE- - . --. F-A 106861 I-13142-31-C II.. ISI F1.20a H-2 Seismic Restraint AUG 2 Core Spray A Discharge OWN
.. .. PRE F-A 106862 ISI-13142-31-C 5is F1.20a H-3 Restraint Hanger AUG 2_. Core Spray A Discharge OWN ....-. P..--.RE .
F-A 106863 , ISI-13142-31-C is . F.20a H4 Seismic Restraint AUG 2 Core Spray A Discharge OWN
...... RE-P...... ....-- .-. - -
F-A 106864 . ISI-13142-31-C i S-F1.20a H-5 Restraint Hanger AUG 2 Core Spray A Discharge OWN
. .... . . . . .- PRE F-A 106865 ISI-13142-31-C ISI F1.20a H-6 Seismic Restraint AUG
- 2. Core Spray A Discharge OWN PRE F-A 106866- ISI-13142-31-C ISI F1.20a H-7 Restraint Hanger AUG 2 Core Spray A Discharge OWN PRE -_-_-_-_-_-_-_-_-_-_-
1SI - - - - F1.20a . H-88 . Restraint Hanger AUG 2 Core Spray A Discharge OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 102 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I v A I . I . Class Summary I ComplD I System Scope I Method I Procedure Code Case q A 1 v2 - F-A 106880 ISI-13142-31-D ISI . F1.20a H- 1 Restraint Hanger AUG 2 Core Spray A Discharge OWN . PRE F-A 106881 ISI-13142-31-D ISI . F1.20a H-2 Restraint Hanger AUG 2 Core Spray A Discharge OWN
-PRE -- - .-
F-A 106890 ISI-1314241-A ISI RE F1.20a H- 1 Restraint Hanger AUG 2 RCIC WATER SUCTION OWN PRE -= F-A 106891 ISI-13142-41-A ISI F1.20a H-2 Restraint Hanger AUG . 2 RCIC WATER SUCTION OWN PRE . . . . . . . . . . . . F-A 106895 ISI-13142-48-A ISI F1.20a H-I Restraint Hanger AUG OWN - - . 2 RHR SERVICE WATER F-A 106896 ISUVT/PEI-z2.05.02 ISI-13142-48-A PSR!E c. F1.20a H-2 PSINTIPEI-02.05.02 Restraint Hanger AUG 2 RHR SERVICE WATER OWN - - - - - - - - - - . PRE . . ISI-13142-4A ISI . . . . . . . . . . . . F-A 106897 H-3 Restraint Hanger AUG - - - - - - - . F1.20a 2 RHR SERVICE WATER OWN F-A 106898 ISI-13142-48-A IPsRE F1.20a H- 4 Restraint Hanger AUG - . 2 RHR SERVICE WATER OWN PRE . . . Res-1trn Ha4ngA ISI F1.20a H- S! Restraint Hanger AUG - - 3 2 RHR SERVICE WATER ( OWN PRE Printed 3/412005
(2 Monticello Nuclear Generating Plant C 4th Interval ISIPlan (Rev.3)
- Page 103 of 332 I.ASMVE Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to, May 31, 2012)
Period ¶ Period 2 Period 3 Category, Iso No. IternNO, Comp. Desc. Class Summary I CompiD I System Scope I Method!I Procedure Code Case 1 23 4 1 2 3 4 1 23 4 F-A 106900 ISI-13142-48-A. S - - - - - - - - - - - - F1.20a H6 Seismic Restraint AUG - - - - - - - - - - - - 2,,l RHR SERVICE WATER OWN- - - - - - - - - -
...... PRE F-A 106901 ISI-13142-48-A [Si - - - - - - - - - - - -
F1.20a H- 7 Restraint Hanger AUG . . . . . . . . . . . . 2 RHR SERVICE WATER OWN - - - -- - - - -
. -. ~. . .. .~.PR E.- -
F-A 106902 ISI-13142-48-A 181 . . . . . F1.20a H-8 Seismic Restraint AUG - - - - - - - - - - - - 2 RHR SERVICE WATER OWN - - - - - - - -
- - -PRE F-A 106910 ISI-13142-48-B ISI F1.20a H- I Seismic Restraint AUG - - - - - - - - - - - -
2 RHR SERVICE WATER OWN - - - - - - - - - - - -
.. . -... PRE F-A 106911 ISI-13142-48-B ISI - - - - - - - - - - - -
F1.20a H.-2 Seismic Restraint AUG 2 RHR SERVICE WATER ,OWN - - - - - - - - - - - -
. .. .. -... ..-. PRE.
F-A 106912 ISI-13142-48-B [Si - - - - - - - - - - - F1.20a H-3 Seismic Restraint AUG- - - - - - - - - - 2 RHR SERVICE WATER OWN - - - - - - - - - - - -
. .PRE - - - - - - - - - - - -
F-A 106913 ISINVTIPEI-02.05.02 ISI-13142-48-B Is[ c - - - - - - - - - - - F1.20a H- 4 Seismic Restraint AUG .-- - - - - 2 RHR SERVICE WATER OWN - PRE - - F-A 106914 . S.15-13142-48-B ISI - - - - - F1.20a H-5 Seismic Restraint AUG - - - - - - - - - - - - 2 RHR SERVICE WATER OWN - - - - - -- PRE - - - - - F-A 106915 ISI-13142-48-B 151 Fl .20a H- 6 Restraint Hanger . AUG 2 RHR SERV'ICE WATER OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval SI Plan (Rev.3) Page 104 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.
.I . e 7 s Class Summary I ComplD I System Scope I Method / Procedure Cnde Case 4 n I F-A 106916 ISI/VT/PEI-02.05.02 ISI-13142-4-B ISI c -
Restraint Hanger AUG - - - - - . F1.20a H-7 RHR SERVICE WATER OWN - - - - - . 2 PRE F-A 106920 - - F0A 106920 ISI-13142-51-A ISI - - - . - .- - - H-2 Restraint Hanger AUG - - - - - . F1.20a 2 RHR A OWN - - - - - - - - - - - - F.....A.. 106921..... PRE......... F-A 106921 ISI-13142-51-A ISI . . . . . . . . Seismic Restraint AUG - - - - - - - . F1.20a H- 3 OWN - . 2 RHR A PRE - - - . - - - . F-A 10692 ISI - - -. F-.2A 1069 ISI-13142-51-A F1.20a H-4 Restraint Hanger AUG OWN - . 2 RHR A PRE ------------ F-A 106923 ISI-13142-51-A 1PSI -- F-A 19 F1.20a H-5 Seismic Restraint AUG OWN 2 RHRA .. OWN . . . . . . .... 1624. ISI-13142-51-A 1-- - . . . . . . F12A 10692 F Fl.20a H 6 Restraint Hanger AUG OWN 2 RHRA PRE - - - - - - - - ISI-13142-51-C ISI -s - - .-- F-A 106946 Restraint Hanger AUG - . . . . . . F1.20a H- 1 OWN - - - - - - . 2 RHR B PRE . . . . . . F-A 106947 IS1-13142-51-C ISI- - - - - - - . Seismic Restraint AUG . . ; F1.20a H-2 OWN - . 2 RHR B
-PRE F-A 14o Sei -a
-1 i14z-Re 'SI - - - -
F1.20a H-3 . Seismic Restraint AUG 2 RHR B OWN - PRE (S: Printed 3/4/2005
C C 4th Interval 1S1 Plan (Rev.3) Page 105 of 332 Monticello Nuclear Generating Plant
-ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 200310o May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Como. Disc. Class Sumnmarv I CompiD I Systemn Scope!I Method I Procedure Code Case 1 23 4 1 23 41 1 2 34 F-A 106949 I SI-13142-51-C Iis - - - - - - - - - - - - F1.20a H-4' Restraint Hanger AUG - - - - - - - - - - - - 2 RHR B OWN7
..-.-..... - PRE F-A 106971 . , SI-13142-51-D I15 - - - - -
F1.20a H-if Restraint Hanger AUG - - - 2RHR B OWN - - - - - - - - - - - -
- .- ... . .... .. -P R E-.- --
F-A 106972 ,ISI-13142-51-D Iis- - - - - - - - - - - - FI.20a H2 Restraint Hanger AUG: 2 RHR B OWN - - - - - - - - - - - -
-... PRE F-A 106973 ISI-13142-51-D ISi FI.20a H-3 Seismic Restraint AUG - - - - - - - - - - - -
2 RH R B OWN - - - - - - - - - - - -
- - . ..-.-...- PRE------
F-A 106974 ISI-13142-51-D -I - 77i F1.20a H- 4 Restraint Hanger AUG . . . . . . . . . . . .
- 2. RHR B OWN - - - - - - - - - - -
F-A 106980 .ISI-13142-62 MISI . . . . .. F1.20a HI Restraint Hanger AUG - - - - - - 2 Fuel Pool Emergency Coaling OWN - - - - - - - - - - - - F-A 106981 . .ISI-13142-62 I1 - -s-- . . 01.20a H- 2 Restraint Hanger AUG - - - - - - - - - - - - 2., Fuel Pool Emergency Cooling OWN - - - - - - - - - - - -
.. . ... .PR E - - - - - - - - - - - - -
F-A 106982 - ISI-13142-62 [Si - ;. . . . .- FI1.t0a H- 3 Seismic Restraint AUG - - - - - - - - - - - - 2 Fuel Pool Emergency Cooling OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - F-A- 106983 . .. . ,,"-" ,~ : '.-ISI-13142-62 . . [Si F1.20a 11Restraint Hanger. , AUG 2 I Fuel Pool Emergency Cooling OWN PRE Printed 3!4N20O5
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 106 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 I 2 3 4 F-A 106984 ISI-13142-62 ISI - - - - . F1.20a H- 5 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN PRE . F-A 106985 ISI-13142-62 ISI F1.20a H-6 Seismic Restraint AUG 2 Fuel Pool Emergency Cooling OWN PRE . . F-A 106986 ISI-13142-62 ISI F1.20a H-7 Seismic Restraint AUG 2 Fuel Pool Emergency Cooling OWN - . PRE F-A 106990 ISINT/PEI-02.05.02 ISI-13142-67 ISI c - F1.20a H- I Restraint Hanger AUG - - - - . 2 Fuel Pool Emergency Cooling OWN - - - - - - - - . PRE - - - - . F-A 106991 ISI-13142-67 ISI - - - - - - - - . F1.20a H-2 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN - . PRE . F-A 106992 ISI-13142-67 ISI F1.20a H-3 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN PRE F-A 106993 ISI-13142-67 ISI - - - - - . F1.20a H-4 Restraint Hanger AUG - - - . 2 Fuel Pool Emergency Cooling OWN - - - - - - . PRE F-A 106994 ISINT/PEI-02.05.02 ISI-13142-67 ISI s F1.20a H-5 Restraint Hanger AUG 2 Fuel Pool Emergency Cooling OWN PRE - - - - . F-A 106995 - . . ISI-13142-67 ISI F1.20a H-6 . '!'" Restraint Hanger . AUG 2 Fuel Pool Emergency Cooling OWN ( S. . PRE Printed 314/2005
C. C Plan. (Rev.3) (C Page 107 of 332 Monticello Nuclear Generating Plant 4th Interval 151 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May. 31, 2012) Period I Period 2 Period 3 Category, Iso No. itemNO, Comip. Desc. Class'..- Summary/IComploIDSystemn Scope I Method!I Procedure Code Case 1 23 4 1 2 3 4 1 23 4 F-A 106996 ISI.13142-67 ISI F1.20a H- 7 Seismic Restraint AUG - - - - - - - - - - - - 2 Fuel Pool Emergency Cooling OWN7 - - - - - - - - - -
. .P RE _ _ _ _ _ __ __
F-A 106997 ISI-13142-67 Is[ F1.20a H-8 Restraint Hanger AUG - - - - - - - - - - - - 2 Fuel Pool Emergency Cooling OWN-
...- . . . - -. ~PRE ~ _ _ _ _
F-A 106998 11-i31 42-67 ISI I1St - - - - -- FI.20a H- 9 Restraint Hanger AUG - - - - - - - - 2 . Fuel Pool Emergency Cooling OWN - - - - - - - - - - - -
.- . PRE . - - -
F-A 106999 ISI-13142-67 [Si F1.20a H-10 Seismic Restraint AUG - - - - - - - - - - - - 2, Fuel Pool Emergency Cooling OWN - - - - - - - - - - - -
.. - . ~PRE -. . -
F-A 107028 ISI-13142-37-D I1S FI.20a H- I Restraint Hanger AU1G' 2RHR A O N -- - - -. - - F- 1 70 9 S -13142-37-D ISI FI.20a H-2 Restraint Hanger AUG - - - - - - - - - - - - 2 RHR A OWN-
- . . .. - ~
. . -. - - - . - .P RE - . - . . . . -
F-A 107048 ISI-13142-37-E ISI F1.20a H- I Restraint Hanger AUG . . . . . . . . . . . 2 RHR A OWN - - - - - - - - - - - -
- .. . -PRE F-A 107050 151-I31i42-37-E [Si F1.20a H-3 Restraint Hanger AUG - - - - - - - - - -
2 RHR A OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - F-A - .,107587 . 5IS-93268-IA _ ISI F1.20a H-20 Tank Support AUG 2 CR0 Scram Header A OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 108 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 F-A 107588 ISI-93268-3A IS1 F1.20a H- 7 Restraint /4 Lugs AUG 2 CRD Scram Header B OWN PRE-- - F-A 107589 ISIVTIPEI-02.05.02 ISI-93268-3A ISt s . . F1.20a H-14 Tank Support AUG 2 CRD Scram Header B OWN PRE-- - F-A 107600 ISI-13142-18-B IS1 F1.20a H-2A Seimic Restraint AUG 2 RHR Discharge B OWN PRE F-A 107603 ISI-13142-51-A ISI F1.20a H-7 Restraint Hanger AUG 2 RHR A OWN PRE F-A 100056 ISI-13142-17-A ISI F1.20b H- I Strut / Clamp AUG 2 RHR Suction A OWN PRE F-A 100057 ISI/VT/PEI-02.05.02 ISI-13142-17-A ISI c r F1.20b H-2 Slide / Clamp AUG 2 RHR Suction A OWN PRE F-A 100058 ISI.13142-17-A ISI F1.20b H-3 Slide Pipe AUG 2 RHR Suction A OWN PRE F-A 100059 IS1I13142-17-A ISI F1.20b H- 4 Strut I Clamp AUG . 2 RHR Suction A OWN PRE ISI-1 3142-17-A ISI - - - - F-A 100065 Slide AUG - - - - F1.20b H- 8 OWN . . . . 2 RHR Suction A I,- ( PRE Prinleri 3J412005
(7 C C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 109 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) . (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. fCIte S.I mm2rw / rnmnIn i Svstem Scone I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 100066 ISI-13142-17-A ISI F1.20b H-9 Slide AUG 2 RHR Suction A OWN -
. - PRE.
F-A 100129 ISI-13142-17-C ISi - - - . F1.20b H- 2 Slide AUG 2 RHR Suction B OWN
.- - . ,.PRE F-A 100130 ISI-13142-17-C ISI FI.20b H-3 Slide AUG 2 . RHR Suction B OWN
. - .- . . PRE F-A 100131 ., ISI-13142-17-C Is' - - - - - - - -
Slide AUG - - - - . . . . F1.20b H- 4 OWN - - - - - - - -
- 2. RHR Suction B - ' - 7
- PRE, F-A 100132 ISI-13142-17-C ISI -
F1.20b H- 5 Strut I Clamp AUG 2 RHR Suction B ... .. OWN 7 7 7
- . PRE-F-A 100174 ISI-13142-18-A iSI F1.20b H- 7 Strut I Clamp AUG 2 RHR Discharge B OWN
.- PRE--
F-A 100209 ISI-13142-18-B ISI F1.20b H-3 Strut Clamp', AUG
- 2. RHR Discharge B OWN
. PRE-F-A 100246 ISI-13142-18-C ISI F1.20b H-1 Strut / Clamp AUG 2 RHR Discharge B OWN PRE F-A 100263 ISI-13142-19-A Ibi F1.20b .. . H-1. .. I . ... .
Snubber / Clamp
.. .. . . I AUG 2 HPCI Steam Disch OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 110 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Scope / Method I Procedure Code Case I 2 A A I 1 2 I A 4 :2 - Class Summary I ComplD I System ISVr/PEI-02.05.02 ISI-13142-19-A ISI c r . . . . . . . . . F-A 100264 F1.20b H- 2 Dbl Snubber / Clamp AUG . . . . . . . . OWN - - - - - - - - . 2 HPCI Steam Disch PRE . . . . . . . . . . . .
.. A 1 ISI-13142-19-A ISI - - - - - - - .-
F-A 100267 F1.20b H-4 Strut / Clamp AUG - - - . OWN - - - - - - - - . 2 HPCI Steam Disch F.A . 100269
.PPRE..
F-A 100269 ISI-13142-19-A ISI . . . . . . . . . . . . Strut / Clamp AUG - - - - - - - . F1.20b H-6 OWN - - - - - - - - . 2 HPCI Steam Disch PRE - - - - - - - - - - . F-A 100272 ISI-13142-19-A IS1 F1.20b H- 8 Strut / Clamp AUG . 2 HPCI Steam Disch OWN F. 023PRE ISI - - . F-A 100273 ISI-13142-19-A F1.20b H-9 Strut / Clamp AUG 2 HPCI Steam Disch OWN - - - . PRE - - - - - - - - - - --- _ 0 ISII/ ISI-13142-20-A ISI- - - - - - - - s F-A 100332 H- 2 Slide AUG - - - - - - - . F1.20b Core Spray A OWN - - - - - - - . 2 PRE . . . . . . .. . . . . H0033 ISI-13142-20-A ISI 1.2G Snu bber A UG- - - - - - - - - - - - F12 0 Co e pr y 2 Core'Spray A ~~~OWN - - - - - - - - - - - - ISI-13142-20-A ISI . . . . . . . . F-A 100335 F1.20b H- 5 Strut / Clamp AUG - - - - - . 2 Core Spray A OWN - - .
~ PRE ._ . . .. . . .
F-A 100362 Pslmrrip 0ni i
- . vv. .
... 1V1*
lSI F1.20b H-2 *. wWwr; Slide Hanger AUG 2 Core Spray B OWN PRE Pr i .4 I s Prined 3/4/2005
C C 4th Interval IS1 Plan, (Rev.3) Page 111 of 3-32 Monticello Nuclear Generating Plant ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, iso No.
- ltirmNO, Class. ..- Summary I CompiD I System . .,Scope!/ Method!I Procedure Comnp. Desc.
Code Case 1 23 4 1 2 3 41 1 23 4 ISI-13142-20-B ISI - - - - - - - - - - - - F-A 100363 Snubber IClamp AUG - - - - - - - - - - - - F1.20b H-3 OWN - - - - - - - - - - - -
- 2. Core Spray B
.. . - PRE -
F-A 100515 ISI-13142-31-B ISI FI.20b H- I Valve Strap AUG 2- Core Spray A OWN F-A 100784 PSiffrIPEI-02.05.02 ISI1-13142-37-A IS[1 F1.20b H- 3 Snubber AUG 2.~ RH R Discharge A OWN
-PRE- C F-A 100786 ,. ISI-1 31 42-37-A ISI Dbi Strut!/ Clamp AUG - - - - - - - - - - - -
F1.20b H-5 OWN - - - - - - - - - - - - 2RHR Discharge A
.- ~ PRE F-A 100787. , 5-1 31 42-37-A IS,, ISI -
F1.20b H-6 Strut /Clamp AUG~ 2.- RHR Discharge A OWN F-A 100823 . .ISI-13142-37-B I1 1 - - - - -- Strut! Clamp AUG - - - - - - - - - - - - FI.20b H-8 OWN - - - - - - - - - - - - 2 . Containment Spray
...... PRE -
100825 ISI-13142-37-B 151 - - - - - F-A Dbi StrutlDbi Clamp AUG - - - - - - - - - - - - F1.20b H-10 OWN - - - - - - - - - - - - 2, Containment Spray PRE F-A 100850 . S. i3142-37-C IS! Dbl Strut!/ Snubber AUG - - - - - - - - - - - - F1.'2bb H.-4 2 RHR Discharge A OWN --- PRE - - - - - - - - - - - - F-A . - - 100851 . ..- ; -;~~.
, . ::, ;, ~ ..
*.1 ISI-1 31 42-37-C-- IS'
, . Dlb! Strut!/ Clamp , , AUG F1.20b, . H- 5-: "
2 RHR Discharge A OWN PRE Printed 314!2005
Monlicello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 112 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category. Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 F-A 100878 ISI-13142-40-A ISI F1.20b H- 4 Strut / Clamp AUG - - - - - - . 2 HPCI Water Side Dsch OWN - - - - - - . PRE - - - .- . F-A 100879 PSINTIPEI-02.05.02 ISI-13142-40-A ISI - - - - - - - . F1.20b H- 5 Snubber / Clamp AUG . 2 HPCI Water Side Dsch OWN - - - - - - . PRE - s - - F-A 100882 ISI-13142-40-A ISI - - - - - - . F1.20b H- 8 Strut / Clamp AUG 2 HPCI Water Side Dsch OWN - - - - - - . PRE F-A 100887 ISI-13142-40-A ISI - - - - - - . F1.20b H-13 Strut / Clamp AUG - . - ... 2 HPCI Water Side Dsch OWN - - - - PRE F-A 100913 ISI-13142-40-B ISI F1.20b H-2 Strut / Clamp AUG - - - . 2 HPCI Water Side Dsch OWN - - - - - - .
....... -...... *. . ... .... .PRE F-A 100919 ISINT/PEI-02.05.02 ISI-13142-40-B ISI E .
F1.20b H-7 PSINVTPEI-02.05.02 Strut / Clamp AUG - . - ... 2 HPCI Water Side Dsch OWN - - - - - - - . PRE . . . . . . F-A 100921 ISINTIPEI-02.05.02 ISI-13142-40-B ISI c - . F1.20b H-8 PSIIVrTPEI-02.05.02 Strut / Clamp / Box AUG . . . . . . . . 2 HPCI Water Side Dsch OWN - - - - - - - . PRE . . . . F-A 100924 ISI-13142-40-B ISI - - - - . F1.20b H-1I Strut / Clamp AUG . . . . . . . . 2 HPCI Water Side Dsch OWN PRE . . . . . . . F-A . 100925 ISI-1314240-B IS' F1.20b H-12 . Strut / Clamp AUG 2 HPCI Water Side Dsch OWN ( PRE . I . . Printed 3/4/2005
c: CC (. Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) I . ..Page 113 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 i Period 3 Category, Iso No. ItemNO, Comp. Desc.
- Summary / ComplO / System .Scope I Method /Procedure ....- Code Case I I I A 1 I I A 4 *2 q A Class . -....
F-A 100980 -. ISI-13142-42-A ISI . F1.20b H- 4 DbI Strut/Dbl Clamp AUG 2- HPCI Steam , - OWN _.... -.-.-- PRE,- - .... ------ F-A 100985.-. ISI-13142-42-A ISI. F1.20b H- 9 Strut Clamp AUG 2 HPCI Steam * .OWN
....-..-. ~~-- PR E _ _ _ _ _ _ _ _ _
F-A 100987 PSINT/PEI-02.05.02 ISI-13142-42-A ISI - -. F1.20b H-1I PSINr/PEI-02.05.02 Snubber/Clamp AUG 2 HPCI Steam PSINVT/PEI-02.05.02 OWN PSINTIPEI-02.05.02 PRE B b - - -- ISI-13142-49-A ISI -. - - - - s F-A 101106 F1.20b H-3 Dbl StruVDbl Clamp AUG 2 RHR Suction A OWN
.PRE--
F-A 101107 -. ISI-13142-49-A ISI-F1.20b H- 4 Snubber / Clamp:. AUG . - - 2 RHR Suction A .O ;.N O WN. --
.-.------.....-.....-- ~'~ PRE--~--.
F-A 101110 ISINTIPEI-02.05.02 ISI-13142-49-A ISI c r - - Dbl StrutVDbl Strut AUG ; F1.20b H-7 2 RHR Suction B OWN PRE - - . - 101113 ISINT/PEI-02.05.02 ISI-13142-49-A ISI c r - - F-A F1.20b H-10 PSINT/PEI-02.05.02 Snubber/Clamp AUG 2 RHR Suction B OWN PRE - .. . .... F-A. 101114 PSINTIPEI-02.05.02 ISI-13142-49-A ISI F1.20b - H-1I Slide AUG 2 RHR Suction B OWN _ PRE - s c a. nsna. .- .- .._ .. - .- ISI-13142-51-A . ISI F1.20b : H- I . .Snubber / Dbl Strut AUG 2 RHR A OWN PRE Printwd 3f4f2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 114 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Code Case 1 2 3 A I 2 3 A I 2 3 A Class Summary I ComplD I System Scope I Method I Procedure F-A 101165 ISI-13142-51-B ISI - . F1.20b H- 1 Strut I Clamp AUG . . 2 Containment Spray OWN - - - . PRE - - - F-A 101169 ISI-13142-51-B ISI - - - - - - - - . F1.20b H- 4 Strut I Clamp AUG - - - - - . 2 Containment Spray OWN - - - - - - - .
- ~~~ ~~~PRE
. . . . .^. . .. _ ..
F-A 101170 ISI-13142-51-B ISI . . . . F1.20b H-5 DbI StrutUDbl Clamp AUG 2 Containment Spray OWN F-A 101173 ISI-13142-51-B IPSR1 E F1.20b H-8 Strut I Clamp AUG - - . 2 Containment Spray OWN PRE - - - - - - - - - - - - F-A 101709 ISI-93268-IA isi E F1.20b H- 8 Strut I Clamp AUG 2 CR0 Scram Header A OWN F-A 101710 ISIVT/PEI-02.05.02 IS1-93268-IA ISI . . . . s F1.20b H-9 Strut I Clamp AUG 2 CRD Scram Header A OWN - - - - - - . PRE . . F-A 101713 PSINT/PEI-02.05.02 ISI-93268-1A ISI - . F1.20b H-12 Snubber/ Clamp AUG . 2 CRD Scram HeaderA OWN . PRE s - - - - - - - - . F-A 101714 IS1-93268-1A ISI - - F1.20b H-13 Strut I Clamp AUG . . . V.. 2 CRD Scram Header A OWN 171s FA PRE rQUV I1rr1-Uz.UD.Uz
- 11-LZUM-1A IS' F1.20b H-14,. Snubber I Clamp AUG . . 3. 2.
2 CRD Scram Header A OWN ( PRE s - Printed 3/4/2005
Monticello Nuclear Generating Plant
*C 4th Interval ISI Plan (Rev.3) Pge 115 of 332 .,ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May, 31, 2012)
IPeriod' 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 2 3 4 I 2 3 A 1 2 3 A Class Summary I Compil) I System Scope I Method!I Procedure Code Case ISI-94966-A S. . . . . . . . . . . . F-A 106041 Double Rigid Strut AUG - - - - - - - - - - - - F1.20b H-I OWN - - - - - - - - - - - 2Vacuum Relief & CGCS Outlet Div.1 1S1-94966-A 1 is1 - - - -- F-A 108042 F1.20b H- 2 Snubberl/Clamp AUG' Vacuum Relief & CGCS Outlet DM1A OWN
- ~_PRE..
F-A 108043 ISI-94966-A ISI-s - - - DbI Spring I U-bait AUG - - - - - - - - - F1.20b H-3 OWN - - - - - - - - - 2 Vacuum Relief & CGCS Outlet DMv1
- PRE - - - - - - - - - - -
S-46 A S - - - - - - - - - - - - F-A 106044 Snubber IClamp AUG - - F1.20b H'-4 2 Vacuum Relieft& CGCS Outlet DMv1 .OWN PR E . -_- -_ -_ _- - _- _ F-A 108046 ISI-94966-A ISI, F1.20b H.-6 Dbl Strut I U-bait AUG 2' Vacuum Relief & CGCS Outlet DMv1 .~OWN
-~ ~ - - - - ~ - - - - . ~ ~
. .. P RE -
108052 ISI-94966-B Isi - - - - - F-A F12b H1DbI Strut IU-bolt AUG - OWN - - - - - - - - - - - 2 Containment Air Purge
.PRE - - -- - - - - - - - -
1S1-94966B ISI - - - - - - - - - - - - F-A 106053 FI.20b H-'2 Strut! Clamp AUG 2' Containment Air Purge OWN-- F-A 106065. ISI-94699-A . PR-E -- 7 - - Double Snubber AUG . . . . . . . . . . . . F1.20b' 1--1/1--2 OWN - - - - - - - - - - - - 2 CGCS OUTLET DIV 2 PRE - - - - - 1-A ISI-1 05531-A IS' F1.20b. H-i' Base Plate' ,. - ' AUG 2 Standby'Gas Trtmnt & Rx Plenum OWN PRE Printed 3141205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 116 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Class Summary i ComplD / System Scope i Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 106097 151-158074-A IS! F1.20b H- I Hanger AUG 2 Torus HPV OWN - - - - PRE F-A 106810 PSI/VT/PEI-02.05.02 ISI-13142-19-B ISI . . . F1.20b H- 1 Double Snubber AUG 2 RCIC Steam Discharge OWN PRE - s F-A 106820 PSUVT/PEI-02.05.02 ISI-13142-26-B ISI . . . . F1.20b H- I Snubber AUG 2 CORE SPRAY B OWN - . PRE - s F-A 106950 PSINT/PEI-02.05.02 ISI-13142-51-C ISI F1.20b H-5 Seismic Snubber AUG - - - - . 2 RHR B OWN . PRE c F-A 107030 PSINTIPEI-02.05.02 ISI-13142-37-D ISI - - - - . F1.20b H-3 PSUVTIPEI-02.05.02 Double Snubber AUG 2 RHR A OWN PRE - s F-A 107049 ISI-13142-37-E ISI F1.20b H- 2 Snubber AUG 2 RHR A OWN : PRE F-A 107568 PSUVT/PEI-02.05.02 ISI-13142-17-C ISI . F1.20b H- 9 Dbl Strut /8 Lugs AUG - - - . 2 RHR Suction B OWN PRE - s . F-A 107573 ISI/VT/PEI-02.05.02 ISI-13142-37-B ISI . . . . $ F1.20b H- 2 Strut /8 Lugs AUG - . 2 Containment Spray OWN PRE F-A 107574 ISUVT/PEI-02.05.02 ISI-13142-37-B ISI s F1.20b H-3 Strut/8 Lugs AUG 2 Containment Spray ( OWN PRE (., Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval 1SI Plan (Rev.3) Page 117 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 ;Period 2 Period 3 Cateaorv. Iso No. ItemNO, Comp. Desc. Class Summary I CompiD I System Scope!I Method I Procedure Code Case I1 2 3 4 I 23 4 I 2 34 F-A 107575 PSINVTIPEI-02.05.02 1S1-13142-37-BIs - - - - - - - - - - - - - F1.20b H1--5 Snubber/ILugs AUG - - - - - - - - - - - - 2 Containment Spray OWN . . . - - - - - - - -
. -.-....--.- *. . --... PRE. c--..
F-A 107578 ISIIVTJPEI-02.05.02 ISt-1 31 42-40-B 151 c r - - - - - - - - - - F1.20b H-6 PSINTI/PEI-02.05.02 Dbl Strut 14 Lugs AUG - - - ------- -- 2 HPCI Water Side Dsch OWN - - - -. - - - - - - - -
,.....PRE - .
F-A 100064 ISI-13142-1 7-A 151 -- - - -- s - - - FI.20c H-7 Spring I Clamp AUG - - - - - - - - - - - - 2' RHR Suction A OWN - - - - - - - - - - - - F-A 100099 ISI-13142-17-B [Si F1.20c H-2 Dbl Spring I Clamp AUG - - - - - - - 2' HPCI Water Side Sctn OWN7 - - - - - - - - -
...- PRE.-
F-A 100128 ISI-13142-17-C 151 - - - - - F1.20c H-I' Spring! Clamp AUG . . . . . . . . . . . . RHR Suctio 2 RHR Sction F-A 100134 1S1-13142-17-C 151 - - - - - F1.20c H-7 Dbl Spring!I Clamp AUG - - - - - - - - - - - - 2 RHR Suction B OWN - -- - - - - - - - - - -
. . .. . ~~~~~PRE -.- - - - . -
F-A 100168 ISI-13142-1 8-A I11 - - - - S - - - - - - - F1.20c H-i Spring!/Clamp AUG - - - - - - - - - - - - 2' RHR Discharge B .OWN - - - - - - - - - - - -
. . ~PRE. -
F-A 100172 .. .S .. -113142-18-A ISI F1.20c H-5 Dbl SprIU-BitJSaddle AUG - - - - - - - - - - - - 2 RHR Discharge B OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - F-A. .1 100173 ,,. Is1 F1.20c H- 6,* Obl SprIU-BItJSaddlie AUG 2 RHR Discharge B OWN PRE-Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 118 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category. Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 F-A 100175 ISI-13142-18-A ISI , F1.20c H-8 Dbl Spr/U-BIUSaddle AUG 2 RHR Discharge B OWN PRE - F-A 100178 ISI-13142-18-A ISI . . F1.20c H-10 Spring/Clamp/Slide AUG 2 RHR Discharge B OWN PRE_ - F-A 100207 ISI-13142-18-B ISI . F1.20c H- I Variable Slide AUG . 2 RHR Discharge B OWN PRE F-A 100208 ISI-13142-18-B ISI . F1.20c H-2 Variable Clamp AUG . 2 RHR Discharge B OWN PRE F-A 100210 ISI-13142-18-B ISI F1.20c H-4 Spring / Clamp AUG 2 RHR Discharge B OWN PRE . . . . . . . . . F-A 100247 ISI-13142-18-C IS1 F1.20c H-2 Spring / Clamp AUG . 2 RHR Discharge B OWN PRE -. F-A 100248 ISI-13142-18-C ISI F1.20c H- 3 Spring / Clamp AUG 2 RHR Discharge B OWN - - . PRE - . F-A 100268 ISI-13142-19-A IS1 F1.20c -_5 Spring I Clamp AUG 2 HPCI Steam Disch OWN PRE ISI F-A 100331 ISIVTIPEI-02.05.02 PSINT/PEI-02.05.02 ISI-13142-20-A Variable Spr / Slide AUG C F1.20c H- I Core Spray A OWN 2
- 1-( PRE Printed 3/4/2005
C. C P( Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) .. Page 119 of 332 ASMVE Section XI (1995 Edition, 1996 Addenda) .(May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, iso No. ItemNO, Comp. Desio.
.Scope I Method I Procedure Code Case 1 23 4 1 23 4 1 23 4 Class . ,. Summary I ComnplD I System_,
IS1-I131 42-20-A S- - - - - - - - - - - - F-A 100334 Variable SprlSlide AUG - - - - - - - - - - - - F1.20c. H- 4 2 Core Spray AOW
..- . ~~~~PRE - .- - ...
ISI-13142-20-B ISI F-A 100361 AUG - - - - - - F1.20c -IVariable OWN 2 Core Spray B ,
~~~PRE- . - . . . . . . .
ISI FI.20C H-3 Spring I Clamp AUG 2 . Co're' Spray B OWN
'. , .. - - ..- ...- IPR;:
ISI . . . . - - - IUUf-1U I ISI-1 3142-26-A F1.20c H-4 Spring I Clamp AUG - - - - - - - OWN - - - - - - - 2 - Core Spray B
- ..... ' I-PPI.
[Si - - - - - - - - - - - - F-A 100516 . .ISI-13142-31-B Dbl Spring /Clamp AUG - - - - - - - - - - - - F1.20c H- 2 OWN - - - - - - - - - - - - 2-, Core Spray A , F- 072ISI-13142-37-A - - Spring IClamp AUG - - - - - - - - - - F1.20c H- I OWN - - - - - - - - - - - - 2 RHR Discharge A
.- ~~~PRE- - .-.-
100783 ISI . - F-A -ISI-13142-37-A Spring! Clamp AUG - - - - - - - - - - - - F1.20c H-2 OWN - - - - - - - - - - - - 2 RHR Discharge A PRE. - - - -. - - ISI F-A 100785 . .ISI-13142-37-A Dbl Spring! Clamp AUG - - - - - - - - - - - - F1.20c_ H-4 OWN - - - - - - - - - - - - 2 RHR Discharge A APRE
. ! , , .,., ISI-13142-37-A
. . . . I .,. _' . [Si I , H 8~ ,.. !:~ ... ,.~
Variable / Clamp AUG F1.20C I . 1;; , , -I .. I . .. . ".. I 2 RHR.Discharge A OWN PRE Printed 3f412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 120 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 100813 ISI-13142-37-B IS-s - F1.20c H- I Variable Spring AUG . 2 Containment Spray OWN PRE . . . . F-A 100817 ISI-13142-37-B ISI - - - - - - - . F1.20c H-4 Variable Spring AUG 2 Containment Spray OWN - - .
. . -PRE -- . - - .- -. - -
F-A 100824 ISI-13142-37-B IS1 - - - - s F1.20c H-9 Spring / Clamp AUG 2 Containment Spray OWN PRE - . F-A 100826 ISI-13142-37-B ISI - - - - . F1.20c H-1I Spring / Clamp AUG - - - - - - . 2 Containment Spray OWN - - - .- . PRE F-A 100827 ISI-13142-37-B ISI - - - - - - - - - - . F1.20c H-12 Spring / Clamp AUG . . . . 2 Containment Spray OWN . PRE . .. F-A 100847 ISI-13142-37-C ISI - . F1.20c H- 1 Spring / Clamp AUG . . 2 RHR Discharge A OWN - - - . . - . PRE . . . F-A 100848 ISI-13142-37-C ISI - - . F1.20c H-2 Spring / Clamp AUG 2 RHR Discharge A OWN - . PRE - - . F-A 100849 ISI-13142-37-C ISI F1.20c H-3 Variable Spring AUG 2 RHR Discharge A OWN PRE F-A F1.20c 2 100875. H- I HPCI Water Side Dsch ISI-13142-40-A
.Spring / Clamp ISI AUG OWN
-.I,--- -- --
{. PRE . Printed 3/4/2005
C Monticello Nuclear Generating Plant *, C 4th Interval ISI Plan (Rev.3) Page 121 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case I 2 3 4 1 2 3 4 I 2 3 4 F-A 100915 ISI-1314240-B IS F1.20c H-4 Spring / Clamp AUG : 2 HPCI Water Side Dsch OWN :
.*--PE .. _^.~ . .
F-A 100922 ISINT/PEI-02.05.02 ISI 1314240-B 11SI c F1.20c H-9 DbI Spring / Clamp AUG 2 HPCI Waler Side Dsch OWN
- -.. -. PRE-.- PRE F-A 100923 ISI-131 42-40-B IS1 F1 .20c H-10 Variable Spring AUG 2 HPCI Water Side Dsch OWN PRE F-A 100977 ISI-13142-42-A ISI F1.20c H- 2 Spring Clamp AUG 2 HPCI Steam OWN
. ,-.. . .. _~~PRE _ _ _ _ _ _ _ _ _
F-A 100981 ISI-1314242-A ISI
,..... . -. I F1.20c H-5 Spring Clamp AUG 2 - HPCI Steam . ' OWN
_..,.........._... .. .. PRE.- F-A 100982 ISI-1314242-A ISI F1.20c H-6 Spring Clamp AUG 2 HPCI Steam OWN
. . . PRE F-A 100983 ISI-1314242-A ISI F1.20c H-7 Spring Clamp AUG 2 HPCI Steam OWN
. . . . . ...... 1.42-4. .A . . PRE F-A 100984 -SISI-1314242-A ISI F1.20c H- 8 Spring Clamp AUG 2 HPCI Steam OWN PRE F-A 100989 ISI-13142-42-A IS' F1.20c H-13 Spring ! Clamp AUG
.. ,. I , .... .. .. .. ... .- .: . ..
. , I . . I 2 HPCI Steam OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 122 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 100990 ISI-1 3142-42-A s - - - - - - - - - - - - F1.20c H-14 Spring I Clamp AUG 2 HPCI Steam OWN . PRE F-A 101104 ISI-13142-49-A ISI . F1.20c H- I Spring / Clamp AUG . 2 RHR Suction A OWN - - . PRE F-A 101105 ISI-13142-49-A ISI . F1.20c H- 2 Dbl Spring / Tee AUG 2 RHR Suction A OWN PRE F-A 101108 ISIUVT/PEI-02.05.02 ISI-13142-49-A IS1 C - F1.20c H-5 Spring I Clamp AUG - - - - . 2 RHR Suction A OWN - . PRE . F-A 101109 ISI-13142-49-A ISI F1.20c H-6 Spring I Clamp AUG - - . 2 RHR Suction B OWN PRE F-A 101111 ISI-13142-49-A ISI F1.20c H- 8 Spring I Clamp AUG . 2 RHR Suction B OWN
.. PRE .
F-A 101112 ISI-1314249-A ISI F1.20c H- 9 Clamp AUG - . 2 RHR Suction B OWN - - . PRE - - - - - - - - F-A 101168 ISI-13142-51-B ISI F1.20c H-3 Dbl Spring I Clamp AUG 2 Containment Spray OWN PRE F-A 101171 ISI-13142-51-B ISI F 1.20c H-6 Spring I Clamp AUG . . . . 2 Containment Spray OWN tK C PRE Printed 3J4/2005
C. C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 123 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
*! Period 1 Period 2 Period 3 Category, Iso No.
itemNO, ' Comp. Desc. Class._ . Summary I ComplD I System .- - Scope I Method ! Procedure. - Code Case -. ... .- ... - - . .- . 1 2.3 .4 1..2. 3- 4 1 -2 .. 3 .4-F-A 101172. ISI-13142-51-B IS1 F-.20c H-7 Spring / Clamp AUG 2 Containment Spray OWN
....... ...... .-.- PRE----.-
F-A 106020.: ISI-13142-29-A ISI . F1.20c H-1; Dbl Strut / U-Bolt AUG - - - - 2, RBCCW ; .- . OWN - - -.-.. .. PRE" ---- _-. - ___ __ _ _ F-A 107564 ISI-13142-17-A ISI F1.20c H-5 Dbl Spr / Half Clamp AUG 2- RHR Suction A OWN
. - 1 . - PRE I I I F-A 107565 ISI-13142-17-A ISI - - - -
F1.20c H- 6 Dbl Spr / Half Clamp AUG - - - - 2 RHR Suction A
-1 OWN
- .- ' -' PRE
F-A 107566 ISI-13142-17-C ISI.- s - F1.20c H- 6 Dbi Spr / Half Clamp AUG 2 . RHR Suction B , . 7 OWN -
- ~ -.-.---. PRE"'
F-A 107567 - ISI-13142-17-C ISI . F1.20c H-8 Dbl Spr / Half Clamp AUG 2 RHR Suction B OWN
.. PRE --
F-A 107569 ISINTIPEI-02.05.02 ISI-13142-18-A ISI. c - F1.20c H- 9 Dbl Spring /4 Lugs AUG
- 2. RHR Discharge B ' , . OWN PRE' - ' ' . . . .-
F-A 107570 ' ' ISI-13142-19-A ISI F1.20c., H-3 Dbl Spring /4 Lugs AUG 2 HPCI Steam Disch OWN - PRE F-A - 107571 * . . -. . .: - - ... .. ; ISI s
, ,- ! ,. SI-13142-19-A - , ~
F1.20c H-77 . ;. - ., . AUG 2 HPCI Steam Disch OWN PRE Prinfohf 1'4*95
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 124 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Class. Summary I ComplD / System Scope I Method I Procedure Comp. Desc. Code Case 1. 2 3 4 1 2 3 4 1 2 3 4 F-A 107572 ISI-13142-37-A ISI . . . . . . F1.20c H-7 Dbl Spring /4 Lugs AUG - - - - - - - . 2 RHR Discharge A OWN - - - - - . PRE - F-A 107576 ISI-13142-37-B IS1 F1.20c H- 6 Dbl SprlClamp&Saddle AUG 2 Containment Spray OWN PRE -_-_ -- - - _-_--- _- _- F-A 107577 ISI-13142-37-B ISI F1.20c H-7 Dbl Spring 14 Lugs AUG 2 Containment Spray OWN PRE F-A 107579 ISI-13142-42-A ISI s F1.20c H-3 Dbl Spring /4 Lugs AUG 2 HPCI Steam OWN PRE F-A 107580 ISI-13142-51-B IS1 F1.20c H- 2 Dbl Spring 14 Lugs AUG 2 Containment Spray OWN PRE [SI F-A 107601 ISI-13142-18-B F1.20c H-2B Variable Clamp AUG 2 RHR Discharge B OWN F-A 1PRE F-A 102229 nd-isl-101 ISI F1.30a SR-563 Seismic Restraint AUG 3 RHR Service Water OWN PRE--- F-A 102230 nd-isi-101 ISI F1.30a SR-81 Seismic Restraint AUG 3 RHR Service Water OWN PRE nd-isl-101 IS1 F-A F1.30a . 102232 SWH-308 Base Plate AUG . .... 3 RHR Service Water OWN .1 . . PRE I (. I- ' Printed 3/4/2005
Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3) C Page 125 of 332
;ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
, Period 1 - Period 2 . Period 3 Category, Iso No. -.
ItemNO, Comp. Desc. Class -. .Summary I CompID / System .. . Scope I Method I Procedure I... Code Case .. 1 2 3. 4 1 2 .. 3 4. .1...2. 3 .4 F-A 102233 nd-isi-101 ISI F1.30a SWH-309 Base Plate AUG 3 RHR Service Water OWN _ F-A 102234 nd-isl-101 ISI F1.30a SWH-310 Base Plate., ... AUG . 3 RHR Service Water OWN - . - - -
-. -. PRE--
F-A 102235 . nd-isi-101 ISI . F1.30a SWH-311 Base Plate AUG 3 RHR Service Water OWN
. .-- - PRE-F-A 102236 .nd-isi-101 I11 - - - - --
F1.30a SWH-312 Seismic Restraint AUG 3- RHR Service Water OWN
.-.-...- PRE F-A 102237 - nd-s-11 IS. - - - - - - - - - - - -
F1.30a SWH-313 Seismic Restraint AUG _ RHR Service Water . OWN - - - .- - -
.,.PRE F-A 102240 nd-lsl-102 IS-s-F1.30a SR-213 Seismic Restraint AUG 3 RHR Service Water . . OWN
. . . .---- PRE F-A 102241. . ISINT/PEI-02.05.02 nd-isi-102 ISI1 -- - s F1.30a SR-79 Seismic Restraint AUG 3 RHR Service Water . . OWN PRE- - -- .
F-A 102242 nd-isi-102' ISI F1.30a SR-80 Seismic Restraint AUG 3 RHR Service Water OWN - PRE F-A : 102244 2 nd-isl-i 02. ;- [SI 5 F1.30a SWH-305 , , : : . . Base Plate ; ;; . AUG 3 RHR Service Water OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 126 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Sumrnmary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 .4 1 2 3 4 F-A 102245 nd-isi-102 IS1 F1.30a SWH-306 Base Plate AUG 3 RHR Service Water OWN PRE - F-A 102246 nd-isi-102 ISI F1.30a SWH-307 Base Plate AUG 3 RHR Service Water OWN PRE - F-A 102247 nd-isi-102 ISI F1.30a SWH-31 Seismic Restraint AUG 3 RHR Service Water OWN PRE - F-A 102248 nd-isi-102 ISI - - - . F1.30a SWH-32 Restraint AUG - - - . 3 RHR Service Water OWN PRE - - - - . F-A 102249 ISIIVTiPEI-02.05.02 nd-isi-103 ISI - - r - - s F1.30a SR-394 Seismic Restraint AUG - - .
- 3. RHR Service Water OWN PRE - . - .
F-A 102250 nd-isi-103 ISI F1.30a SR-395 Seismic Restraint AUG 3 RHR Service Water OWN PRE F-A 102251 nd-isl-103 ISI . F1.30a SR-396 Seismic Restraint AUG . 3 RHR Service Water OWN - . PRE - - --- . -. - F-A 102252 nd-isi-103 ISI - . F1.30a SR-459 Seismic Restraint AUG 3 RHR Service Water OWN PRE . . . F-A 102254.'.: - nd-isi-103 ISI F1.30a SR-84: Seismic Restraint AUG . . 3 *RFIR Service Water OWN Pn 2.. PRE Printed 3/4/2005
C 4th Interval ISI Plan (Rev.3) (. 7: Page 127 of 332
, Monticello Nuclear Generating Plant
. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 F-A 102255 nd-isi-103 ISI F1.30a SWH-161 Rod & Strut AUG ; 3 RHR Service Water OWN
-.- PRE . ... ..- ... .. . .
F-A 102256 nd-isi-104 ISI F1.30a SR-460 Seismic Restraint AUG 3 RHR Service Water OWN ; F-A 102257 nd-lsi-104 [SI F1.30a SR-461 Seismic Restraint AUG 3 RHR Service Water OWN
. .. . .. . _ . PRE-
- F-A 102258 nd-isl-104 ISI F1.30a SR-462 Seismic Restraint AUG 3.
3 RHR Service Water OWN
.PRE F-A 102259 nd-isi-104 ISI F1.30a SR-463 Rod AUG_
3 RHR Service Water OWN F-A 102260 nd-lsl-104 ISI Fi.30a SR-473 Rod AUG 3 RHR Service Water OWN ;
* . ---- --
- PRE F-A 102261 nd-isi-104 ISI - . - ...
F1.30a SWH-45 Rod AUG . 3 RHR Service Water OWN
... , . . .. . . PRE F-A 102262 -
- nd-1sl-105 ISI F1.30a SR-481 Seismic Restraint AUG 3 RHR Service Water OWN PRE F-A . . 102263 . 1. . , .
nd-lsl-1 05 [SI F1.30a SR-482 Seismic Restraint AUG
- . 1: I ., . .. ,;..- .I ..
3 RHR Service Water OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 128 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 102264 nd-isi-105 ISI - - - - . F1.30a SR-90A Rod AUG - - - - - - - - - - - - 3 RHR Service Water OWN - - - - - - - . PRE F-A 102265 nd-isi-105 ISI . . . . . . . . F1.30a SW-21 Rod AUG - - - - - - - - . 3 RHR Service Water OWN - - - - - - - . PRE F-A 102266 nd-isi-105 ISI - - - - - - - . F1.30a SW-22 Rod AUG - - - - - - - . 3 RHR Service Water OWN PRE - - - - - - - - . F-A 102267 nd-isi-105 ISI - - - . F1.30a SWH-483 Rod AUG - .... 3 RHR Service Water OWN - - - - - - - . PRE F-A 102268 nd-isi-106 ISI . F1.30a SR-18 Rod AUG - - - - - - - - - - - 3 RHR Service Water OWN - - - - - . PRE . - - - - - - - - - . F-A 102269 nd-isi-106 IS1 F1.30a SR-398 Seismic Restraint AUG - - - - - -.-..-..-. 3 RHR Service Water OWN PRE F-A 102272 nd-isi-106 ISI - - . - ...- F1.30a SR-95 Seismic Restraint AUG - - - - - - - - . 3 RHR Service Water OWN PRE - . - - - - - - - . - F-A 102273 nd-isi-106 ISI . . . . . . . . . . . . F1.30a SR-97 Seismic Restraint AUG - - - - - - - - . 3 RHR Service Water OWN - PRE - - - - - . F-A 102274 nd-isi-106 I5 F1.30a' SW-15 Rod . . . AUG 3 RHR Service Water OWN C PRE Printed 34/42005
C. Monticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3)
- Page 129 of 332 7
ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
- o. . . C .. .sNo Period I Period 2 Period 3 Category,_ . Iso No.
ItemNO, Comp. Desc.
, Scope I Method I Procedure Code Case I 2 3 A I I It A 4 I i A Class Sunmary I CompID / System nd-isi-106 ISI .
F-A 102275 Rod AUG . F1.30a SW-16 OWN 3 RHR Service Water F-A 102276 nd-isi-106 IS1 Seismic Restraint AUG - ; Fi.30a SW-4A
- 3. RHR Service Water OWN -
... .PRE--
4F
, U4.L A,,7v
. . I nd-ism-107 lSI S Fi.30a IS-SWH-75 Rod AUG 3 RHR Service Water OWN
. . PRP ....
102278 nd-isi-107 ISI . F-A F1.30a IS-SWH-76 Rod AUG . 3 RHR Service Water OWN PRE * .... ..-.-... - F-A 102281 nd-isi-107 ISI Seismic Restraint AUG . . . : F1.30a SR-399 3 RHR Service Water ,OWN 102282 nd-isi-107 ISI F-A Seismic Restraint AUG ; F1.30a SR-451 3 RHR Service Water OWN .
., . . .. . .. . .. . . . - -- -.- -PRE . .. ..
F-A 102283 nd-isi-107 ISI FI.30a SR-452 Seismic Restraint AUG OWN - ; 3 RHR Service Water
,< , , - PRE nd-isi-1 07 ISIR- -_- - - -
F-A 102284 . F1.30a SR-453 Seismic Restraint AUG 3 RHR Service Water OWN PRE - - - - , F- A I Ut~t.D - r , I I -. - - Se-ismclRea-it07, ISI VrM . AUG F1.30a SR-454 - ., .-, - ;. . * . I .. .,L .,I . , Seismic I, ~ Restraint
. I 3 RHR Service Water OWN PRE Printed 314t2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 130 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. e . 4 e, A * . I . I - Class Summary / ComplD I System Scope I Method / Procedure Code Case ~_ zJ 4 F-A 102286 ndii17ISI F1.30a SR-455 Seismic Restraint AUG 3 RHR Service Water OWN F- ~~PRE nd-isi-107 jIS1 .E F-A 102288 Fl.30a SR-469 Seismic Restraint AUG 3 RHR Service Water OWN
- PRE - _ ... . . -. -
F-A 102291 ISINT/PEI-02.05.02 nd-isi-107 ISI c r - - F1.30a SWH-8 Dead Weight Support AUG 3 RHR Service Water OWN PRE - - - - - - - - - - - - F-A 102294 PRnd-isi-108 F1.30a ISI-SWH-69 Rod AUG - - - 3 RHR Service Water OWN PRE nd-isl-108 -RE F-A 102295 Fl.30a ISI-SWH-70 Dead Weight Support AUG 3 RHR Service Water OWN F-A 12296PRE F-A 102296 ISlVTIPEI-02.05.02 nd-isi-108 15E c r F1.30a SR-100 Double Rod AUG 3 RHR Service Water OWN F-A 102297 nd-isi-108 IPSR1E F1.30a SR-103 Double Rod AUG 3 RHR Service Water OWN F-A 102298- nd-isl-108 IS.I E F1.30a SR-104 Seismic Restraint AUG 3 RHR Service Water OWN PRE _____-_PR F-A 102307 'SI F1.30a SWH-1 1 Rod AUG 3 RHR Service Water OWN ( PRE Printed 3/4/2005
C. C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 131 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class ,, Summary / ComplD / System . , _ Scope / Method / Procedure Code Case I 2 3 4 1 2 3,4 1, 2 3 4 F-A 102308 nd-isi-108 IS1 F1.30a SWH-9 Rod AUG 3 ., RHR Service Water OWN PRE . ------- F-A 102309 . nd-Isi-108 IS1 . F1.30a SWH-9A Rod AUG 3 RHR Service Water , OWN -;
.... -- - PRE -* , .,
F-A 102315 nd-isl-109 [SI . 7 F1.30a SR-94 Seismic Restraint AUG 3 RHR Service Water OWN
. . .. ... ....-1 - PRE
- 4. 4. 4.
F-A 102316 nd-isi-109 ISI F1.30a SR-96 Seismic Restraint AUG 3, RHR Service Water OWN
-. 1. _ ... ... .._ ..... . .. ... . ... -1 ... . ...-. .. .. .1 .' . .. PRE -
F-A 102317 -. . nd-isi-109 IS. -, F1.30a SW-24, Rod AUG RHR Service Water OWN
,,._,_-,,, _,, ,,, . ~.. ... - PRE -"-- -- --
F-A 102318 nd-Isi-109 ISI , F1.30a SW-26 Rod AUG 3 RHR Service Water OWN
....-- -PRE -
F-A 102319 nd-isi-109 ISI,, F1.30a SW-B Seismic Restraint AUG 3 RHR Service Water , OWN PRE F-A 102320 ' ' nd-isf-109 IS1 F1.30a SWH490 Rod AUG 3 RHR Service Water OWN PRE F-A ,. 102321 . . . , . , - nd-isi-109 iSI
. . IR F1.30a SWH-498 , ,:,. : ., ;-1 , , Rod AUG 3 RHR Service Water OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 132 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 I 2 3 4 F-A 102323 nd-isi-110 ISI FI.30a SR-91 Seismic Restraint AUG 3 RHR Service Water OWN PRE F-A 102324 nd-isl-1 10 ISI F1.30a SW-29 Rod AUG 3 RHR Service Water OWN PRE-F-A 102325 nd-isi-1 10 ISI F1.30a SWH493 Rod AUG 3 RHR Service Water OWN PRE F-A 102327 nd-isi-123 ISI F1.30a H-201 Rod AUG 3 RHR Service Water OWN PRE F-A 102328 nd-isi-123 ISI-s F1.30a H-202 Rod AUG 3 RHR Service Water OWN '. ' ~PRE F-A 102329 nd-isi-123 IS1 FI.30a H-203 Rod AUG 3 RHR Service Water OWN PRE F-A 102330 nd-isi-123 ISI F1.30a H-204 Rod AUG 3 RHR Service Water OWN PRE F-A 102331 nd-isi-123 ISI F1.30a H-205 Rod AUG 3 RHR Service Water OWN PRE F-A 102228 nd-isi-100. iSI F1.30b SWH-180 Clevis AUG 3 RHR Service Water OWN (. ( PRE Printed 3/412005
C. C 4th Interval ISI Plan (Rev.3) C Page 133 of 332 Monticello Nuclear Generating Plant PI ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
. I Period 1 - Period 2 Period 3 Category, Iso No.
ItemNO, Comp. Desc. Summary I ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 I 2 3 4 I 2 3 4 Class F-A 102231 nd-isi-101 [SI . Ft.30b SS-562 Dbl Strut Snubber AUG 3 RHR Service Water OWN
._........._ -.- PRE ....
F-A 102238 nd-isi-101 ISI F1.30b SWH-375 Strut AUG ; 3 RHR Service Water OWN - ;
. ... . -... PRE.-. ... .. - -
F-A 102239 nd-isl-101 ISI F1.30b SWH-43 Stanchion AUG 3 RHR Service Water OWN I- PRE I I I F-A 102253 nd-isl-1103 ISI S F1.30b SR-464 Strut AUG 3 RRHR Service Water OWN _ I _ - PRE F-A 102270 nd-isi-106 ISI F1.30b SR450 Strut AUG 3 RHR Service Water OWN
.. PR PRE F-A 102271 nd-isi-106 ISI -
F1.30b SR-457 Anchor AUG 3 RHR Service Water OWN PRE F-A 102279 nd-isl-107 ISI F1.30b SR-105 Stanchion AUG 3 RHR Service Water OWN
* * . . . . . PRE F-A 102280- nd-isi-107 ISI F1.30b SR-397 Double Strut AUG 3 RHR Service Water OWN PRE ---
F-A 102287 ,_. .. iSI nd-isi-107 AUG F1.30b SR-456 3 RHR Service Water OWN PRE Printed 3/4t2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 134 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method / Procedure Code Case I 2 3 4 1 2 34 1 2 3 4 F-A 102289 nd-isl-1 07is - - - - - - - - - - - - F1.30b SWH-72A Stanchion AUG - . 3 RHR Service Water OWN PRE F-A 102290 nd-isi-107 ISI . . F1.30b SWH-728 Stanchion AUG - . 3 RHR Service Water OWN . PRE . F-A 102292 nd-isi-108 ISI F1.30b IS-SWH-65 Stanchion AUG 3 RHR Service Water OWN - - . PRE F-A 102293 nd-isi-108 ISI F1.30b IS-SWH-66 Stanchion AUG 3 RHR Service Water OWN PRE . F-A 102299 ISWNT/PEI-02.05.02 nd-isi-108 ISI c r - - - . F1.30b SR-106 Stanchion AUG
- 3. RHR Service Water OWN
.PRE- .
F-A 102300 nd-isi-108 ISI F1.30b SR-382 Strut AUG - . 3 RHR Service Water OWN . PRE F-A 102301 nd-isi-108 IS1 . F1.30b SR-383 Strut AUG 3 RHR Service Water OWN . PRE F-A 102302 nd-isi-108 ISI F1.30b SR-384 Strut AUG - - - . 3 RHR Service Water OWN PRE F-A 102303 nd-isi-108 Is' F1.30b SR-385 SRW . . Strut AUG 3 RHR Service Water OWN Q. (. PRE Pnd/2 Printed 3/4/2005
( C, I IMonticello Nuclear Generating Plant 4th Interval ISt Plan (Rev.3) I Page 135 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to. May 31, 2012) Period I .. Period 2 Period 3 Category, iso No. ltemNO, Comp. Desc. Class Summary I CompiD I System Scope I Method I Procedure Code Case 1 2 3 4 I 2 3 4 11 2 3 4 F-A 102304 nd-isl-1 08 S. . . . . . . . . . . . FI.30b SR-386 Strut AUG - - - - - - - - - - - - 3R Rservice Water OWN - - - - - - - - - - - -
.. *. ..- * .. P R E - -
F-A 102305 nd-sisI-108 1St. FI.30b SR-400 Strut AUG - - - - - - - - - - 3 RHR Service Water OWN - - - - - - - - - - --
. .... ..... PRE F-A 102306 nd-isl-1 08 [Si F1.30b SR-401 Strut AUG' 3 RHR Service Water OWN PRE. -
F-A 102310 *.nd-isi-109 iSI FI.30b SR-337 Strut AUG - - - - - - - - - - - - 3 - RHR Service Water OWN - - - - - - - - - - - -
.- .... -. .P RE _
F-A 102311 nd-isi-109 isI F1.30b SR-402 Strut AUG - - - - - - - - - - 3 RHR Serice'Water . OWN . . -. . . . . . . .. .
.. PRE F-A 102312 nd-islIO19 iSI -
F1.30b SR-458 Anchor AUG - 3 RHR Service Water OWN PRE . - . F-A 102313 nd-isl-109 IS! F1.30b SR-491 Double Strut AUG ... 3 RHR Service Water OWN ---------
.O ., . RE - - - - - - - - - - - -
F-A 102314. . . .. *.nd-isi-109 ISI F1.30b' SR-492 Strut: AUG RHR Service Water OWN - - - - - - - - - - - - PRE . . . . . . . . . . . . F-A 102322 nd-isi-1 10 IS' F1.30b - SR494 . AUG 3 RHR Service Water OWN PRE Printed 314=205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 136 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 72 - A 1 7 I1 A 4 q e s Class Summary I ComplD I System Scope I Method I Procedure Code Case F-A 102326 ISINVTIPEI-02.05.02 nd-isi-1 11 ISI s - F1.30b SR-88 Stanchion AUG - - . - ...- 3 RHR Service Water OWN - - - - - - - .
.. PRE - - - - - - - - - - -.
F-A 102243 ISIIVTIPEI-02.05.02 nd-isi-102 ISP - - - - s - - - . F1.30c SWH-304 Double Spring AUG - - - - - . 3 RHR Service Water OWN - - - . PRE - - - - - - - - - - -. 101682 ISI-829242A ISP - - - - s . . . . . .. F-A F1.40a DVMX Supp A DVMX Pump Support AUG - - - - - - - . 2 HPCI Pumps OWN - . PRE . . . . . . . . . . . f-A 101683 ISI-8292-42A ISI . - . s - - - - . F1.40a DVMX Supp B DVMX Pump Support AUG - - - . 2 HPCIPumps OWN - - - - - - - - . PRE - - - - - - - - - - - - 101684 ISI-829242A ISP R - - - - - - - F-A F1.40a OVMX Supp C DVMX Pump Support AUG - - - . 2 HPCI Pumps OWN . . . . . . . . PRE - - - - - - . 101685 ISI-8292-42A ISI- - s - - - - f-A F1.40a DVMX Supp D DVMX Pump Support AUG - - - - - - - . 2 HPCI Pumps OWN - - - - - . PRE - - - - - - - - - - - - . F-A 101686 ISIIT/PEI-02.05.02 ISI-8292-42A ISI c r - - ---- _ _--_ -- F1.40a DVS Supp A DVS Pump Support AUG - - - - - - - . 2 HPCI Pumps OWN - . PRE - - - - - - - - . f-A 101687 ISUVT/PE142.05.02 ISI-8292-42A ISI c r - - . . . F1.40a DVS Supp B DVS Pump Support AUG - - - - - - . 2 HPCI Pumps OWN - - - - - - . PRE ... F-A is' S F1.40a DVS Supp C DVS Pump Support AUG 2 HPCI Pumps OWN PRE (I k,-. Printed 3/4/2005
C C 4th Interval ISI Plan. (Rev.3) K Monticello Nuclear Generating Plant Page 137 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 . Period 2 . Period 3 Category, Iso No. ItemNO, Comp. Desc.' Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 101689 ISI-8292-42A ISI s F1.40a DVS Supp D DVS Pump Support AUG 2 HPCIPumps OWN
.-. *-* . -...- PRE-F-A 102074. , ISI-97005-C ISI - -S F1.40a H-10 Restraint AUG 1 . Recirculation A ' OWN _'
- - -- . ~--PRE - - .. --
F-A 102181 . ISI-97006-C ISI FI.40a H-10 Restraint AUG 1 Recirc Pump B OWN
,-..- . . . ..- PRE ..-
F-A 102741. ISI// IS147 IS[ - r s F1 .40a Pump Supp A Pump Support AUG
- 2. RCIC Turbine & Pump OWN
...- .. .. -. -- PRE - . .. . .
F-A 102742 ISII/ ISI-47 SI - r s F1.40a Pump Supp B Pump Support AUG 2 RCIC Turbine & Pump . OWN - - -.
. - -. . . .- * .- .. -.. .--.. - PRE . . . .-.
F.A 102743 ISI// ISI-47 ISI - r s _ F1.40a Pump Supp C Pump Support AUG 2 RCIC Turbine & Pump OWN
,.,. -.. PRE-F-A 102744 . . ISI ISI-47 ISI - r ss F1.40a Pump Supp D Pump Support AUG 2 RCIC Turbine & Pump , , ' OWN
-. PRE . -
F-A 107562 . . IS Fig 3 ISI - - - -- s - - - F1.40a W-12 B.H. to Skirt Weld AUG Reactor Vessel OWN PRE - - - - ' F-A . 107581 , .. . .I ISITVr/PEI-02.05.02
,, , ,, ISI-7905-32A ,,, 'SI S Support A 'I I. ; SdpportA,E200A, O AUG F1.40a 2 RHR Heat Exchanger A OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 138 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary / ComplD / System Scope / Method / Procedure Comp. Desc.
Code Case 1. 2 3 A 1. 2 ft A 1. 12 '3 A F-A 107582 ISIIVTIPEI-02.05.02 ISI-7905-32A ISI s F1.40a Support B Support B,E200A 180' AUG . 2 RHR Heat Exchanger A OWN PR - -. - - -- F-A 107583 ISINT/PEI-02.05.02 ISI-7905-32A ISI s F1.40a Support C Support C,E200A 315 AUG 2 RHR Heat Exchanger A OWN
--- PRE. -
F-A 107584 ISI-7905-32B ISP --- - F1.40a Support A Support A,E200B 01 AUG 2 RHR Heat Exchanger B OWN PRE - - - - - - - - - - - - F-A 107585 ISI-7905-32B ISP-- F1.40a Support B Support B,E200B 180' AUG 2 RHR Heat Exchanger B OWN PRE - - - - - - - - - - - - F-A 107586 ISI-7905-32B ISI F1.40a Suppot C Support C,E200B 315- AUG 2 RHR Heat Exchanger B OWN
.... - - - -- -R F-A 107590 ISP48 ISR F1.40a RHR Support C Pump Support AUG 2 RHR Pumps P OWN F-A 107591 , ISIR48 [SI _
F1.40a RHR Support D Pump Support AUG 2 RHR Pumps OWN ___PRE ...... ...... F-A 107592 ISI4 ISI - F1.40a RHR Support A Pump Support AUG 2 RHR Pumps OWN PRE F-A 1in7ROA Ibl-40 S15 F1.40a RHR Support B Pump Support AUG 2 RHR Pumps OWN C PRE Printed 314/2005
C.I- C C Monticello Nuclear Generatinri Plant 4th Interval IS1 Plan (Rev.3) Page 139 of 332 I.ASMVE Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) 1.I. Period I Period 2 Period 3 Category Iso No. ltemNO, Comp. Desc.' Class -- Sumnmary I ComplD I Systemn I - -Scope I Method I Procedure Code Case 1 23 4 1 23 4 1 23 4 F-A 107594 [StIS!TIPEI-02.05.02 ISI-49 S r rs F1.40a Support, Pump A Pump Support AUG . . . . . . . . . . . .
- 2. Core Spray Pumps A OWN - - - - - - - - - - - -
.~~~PRE ----
F-A 107595 ~,ISI-49 IS1 FI.40a Support, Pump B Pump Support AUG - - - - - - - - - - - 2 Core Spray Pumps OWN ---
... . -, ~PR E.. ..-..
F-A 107604 ISINTr/PEI-02.05.02 ISI-8292-48-A ISI C Fl .40a Turbine Suppt A HPCI Turbine Support A AUG - - - - - - 2 HPCI OWN - - - - - - -
.PRE F-A 107605 ISI-8292-48-A ISI- - - - - s-Fl .40a Turbine Suppt B . . HPCI Turbine Support B AUG . . . . . . . . . . . .
HPCI - . OWN -- - - - - - - - -
. .- , . .P RE-- - .
F-A 107540 ISINTIPEI-02.05.02 ISI-97005-C ISI-.s .- .- .- 01.40b H-7 .. Snubber/I Lugs .AUG - - - - - - - - I Recirc PumnpA PR-OWN* - . --- - - --- -- F-A 107541 .PSIfVT/PEI-02.05.02 ISI-97005-C ISI - s- - - - - - - - Fl .40b H-8 ISINVrIPEI-02.05.02 Snubber / Lugs AUG . . . . . . . . . . 1 Recirc Pump A OWN - - - - - - - - - - - -
..- -- PRE -- S.-
F-A 107542 ISI/VTIPEI-02.05.02 ISI-97005-C ISI-.s .- .- .- F1.40b H-9 Snubber/ILugs AUG - - - - - - - - - - - - 1 Recirc Pump A OWN - - - - - - - - PRE F-A 107559 . PS!INTIPEI-02.05.02 IS!-97006-C ISI Fl .46b H- 7 ISINTr/PEI-02.05.02 Snubber- I Lugs AUG - - - - - - - - - - - - 1 Reciro Pump B OWN - - - - - - - - - PRE - b - F-A .,- 107560 PSINVT/PEI-02.05.02 _. ISI-97006-C. IS' FI.40b . H- 8 Snubber/ILugs' AUG 1Recirc Pump B OWN PRE C - Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 140 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD / System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 F-A 107561 PSWT/PEI-02.05.02 ISI-97006-C ISI - - - - - . F1.40b H-9 Snubber/Lugs AUG . . . . . . .. . . . . 1 Recirc Pump B OWN - - - - - - . PRE H - . F-A 106108 ISVVTIPEI-02.05.02 ISI Fig 4 [SI . . .s . F1.40c Vsl Stblzr / Lug @ 90 deg. Vsl Stbzr I Lug @ 90 deg. AUG - - - - - - - . 1 Reactor Vessel OWN PRE . ... . . . . . . F-A 106109 ISINT/PEI-02.05.02 ISI Fig 4 IS1 - - s - - F1.40c Vsl Stblzr / Lug @ 80 deg. Vsl Stblzr Lug@ 1B0 deg. AUG 1 Reactor Vessel OWN . PRE F-A 106110 ISI/VT/PEI-02.05.02 ISI Fig4 IS1 - s - - F1.40c Vsl Stblzr / Lug @ 270 deg. Vsl Stbizr / Lug @ 270 deg. AUG 1 Reactor Vessel OWN PRE F-A 107534 ISIVTIPEI-02.05.02 ISI-97005-C 11 - - - - s. F1.40c H-I Rod/Clevis Grip/Lugs/Constant-Support AUG 1 Recirc Pump A OWN PRE -. -. . . . F-A 107535 ISUVTIPEI-02.05.02 ISI-97005-C ISI - - - - s . . . . . . . F1.40c H-2 Rod/Clevis Grip/Lugs/Constant-Support AUG' 1 Recirc Pump A OWN PRE -.- F-A 107536 ISIVTIPEI-02.05.02 ISI-97005-C ISI s . . . F1.40c H-3 Rod/Clevis Grip/Lugs/Constant-Support AUG . 1 Recirc Pump A OWN - - - - - - . PRE -- F-A 107553 ISI-97006-C IS1I. . F1.40c H-1 Rod/Clevis Grip/Lugs/Constant-Support AUG 1 Recirc Pump B OWN - - . PRE - - - - - - - - F-A 107554 , . ISI-97006-C lSI F1.40c H-2 Rod/Clevis Grip/Lugs/Constant-Support AUG I Recirc Pump B OWN (. PRE I. Printed 3/4/2005
C C C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 141 of 332 I ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 2 . Period 3 Category, Iso No. 'II
- ItemNO, Summary I ComplD I System Scope / Method I Procedure Comp. Desc.
Code Case 1 2 3 4
- 1 2 3 4 I.
1 2 3' 4 Class
......... ----- ISINT/PEI-02.05.02 ISI-97006-C S1S C F-A 107555 --
F1.40c H- 3 RodlClevis GriplLugs/Constant-Support AUG
- 1. Recirc Pump B OWN F-A 107563 ISINT/PEI-02.05.02 ISI Fig 4 ISI r r s F1 .40c Vsl Stblzr I Lug @ 0 deg. Vsl Stblzr / Lug @ 0 deg. AUG .
1 Reactor Vessel OWN PRE- - HELB 105009 ISI/UT/PEI-02.03.01 NC-ISI-37 ISI B b --- - b b; - s - -- NCR95-068 W- 1 ISINUT/PEI-02.03.01 Pipe-to-Pipe AUG : RCIC Feedwater . . OWN
.. . PRE -. - -
HELB 105010 ISIUUT/PEI-02.03.01 NC-ISI-37 IS1 B b - - b b - - s - - - NCR95-068 W- 2 ISI/UT/PEI-02.03.01 Pipe-to-Tee AUG RCIC Feedwater OWN HELB 105011.1 ISI/UTIPEI-02.03.01 NC-ISI-37 1S. B b - - b b - - s NCR95-068 W- 3 ISINUT/PEI-02.03.01 Tee-to-Pipe AUG _
- RCIC Feedwater OWN
. .. . .. . - PRE . .
HELB 105012 ISI/UTIPEI-02.03.01 NC-ISI-37 IS1 B b - - b b - - s - NCR95-068 W-4i ISIIUT/PEI-02.03.01 Tee-lo-Elbow AUG . RCIC Feedwater OWN
. .- .PRE.
HELB 105013 ISI/UTIPEI-02.03.01 NC-ISI-37 . .IS B b - - b b - - s - NCR95-068 W-12 ISI/UT/PEI-02.03.01 Pipe-to-Pipe AUG RCIC Feedwater OWN PRE -- - - - HELB 105014 ISI/IUTIPEI-02.03.01 NC-ISI-37 Is' b b - - S - - -
- ,1 . I* . 1 : .
............... I I "... ., . ; . PI t.o T.
NCR95-068 W-12A' . ISIIUTIPEI-02.03.01 ; . . Pipe-to-Tee ', .. . : AUG RCIC Feedwater OWN Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 142 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. lemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 411 2 3 4 1 2 3 4 HELB 105016 ISUPT/PEI-02.01.01 NC-ISI-51 ISI B b b b NCR95-068 W-11 ISIUUT/ISI-UT-16 Pipe-to-Tee AUG CRD TO RWCU ISUPTIPEI-02.01.01 OWN ISI/UT/PEI-02.03.11 PRE ._...... HELB 105017 ISI/PTIPEI-02.01.01 NC-ISI-51 [SI B b b b NCR95-068 W-12 ISUUT/ISI-UT-16 Pipe-to-Tee AUG . . . CRD TO RWCU ISUPT/PEI-02.01.01 OWN ISI/UT/PEI-02.03.02 PRE HELB 105018 ISIIPT/PEI-02.01.01 NC-ISI-51 ISI B b - b b - - s - NCR95-068 W-13 ISI/UT/ISI-UT-16 Tee-to-Pipe AUG CRD TO RWCU ISl/PTIPEI-02.01.01 OWN . ISI/UT/PEI-02.03.02 PRE NC 105015. ISINTNT by Owner NC-7879-6 IS1 - s NC-SAC SBLC Tank Internals AUG NC SBLC OWN PRE R-A(H) 100993 IS1-13142-42-A ISI 5 - - - - - - - - - - R1.1I W- 1 Sweepolet-to-Elbow AUG I HPCI Steam OWN PRE . . R-A(H) 100994 ISI-13142-42-A ISI -- R1.11 W- 2 Elbow-to-Pipe AUG 1 HPCI Steam OWN PRE R-A(H) 100995 ISI-1314242-A ISI ... -.. - R1.11 W-3 Pipe-to-Venturi AUG 1 HPCI Steam OWN PRE R-A(H) 100996 ISI-13142-42-A ISI R1.11 . W-4 . - Venturi-to-Pipe AUG
- 1. HPCI Steam OWN PRE
(-. Printed 3/4/2005
C C ( Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 143 of 332
.ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Pr!
Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class hSummary I ComplD I System Scope I Method I Procedure Code Case I 2 3 4 11 2 3 4 11 2 3 4 R-A(H) 100997 ISI-13142-42-A IS1 R1.1I W- 5 Pipe-to-Valve AUG - - - - - - - .
- 1. HPCI Steam OWN .
- PRE -- -
R-A(H) 101007 ISI-13142-42-A ISI - . - - . R1.11 W-15 Pipe-to-Pipe AUG 1- HPCI Steam OWN'
-- PRE-._._
R-A(H) 101008 ISI-13142-42-A ISI -s - - _-- R1.11 W-16 Pipe-to-Pipe AUG - - .... 1 HPCI Steam OWN - - .
. - - - - - - PRE.
R-A(H) 101009 ISI-13142-42-A ISI - . s R1.11 W-17 Pipe-to-Valve AUG - - - - - - - - - . 1 HPCI Steam OWN - .
- - -- PRE . . ... .
R-A(H) 101208 ISI-13142-52-A ISI - - - - - - - . R-I.11 W-2 Tee-to-Pipe AUG 2 , Feedwater , . OWN -
. ~--.-----~---PR E - - ~ -
R-A(H) 101209 ISI-13142-52-A ISI - . R1.11 W- 3 Pipe-to-Pipe AUG - - - - - . 2 Feedwater OWN - . - ...
* - -* - - - -PRE -.
R-A(H) 101210 ISI-13142-52-A ISI - - - - - - - - - . R1.11 W-.4 Valve-to-Pipe AUG - - - . 2 Feedwater OWN - - - . .- -
- - - ;- -- - - -- - - - *-- -PRE - . .
R-A(H) 101211 - - ISI-13142-52-A [SI . . . . R1I.-1 W- 5 Valve-to-Pipe AUG - - - - . 1 Feedwater OWN - . - . PRE - - - - - - - - - . R-A(H) -- 101212 --- . -. - - -I . -ISI-13142-52-A IS! R1.11 - W-6 - ; ' Pipe-tI-Pipe - AUG 1 Feedwater OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 144 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I Syslem Scope / Method I Procedure Code Case 1 2 3 4 11 2 3 4 11 2 3 4 R-AJH) 101227 ISIIUTIPEI-02.03.01 ISI-13142-52-A ISI - s R1.11 W-2i Pipe-to-Elbow AUG 1 Feedwater OWN PRE - R-A(H) 101228 ISI/UT/PEI-02.03.01 ISI-13142-52-A ISI - s R1.11 W-22 Elbow-to-Pipe AUG 1 Feedwater OWN PRE R-A(H) 101229 ISI/UTIPEI-02.03.01 151-13142-52-A ISI - s R1.11 W-23 Pipe-to-Safe End AUG 1 Feedwater OWN PRE R-A(H) 101241 ISI-13142-52-A ISI R1.11 W-35 Pipe-to-Elbow AUG . 1 Feedwater OWN PRE R-A(H) 101242 ISI-13142-52-A ISI R1.11 W-36 Elbow-to-Pipe AUG 1 Feedwater OWN PRE . - R-A(H) 101243 ISI-13142-52-A ISI RI.11 W-37 Pipe-to-New Safe End AUG I Feedwaier OWN PRE - R-A(H) 101260 ISI-13142-53-A ISI R1.11 W- 1 Valve-to-Tee AUG 2 Feedwater OWN PRE R-A(H) 101261 IS1-13142-53-A ISI R1.11 W- 2 Tee-to-Pipe AUG 2 Feedwater OWN PRE R-AIH) 101262
- ISI-13142-53-A IsI R1.11 W-3; Pipe-to-Pipe ! AUG 2 Feedwater OWN
( . PRE Printed 3/4/2005
(, (.C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 145 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I
- Period 2 Period 3 Category, Iso No..
ItemNO, Comp. Desc. I S ,M h. Pr I. 1 2 3 4 1 2 3 4 1 23 A Class.-*- - Summary / CompiD /System - . Scope I Method I Procedure Code Case ..-. R-A(H) 101263 ISI-13142-53-A MI - - . R1.1 1 W- 4 Pipe-to-Valve AUG 2 Feedwater - .- OWN OW . - .- - - PRE ISI-13142-53-A ISI . . s R-A(H) 101264 R1.11 W- 5 Valve-to-Pipe AUG OWN - - _ 1 , Feedwater PRE-- 11¶0Atfi) lUlZbo ISI-13142-53-A lSI' 5 R1.1 I W- 6 Pipe-to-Pipe AUG Feedwater OWN Par_ 101268 ISI-13142-53-A ISI-R-A(H) R1.11 W- 9 Valve-to-Elbow AUG I . Feedwater OWN
... .RE -. -- -- - ---- *-- --- - -- - --
- R
-' , ,~~
ISI-13142-53-A PIS . - - - - - - - - - - - R-A(H) 101269 R1.1 1 W-10 Elbow-to-Valve AUG . 1 Feedwater --1 - - - - - - .
- -,.-., -- - PRE : - - . _
R-A(H) 101270 ISI-13142-53-A ISI R1.1 1 W-1I Valve-to-Pipe AUG 1 Feedwater OWN
. - --. -. -- - - ~ PRE -. : - . -- .
R-A(H) 101280 ISI-13142-53-A ISI - . . Pipe-to-Elbow AUG - . R1.1 1 W-21
; - OWN 1 Feedwater PRE - - - -
ISI-13142-53-A ISI s - R-A(t) 101281 R1.11 W-22 Elbow-to-Pipe AUG . . . . . 1 Feedwater OWN PRE K2, .. I
- 1e1-1t14o-Sae E P ISI s - -
R1.1 I - W-23 '. . . IPipe-to-Safe End AUG 1 Feedwater OWN PRE Printed 3I412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 146 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class - Sunmmary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 R-AIH) 101285 ISI-13142-53-A IS1 . R1.11 W-26 Tee-to-Reducer AUG 1 Feedwater OWN PRE R-A(H) 101286 ISI-13142-53-A IS1 s-R1.11 W-27 Reducer-to-Pipe AUG 1 Feedwater OWN .... PRE R-A(H) 101294 ISI-13142-53-A ISI . R1.11 W-35 Pipe-to-Elbow AUG 1 Feedwater OWN - - - . PRE - R-A(H) 101295 ISI-13142-53-A ISI R1.11 W-36 Elbow-to-Pipe AUG I Feedwater OWN . PRE - . R-A(H) 101296 ISI-13142-53-A ISI R1.11 W-37 Pipe-to-New Safe End AUG I Feedwater OWN PRE - - - - - R-A(H) 101869 ISI-97003-A ISI . R1.11 W-10 Pipe-to-Weldolet AUG 1 RHR Return A OWN - PRE - R-A(H) 101870 ISI-97003-A [SI - - - . R1.1 1 W-11 Weldolet-to-Flange AUG 1 RHR Return A OWN PRE R-A(H) 101871 ISUUTIPEI-02.03.01 ISI-97003-A ISI c r - - . - .. R1.11 W-12 Pipe-to-Elbow AUG - - - . 1 RHR Return A OWN - - - - - - - PRE - - - . R-A(H)- 101872 ISVIUT/PEI-02.03.01 . ISI-97003-A ISI c R1.11 - W-13. ' Elbow-to-Pipe AUG I PH-R Return A OWN (... PRE Printed 31412005
- C : -, C .1 o Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 147 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
. - Period 1 Period 2 Period 3 Category, Iso No. -:
ItemNO, Comp. Desc. Class -. Summary /CompID / System - --Scope I Method I Procedure CodeCase -. - . - I .2, 3..4 1 2 3 4 1 .2 .3. 4 R-A(H) 101873 . ISI-97003-A ISI, R1.11 W-14 Pipe-to-Branch AUG 1 RHR Retum A OWN PRE R-A(H) 101874 ISI-97003-A S- ISI s R1.11 W-15 Pipe-to-Elbow AUG 1 RHR Retum A , - OWN R-A(H) 101875 ISI-97003-A IS1-S R1.11 W-16 Elbow-to-Pipe AUG
- 1. RHR Retum A OWN
,, . ..- 'PRE R-A(H) 101876 ISI-97003-A ISI R1.11 W-17 Pipe-to-Elbow AUG 1 RHR Retum A OWN
. - PRE R.A(H) 101877 : ISI-97003-A ISI-,
R1.11 W-18--S Elbow-to-Pipe AUG 1 ' RHR Retum A -OWN.-- PRE R-A(H) 101878. ISI-97003-A IS1 R1.11 W-19 Pipe-to-Elbow AUG 1 RHR Retum A OWN
- - - - PRE' R-A(H) 101879 ISI-97003-A ISI -
R1.11 W-20 Elbow-to-Pipe AUG 1 RHR Retum A OWN PRE R-A(H) 101880 ISI-97003-A ISI R1.11 W-21 Pipe-to-Branch AUG 1 RHR Retum A OWN - PRE - - - - - - - - - - - -- R-A(H) 101881 ' '; ' .. ,IS1-97W3-A . . ,i I , ISI R1.11 I W-22 . - ; ., . . Branch-to-Flange AUG 1IA RHR Retum A OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 148 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 .1 ,2 3 4 R-A(H) 101882 ISI-97003-A ISI R1.11 W-23 Pipe-to-Valve AUG 1 RHR Return A OWN PRE - - - . R-A(H) 101883 ISI-97003-A ISI R1.11 W-24 Valve-to-Pipe AUG 1 RHR Return A OWN PRE R-A(H) 101884 ISI-97003-A ISI R1.11 W-25 LS D Pipe-to-Pipe AUG I RHR Return A OWN PRE R-A(H) 101949 ISI-97004-A ISI.s R1.11 W-10 Pipe-to-Elbow AUG 1 RHR Return B OWN PRE R.A(H) 101950 ISI-97004-A ISI-s R1.11 W-11 Elbow-to-Pipe AUG 1 RHR Return B OWN PRE' R-A(H) 101951 ISI-97004-A ISI R1.11 W-12 Pipe-to-Weldolet AUG 1 RHR Return B OWN PRE' R-A(H) 101952 ISI-97004.A ISI R1.11 W-13 Pipe-to-Weldolet AUG 1 RHR Return B OWN PRE R-A(H) 101953 ISI-97004-A ISI R1.I1 W-14 Weldolet-to-Flange AUG V 1 RHR Return B OWN PRE R-A(H) 101954- ISUUTiPEI-02.03.01 ISI-97004-A IS' C R1.11. W-15 ' Pipe-to-Elbow AUG 1 141R Return B OWN PRE C. p
C C Pg C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 149 of 332
. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
I I
-Period I Period 2 Period 3 Category, Iso No.
ItemNO, Comp. Desc. Code Case 1 2 3 4 1 2 3 A 1 9 A I Class Summary I/ComplD I System Scope I Method I Procedure
... ISIIUTIPEI-02.03.01
... . ISI-97004-Ais c.
R.A(H) 101955 R1.1 1 W-16 Elbow-to-Pipe AUG . 1 . RHR Retum B OWN .
-.-.-- =---. -. . PRE -
R-A(H) 101956 ISI-97004-A ISI R1.11 W-17 Pipe-to-Elbow AUG . OWN 1 RHR RetumB PREN - .. .- ..- - . .. - R-A(H) 101957 ISI-97004-A' ISI R1.11 W-18 Elbow-to-Pipe AUG . OWN. RHR Return .P RE - -. . - - . -.- - - --. R-A(H) 101958 ISI-97004-A ISI W-19 Pipe-to-Elbow AUG - - . R1.11 OWN I RHR RetumB N -. - -. ,. - -- PR ISI-97004-A - - - - - . . R-A(H) 101959 R1.1 1 W-20 Elbow-to-Pipe AUG - - - : OWN 1 . RHR RetumB
------ PRE- - . . - . . .
101960 ISI-97004-A IS - - - - R-A(H) W-21 Pipe-to-Weldolet AUG a - - . R1.1 1 OWN - . 1, RHR Return B
.. .. . . ...... . PR.E.
R-A(H) 101961 , ISI-97004-A [SI R1.11 W-22 Weldolet-to-Flange AUG . OWN 1, , RHR ReturnB R-A(H) 101962 ! ' ' : PREISI-97004A [St R1.11 W-23 Pipe-to-Valve AUG RHR ReturnBB OWN - . 1 PRE - - - - . Jbi-VIUU4-A ISI R1.11, W -24 , , . . , , . - Vatve-to-Pipe ' AUG 1 RHR RetumnB OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 150 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. lIemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 411 2 34 1 2 3 4 R.A(H) 100453 ISI-13142-26-A 151 - - - - - R1.14 W-20 Safe End-to-Nozzle AUG 1 Core Spray B OWN PRE - - - - ... R-A(H) 100514 ISI/UT/PEI-02.03.01 ISI-13142-31-A ISI - s R1.14 W-15 Safe End-to-Nozzle AUG 1 Core Spray A OWN PRE-R-A(H) 101230 ISI/UT/PEI-02.03.01 ISI-13142-52-A ISI - s R1.14 W-24 New S.E.-to-Old S.E. AUG 1 Feedwater OWN PRE R-A(H) 101231 ISI/UTiPEI-02.03.01 ISI-13142-52-A ISI - s . R1.14 W-25 Safe End-to-Nozzle AUG 1 Feedwater OWN PRE - - - - - - - - - - - - R-A(H) 101244 ISI-13142-52-A ISI E R1.14 W-38 New S.E.-to-Old S.E. AUG I Feedwater OWN PRE R-A(H) 101245 ISI-13142-52-A ISI R1.14 W-39 Safe End-to-Nozzle AUG 1 Feedwater OWN PRE R-AIH) 101283 ISI-13142-53-A ISI R1.14 W-24 New S.E.-to-S.E. AUG 1 Feedwater OWN PRE R-A(H) 101284 ISI-13142-53-A ISI R1.14 W-25 Safe End-to-Nozzle AUG 1 Feedwater OWN PRE R-A(H). - 101297 ISI-13142-53-A 5lS R1.14 W-38 New S.E.-to-S.E. AUG P.. .. 1 Feedwater OWN ( PRE Printpd 1/41?rf05
C C C
. Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 151 of 332
- - ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 1 2 3 A 2 3 A 1 I I A Class_ Summary I ComplD I System Scope I Method I Procedure Code Case 1 R-A(H) 101298 ISI-13142-53-A ISI . R1.14 W-39 Safe End-to-Nozzle AUG 1 Feedwater OWN
-.- PRE-102034 ISI-97005-B IS5 R-A(H)
R1.14 W-4 Safe End-to-Nozzle AUG 7 1 Recirc Manifold A OWN - - - ; 102041- *R-A-H- -PRE -- - -- - -.-.-. - -- ~ 102041 ISI-97005-B ISI - - - - s R-A(H) Safe End-to-Nozzle AUG - ; R1.14 W-11 OWN 1 Recirc Manifold A -*OW - - -- -- -- 7 -R PRE R-A(H) 102048- . ISI-97005-B ISI-R1.14 W-18 Safe End-to-Nozzle AUG .1 . . Recirc Manifold A OWN 102055 ISI/UTIPEI-02.03.11 ISI-97005-B IS_. s R-A(H) W-25 Safe End-to-Nozzle AUG Ri.14 Recirc Manifold A OWN 1 r
.- --. ~ - PRE-O N -.-- - - - -^
R-A(H) 102062 ISI-97005-B ISI, R1.14 W-32 Safe End-to-Nozzle AUG Recirc Manifold A OWN - - ; 1
.- PRE R-A(H) 102143 . ISI-97006-B ISI R11.14 W- 4 Safe End-to-Nozzle AUG 1 Recirc Manifold B OWN
'- - ' - - - - - PRE - -
R-A(H) 102150 ISI-97006-B ISI R1.14 W-11 Safe End-to-Nozzle AUG 1 Recirc Manifold B OWN PRE - ' t¶-AlflJ 1UZ15 . , I ISI-97006-B lS1 R1.14 W-18 ;' ; Sate End-to-Nozzle AUG 1 Recirc Manifold B OWN PRE Printed 3M/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 152 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. 2 I A 4 2 i A 4 '1 I Class Summary I ComplD I System Scope I Method / Procedure Code Case 1 ISI-97006-B ISI s R.A(H) 102164 W-25 Safe End-to-Nozzle AUG - . R1.14 1 Recirc Manifold B OWN PRE- - R-Alh) 102171 ISI-97006-B ISR - . R1.14 W-32 Safe End-to-Nozzle AUG 1 Recirc Manifold B OWN ___(L) 100054 PRE R-A(L) 100054 ISI-13142-17-A ISI R1.20 W- 2 Valve-to-Reducer AUG 2 RHR Suction A OWN R-A(L) 100067 ISI-13142-17-A IPS-RE R1.20 W- 1 Pipe-to-Valve AUG 2 RHR Suction A OWN R-A(L) 100068 ISI-13142-17-A 151 E R1.20 W- 3 Reducer-to-Tee AUG 2 RHR Suction A OWN 100069 ISI-13142-17-A IPSRE R-A(L) Tee-to-Pipe AUG R1.20 W- 4 2 RHR Suction A OWN PRE - R-A(L) 100070. ISI-13142-17-A 151 E R1.20 W- 5 Pipe-to-Weldolet AUG 2 RHR Suction A OWN R-A(L) 100071 ISI-13142-17-A ISI R1.20 W- 6 Pipe-to-Weldolet AUG 2 RHR SucUon A OWN PRE R-AILI 100072 lIs R1 .20 W-7 Pipe-to-Weldolet AUG 2 RHR Suction A OWN C. PRE L. 3 Printed 3/4/2005
C , C I C,
- Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) - Page 153 of 332 ASME Section Xl. (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) i I -- - . .
Period I1 Period 2 Period 3 Category, . Iso No. ltemNO, Comp. Desc.
- - Scope I Method / Procedure . -- Code Case -: 1 2--3 4 1 .2 3 4 i -2 3. 4 Class ' - Summary I ComplD I System R-AIL) 100073 ISI-13142-17-A ISI .
R1.20 W- 8 Pipe-to-Cap AUG RHR Suction A OWN - - - - - - - - - - - - 2',
.-- - . .- PRE - - - - - - - - - - - -
R-A(L) 100074 ISI-13142-17-A ISI-R1.20 W- 9 Weldolet-to-Pipe AUG RHR Suction A ... - OWN OWN - -- - - - 2 PRE -_ -_ -_ -_ - - - - - - - R.A(L) 100075 ISI-13142-17-A ISI; _ R1.20 W-10 Pipe-to-Pipe AUG 2 RHR Suction A OWN
~PRE .--
R-A(L) 100076 ISI-13142-17-A ISI _ R1.20 W-11 Pipe-to-Pipe AUG - . 2 RHR Suction A.. . .- OWN PRE - - - - - - R.A(L) 100077 - ISI-13142-17-A ISI: . . _ R1.20 W-12 Pipe-to-Valve AUG - . 2 RHR Suction A - -OWN - - - - .- - PRE--- R-A(L) 100078 ISI-13142-17-A ISI R1.20 W-13 Valve-to-Elbow AUG 2 RHR Suction A OWN
.. -- .. - PRE - - - -
R-A(L) 100079 ISI-13142-17-A ISI - R1.20 W-14 Elbow-to-Elbow AUG 2 RHR Suction A OWN
- PRE- - ; - -
R-A(L) 100080 ISI-13142-17-A ISI . R1.20 W-15 Elbow-to-Pump AUG RHR Suction A OWN - - .- 2 PRE . R.A(L) . 100081 ISI-131 42-1 7-A ISI R1.20 : W-16 .IIWeldolet-to-Pipe AUG 2 RHR Suction A OWN PRE n,;m^,vvir,>nnr,
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 154 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 34 1 2 3 4 R-A(L) 100082 ISI-13142-17-A ISI . . . . R1.20 W-17 Pipe-to-Pipe AUG . 2 RHR Suction A OWN . PRE - R-A(L) 100083 ISI-13142-17-A ISI R1.20 W-18 Pipe-to-Pipe AUG 2 RHR Suction A OWN PRE R-A(L) 100084 ISI-13142-17-A IS1 . . . . . R1.20 W-19 Pipe-to-Valve AUG . 2 RHR Suction A OWN PRE - - - . R-A(L) 100085 ISI-13142-17-A IS1 . R1.20 W-20 Valve-to-Elbow AUG . . . . 2 RHR Suction A OWN PRE . R-A(L) 100086 ISI-13142-17-A ISI R1.20 W-21 Elbow-to-Elbow AUG 2 RHR Suction A OWN PRE R-A(L) 100087 ISI-13142-17-A ISI R1.20 W-22 Elbow-to-Pump AUG - 2 RHR Suction A OWN . PRE : R-A(L) 100088 ISI-13142-17-A ISI . . . . R1.20 W-23 Tee-to-Pipe AUG - - . 2 RHR Suction A OWN PRE . . . R-A(L) 100089 ISI-13142-17-A ISI R1.20 W-24 Pipe-to-Elbow AUG . . . 2 RHR Suction A OWN . PRE - - - - - . R-A(L) 100090 ISI-13142-17-A IS' R1i.20 W-25 Elbow-to-Pipe AUG 2 CR Suction A OWN ( PRE Prn6'4,PY
C .C
.MontiC cello Nuclear Generating Plant ASME Section Xi (1995 Edition, 1996 Addenda) 4th Interval 151 Plan (Rev.3)
(May 1, 2003 to May 31, 2012) Page 155 of 332 Period 1 Period 2 Period 3 Category, Iso No. IternNO, Como~. Desci. Class Summary I CompiD I System Scope I Method I Procedure Code Case - 1 23 4 1 23 A I 2 34 R.A(L) 100091. ISI-1 3142-17-A[S- - - - - - - - - - - - R1.20 W-26 Pipe-to-Elbow AUG - - - - - - - - - - - 2 ,. RHR Suction A OWN . . . . . . . . . . . .
-- . -~PRE- -
R.A(L) 100092 .ISI-13142-17-A ISI RI.20 W-27 Elbow-to-Pipe A G - - - - . . RHR Suction A OWN - - -: - - - --- - - - 2
... . - . , . - ..- PR E . -
R-A(L) 100093 ISlI 131 42-1 7-A I1St - - - - - - R1.20 W-28 Pipe-to-Elbow AUG - - - - - - - - - 2, , RHR Suction A .OWN - - - - - - - - - - -
- ... PRE R-A(L) 100094 1S51-I31 42-1 7-A IS!
R1.20 W-29 Elbow-to-Pipe AUG - - - - - - - - - - - - 2 . RHR Suction A OWN - - - - - - - - - - - -
- ..-.-. PRE.
R-A(L) 100095 ISI-13142-1 7-A ISI R1.20 W-30 Pipe-to-Valve AUG - 2RHR Suction A OWVN
~ .,. . . -. . . . , PR E ., -
R-A(L) 100096 1SI.13142-1 7-A 1St R1.20 W-3i1 Valve-to-Weldolet AUG. . . . . . . . . . 2 RHR Suction A OWN
-.. . PRE R-A(L) 100097 ISI-13142-1 7-A t S1S - - - - --
R1.20 W-32 Valve-to-Tee AUG - - - - - - - - - - - - 2 ,. RHR Suction A OWN - - - - - - - - - - - - R-A(L) 100102 ,. . ISI-13142-17-B I11 R1.20 W-1I Tee-to-Pipe AUG - - - - - - - - - - - - 2 HPCI Water Side Sctn OWN PRE - - - - - -- - - - - - R-A(L) '.10.0103 ~ ;' ' ISI-13142-17-B S11 RI.20 j W-.2, _ Ppe-to-Elbow- AUG 2 HPC~I Water Side Sctn OWN PRE Printed 3141205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 156 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case 1 2 3 4 I 2 3 4 1 2 3 4 R-A(L) 100104 ISI-13142-17-B IS1 - - - - - - - . R1.20 W- 3 Elbow-to-Pipe AUG . - - . 2 HPCI Water Side Sctn OWN - - - - - - - . PRE R-A(L) 100105 ISI-13142-17-B IS1 . . . . . . R1.20 W- 4 Pipe-to-Valve AUG - - - - . 2 HPCI Water Side Sctn OWN - - - - - - - . PRE R-A(L) 100106 ISI-13142-17-B [SI . . . . . . . . . . R1.20 W- 5 Valve-to-Pipe AUG 2 HPCI Water Side Sctn OWN - - - - - - - . PRE R-A(L) 100107 ISI-13142-17-B ISI R1.20 W-6 Pipe-to-Elbow AUG 2 HPCI Water Side Sctn OWN - - - - . PRE R-A(L) 100108 ISI-13142-17-B IS1 R1.20 W-7 Elbow-to-Pipe AUG - - - . 2 HPCI Water Side Sctn OWN - - - - - - - . PRE - - - - . R-A(L) 100109 ISI-13142-17-B ISI R1.20 W- 8 Pipe-to-Elbow AUG 2 HPCI Water Side Sctn OWN PRE - - - . R-A(L) 100110 S1-13142-17-B ISI . R1.20 W- 9 Elbow-to-Pipe AUG 2 HPCI Water Side Sctn OWN - - - - - - - . PRE R-A(L) 100111 IS-13142-17-B ISI R1.20 W-10 Pipe-to-Valve AUG 2 HPCI Water Side Sctn OWN PRE R-A(L) 100112 I ISI-13142-17-B 1SI R1.20 W-11 Valve-to-Pipe AUG 2 HPCI Water Side Sctn OWN ( C PRE Printed 3/4/2005
C. C,
- C.
1.Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 157 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class' .Summwary/ICompiD/ISystem Scope I Method I Procedure Code Case 1 23 4 1 23 4 1 2 34
- s. . . . . . . . . . . .
R-A(L) 100113 .ISI-13142-17-B R11.20 W~-12 Pipe-to-Valve AuJG 2 HPCI Water Side SctnOW ISI-13142-17-C S- - - - - - - - - - - - R-A(L) 100137. . Tee-to-Pipe AUG R1.20 W- I OWN
- 2. RHR Suction B
- .. E_ _ _ _ _ _ _PR R.A(L) 100138 .ISI-13142-17-C IS!
Pipe-to-Elbow AUG - - - - - - - - - - - - R11.20 W- 2 OWN -- - - - - - - - - - - - 2 RHR Suction B 151 . . . . . . R-A(L) 100139 .. .ISI-13142-17-C RI.20 W- 3 Elbow-to-PipeAG RHR Suction B OWN 2 . P- W N.-.- - - - -...- -
.- .. ~ ..
R-
.ISI-1 ( ) 1 0 4 ~ 31 42-1 7-C ISI1 W- 4 Pipe-to-Elbow AUG R1.20 OWN 2 RHR Suction B PR E -
ISI-13142-1 7-C ISI R.A(L) 100141 Elbow-to-Pipe AUG' - - - - RI1.20 W-15 OWN ---- 2 RHR Suction B PRE -- -- - - - - - - IS15-13142-17-C I1S t - - - - -- R-A(L) 100142 Pipe-to-Elbow 'AUG R1.20 W- 6
- 2. RHR Suction BOW P RE _ _ _ _ _ _ _ _ _ _ _
R-A(L) 100143 ISI1-I31 42-1 7-C Isi-W - - - - R11.20 W-7 Elbowv-to-Pipe .AUG - - - - - - - - - - - - OWN - - - - - - - - - - - - 2 RHR Suction B
. . .. .PRE PRE R1.20, W - 8._. - . . : Pipe-to-Valve' AUG 2 RHR Suction B OWN PRE Printpcl 314I2O05
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 158 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO. Comp. Desc. Class Summary I ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100145 ISI.13142-1 7-C I11 - - - - -- R1.20 W- 9 Valve-to-Weldolet AUG 2 RHR Suction B OWN PRE R-A(L) 100146 ISI-13142-17-C [SI R1.20 W-10 Weldolet-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 100147 ISI-13142-17-C ISI R1.20 W-11 Valve-to-Reducer AUG 2 RHR Suction B OWN PRE R-A(L) 100148 ISI-13142-17-C ISI R1.20 W-12 Reducer-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 100149 ISI-13142-17-C IsI R1.20 W-13 Pipe-to-Weldolet AUG 2 RHR Suction B OWN PRE. R-A(L) 100150 ISI-13142-17-C ISI R1.20 W-14 Weldolet-to-Valve AUG 2 RHR Suction B OWN PRE R-AIL) 100151 ISI-13142-17-C ISI - R1.20 W-15 Valve-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 100152 ISI-13142-17-C ISI R1.20 W-16 Pipe-lo-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 100153 ISI-13142-17-C ISI R1.20 W-17 Pipe-to-Pipe AUG -- --. 2 RHR Suction B OWN PRE I. Printed 3/4/2005
C 4th Interval ISI Plan (Rev.3)
.C Page 159 of 332 Monticello Nuclear Generating Plant
. ASME Section Xi (1995 Edition, 1996 Addenda) .(May 1, 2003 to May 31, 2012)
- I Period I - Pe Hod 2 - Period 3 Category, - Iso No..
ItemNO, - Comp. Desc. Class - Summary I CompiD I System Scope / Method I Procedure - Code Case - - - . 1. - 2 .3 4 -1 .2 . 3_.4 I1 2., 3 -4.-
~~ .1_ .2. _3._..4.
R-A(L) 100154 - 151-13142-17-C IS, R1.20 W-18 Pipe-to-Elbow AUG - _ 2 RHR Suction B . OWN - - . PRE . . . ._ '. . . . . . . R-A(L) 100155 ISI-13142-17-C ISI . R1.20 W-19 Elbow-to-Elbow AUG . . . . 2 - ' RHR Suction B OWN . PRE R-A(L) 100156 ISI-13142-17-C ISI- . . . . . . . . . . . R1.20 W-20 Elbow-to-Pump AUG . 2 RHR Suction B OWN - .
-'PRE - - -
RAL 100157 --- R-A(L) 100157 ISI-13142-17-C ISI . . . . . . R1.20 W-21 Pipe-to-Weldolet AUG 2 RHR Suction B - OWN PRE ISI-13142-17-C ISI - - . R-A(L) 100158 Rl.20 W-22 Weldolet-to-Valve AUG . RHR SuctionB -- ' ' ; :" OWN - - - - - - - - - - - - 2
- .-.. ,-.~PRE- '.-
R-A(L) 100159 ISI-13142-17-C ISI
- R1.20 W-23 Valve-to-Pipe-. AUG 2 RHR Suction B - - OWN PRE R-A(L) 100160 ISI-13142-17-C ISI Ri.20 W-24 Pipe-to-Pipe AUG . .
2; RHR Suction B OWN
. - -PRE R-A(L) 100161 ISI-13142-17-C ISI R1.20 W-25 Pipe-to-Pipe AUG RHR Suction B OWN -
2 PRE n~- -!._ ISI rn Af*t - IS1-13142-17-C n-MILJ RI.20 W-26 Pipe-to-Elbow. - AUG 2 RHR Suction B OWN PRE Printed 3/4t2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 160 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO. Comp. Desc. Class Summary I ComplD / System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100163 ISI-13142-17-C ISI - R1.20 W-27 Elbow-to-Elbow AUG 2 RHR Suction B OWN PRE - R-A(L) 100164 ISI-13142-17-C ISI R1.20 W-28 Elbow-to-Pump AUG . 2 RHR Suction B OWN PRE - - - - - -. R-A(L) 100165 ISI-13142-17-C ISI R1.20 W-29 Valve-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 100166 ISI-13142-17-C ISI . R1.20 W-30 Pipe-to-Elbow AUG 2 RHR Suction B OWN PRE - . R-A(L) 100167 ISI-13142-17-C IIs . R1.20 W-31 Elbow-to-Pipe AUG 2 RHR Suction B OWN PRE . . . . . . . .. . . . R-A(L) 100181 ISI-13142-18-A ISI R1.20 W- 1 Tee-to-Pipe AUG 2 RHR Discharge B OWN PRE R-A(L) 100182 ISI-13142-18-A ISI R1.20 W- 2 Pipe-to-Elbow AUG 2 RHR Discharge B OWN PRE R-A(L) 100183 ISI-13142-18-A ISI R1.20 W- 3 Elbow-to-Reducer AUG 2 RHR Discharge B OWN PRE R-A(L) 100184 :ISI-13142-1 8-A iSI R1.20 W-4 Tee-to-Pipe AUG 2 uR Discharge B OWN PRE C PrinLnd 114r;nn
C -
-Monticello Nuclear Generating Plant C
4th Interval ISI Plan (Rev.3) g Page 161 of 332
.( 3
-, ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I 2 A A I I 3 A 1 I 3 A Class- - Surmmary I ComplD I System Scope I Method / Procedure Code Case R-A(L) 100185 . ISI-13142-18-A ISI R1.20 W- 5 Pipe-to-Elbow AUG . 2 . RHR Discharge B OWN PRE -- . .. R-A(L) 100186 ISI-13142-18-A ISI . R1.20 W- 6 Elbow-to-Pipe AUG 1. R .,,..A '2 A1 R.^ll~~~~~~ .- 2 RHR Discharge B OWN R-A(L) 100187 - ISI-13142-18-A ISI W- 7 Pipe-to-Elbow AUG . R1.20 2 RHR Discharge B OWN
......- - PRE wloou - I., Ib15-1 31 4Z-1 B-A ISI R1.20 W- 8 Elbow-to-Pipe AUG 2 .; RHR Discharge B OWN Dom _
R-A(L) 100189 , ISI-13142-18-A ISI Pipe-to-Elbow AUG - : R1.20 W- 9 OWN : ; : : : : 2 . RHR Discharge B
- ---..- . .-. -.-. ,. .-.-. . ---- . PRE-. .- , -
ISI-13142-18-A ISI _ R-A(L) 100190 W-10 Elbow-to-Pipe AUG - - - : R1.20 2 RHR Discharge B OWN
- -. . - .- . . -. ~P RE-. - - - . , - -
ISI-13142-18-A ISI - . R-A(L) 100191 W-11 Pipe-to-Pipe AUG - - : R1.20 2 RHR Discharge B OWN PRE-. R-A(L) 100192 SI-13142-18-A ISI - Ri.20 W-12 Pipe-to-Pipe AUG 2 RHR Discharge B OWN PRE *-4f- - - - -PRE-a {l1 nI'.ML.1 A lVIYJ II . . ISI-13142-18-A . IS' Rl.20- W-13, -: . Pipe-to-Tee AUG 2 RHR Discharge B OWN PRE Printed 314/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 162 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Perlod 1 PerIod 2 Period 3 Category, Iso No. IlemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100194 ISI-13142-18-A ISI - R1.20 W-14 Tee-to-Pipe AUG . . . . . . . . ... . . 2 RHR Discharge B OWN PRE - R-A(L) 100195 ISI-13142-18-A ISI R1.20 W-15 Pipe-to-Pipe AUG - - . - ...- 2 RHR Discharge B OWN - - - - - - - - . PRE - - - - .. . R-A(L) 100196 ISI-13142-18-A ISIs - - - - - R1.20 W-16 Pipe-to-Valve AUG - - .- . - 2 RHR Discharge B OWN - - - - - . PRE . . R-A(L) 100197 ISI-13142-18-A ISI - . R1.20 W-17 Valve-to-Elbow AUG - - - - . 2 RHR Discharge B OWN - - - - - . PRE R-A(L) 100198 ISI-13142-18-A ISI - - - - - - - - . R1.20 W-18 Elbow-to-Valve AUG - - .- ... 2 RHR Discharge B OWN - - - - - . PRE - R.A(L) 100199 ISI-13142-18-A ISI - - - - - - - - - - . R1.20 W-19 Tee-to-Elbow AUG 2 RHR Discharge B OWN - - - - - - . PRE - - - - - - . R-A(L) 100200 IS1-13142-18-A IS1 . . . . R1.20 W-20 Elbow-to-Reducer AUG - - - . 2 RHR Discharge B OWN - - - - - - . PRE . . ... . R-A(L) 100201 ISI-13142-18-A ISI - - - - - - R1.20 W-21 Reducer-to-Pipe AUG . . . . . . . . . . . . 2 RHR Discharge B OWN .I - - - - - - . PRE R-A(L) 100202 ISI-13142.18-A iSI R1.20 W-22 Pipe-to-Elbow AUG . 7 . .- I. 2 RHR Discharge B OWN ( C PRE printed 3/4/2005
i Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) , Page 163 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 .: Period 2 . Period 3 Category, , Iso No. *I I - I. ItemNO, -- r Comp. Desc.. Scn/ehd- /Procedure- Code Case- 1. 2 3_4 1 2 .3 4 1 2. 3. 4, R-A(L) 100203 -. ISI-13142-18-A [SI. - - R1.20 W-23 Elbow-to-Valve AUG 2 RHR Discharge B . OWN - - - - -
,,, ,,.PRE .- -; -- : .. -
R.A(L) 100204 ISI-13142-18-A ISI .- - . R1.20 W-24 Valve-to-Pipe.. AUG . . . . 2 RHR Discharge B , - - OW - .- - - - - -
.-. PRE
~
*IU se*-R no r.-$*
R-A(L) 100205- ISI-13142-1 8-A 1Sl1 Pipe-to-Weldolet AUG R1.20 W-25 2 RHR Discharge B OWN PRE R-A(L) 100206 ISI-13142-18-A ISI R1.20 W-26 Pipe-to-Valve AUG 2 RHR DischargeBB OWN - -
- ~ ~~PR E - ~ - ' .
R-A(L) 100213 ISI-13142-18-B ISI,, R1.20 W- 1 Pump-to-Elbow AUG 2 RHR Discharge B
~....
.. ......- ~,OW *PRE-.
- --- - ~---.~~
R-A(L) 100214 ISI-13142-18-B ISI R1.20 W- 2 Elbow-to-Reducer AUG 2 RHR DischargeB OWN
,, ,.--PRE R-A(L) 100215 ISI-13142-18-B ISI :
R1.20 W- 3 Reducer-to-Valve AUG 2 RHR Discharge B OWN
- -:-PRE R-A(L) 100216 ISI-13142-18-B ISI R1.20 W- 4 Valve-to-Pipe AUG 2 RHR Discharge B OWN PRE - - - - - - - - - - - -
R-A(L) 100217 : .151e-t14Z-1V P v - 101 W- 5
- 1 Pipe-to-Valve : AUG R1 .20 . .
2 RHR Discharge B OWN PRE PrWarl 1141?nn;
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 164 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary / ComplD I System Scope / Method I Procedure Comp. Desc.
Code Case 2 d1 r1 1II 1 1.4 2) - A R-A(L) 100218 ISI-13142-18-B ISI R1.20 W- 6 Valve-to-Elbow AUG 2 RHR Discharge B OWN PRE R-A(L) 100219 ISI-13142-18-B ISI R1.20 W- 7 Elbow-to-Elbow AUG 2 RHR Discharge B OWN PRE R-A(L) 100220 ISI-13142-18-B ISI R1.20 W- 8 Elbow-to-Pipe AUG 2 RHR Discharge B OWN PRE R-A(L) 100221 ISI-13142-18-B ISI R1.20 W-9 Pipe-to-Tee AUG 2 RHR Discharge B OWN PRE R-A(L) 100222 ISI-13142-18-B ISI R1.20 W-10 Pump-to-Elbow AUG 2 RHR Discharge B OWN PRE R-A(L) 100223 ISI-13142-18-B ISI R1.20 W-11 Elbow-to-Reducer AUG 2 RHR Discharge B OWN PRE R-A(L) 100224 ISI-13142-18-B ISI RI.20 W-12 Reducer-to-Valve AUG 2 RHR Discharge B OWN PRE-R-A(L) 100225 ISI-13142-18-B ISI R1.20 W-13 Valve-to-Pipe AUG 2 RHR Discharge B OWN PRE I I1I-13142-18'-B ISI R1.20 W-14 : Pipe-to-Valve . AUG 2 RHR Discharge B OWN PRE C -P- Ptin~led 31412005
C C 4th Interval ISI Plan (Rev.3) C1 Page 165 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class' Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100227 ISI-13142-18-B ISI R1.20 W-15 Valve-to-Elbow AUG - : 2 RHR DischargeB OWNB R-A(L) 100228 ISI-13142-18-B ISI _ R1.20 W-'16 Elbow-to-Elbow AUG - - - - ; 2 RHR Discharge B OWN _._PRE R-A(L) 100229 ISI-13142-18-B ISI R1.20 W-17 Pipe-to-Pipe AUG - - - : 2 RHR Discharge B OWN ; PRE -- - - - -- - - - R-A(L) 100230 ISI-13142-18-B ISI R1.20 W-18 Pipe-to-Tee AUG 2 RHR Discharge B OWN - - - : PRE - - - - - - - - - - - - R-A(L) 100231 . - ISI-13142-18-B ISI R1.20 W-19 Elbow-to-Reducer AUG' : 2 RHR Discharge B - - OWN
... . --.-. .-.. .... . .. ......- PRE..-..- : : ::
R-A(L) 100232 ISI-13142-1 8-B ISI ------------ R1.20 W-20 Reducer-to-Pipe AUG ; 2 RHR Discharge B OWN : PRE - ;- R-A(L) 100233 ISI-13142-18-B ISI R1.20 W-21 Pipe-to-Tee AUG 2 RHR Discharge B OWN PRE . ; R-A(L) 100234 ,.. ISI5-13142-18-B ISI R1.20' W-22 Tee-to-Pipe AUG 2 RHR Discharge B OWN PRE . . - R-A(L) . 100235 ISI-13142-18-B lSI R1.20 W-23 Pipe-to-Tee AUG 2 RHR Discharge B OWN PRE Printed 3/412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 166 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I q . 4 q e Code Case f A Class Summary I CompiD / System Scope / Method / Procedure 4 I R-A(L) 100236 ISI-13142-18-B SI R1.20 W-24 Tee-to-Pipe AUG 2 RHR Discharge B OWN
- ~~~~~~PRE R-A(L) 100237 ISI-13142-18-B ISI R1.20 W-25 Pipe-to-Elbow AUG 2 RHR Discharge B OWN R-A(L) 100238 ISI-13142-1PRE IS1 E R1.20 W-26 Elbow-to-Valve AUG 2 RHR Discharge B OWN R-A(L) 100239 ISI-13142-18-B IPsRi E
R1.20 W-27 Valve-to-Reducer AUG 2 RHR Discharge B OWN PRE - - - - - - - - - - - - R-A(L) 100240 ISI-13142-18-B ISI E R1.20 W-28 Reducer-to-Nozzle AUG 2 RHR Discharge B OWN PRE R-A()
-1024 ISI-R-A(L) 100241 ISI-13142-18-B R1.20 W-29 Tee-to-Pipe AUG 2 RHR Discharge B OWN R-A(L) 100242 ISI-13142-18-B ISI R1.20 W-30 Pipe-to-Elbow AUG 2 RHR Discharge B OWN PRE R A(L) 100243 ISI-13142-18-B ISI R1.20 W-31 Elbow-to-Valve AUG 2 RHR Discharge B OWN PRE I~ ^On R-A(L) 100244 alv-to-Pipe lSI R1.20 W-32 Valveo-tPipe AUG 2 RHR Discharge B OWN
( PRE Printed 314/2005
C i~ .... Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) ; ., ; Page 167 of 332, ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
,I
- Period I Period 2 Period 3 Category. Iso No. 'I 1I ItemNO, Comp. Desc.
Class - - I. . Summarv i ComnlD i' Svstem Methnd, 1DI-rnc.rl. Code Case 1 2 3 4 1 2 3 4 1 2 3 4
- __ - __- ___ , -- - - - -_ - j _- -' vxvr-c
/InAe
~VUtrvxU~
R-A(L) 100245 . .ISI-13142-13 ISI. R1.20 W-33 Pipe-to-Tee AUG 2 . RHR Discharge B OWN
-R-APRE-100249--PRE-R-A(L) 100249 ,. ISI-13142-18-C ISI R1.20 W- 1 Nozzle-to-Elbow AUG 2 RHR Discharge B -OWN A-.L----100250----PRE ...
R.A(L) 100250 . ISI-13142-18-C ISI R1.20 W-2 Elbow-to-Pipe AUG - - - - - - - 2 RHR Discharge B OWN . . . . PRE.-...-. R-A(L) 100251 . ISI-13142-18-C ISI - - - - . R1.20 W- 3 Pipe-to-Elbow AUG . . . . . . . 2 RHR Discharge B OWN
-- - -PRE - -
R-AL 100252. ... . ... R-A(L) 100252 ISI-13142-18-C ISI R1.20 W-i Elbow-to-Pipe AUG . _. OWN .; . . 2 RHR Discharge B
........... .............. _-..-PRE--.....
R-A(L) 100253 .ISI;13142-1 8-C ISI -- W- 5 Pipe-to-Elbow AUG . . . . . . . . . R1.20 2 RHR Discharge B OWN .
- PRE-R-A(L) 100254 ISI-13142-18-C ISI - - - - - - - .
R1.20 W-6. Elbow-to-Pipe AUG - : RHR Discharge B OWN . . . . . . . . 2 .
- --- PRE - ..
R-A(L) 100255 ISI-13142-18-C ISi . R1.20 W-7 Pipe-to-Valve AUG 2 RHR Discharge B OWN - - - - - . PRE - - - - - - - - - . f%-MtL , 1 ULO . ISI
. a.IS-13142- 18-C R1.20 W- 8 AUG 2 RHR Discharge B OWN PRE Printed 3/412wS
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 168 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100257 ISI-13142-18-C IS R1.20 W- 9 Elbow-to-Pipe AUG 2 RHR Discharge B OWN PRE . - - R-A(L) 100258 ISI-13142-18-C ISI R1.20 W-10 Pipe-to-Tee AUG 2 RHR Discharge B OWN PRE R-A(L) 100259 ISI-13142-1 8-C IS1 Ri.20 W-11 Tee-to-Pipe AUG . 2 RHR Discharge B OWN PRE R-A(L) 100260 ISI-13142-1 8-C ISI R1.20 W-12 Pipe-to-Elbow AUG 2 RHR Discharge B OWN PRE R-A(L) 100261 ISI-13142-1PiC ISI R1.20 W-13 Elbow-lo-Pipe AUG 2 RHR Discharge B OWN PRE . _. .. t t R-A(L) 100262 ISI-13142-18-C ISI R1.20 W-14 Pipe-to-Tee AUG 2 RHR Discharge B OWN PRE R-A(L) 100274 ISI-13142-19-A ISI R1.20 W- 1 Cap-to-Pipe AUG 2 HPCI Steam Disch OWN PRE - R-A(L) 100275 ISI-13142-19-A ISI R 1.20 W- 2 Tee-to-Pipe AUG 2 HPCI Steam Disch OWN PRE R-A(L) 100276 . I. ISI-13142-19-A ISI R1.20 W-3 Flange-to-Tee. AUG 2 IHPCI Steam Disch OWN Q.. C. PRE Printr-1 IM1200.9
PC Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) : Page 169 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
.P. Ii
.. . Periodd 1 Period 2 j Period 3 Category, Iso No.
ItemNO, Comp. Desc. Class . Summary / CompiD / System . . . Scope/ Method / Procedure Code Case 1 2 3 4 I1 2 3 4 1 2 3 4 ISI-13142-19-A _ R-A(L) 100277 R1.20 W- 4 Tee-to-Reducer AUG .
, ., , OWN
- 2. HPCI Steam Disch
- pRE...
R-A(L) 100278 ISI-13142-19-A ISI , Reducer-to-Elbow AUG - r R.20 W-2 HPCI Steam Disch . OWN - .:
- -- - --- PRE . ; _
R-A(L) 100279 ISI-13142-19-A 1..
.-.. .. .-.-. .,..,. .-..- PR..E R1.20 W- 6 Elbow-to-Pipe AUG 2 HPCI Steam Disch OWN
.- - PRE -
R-A(L) 100280 ISI-13142-19-A IS-R1.20 W- 7 Pipe-to-Elbow AUG 2- HPCI Steam Disch . .. W
. . Ds Sa. .OWN - - - - - - - - -
R-A(L) 100281 .. ISI-13142-1 9-A ISI _ Elbow-toPpe
- - - - ~~ ~
- - * -- PR E -
AUG R1.20 W- 8 .- - - - -. . 2 HPCI Steam Disch . OWN
- -- -. PRE R-A(L) 100282 ISI-13142-19-A ISI .1_
R1.20 W- 9 Pipe-to-Elbow AUG 2 HPCI Steam Disch OWN 7 PRE R-A(L) 100283 - - ISI-13142-19-A 131 - - - -- R1.20 W-10 Elbow-to-Pipe AUG ............ 2 - HPCI Steam Disch..OW - -
-W .. -- - - *--R - - - -- -.
R-A(L). 100284 -;ISI-13142 19- IS R1.20 W-11 Pipe-to-Tee AUG 2 HPCI Steam Dlsch OWN D aPRE MK#4%Ll '1 W 'd Z) ; . -. . . - I. ISI-13142-19-A ISI R1.20 - .W-12. ;.. I Tee-to-Flange AUG 2 HPCI Steam Disch OWN PRE Printpd 1t4t2nO5
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 170 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I 2 3 2 3 I I 72 1 A Class Summary I ComplD I System Scope I Method I Procedure Code Case A I A R-A(L) 100286 ISI-1 3142-19-A ISI R1.20 W-13 Flange-to-Pipe AUG 2 HPCI Steam Disch OWN PRE - - R-A(L) 100287 ISI-13142-19-A ISI R1.20 W-14 Pipe-to-Flange AUG 2 HPCI Steam Disch OWN PRE R-A(L) 100288 ISI-13142-19-A IS-I E R1.20 W-15 Tee-to-Pipe AUG 2 HPCI Steam Disch OWN PRE . . . . . . . . . . R-A(L) 100289 ISI-13142-19-A ISI R1.20 W-16 Pipe-to-Elbow AUG 2 HPCI Steam Disch OWN
-AI _ _ PRE-PREA~.n .- 9
.-. A..A . .. ...
Elw-1to14Z-1PiA ISI R1.20 W-17 Elbow-lo-Pipe AUG 2, HPCI Steam Disch OWN noc llV)l'-' VnI ! - - - I - - - I - - IW
.. Pip-1314t-19-A ISI R1.20 W-18 Pipe-to-Elbovw AUG 2 - HPCI Steam Disch OWN DDD .
rr . R-A(L) 100292 ISI-13142-19-A ISI R1.20 W-19 Elbow-to-Valve AUG 2 HPCI Steam Disch OWN R-A(L) 100293 ~~~PRE ------------ R-A(L) 100293 ISI-13142-19-A IS[ R1.20 W-20 Valve-to-Pipe AUG 2 HPCI Steam Disch OWN R.AII I 4 AA PRE ISI-13142-19-A 5lS 1RI.20. W-21 Pipe-to-Valve AUG 2 HPCI Steam Disch OWN _Q. ( PRE Printed 3/412005
C IMonticello Nuclear Generating Plant C 4th Interval ISI Plan (Rev.3)
-I .
Page 171 of 332 C
. ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to May.31, 2012)
- Period I Period 2 Period 3 Category, iso No.
ItemNO, Comp. besc. Code Case 1 23 4 23 A I1I2 A Class~ Summary I CompiD I System Scope I Method I Procedure 1 3142-1 9-A I7 . . . . . . . . . R.A(L) 100295 *ISI.1 Valve-to-Pipe AUG - - - - - - - - - -- - - R1.20 W-22' 2 HPCI Steam DischOW
---.....-..- ~-PRE ~ _ _
ISI-13142-1 9-A S R.A(L) 100296 AUG- - - - - - - - R12 -3Pipe-to-Valve HPCI Steam Disch OWN 2
... .. -. ~ PRE...
~~~~.. - - ~- . , .
ISI-13142-1 9-A Isi - - - - - - - - - - - - R.A(L) 100297 Valve-to-Pipe AUG' R1.20 W-24 OWN - - - - - - - - - - - - 2 HPCI Steam Disch PRE __ _ _ _ _ _ _ _ _ _ ISI-13142-1 9-A -isi - - - - R.A(L) 100298 Pipe-to-Reducer AUG - - - - - - - - - - - - R1.20 W.2~5 OWN - - - - - - - - - - - - 2HPCI Steam Disch PRE. ISI - - - - - - - - - - - - R-A(L) 100299 .ISI-13142-19-A W-26 Reducer-to-Pipe AUG RI.20 OWN . . . . . . - - - -
- 2. HPCI Steam Dlsch
. . -......--..-.. . .. ~ , ~P R E - _ _ _
ISI-I131 42-1 9-A -. - - -.- - -- - - - - - R-A(L) 100300 AUG- - - - - - - - - - - - - R12 -7Pipe-to-Elbow O N - - - 2 HPCI Steam Dlsch ISI-13142-1 9-A [S' - - - - - - - - R-A(L) 100301 R12 -8Elbow-to-Pipe AUG, HPCI Steam Disch OWN 2
.. PRE -__- - __--___ - -
100302 5-13142-19-A S. Isi R.A(L) . . . .. Pipe-to-Towus Pent. AUG - - - - - - - - - - - - RI.20' W-29 OWN . . . . . . . . . . . . 2 HPCI Steam Disch PRE __--_- _ I%-kL~j . . . ISI-1 31 42-20-A r is' w U.-10 Torus Pent-to-Elbow~ AUG RI1.20 2 Core SprayA OWN PRE Printed 3141200
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 172 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Scope / Method / Procedure Code Case 1 2 3 4 1 2 3 A 1 2 3 A Class Summary I ComplD / System R.A(L) 100337 ISI-13142-20-A ISI R1.20 W-2 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100338 ISI-13142-20-A ISI R1.20 W- 3 Pipe-to-Elbow AUG 2 Core Spray A OWN PRE R-A(L) 100339 ISI-13142-20-A ISI R1.20 W- 4 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100340 ISI-13142-20-A ISI R1l.20 W- 5 Pipe-to-Pipe AUG 2 Core Spray A OWN PRE R-AIL) 100341 ISI-13142-20-A ISI R1.20 W- 6 Pipe-to-Elbow AUG 2 Core Spray A OWN PRE - - - - - - - - - - - - R-A(L) 100342 ISI-13142-20-A I-SI E Rl.20 W- 7 Elbow-to-Elbow AUG 2 Core Spray A OWN PRE R-A(L) 100343 ISI-13142-20-A ISI R1.20 W-8 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 10344 ISI-13142-20-A ISI R1.20 W- 9 Pipe-to-Valve AUG 2 Core Spray A OWN PRE A L. M. -.j . s. fr . .. . . IbI-1314Z-;ZUA PRE 1SI R1.20 W-10; Valve-to-Pipe
, AUG I I 2 Core Spray A OWN PRE K -3//-
Printed 314/2005
C C . . C, Page 173 of 332 o 3 Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100346 ISI-13142-20-A ISI- - - - - - - - - - - - R1.20 W-11 Pipe-to-Valve AUG - - 2 Core Spray A OWN - : R-A(L) 100347 ISI-13142-20-A ISI R1.20 W-12 Valve-to-Pipe AUG : 2 Core Spray A - OWN - ; -- R-A(L) 100348 ISI-13142-20-A ISI R1.20 W-13 Pipe-to-Tee AUG - ;; 2 Core Spray A OWN
*
- P RE .
R-A(L) 100349 ISI-13142-20-A ISI R1.20 W-i4- Tee-to-Pipe AUG 2 - Core Spray A OWN - ; ; PRE R-A(L) 100350 ISI-13142-20-A [SI - - - - - . R1.20 W-15 Pipe-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100351 ISI-13142-20-A [SI R1.20 W-16 Pipe-to-Elbow AUG ; 2 Core Spray A OWN - ;
... . .. . .PRE.
R-A(L) 100352 ISI-13142-20-A ISI R1.20 W-17 Elbow-to-Pipe AUG ; 2 Core Spray A OWN - ;
.PRE . ;
R-A(L) 100353 . ISI-13142-20-A ISI R1.20 W-18 Pipe-to-Elbow AUG . 2 Core SprayA OWN PRE R-A(L) 100354 ISI-13142-20-A ISI R1.20 W-19 Elbow-to-Elbow AUG El ' I a!wv@.. 2 Core'Spray A OWN PRE Printed 3t412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 174 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 11 2 3 4 R-A(L) 100355 ISI-13142-20-A ISI = . R1.20 W-20 Elbow-to-Pipe AUG - - . 2 Core Spray A OWN . PRE R-A(L) 100356 ISI-13142-20-A ISt . R1.20 W-21 Pipe-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100357 ISI-13142-20-A IS1 R1.20 W-22 Pipe-to-Pump AUG 2 Core Spray A OWN PRE R-A(L) 100358 ISI-13142-20-A ISI . R1.20 W-23 Valve-to-Elbow AUG 2 Core Spray A OWN PRE R-A(L) 100359 ISI-13142-20-A ISI R1.20 W-24 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100360 ISI-13142-20-A ISI . R1.20 W-25 Pipe-to-Tee AUG 2 Core Spray A OWN PRE R-A(L) 100366 ISI-13142-20-B IS1 - - . R1.20 W- 1 Torus Pent-to-Elbow AUG - . 2 Core Spray B OWN PRE - - - - - - - - - - - - R-A(L) 100367 - ISI-13142-20-B IS[ R1.20 W- 2 Elbow-to-Pipe AUG . 2 Core Spray B OWN PRE . R-A(L) 100368 ISI-13142-20-B ISI . . .. R1.20 W- 3 Pipe-to-Pipe AUG . . . 2 Core Spray B OWN C PRE Printed 314/2005
C C 4th Interval ISI Plan (Rev.3) C. Page 175 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May'31, 2012) Period I Period 2 Period 3 i Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100369 ISI-13142-20-B ISI RI.20 W- 4 Pipe-to-Elbow AUG 2 Core Spray B OWN . PRE 100370 ISI-13142-20-B ISI: - - - - - - . - - - - R-A(L) R1.20 W- 5 Elbow-to-Pipe AUG . . . . . . . 2 Core Spray B OWN - - - - .---
; '-PRE R-A(L) 100371 ISI-13142-20-B ISI . ; ,
R1.20 W- 6 Pipe-to-Valve AUG 2 Core Spray B OWN PRE R-A(L) 100372 ISI-13142-20-B ISI . RI.20 W-7 Valve-to-Pipe AUG' 2 Core Spray B OWN PRE R-A(L) 100373 ISI-13142-20-B ISI; R1.20 W- 8 Pipe-to-Valve AUG L _ j L _ 2 Core Spray B , . ,' OWN :
- .' PRE R-A(L) 100374 ISI-13142-20-B ISI R1.20 W-9 Valve-to-Tee AUG 2 Core Spray B OWN
- .PRE R-A(L) 100375 ISI-13142-20-B ISI R1.20 W-10 Valve-to-Pipe AUG - - .
- OWN - .
2 Core Spray B PRE - - - . ISI-13142-20-B ISI . R-A(L) 100376 R1.20 W-11 Pipe-to-Elbow AUG 2 Core Spray B OWN PRE R-A(L) 100377 ISI-13142-2G-B IS' R1.20 W-12 II . 'Eibov~i-to-Pipe - ! AUG 2 Core Spray B ' ' OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 176 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD / System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 R.A(L) 100378 ISI-13142-20-B ISI R1.20 W-13 Pipe-to-Tee AUG - - . - ... 2 Core Spray B OWN - - - - - - - - . PRE . . . . . . . . . . . R-A(L) 100379 ISI-13142-20-B ISI R1.20 W-14 Tee-to-Pipe AUG - - - . 2 Core Spray B OWN . PRE - - - - - - - - - - . R-A(L) 100380 ISI-13142-20-B ISI - - - - R1.20 W-15 Pipe-to-Elbow AUG . . . . . . . . . . . . 2 Core Spray B OWN PRE - - - - - - - - - - - - R-A(L) 100381 ISI-13142-20-B ISI . . . . . . . . . . . R1.20 W-16 Elbow-to-Pipe AUG 2 Core Spray B OWN . PRE - - - - - - - - - - . R.A(L) 100382 ISI-13142-20-B ISI - - - - - - - - . R1.20 W-17 Pipe-to-Pipe AUG . . . . . . . . ... . . 2 Core Spray B OWN - - . PRE - - - - - - - - - - . R-A(L) 100383 ISI-13142-20-B ISI . . . . . . . . . . . R1.20 W-18 Pipe-to-Pipe AUG - - - - - - - - . 2 Core Spray B OWN - - - - - - - - . PRE R-A(L) 100384 IS1-13142-20-B ISI - - - - - . R1.20 W-19 Pipe-to-Pipe AUG - - .- ... 2 Core Spray B OWN PRE - - - - - - - - - - - - R.A(L) 100385 ISI-13142-20-B ISI - - - - - - - - - - - - R1.20 W-20 Pipe-to-Elbow AUG . . . . . . . . . 2 Core Spray B OWN - - - - - . PRE R-A(L) 100386 ISI-13142-20-B ISI . .3.2. R1.20 W-21 Elbow-to-Pipe AUG 2 Core Spray B OWN PRE ( ( Printed 31412005
C C 4th Interval ISI Plan (Rev.3) C. Page 177 of 332 Monticello Nuclear Generating Plant ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, ISO No. ItemNO, Comp. Desc.' 1 23 A 127 A 1 I f A Class'I Summary I Comp lD I System Scope I Method I Procedure Code Case, R.A(L) 100387 ISI-1 3142-20-B Pipe-to-Elbow AUG - - - - - - - - - - - R1.20 W-22 2 Core Spray B W 100388 ISI-13142-20-B ISI R-A(L) R1.20 W-23Ebo toPpAU 2 Core Spray BOW 1SI-13142-20-B ISI - - - - - - - - - - - - R-A(L) 100389 Pipe-to-Elbow AUG - - - RI.20 W-24 2 Core Spray B OWN - - - - - - - - - - -
- PR E .
- _ _ _
3142-20-B 151-ISI ISI - - - - - - - - - - - - R-A(L) 100390 Elbow-to-Pipe AUG - - - - - - - - - - - - RI .20 W-25 OWN - - - - - - - - - - - - 2Core Spray B PR E ISI-i131 42-20-B 1s5 1 .. .. . . . R-A(L) 100391 R1.20 W-26 Pipe-to-Elbow AUG' 2 , Core'Spray BOW RE - - _ _ _
....-.. =-~~P IS1-13142-20-B 151 - - - - -
R-A(L) 1100392 W-27 Elbow-to-Pump AUG --- R1.20 OWN - - - - - - - - -
- 2. Core Spray B . PRE . .
100434 ISI-13142-26-A ISt R-A(L) Valve-to-Pipe AUG - - - - - - R1.20 W-1 Core Spray B OWN 2
- _ -. PR E - _ _ -- _ _- - _- _ - -_-_- -_-_
R-A(L) 100435 . . .. .S-I3 422 AIS Pipe-to-Elbow AUG - - - - - - - - - - - - R1.20 W- 2 2Core Spray BOW PRE - - - - - - - 1UU4,Su . ISI-13 142-26-A ISI - - - - K1-AILI _ Rl.20 W- 3 . Elbov~-o-'Pipe AUG - - - - Core Spray B OWN - - - - 2 PRE - - - - Printed 3/41205
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 178 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 . Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100437 ISI-13142-26-A ISI R1.20 W- 4 Pipe-to-Elbow AUG 2 Core Spray B OWN PRE . R-A(L) 100438 ISI-13142-26-A ISI R1.20 W- 5 Elbow-to-Valve AUG 2 Core Spray B OWN PRE . . . R-A(L) 100443 ISI-13142-26-A ISI R1.20 W-10 Pipe-to-Pipe AUG 1 Core Spray B OWN . PRE R-A(L) 100444 ISI-13142-26-A IS1 R1.20 W-11 Pipe-to-Elbow AUG 1 Core Spray B OWN PRE R-A(L) 100445 ISI-13142-26-A ISI R1.20 W-12 Elbow-to-Pipe AUG 1 Core Spray B OWN PRE . R-A(L) 100446 ISI-13142-26-A ISI R1.20 W-13 Pipe-to-Valve AUG 1 Core Spray B OWN PRE R-A(L) 100454 ISI-13142-26-B ISI R1.20 W-12 Pipe-to-Elbow AUG 2 Core Spray B OWN PRE R-A(L) 100455 ISI-13142-26-B ISI R1.20 W- 1 Reducer-to-Valve AUG 2 Core Spray B OWN PRE R-A(L) 100456 ISI-13142-26-B ISI R1.20 W-2 Pipe-to-Reducer AUG 2 Core Spray B OWN C PRE P Printed 3/412005
(7,. C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 179 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
, Period I Period 2 . Period 3 Category, Iso No.
ItemNO, Comp. Desc. Scope I Method I Procedure , Code Case 1 2 3 4 1 2 3 4 1 2 3 4 Class Summary I ComplD I System . .. .. ..- ISI-13142-26-B ISI - .- - . R-A(L) 100457 Tee-to-Pipe AUG . R1.20 W-3 Core Spray B . OWN ; 2
. .... .-.. _--------.--.--..----PRE..._.-.-..
R-A(L) 100458 ISI-13142-26-B ISI, W- 4 Tee-to-Pipe AUG R1.20 2 -- Core Spray B ,., OWN
,,,,,,,,,_.........---PRE........-
R-A(L) 100459 . ISI-13142-26-B 1SI -- W- 5 Pipe-to-Elbow AUG R1.20 Core Spray B ... .OWN 2 -
.-PRE-100460 ISI-13142-26-B IS1 R.A(L) -
W- 6 Elbow-to-Elbow AUG R1.20 Core Spray B OWN 2
..... ....-.... -.- . PRE R-A(L) 100461 , ISI-13142-26-B IS1 R1.20 W-7 - Elbow-to-Pipe AUG 2 Core Spray B .O OWN 7 R-A(L) 100462 . ISI-13142-26-B ISI, R1.20 W- 8 Pipe-to-Pipe AUG 2 Core Spray B OWN PRE-----
R-A(L) 100463 ISI-13142-26-B ISI W- 9 Pipe-to-Pipe AUG R 1.20 2,, Core Spray B OWN
-.. ,. - PRE R-A(L) 100464 - . . ISI-13142-26-B [SI W-10 Pipe-to-Eltow AUG R1.20 .
2 Core Spray B OWN PRE R-A(L) : 100465 . ' I !I'- - ,.ISI-13142-26-B , 1SI
. i I. I ., 1 -" Ifl 7)
R1.20 -W-13 1, ' .. ? .,- .,~L- , , Elbow-to-Pipe AUG
': I ,,
2 Core Spray B OWN PRE Printpd.11412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 180 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. Comp. Desc.
- ltemNO, Class Summary I ComplDI System Scope I Method I Procedure Code Case 1. 73 1 A I tt 7) n A 1 1 . A R-A(L) 100466 ISI-13142-26-B ISI R1.20 W-14 Pipe-to-Elbow AUG 2 Core Spray B OWN - - - - - - - .
PRE - - - - - - - R-A(L) 100467 ISI-13142-26-B iS --- R1.20 W-15 Elbow-to-Pipe AUG 2; Core Spray B OWN PRE R-A(L) 100468 ISI-13142-26-B ISI E R1.20 W-16 Pipe-to-Pipe AUG 2 Core Spray B OWN PRE - - - - - - - - - R-A(L) 100469 ISI-13142-26-B ISI R1.20 W-17 Pipe-to-Reducer AUG 2 Core Spray B OWN PRE R-A(L) 100470 ISI-13142-26-B Is - R1.20 W-18 Reducer-to-Valve AUG 2 Core Spray B OWN R-A(L) 100471 ISI-13142-26-C SiS R1.20 W- 1 Pump-to-Elbow AUG . 2 Core Spray B OWN PRE -- . ... R-A(L) 100472.. ISI-13142-26-C PR . R1.20 W- 2 Elbow-to-Pipe AUG - . - - - - . 2 Core Spray B OWN . . . . R-A(L) I 00473 ISI-13142-26-C iSP R1.20 W- 3 Pipe-to-Valve AUG . . . . . . . . 2 Core Spray B OWN - - - - - . PRE. RAi . 1 I 74 . Val-1e14t I I
-P&e lSI R1.20 W-4 Valve-to-Pipe AUG 'I. -
2 Core Spray B OWN PRE Printed 3/4/2005
I C. Monticello Nuclear Generating Plant C 4th Interval 151 Plan (Rev.3) Page 181 of 332 C. ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012) IPeriod I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. I I A I 4 1 q A 4 11 -1 A Classi Sumimary I ComplD I System Scope!I Method!I Procedure Code Case [iS-13142-26-C S - - - - - - - - - - - - - R.A(L) 100475 AUG R12 -5Pipe-to-Elbow 2 Core Spray BOW
-- . . , . . .- -. . . - -. - , . -- PR E . --. - .
ISI-13142-26-C MIS R-ACL) 100476 Elboyw-to-Pipe AUG R.0 W- 6 2,1 Core Spray B .OW ISI-13122- s R.A(L) 100477 AUG ----- R20 W7Pipe-to-Flange OWN ---- 7 2 Core Spray B PRE. R-A() 10478 . . 31 42-26-C ISi R-() 1048ISI-1 Flange-to-Pipe AUG R1.20 W- 8 Core Spray B . . ISI-13142-26-C PE --.- -. R.A(L) 100479 R1.20 W-9 Pp-oEbwAG; P120 AUG ------ Wp0Elo-to-Pipew 2 ~Core~Spray BOW . P R E-. OW.. - - -..---.--.---
.. PRE . . . . . . ...
ISI-I131 42-26-C MII - - -- . R-A(L) 100482 Elbow-to-Pipe AUG--- R1.20 W-12 2 Core Spray BOW I?.AI~ in~iPRE IS' R1.20 .W-13 ._~. Pipe-to-Elbow' AUG 2 Core Spray B OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 182 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. 22 A I 2 3 A 4 2-, A Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 ISI-13142-26-C ISI . . . . . . . . . . . R-A(L) 100484 R1.20 W-14 Elbow-to-Pipe AUG - . 2 Core Spray B OWN - - - - - - - . ISI-13142-26-C ISP E - - - - , R-A(L) 100485 Pipe-to-Elbow AUG . . . . . . . . . . . . R1.20 W-15 2 Core Spray 8 OWN - - - - - - - . PRE - - - - - - - - - -- - R-A(L) 100486 ISI-13142-26-C ISI Elbow-to-Pipe AUG - - - - - - - - - - . R1.20 W-16 2 Core Spray B OWN - - - - . PRE . . . . . . . . . . R.A(L) 100487 ISI-13142-26-C ISI - - - . R1.20 W-17 Pipe-to-Elbow AUG 2 Core Spray B OWN - . PRE - - - - - - - - - - . R-A(L) 100488 ISI-13142-26-C ISI - . R1.20 W-18 Elbow-to-Pipe AUG . . 2 Core Spray B OWN PRE - . . R1A(L) 100489 IS1-13142-26-C ISI Pipe-to-Flange AUG - - . R1.20 W-19 2 Core Spray B OWN - - - - - - - - .
-PRE - - - - - - - -- - - - - -
ISI-13142-26-C IS . . . . . . . . . . . R.A(L) 100490 Flange-to-Pipe AUG - - .... R1.20 W-20 2 Core Spray B OWN - - - - - - - . PRE - - - - - - - -. - - - ISI-13142-31-A PISI - - - - - - . R-A(L) 100504 R1.20 W- 5 Pipe-to-Pipe AUG . . . . . . . . 1 Core Spray A OWN - - - - - . PRE .. . . R-AIL) lSI R11.20 W-6 Pipe-to-Elbow AUG I Core Spray A OWN ( PRE
-C Prinlfpd 3/41200.9
C C 4th Interval ISI Plan ~(Rev.3) C Page .183 of 332 Monticello Nuclear Generating Plant I i
.,ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012)
IPeriod I Period 2 Period 3 I-- I a S Category. Iso No. 1temNO, Comp. Desc. Class sumnmarv I ComvlD I System Scope I Method I Procedure Code Case 1 23 4 I 2 3 4 1 23 4 R.A(L) 100506 ISI-13142-31-A ISI R1.20 W- 7 Elbow-to-Pipe AUG - - - - - - - - - - - - Core Spray AOW
. --... ~~~PRE..--. ._ _
R.A(L) 100507 ISI-13142-31-A ISI R1.20 W- 8 Pipe-to-Valve AUG . . . . . . . . . . . . I: Core Spray A OWN - - - - - - - - - - - -
.~...~.PRE R.A(L) 100518 ISI.13142-31-B - - -
Tee-to-Valve AUG - - - Ri .20 W- I Core Spray A OWN - - - 2
- PRE - - -
R.A(L) . 100519 .ISI-13142-31-B 151 . . . . . R1.20 W- 2 Valve-to-Reducer AUG - - - - - - - - - - - - 2 Core Spray A . OWVN - - - - - - - - - - - -
.. ~. . ........ PRE - - - .
R-A(L) 100520 ISI-13142-31-B I181 - - - - -- RI.20 W- 3 .. Reducer-to-Flange AUG - - - - - - - - - - - - 2 Core Spray A . -OWN R-A(L) 100521. ISI-13142-31-B I.11 - - - - -- R1.20 W- 4 Tee-to-Pipe AUG - - - - - - - - - - - - 2 Core Spray AOW - - - - - - - - - - - -
-. .-. .~.... . .. PRE R-A(L) 100522 ISI-13142-31-B I11 - - - - --
RI.20 W- 5 Pipe-to-Pipe AUG - - - - - - - - - - - - 2Core Spray A.OWN - - - - - - - - - - - - R.A(L) 100523 IS1-13142-31-B 181 - - - - - k1.20 W- 6 Pipe-to-Pipe AUG - - - - - - - - - - - - 2 Core Spray A OWN - - - - - - - - - - - - PRE R-A(L) 100524 ,I; t. ISI-3142-31-B _ - W- 7, .- : Pipe-to-Elbow AUG R1.20 OWN 2 Core Spray A PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 184 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 R-A(L) 100525 ISM-13142-31-B ISI - - - - - - - - - - - R1.20 W-8 Elbow-to-Pipe AUG 2 Core Spray A OWN - - - - - - - . PRE - - - - - - - - - . - - R-AIL) 100526 ISI-13142-31-B ISI - - - - - --- - . R1.20 W-9 Pipe-to-Elbow AUG 2 Core Spray A OWN . PRE . R-A(L) 100527 ISI-13142-31-B [SI R1.20 W-10 Elbow-to-Pipe AUG 2 Core Spray A OWN - - - - - - - . PRE R-A(L) 100528 ISI-13142-31-B ISI - - - - - . R1.20 W-11 Pipe-to-Elbow AUG 2 Core Spray A OWN PRE R-A(L) 100529 ISI-13142-31-B ISI R1.20 W-12 Elbow-lo-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100530 ISI-13142-31-B IS1 R1.20 W-13 Pipe-to-Reducer AUG 2 Core Spray A OWN PRE - - - - - - - - - - - - R-A(L) 100531 151-13142-31-B IS1 Rl.20 W-14 Reducer-to-Valve AUG - 2 Core Spray A OWN PRE - - - - - - - - - .- R-A(L) 100532 ISI-13142-31-B ISI - - - - - - . Rl.20 W-15 Valve-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) - 100533. - ISI -13142-31-B Isl Ri.20 W.16 Pipe-to-Elbow AUG 2 Core Spray A OWN ( PRE Printed 3/4/2005
C C onnn I -C for, _r 11,11) Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) 4 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 ! Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summiary / ComplD / System Scope I Method I Procedure Code Case I 2 3 4 11 2 3 411 2 3 4 R-A(L) 100534 ISI-13142-31-B ISI . R1.20 W-17 Elbow-to-Pipe AUG 2 Core Spray A OWN .
. .. _.- ... -**.PRE- ..-.. .- ...
R-A(L) 100535 ISI-13142-31-B ISI R1.20 W-18 Pipe-to-Elbow AUG . 2 Core Spray A -OWN
.. ..... ... -- PRE- ... ...
R-A(L) 100536 ISI-13142-31-B IS1 R1.20 W-19 Elbow-to-Valve AUG . 2 Core Spray A OWN -
... .... . 7_ -
..- - - - - --R-..
. .. - .PR E-R-A(L) 100537 ISI-13142-31-C ISI R1.20 W- 1 Pump-to-Elbow AUG 2 ,, Core Spray A OWN
...................... ...........-.---.--- PRE.. . ...
R-A(L) 100538 . ISI-13142-31-C ISI ~ ~~I, .- .. . 7 - - - - - - - 7 I I - R1.20 W- 2 Elbow-to-Pipe AUG I . . 2 Core Spray A OWN
-....-..-. -... . - .-. -. . .. ~P . ..--. --..--.- -_ ---.
.-.--- .------PE R-A(L) 100539 ISI-13142-31-C ISI R1.20 W- 3 Pipe-to-Valve AUG 2 Core Spray A OWN
....... PRE R-A(L) 100540 . ISI-13142-31-C IS1 R1.20 W-4 Valve-to-Pipe AUG 2 Core Spray A OWN
... . ,. PRE R-A(L) 100541 ISI-13142-31-C ISI R120 W- 5 Pipe-to-Elbow AUG 2 Core Spray A OWN PRE ISI-13142-3El-C ISI . . .
,I,1, Elbow-to-Elbow * - AUG . . .
R1.20 W-6 Core Spray A OWN . . . 2 PRE . . . Printwi 3M4f2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 186 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 _ R-A(L) 100543 R1.20 W- 7 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100544 ISI-13142-31-C ISI R1.20 W- 8 Pipe-to-Elbow AUG 2 Core Spray A OWN
.. . . . ... . . PRE R-A(L) 100545 ISI-13142-31-C IS1 R1.20 W- 9 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100546 ISI-13142-31-C IS1 R1.20 W-10 Pipe-to-Flange AUG 2 Core Spray A OWN PRE R-A(L) 100547 ISI-13142-31-C ISI R1.20 W-11 Flange-to-Pipe AUG 2 Core Spray A OWN PRE-R-A(L) 100548 ISI-13142-31-C ISI R1.20 W-12 Pipe-to-Elbow AUG 2 Core Spray A OWN
- - - PRE R-A(L) 100549 ISI-13142-31-C ISI R1.20 W-13 Elbow-to-Pipe AUG 2 Core Spray A OWN PRE R-A(L) 100550 ISI-13142-31-C ISI R1.20 W-14 Pipe-to-Elbow AUG 2 Core Spray A OWN PRE R-A(L) 100551 IS1-13142-31-C 'SI R1.20 W-15 Elbow-to-Pipe AUG 2 Core Spray A OWN 3/4200
( PRE - Printed 3/4/2005
C... C (. Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) I Page 187 of 332
- ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ; ItemNO, Comp. Desc. Class Summary ComplD I System. Scope/ /Method / Procedure-. Code Case . .. - .1 2 3 4 11 2 3 411 2 3 4 R-A(L) 100552 ISI-13142-31-C [SI R1.20 W-16 Pipe-to-Elbow AUG . . . 2 *, Core Spray A OWN .
...-.-_ .... .. -. . .- PRE *- --
R-A(L) 100553 - ISI-13142-31-C IS1I R1.20 W-17 Elbow-to-Elbow AUG . . .... . . 2 Core Spray A . OWN - - .- -
- PRE- - -
R-A(L) 100554 ISI-13142-31-C ISI. - . R1.20 W-18 Elbow-to-Pipe AUG 2 Core Spray A OWN .
*------ PRE - -- -
R-A(L) 100555 ISI-13142-31-C ISI - . R1.20 W-19 Pipe-to-Elbow AUG . 2 Core SprayA - OWN .
.-. .. . . . . . . - - .. . -P RE '
R-A(L) 100556 ISI-13142-31-C ISI . RI.20 W-20 Elbow-to-Pipe AUG . 2 . * : OWN - . ; -- -
-- r, Core Spray A j .
..- PRE R-A(L) 100557 - ISI-13142-31-C ISI . .
R1.20 W-21 Elbow-to-Elbow AUG - - - - - - - - . 2 Core Spray A . - OWN ;
- PRE - - -
R-A(L) 100558 ISI-13142-31-C IS[ - R1.20 W-22 Elbow-to-Pipe AUG - . OWN 2 Core Spray A
- - - - -PRE - - - - - -
R-A(L) 100559 - ISI-13142-31-C IsI R1.20 W-23 Pipe-to-Flange AUG - - ... 2 Core Spray A OWN - - ; PRE . . . . . . . . . Dtl
-sn:n
%-lML All.......
-1 I UUQUU i , " - ., , -,I - - . -F-1ag-13142-31-C ISI R1.20 W-24 - * , , Flange-to-Pipe. AUG 2 Core Spray A OWN PRE Printpd 314f2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 188 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. lternNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 41 1 2 3 4 R-A(L) 100561 ISI-13142-31-C ISI R1i.20 W-25 Pipe-to-Elbow AUG . 2 Core Spray A OWN PRE - R-A(L) 100562 ISI-13142-31-C 1 .. R1.20 W-26 Elbow-to-Elbow AUG . 2 ,. Core Spray A OWN . PRE R-A(L) 100563 ISI-13142-31-C ISI E R1.20 W-27 Elbow-to-Elbow AUG 2 Core Spray A OWN - . PRE R-AIL) 100564 ISI-13142-31-C IS1 - - - - - - - - . R1.20 W-28 Elbow-to-Pipe AUG - - . 2 Core Spray A OWN - - - - - - . PRE R-A(L) 100565 ISI-13142-31-C ISI . . . . . . . R1.20 W-29 Pipe-to-Tee AUG - - . 2 , Core Spray A OWN PRE - - - - . R-A(L) 100615 ISI-13142-33-A ISI R1.20 W-27 Valve-to-Pipe AUG - - - - - - . I Main Steam A OWN - - .
'PRE R-A(L) 100616 ISI-13142-33-A ISI. - - .
R1.20 W-28 Pipe-to-Pipe AUG . . 1 Main Steam A OWN - . PRE. . . . . . . . . R-A(L) 100617 ISI-13142-33-A IS1 R1i.20 W-29 Pipe-to-Pipe AUG- s 1 Main Steam A OWN PRE
- 100618 . ISI-13142-33-A . ISI - - - -
R-A(L) Pipe-to-Pipe AUG - - - - S R1.20. W-30 Pain Steam A OWN - - - - - - - 1 (., C PRE - - - -
C C - *
. . C C
Monticello Nuuclear Generating Plant 4th Interval ISI Plan (Rev.3) j Page 189 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) i P Period I ' i Period 2 Period 3 Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100619 ISI-13142-33-A ISB-. R1.20 W-31 ' Pipe-to-Pipe AUG s 1 Main Steam A OWN PRE R-A(L) 100620 AUGIUT/PEI-02.03.01 ISI-13142-33-A ISI ; R1.20 W-32 Pipe-to-Valve AUG' s - - - _ 1 Main Steam A OWN - - PRE R-A(L) 100665 ISI-13142-34-A ISI R1.20 W-27 Valve-to-Pipe AUG' 1 Main Steam B OWN . PRE R-A(L) 100666 ISI-13142-34-A ISI R1.20 W-28 Pipe-to-Pipe AUG 1 Main Steam B OWN PRE . R-A(L) 100667 ISI-13142-34-A iSI' . . . R1.20 W-29 Pipe-to-Pipe AUG . . -. . . s 1 Main Steam B OWN . PRE R-A(L) 100668 ISI-13142-34-A ISI' R1.20 W-30
- Pipe-to-Pipe AUG - - .
1 Main Steam B OWN . PRE - . R-A(L) 100669 ISI113142-34-A ISI R1.20 W-31 Plpe-to-Pipe AUG - s - 1 Main Steam B OWN PRE R-A(L) 100670 ISI-13142-34-A ISI -- - - R1.20 W-32 Pipe-to-Pipe AUG - s 1 Main Steam B - OWN - . PRE .,- R-A(L) 100671 AUGtUT/PEI-02.03.01 ISI-13142-34-A iSI R1.20 W-33 Pipe-to-Valve . ' ` ' AUG - 5 1' , " ., I ., - I ,, , ,1 ,;,. 1 Main Steam B OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 190 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method / Procedure Code Case I 2 A A 1 I 3 A I I -1 A R-A(L) 100717 ISI-13142-35-A IS . . . . . . . . . . . R1.20 W-27 Valve-to-Pipe AUG 1 Main Steam C OWN , PRE - - - - - . R-A(L) 100718 ISI-13142-35-A ISI - - - - - - - - - R1.20 W-28 Pipe-to-Pipe AUG . . . . . . . . . . . . I Main Steam C OWN - - - - - - - . PRE R-A(L) 100719 ISI-13142-35-A ISI . . . . . . . . R1.20 W-29 Pipe-to-Pipe AUG-- s 1 Main Steam C OWN PRE . . . . . . . . . . . . R-A(L) 100720 ISI-13142-35-A 15tE R1.20 W-30 Pipe-to-Pipe AUG - - - .. s 1 Main Steam C OWN - - - - - . PRE - . R-AtL) 100721 ISI-13142-35-A ISI - - - - - . R1.20 W-31 Pipe-to-Pipe AUG - -.-..... s . -. I Main Steam C OWN - - - - - - - . PRE . . . . . . . . . . . R-A(L) 100722 ISI-13142-35-A ISI - - - - . - - - - - . R1.20 W-32 Pipe-to-Pipe AUG ... . s - - . - ... 1 Main Steam C OWN - - - - . PRE R-A(L) 100723 ISI-13142-35-A IS-I E R1.20 W-33 Pipe-to-Pipe AUG .... s - - . - ... 1 Main Steam C OWN - - - - - - - . PRE . . . . . . . R-A(L) 100724 AUG/UT/PEI-02.03.01 ISI-13142-35-A ISI . . . . .- R1.20 W-34 Pipe-to-Valve AUG - s - - - - - - . I Main Steam C OWN - . . . . . . . . tnn77< PRE . . . . . . . . . . . 0Ar* 4 ISI-13142-36-A ISI . . ...
. -"t- Ivy,
% Il R1.20 W-29 Valve-to-Pipe AUG OWN . f- . .
1 Main Steam D
. PRE Princted. 31/4/20-05
C C 4th Interval ISI Plan (Rev.3)
-C
- Monticello Nuclear Generating Plant Page 191 of 332
. ASME Section Xi (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012)
I.I. -Period I IPeriod 2 Period 3 Category, .- i Iso No. iternNO, Comp. Desc. Class , . Summary I CompiD I System , __ ,. _._. Scope I Method I Procedure I 2 34 I 2 3 4 1 2 34 R.A(L) 100776IS 13 42 6-Pipe-to-Pipe. AUG . . . . . . . . . . . . RI'.20 W-30. OWN 1 - Main Steam D
~PRE ISI-13142-36-A 151 R.A(L) 100o77 Pipe-to-Pipe AUG-s -
RI.20 W-31 1 Main Steam DOW
.-- ~~~.. PR E --- - * . . .
ISI-13142-36-A ISI R-A(L) 100778 Pipe-to-PIpe AUG ---- s Ri .20 W-32 OWN - - - - - - - - - - - 1 Main Steam D
-PRE-- - -
ISI51-i31 42-36-A ISI R-A(L) 100779 Pipe-to-Pipe. AUG - - - - S - - - - - - - Ri1.20 W-33 OWN - - - - - - - - - - - - 1Main Steam D RE- -
- - -P ISI-13142-36-A [I.S! - - - -
R.A(L) 100780 Pipe-to-Pipe_ AUG - - - - s RI.20 W-34 W IMain Steam D .
.-...- -..- ~~~P RE - - - - - . . . - . .
ISI-13142-36-A ISI, - - -- - - R.A(L) 100781 AUGIUTIPEI-02.03.01 Pipe-to-Valve AUG c . . . . . . . . . R1.20 W-35 OWN ------- 1~ Main Steam 0 ISI-13142-37-A ISI R-Atll) 100791 Pipe-to-Tee AUG R1.20 W-1 OWN - - - - - - - - - - - - 2 RH.R Discharge A
- PRE - .-
ISI1-i31 42-37-A I5l T- . . .-. . . . R-A(L) 100792 Tee-to-Reducer AUG - - - - - - - - - - - - R1.20 . W- 2 OWN 2 RHR Discharge A PRE - - - - - - - - -
!¶-PMtLI , j, I . I -I 1. ; ISI-13142-37-A [SI R1.20 W-3. -. -, I .Tee-to-Pipe AUG 2 RHR Discharge A OWN PRE Printpd 1V4rX005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 192 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 34 1 2 3 4 R-A(L) 100794 ISI-13142-37-A ISI R1.20 W- 4 Pipe-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100795 ISI-13142-37-A ISI R1.20 W-5 Pipe-to-Pipe AUG 2 RHR Discharge A OWN PRE - R-A(L) 100796 ISI-13142-37-A ISI R1.20 W- 6 Pipe-to-Elbow AUG 2 RHR Discharge A OWN PRE R-A(L) 100797 ISI 13142-37-A ISI R1.20 W- 7 Elbow-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100798 IS1-13142-37-A ISI R1.20 W- 8 Pipe-to-Elbow AUG 2 RHR Discharge A OWN PRE R-A(L) 100799 ISI-13142-37-A ISI R1.20 W- 9 Elbow-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100800 IS1-13142-37-A ISI R1.20 W-10 Pipe-to-Elbow AUG 2 RHR Discharge A OWN PRE R-A(L) 100801 ISI-13142-37-A MI . . . . . . . . . . . . R1.20 W-11 Elbow-to-Pipe AUG . 2 RHR Discharge A OWN PRE - - - - -- - - - - - - R-A(L) 100802' , , ISI-13142-37-A ISI R1.20 W-12, Pipe-to-Tee . AUG 2 RHR Discharge A OWN ( PRE Printpfi14420
C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 193 of 332-
.. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
- Period 1 Period 2 Period 3 Category, Iso No.
ItemNO, Comp. Desc. - Class . Summary I ComplD I System - --
.- Scope I Method I Procedure ---- -- Code Case 1.- 2 3. 4 1 2. 3 4 1 2 3- 4..
R-A(L) 100803 ISI-13142-37-A ISI R1.20 W-13 Valve-to-Elbow AUG 2 - RHR DischargeA .-
.WN .--: OWN - -
... *PRE R-A(L) 100804 ISI-13142-37-A ISI-R1.20 W-14 Elbow-to-Pipe AUG 2 RHR Discharge A .R
- OWN
- - - - - - - -=
R-A(L) 100805 ISI-13142-37-A 1Si --. R1.20 W-15 Pipe-to-Reducer AUG 2 ; RHR Discharge A OWN PRE' R-A(L) 100806 ISI-13142 A ISI R1.20 W-16 Reducer-to-El bow AUG 2 RHR Discharge A - OWN
.-.... --- PRE R-A(L) 100807 - ISI-13142-37-A ISI
- R1.20 W-17 Elbow-to-Tee AUG 2' RRHR Discharge A ,. , . OWN PRE R-A(L) 100808 ISI-13142-37-A ISI -
R1.20 W-18 Tee-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100809 ISI-13142-37-A IS1 R1.20 W-19 Pipe-to-Pipe AUG 2 RHR Discharge A . - OWN PRE R-A(L) 100810 ISI-13142-37-A ISI R1.20 W-20 Pipe-to-Valve AUG 2 RHR Discharge A OWN _ PRE - - - - - - - - - -. - - R-A(L) 100811 ISI-13142-37-A ISI R1.20 W-21 i . Valve-to-Elbow AUG 2 RHR Discharge A OWN PRE Prinf-id 11t4'2O7M
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 194 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Class Summary / ComplD I System Scope i Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R.A(L) 100812 ISI-1 31 42-37-A 1 I18 . . . . .. R1.20 W-22 Elbow-to-Valve AUG 2 RHR Discharge A OWN PRE R-A(L) 100828 ISI-13142-37-B [SI R1.20 W- 1 Reducer-to-Tee AUG 2 Containment Spray OWN PRE R-A(L) 100829 ISI-13142-37-B IS1 R1.20 W- 2 Tee-to-Pipe AUG 2 Containment Spray OWN PRE R-A(L) 100830 ISI-13142-37-B IS1 R11.20 W- 3 Pipe-to-Elbow AUG 2 Containment Spray OWN PRE R-A(L) 100831 ISI-13142-37-B ISI R1.20 W- 4 Elbow-to-Pipe AUG 2 Containment Spray OWN PRE R-A(L) 100832 ISI-13142-37-B IS-R1.20 W- 5 Pipe-to-Pipe AUG 2 Containment Spray OWN PRE R-A(L) 100833 ISI-13142-37-B IS1 R1.20 W-6 Pipe-to-Elbow AUG 2 Containment Spray OWN PRE R-A(L) 100834 ISI-13142-37-B ISI R1.20 W-7 Elbow-to-Elbow AUG 2 Containment Spray OWN PRE R-A(L) 100835' - I .ISI-13142-37-B ISI R1.20 W-8 S Elbow-to-Pipe AUG OWN d-2 Onntainment Spray (. PRE
C. : 4th Interval ISI Plan (Rev.3) C Page 195 of 332 Monticello Nuclear Generating Plant
' ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period I . Period 2 Period 3 Category, Iso No. ItemNO . Comp. Desc. eCe. - -
- Summary I CompnlD I System. . .. Scope I Method I Procedure Code Case. - 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100836 ISI-13142-37-B IS1 R1.20 W- 9 Pipe-to-Tee AUG 2 ContaInment Spray OWN
...... . ----- .--. v-**....-.-..,.~... ...-------------- PRE-.- ---
R-A(L) 100837 ISI-13142-37-B .SI R1.20 W-10 Pipe-to-Valve AUG . 7 2 Containment Spray . . - - - - - - - -
...-- .PRE R-A(L) 100838 ISI-13142-37-B ISI R1.20 W-11 Tee-to-Pipe AUG 2 Containment Spray OWN PE.RE -
- .P R-A(L) 100839 ISI-13142-37-B ISI .
R1.20 W-12 Tee-to-Pipe AUG 2 . Containment Spray OWN
- - PRE R-A(L) 100840 ISI-13142-37-B ISI- .
R1.20 W-13 Pipe-to-Elbow AUG OWN 2- Containment Spray 7
.. . . -PRE-
. .. *-*- - - ~- ------------- R R-A(L) 100841 ISI-13142-37-B ISI R1.20 W-14 Elbow-to-Pipe AUG 2 Containment Spray OWN
.... PRE R-A(L) 100842 - ISI-13142-37-B IS1I R1.20 W-15 Pipe-to-Elbow AUG 2 Containment Spray OWN PRE-R-A(L). 100843 ISI-13142-37-B ISI R1.20 W-16 Elbow-to-Pipe AUG 2 Containment Spray OWN PRE
- R-A(L) 100844; . I . .. - 1. .- .. .. - Ipe-1t142-3P-B
.. ip 151 - - - -
,.11 .Pipe-to -Pipe f ! ,. - AUG - - - -
R1.20 .,. W - OWN - - - - 2 Containment Spray PRE - - - - Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 196 of 332
- ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Iso No.
- Category, ItemNO, Class Summary / ComplD I System Scope I Method I Procedure Comp. Desc.
Code Case 1 ') '1 A 1. n '1 . 1. ., s . R-A(L) 100845 ISI-13142-37-B ISI W-18 Pipe-to-Reducer AUG R1.20 OWN - - - . 2 Containment Spray
.PRE -- - - - - - - - - - -
ISI-13142-37-B ISI - - R-A(L) 100846 W-19 Reducer-to-Valve AUG .... R1.20 OWN 2 containment Spray
-PRE - - - - - - - - - - - -
R-A(L) 100852 ISI-13142-37-C ISI W- 1 Tee-to-Pipe AUG R1.20 OWN 2 RHR Discharge A R-A(L 100853 ISI-13142-37-C Isi E R1.20 W- 2 Pipe-to-Elbow AUG 2 RHR Discharge A OWN 100854 ISI-13142-37-C E IPsRl R-A(L) R1.20 W- 3 Elbow-to-Pipe AUG 2 RHR Discharge A OWN - - - - - - - - - - PRE - - - - - - - - - - - - R-A(L) 100855 ISI-13142-37-C ISP R1.20 W- 4 Pipe-to-Elbow AUG OWN 2 RHR Discharge A PRE R R-A(L. 100856 ISI-13142-37-C ISI R1.20 W- 5 Elbow-to-Valve AUG 2 RHR Discharge A OWN
. PRE- - - - - - - - - - - - -
R-A(L) 100857 ISI-13142-37-C PSI R1.20 W- 6 Valve-to-Pipe AUG RHR Discharge A OWN 2 PRE
.AR N 7^
lSI - - - - R-A(L 1088 1111-1;314z-j/-LC Pipe-to-Elbow AUG - - - - R1.20 W-7 OWN - - - - 2 (PI4R Discharge A PRE . . . . Print-'1 VIW2009
C C ( Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 197 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I - Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System - - ---- Scope I Method I Procedure -- Code Case .- - - I 2 .. 3 4 11 2 3 4 1 2.3.4 R-A(L) 100859 ISI-13142-37-C ISI - - R1.20 W- 8 Elbow-to-Pipe AUG 2 RHR Discharge A OWN - . PRE : ISI-13142-37-C ISI - - - - -. - - - - - - - R-A(L) 100860 - R1.20 W- 9 Plpe-to-Elbow AUG 2 - RHR Discharge A OWN .
,...-~PRE R-A(L) 100861 ' ISI-13142-37-C ISI - .
R1.20 W-10 Elbow-to-Tee AUG . 2 RHR Discharge A OWN PRE - - : : R-A(L) 100862 ' ISI-13142-37-C ISI .- RI.20 W-1 Nozzle-to-Reducer AUG 2 ' RHR Discharge A OWN
-' PRE' R-A(L) 100863 1I1-13142-37-C S . ---... .
RI.20 W-12 Reducer-to-Elbow AUG 2 .rT - RHR Discharge A . . OWN . PRE . - - -- ---- R-A(L) 100864 -- ISI-13142-37-C ISI - . R1.20 W-13 Elbow-to-Pipe AUG 2 RHR Discharge A . OWN PRE R-A(L) 100865 ISI-13142-37-C ISI -. R1.20 W-14 Pipe-to-Elbow AUG 2 RHR Discharge A OWN R-A(L). 100866 ISI-13142-37-C ISI R1.20 W-15 Elbow-to-Pipe AUG . OWN . . 2 RHR Discharge A PRE n7Al r.a I A ISI-13142-37-C .; ISI . . . . I I DIJ
, Pipe-to-Elbow. -. AUG - - - -I R1.20. W-1 6 OWN - - - -
2 RHR Discharge A PRE . . . . Printed 314t2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 198 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary / CompID / System Scope I Method I Procedure Code Case II 2 3 4 l 1 2 3 4 1 2 3 4 R-A(L) 100868 ISI-13142-37-C ISI R1.20 W-17 Elbow-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100869
- ISI-13142-37-C ISI .
RI.20 W-18 Pipe-to-Elbow AUG 2 RHR Discharge A OWN - - - . PRE . R-A(L) 100870 ISI-13142-37-C ISI R1.20 W-19 Elbow-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100871 ISI-13142-37-C ISI R1.20 W-20 Pipe-to-Valve AUG 2 RHR Discharge A OWN - - . PRE - - - - . R-A(L) 100872 ISI-13142-37-C ISI R1.20 W-21 Valve-to-Pipe AUG 2 RHR Discharge A OWN PRE R-A(L) 100873 ISI-13142-37-C ISI R1.20 W-22 Pipe-to-Tee AUG 2 RHR Discharge A OWN PRE R-A(L) 100874 ISI-13142-37-C ISI - . RI.20 W-23 Tee-to-Pipe AUG . . 2 RHR Discharge A OWN PRE. . . . . . R-A(L) 100890 ISI-1314240-A ISI R1.20 W- 1 Pump NozzlelRed.Elb AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100891 ISI-13142-40-A ISI R1.20 W- 2 Elbow-to-Pipe AUG 2 HIPCI Water Side Dsch OWN I9-PRE C. Print-.d 114I2rAlr
-C . .. i Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) , 1, .
I i
- -;! Page 199 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1 2003 to May 31, 2012) I Period I Period 2 Period 3 Category, - so No.
ItemNO, Comp. Desc. Class - - Summary I ComplD / System - - - Scope / Method I Procedure - Code Case - 1. 2 3 -.4 1. 2 3 4 1 2 3. 4 R-A(L) 100892 ISI-13142-40-A ISI . . . . . - - - - . R1.20 W- 3 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch - :OWN -.- - - R-A(L) 100893 ISI-131 42-40-A IS . . . . . . R1.20 W- 4 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch . -- - OWN - - - - - - .
- -PRE-R-A(L) 100894 ISI-13142-40-A ISIF - - - - - - - - - - -
R1.20 W- 5 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100895 ISI-1 314240-A lSI R1 .20 W- 6 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN
. . . . . . _ e,.
PRE R-A(L) 100898 ISI-13142-40-A ISI-R1.20 W-7 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch . * -- OWN PRE R-A(L) 100897 - ISI-13142-40-A ISI R1.20 W- 8 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch . OWN PRE - - R-A(L) 100898 ISI-13142-40-A ISI R1.20 W-9 Pipe-to-Flange AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100899 ISI-13142-40-A IS1 R1.20 W-10 Flange-to-Pipe AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) ' 100900 ' I ... I* ? - ISI-1314240-A 7 IsI R1.20 W-11 . , - ,. :, , .;I .- - Pipe-to-Valve . AUG 2 HPCI Water Side Dsch OWN PRE Prinfrpd 1f14Mn;
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 200 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ltemlNO, Comp. Desc. Class Summary I ComplD I System Scope / Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100901 ISI-13142-40-A ISI R1.20 W-12 Valve-to-Elbow AUG 2 HPCI Water Side Dsch OWN PRE . R-A(L) 100902 ISI-13142-40-A ISI R1.20 W-13 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN PR . PRE R-A(L) 100903 - ISI-13142-40-A ISI R1.20 W-14 Pipe-to-Tee AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100904 ISI-13142-40-A ISI R1.20 W-15 Pipe-to-Valve AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100905 ISI-1314240-A ISI R1.20 W-16 Reducer-to-Pipe AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100906. ISI-13142-40-A ISI R1.20 W-17 Tee-to-Reducer AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100907 ISI-13142-40-A ISI R1.20 W-18 Tee-to-Elbow AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100908 ISI-13142-40-A ISI R1.20 W-19 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN PRE ISI-13142-40-A ISI - - - R-A(L) 100909 W-20 Pipe-to-Pipe AUG - - - R1.20 14-CI Water Side Dsch OWN . . . 2 (. PRE - - - pri'rfrd T1"'2(li)
C I C -I. I .I Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 201 of 332
. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class - Summary / ComplD I System Scope I Method I Procedure Code Case 1 2 3 A I 2 3 A I 2 I A R-A(L) 100910 . . ISI-13142-40-A IS R1.20 W-21 Pipe-to-Valve AUG 2 HPCI Water Side Dsch OWN
.~~~~~PRE - .... .-
R-A(L) 100911 .,. .; .ISI-13142-40-A IS1 R1.20 W-22 Valve-to-Pipe AUG 2 . HPCI Waler Side Dsch OWN R-A(L) 100926 . . . ISI-13142-40-B ISI-- R1.20 W- 1 Pipe-to-Elbow AUG 2 .. HPCI Water Side Dsch . . OWN
.PRE -
R-A(L) 10.027 .ISI-13142-40-B ISI R1.20 W- 2 Elbow-to-Pipe AUG OWN 2, > HPCI Water Side Dsch -. R-A(L) 100928 . ISI-13142-40-B ISI. . R1.20 W- Pipe-to-Elbow AUG OWN
- 2. HPCi Water Side Dsch
.. .- *.,--.---,.---. ........----.- ---.--- PROWNA-L-- - -- -.-.------- -R - - --- -
R-A(L) 100929 ISI-13142-40-B ISI R1.20 W- 4 Elbow-to-Pipe AUG 2 . HPCI Water Side Dsch OWN
- .PRE R-A(L) 100930 ISI-13142-40-B ISt -
R1.20 W- 5 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch OWN PRE-. R-A(L) 100931 ISI-13142-40-B ISI - R1.20 . W- 6 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN PRE OAII% 1 ISI R1 .20 W-7 . . .. . , Pipe-to-Elbow : AUG 2 HPCI Water Side Dsch OWN PRE Printed 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 202 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 100933 ISI-13142-40-B IS . R1.20 W- 8 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN - . PRE R-A(L) 100934 ISI-13142-40-B ISI R1.20 W- 9 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN
.. .... . . - PRE R-A(L) 100935 ISI-13142-40-B ISI R1.20 W-10 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch OWN .
PRE R-A(L) 100936 ISI-13142-40-B ISI R1.20 W-11 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100937 ISI-13142-40-B ISI R1.20 W-12 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100938 ISI-13142-40-B ISI R1.20 W-13 Pipe-to-Elbow AUG 2 HPCI Water Side Dsch OWN PRE - R-A(L) 100939 ISI-13142-40-B ISI R1.20 W-14 Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN PRE . R-A(L) 100940 ISI-13142-40-B ISI R1.20 W-15 Pipe-to-Eltbow AUG 2 HPCI Water Side Dsch OWN PRE R-A(L) 100941 , . ISI-13142-40-B IS' R1.20 W-16. Elbow-to-Pipe AUG 2 HPCI Water Side Dsch OWN (.. ( PRE Prite V Printerl .3!4/2005
C. C 4th Innterval ISI Plan (Rev.3) Page 203 of 332. C Monticello Nuclear Generating Plant ASME Section Xi (1995 Edition, 1996 Addenda) (May 11,2003 to May 31, 2012) .I .I . Period I . Period 2 Period 3 Category, Iso No.
- ItemNO, Class Surnmary / ComplD / System . Scope I Method I Procedure Comp. Desc.
Code Case 1. 2 A A 4 1 A 4 It f A R-A(L) 100942 ISI-13142-40-B ISI . R1.20 W-17 Pipe-to-Elbow AUG 2 - HPCI Water Side Dsch . . OWN
.~PRE-R-A(L) 100943. . ISI-13142-40-B ISI R1.20 W-18 Elbow-to-Valve AUG 2 : HPCI Water Side Dsch . -....
- OWN
.~...*--~~~*-PRE R-A(L) 100950 . ISI-13142-41-A IS1.
R1.20 W- 1 Penetration-to-Pipe AUG 2 RCIC Water Suction . -- OWN
.... -- -- . - _ - - - --- -PRE*--
R-A(L) 100951 ISI-13142-41-A ISI R1.20 W- 2 Pipe-to-Elbow AUG 2 - RCIC Water Suction OWN --.
.. - .. . -. -- -- - -- --* * -PR E - --- - -; - - - - .- -
R-A(L) 100952 ISI-13142-41-A ISI R1.20 W- 3 Elbow-to-Pipe AUG 2 RCIC Water Suction ; - . . OWN
.. _ ..... - -.-- PRE - --- ..- .
R-A(L) 100953 - ISI-13142-41-A ISI R1.20 W- 4 Pipe-to-Elbow AUG 2- RCIC Water Suction OWN PRE - - - R-A(L) 100954 ISI-13142-41-A ISI - R1.20 W- 5 Elbow-to-Pipe AUG 2 - RCIC Water Suction OWN - ;
.. .... - -- - . -- PRE -.
R-A(L). 100955 - ISI-13142-41-A ISI R1.20 .. W- 6 Pipe-to-Elbow AUG 2 RCIC Water Suction OWN , PRE PRE - - - - -- -
.. --A-_
A
------ I ... , .. ' . I ".. ,', 1 : lbw-to-V al ISI R1.20 .
- W-7 . -* .: i. .;. . 1 .. Elbow-to-Valve.. AUG - 7 - I- I -
2 RCIC Water Suction OWN PRE Print~d .3f4f2nO0
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 204 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. A Class Summary / ComplD I System Scope / Method / Procedure Code Case 4 o k . , R-A(L) 100957 ISI-13142-41-A ISI W. 8 Valve-to-Pipe AUG R1.20 2 RCIC Water Suction OWN PRE - - - - - - - - - - - - - R-A(L) 100958 ISI-1314241-A ISP R1.20 W- 9 Pipe-to-Valve AUG 2 RCIC Water Suction OWN R-A(L) 100959 ISI-131424P1-A [SRi E R1.20 W-10 Valve-to-Pipe AUG - 2 RCIC Water Suction OWNValve-to-PipeA R-A(L) 100960 ISI-13142-41-A 151 E R1.20 W-11 Pipe-to-Valve AUG 2 RCIC Water Suction OWN 100998 ISI-1314242-A IPSR1E . R-A(L) R1.20 W- 6 Valve-to-Pipe AUG 1 HPCI Steam OWN R-A(L) 100999 ISI-13142-42-A IS1 R1.20 W- S Pipe-to-Elbow AUG 1 HPCI Steam OWN PRE R-A(L) 101000 ISI-13142-42-A ISI R1.20 W- 8 Elbow-to-Pipe AUG 1 HPCI Steam OWN R-A() 10001PRE R-A(L) 10100t ISI-13142-42-A IS-I E R1.20 W- 9 Pipe-to-Elbow AUG 1 HPCI Steam OWN PRE R-A(L) 101002 151 R1.20 W-10: Elbow-to-Pipe AUG 1 HPCI Steam OWN (. PRE Pri ' 345l.
(I C . C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) .- .. Page 2205 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) - I
- Period 1 Period 2 Period 3 Category, -.
- Iso No.
ItemNO, . . Comp. Desc. Class -- - Summ ary I ComDID I System *- - Scope I Method I Procedure ...-........ Code Case 1. _2 3. 4 t 2 .3 4 1. 2 3 4 R-A(L) 101003 ISI-1314242-A ISI R1.20 W-11 Pipe-to-Pipe AUG 1 HPCI Steam - - - - - - - - - - R-A(L) 101004 ISI-1314242-A [SiI - - - - - .. - - - R1.20 W-12 Pipe-to-Elbow AUG - - - - . 1 HPCI Steam OWN - - - - - - .
. -_ ..-- * ----- -- - .- -PRE R-A(L) 101005 ISI-13142-42-A ISI - - - - - - - .
R1.20 W-13 Elbow-to-Pipe AUG . 1 HPCI Steam OWN - - - - - - - - . R-A(L) 101006 ISI-13142-42-A ISI R1.20 W-14 Pipe-to-Pipe AUG . HPCI Steam. . . OWN PR E R-A(L) 101043 ISI-1314243-A ISI. - - - - - . R1.20 W- I Sweepolet-to-Elbow AUG - - . 1 -. RCIC Steam ;
. ! :' '. OWN - - - - - - - - .
.- . - .. . - . -.. . -- P RE" ---
R-A(L) 101044 ISI-1314243-A [SI - . R1.20 W- 2 Elbow-to-Pipe AUG - - - . 1 RCIC Steam -- OWN PRE ': - - R-A(L) 101045 ISI-13142-43-A ISI R1.20 W-3 Pipe-to-Valve AUG RCIC Steam - . . OWN PRE . . . . -. .* . . . R-A(L) 101046 ISI-1314243-A ISI . R1.20 W- 4 Valve-to-Elbow AUG 1 RCIC Steam OWN . PRE R-A(L) 101047 ' : '.: .. 1;" ; I I ' ' , ; , I '; j I I !I.': %,iSI-13142-43-A lIs R1 .20 W I Iz!' 1i . , Elbow-to-Pipe. ..; AUG 1 RCIC Steam OWN PRE Printpri 1V411O05
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 206 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. llemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 101048 IS,-13142-43-A ISI R1.20 W- 6 Pipe-to-Elbow AUG . 1 RCIC Steam OWN - - . PRE : - R-A(L) 101049 ISI-1314243-A ISI . . . . R1.20 W- 7 Elbow-to-Pipe AUG 1 RCIC Steam OWN PRE R-A(L) 101050 151-13142-43-A )SI R1.20 W-8 Pipe-to-Pipe AUG : 1 RCIC Steam OWN PRE R-A(L) 101051 ISI-13142-43-A ISI . R 1.20 W- 9 Pipe-to-Elbow AUG - . I RCIC Steam OWN PRE . R-A(L) 101052 ISI-1314243-A ISI . R1.20 W-10 Elbow-to-Pipe AUG 1- RCIC Steam OWN PRE - - - R-A(L) 101053 ISI-13142-43-A ISI . . . . R1.20 W-11 Pipe-to-Pipe AUG 1 RCIC Steam OWN - . PRE . R-A(L) 101054 ISI-13142-43-A ISI . R1.20 W-12 Pipe-to-Pipe AUG . I RCIC Steam OWN . PRE. . . . .. . I . . R-A(L) 101055 ISI-13142-43-A iSI . R1.20 W-13 Pipe-to-Pipe AUG s - 1 RCIC Steam OWN - . PRE R-A(L) 101056 151-13142-43-A 'SI R1 .20 W-14 Pipe-to-Valve. AUG s 1 RCIC Steam OWN ( PRE Printed 3/4/2005
C C ; (.. Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) - - Page 207 of 332
. . . . I ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
Period 1 Period 2 Period 3 Iso No.
-- 1Ii Category, ?
ItemNO, Comp. Desc. Class Summary I ComplD I System -- - -- " Scope I Method I Procedure - - Code Case -- - -. - 2 1 2 -3 4 1 2 3 4-ISI-13142-48-A ISI . . . . . . . . . . R-A(L) 101057 Pipe-to-Elbow AUG - - - - - - . R1.20 W- 1 2 RHR Service Water.- , ,, ,,- , , , - - - ISI-13142-48-A ISI . . . . . . . . . R-A(L) 101058 W- 2 Elbow-to-Pipe AUG . . . . . . R1.20 2 RHR Service Water . OWN, -. - - - - --
.PRE - - - - - - - - - - --
ISI-13142-48-A ISI . . . . . . . . . . . R-A(L) 101059 Pipe-to-Elbow AUG . . . . . . . R1.20 W- 3 2 - -- RHR Service Water OWN - - PRE . . . . . . . ._._. . . ISI-13142-48-A ISI . . . . . . . . . R-A(L) 101060 R1.20 W- 4 Elbow-to-Pipe AUG - - .
, RHR Service Water OWN - - -
2 PRE - - - - - - - - - - - - R-A(L) 101061 ISI-13142-48-A ISH i - . W- 5 Pipe-to-Elbow AUG . . . . . . R1.20 2 RHR Service Water - ;- - OWN . . . . . .
,,~~~~~~ ..- . .- . .- - - - - - . PE..:-
.~~PRE - ;
ISI-13142-48-A IS1 - - - . R-A(L) 101062 W- 6 Elbow-to-Pipe AUG - - - - . R1.20 2 RHR Service Water . - :OWN OW . . . . . . . ... PRE - - - - - - - - - - . ISI-13142-48-A ISI .- - - - - - - . R-AIL) 101063 R1.20 W-7 Pipe-to-Elbow AUG 2 RHR Service Water , OWN - - - - - . PRE 101064 ISI-13142-48-A ISI - . . R.A(L) R1.20 W- 8 Elbow-to-Pipe AUG RHR Service Water OWN - 2 PRE - - - - - . f--MtLJ lUIUO0 I I I ..I .ISI-13142-48-A ; 1SI R1.20 W-9 ' -, ' ': : Pipe-to-Elbow - , AUG 2 RHR Service Water OWN PRE Printpd 31412005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 208 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No.
- ItemNO, Class Summary I ComplD I System Scope I Method I Procedure E
Comp. Desc. Cnode Cas *41
- 1. A1 4 a4 1. A A
- 4Z 4 R-A(L) 101066 ISI-13142-48-A ISI R1.20 W-10 Elbow-to-Pipe AUG 2 RHR Service Water OWN PRE : ..- .
R-A(L) 101067 ISI-13142-48-A ISI . . R1.20 W-11 Pipe-to-Elbow AUG 2 RHR Service Water OWN PRE -: R-A(L) 101068 ISI-13142-48-A ISI R1.20 W-12 Elbow-to-Pipe AUG 2 RHR Service Water OWN PRE -. R-A(L) 101069 ISI-13142-48-A ISI . R1.20 W-13 Pipe-to-Pipe AUG 2 RHR Service Water OWN PRE - - - - - - - - - - - - R-A(L) 101070 ISI-13142-48-A ISI R1.20 W-14 Pipe-to-Elbow AUG 2 RHR Service Water OWN PRE . R-A(L) 101071 ISI-1314248-A PSR. - - - . R1.20 W-15 Elbow-to-Pipe AUG 2 RHR Service Water OWN - - . PRE . . ... . . . . . . . R-A(L) 101072 ISI-13142-48-A ISI R1.20 W-16 Pipe-to-Elbow AUG . 2 RHR Service Water OWN PRE --. R-A(L) 101073 ISI-13142-48-A ISI - - . R1.20 W 17 Elbow-to-Pipe AUG . . . . . . . . . 2 RHR Service Water OWN . . . . . . . PRE -. - - - - - P REiWA R. AIfL7A ISI-13142-48-A ISI R1.20 W-18 Pipe-to-Elbow AUG 2 .PHR Service Water OWN PRE Pr fnf1!4!7nn;
I i C CP Monticello Nuclear Generating Plant 4th Interval ISI Plan. (Rev.3) Page 209 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (MayI 1,. 2003 to May 31, 2012)
. . .- - .. . .. . I . ........
Period I Period 2 ; Period 3 I . Category, Iso No. ItemNO, Comp. Desc.
. Scope I Method / Procedure . . - Code Case 2 31 A I 2 I A I I A A Class'. - - Summary I ComplD I System R-A(L) 101075 - - . I-13142-48-AISI R1.20 W-19 Elbow-to-Pipe AUG .
2 RHR Service Water OWN
.-.... PRE' R-A(L) 101076 ISI-13142-48-A ISI ..
R1.20 W-20 Pipe-to-Pipe AUG RHR Service Water OWN ; 2
.. . ...... .- - - - -- -PRE R-A(L) 101077- ISI-13142-48-A ISI R1.20 W-21 Pipe-to-Pipe AUG 2 RHR Service Water OWN
..-.- PE PRE- -
R-A(L) 101078 ISI-13142-48-A IS1 R1.20 W-22 Pipe-to-Pipe AUG 2 RHR Service Water OWN
.............. .... -,-.- - ".... ... PRE R-A(L) 101079 :- ISI-13142-48A ISI .
R1.20 W-23 Pipe-to-Elbow AUG
- 2. RHR Service Water OWN
......-.--- PRE- ;.....
R-A(L) 101080 ISI-13142-48-A ISI R1.20 W-24 Elbow-to-Pipe AUG 2 RHR Service Water OWN PRE R-A(L) 101081 ISI-13142-48-A ISI - R1.20 W-25 Pipe-to-Pipe AUG 2 RHR Service Water OWN PRE - - - -- R-A(L) 101082 ISI-1314248-A ISI R1.20 ,. W-26 Pipe-to-Valve AUG 2 RHR Service Water OWN PRE 1' IV- W ......._ w-#~~~l'Jluu~~w*.- lU ' _ . Vav-1314t-EAlb ISI R1.20 : W - - - .. .'; Vaive-to-Elbsow. AUG 2 RHR Service Water OWN PRE Print r1 314r2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 210 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3
- Category, ltemNO, Class Summary I ComplD I System Scope I Method I Procedure Iso No.
Comp. Desc. Cndel rCae 4 q e j 1.- - 1, R-A(L) 101084 ISI-13142-48-A ISi R1.20 W-28 Elbow-to-Pipe AUG 2 RHR Service Water OWN PRE . . . . . . . . . . . . R.A(L) 101085 ISI-13142-48-A ISP R1.20 W-29 Pipe-to-Tee AUG 2 RHR Service Water OWN PRE ISI- - -- - - - - - R-A(L) 101086 - - - - - - - - - - - - R1.231204-BISI R1.20 W- 1 Valve-to-Elbow AUG 2 RHR Service Water OWN PRE - - - - - - - - - - - - R-A(L) 101087 ISI-13142B ISI R1.20 W-2 Elbow-t-Pipe AUG 2 RHR Service Water OWNE-bow-t--PpeAU PRE R-A(L) 101088 ISI-13142-48-B ISI R1.20 W-3 Pipe-to-Elbow AUG
- 2. RHR Service Water OWN PRE 101089 ISI-13142-48-B ISP -- -
R-A(L) R1.20 W- 4 Elbow-to-Pipe AUG 2 RHR Service Water OWN PRE R-A(L) 101090 ISI-13142-48-B IsI R 1.20 W- 5 Pipe-to-Elbow AUG OWN 2 RHR Service Water R-A(L) 101091 ISI-13142-4-B IPSR E . R1.20 W- 6 Elbow-to-Pipe AUG OWN 2 RHR Service Water PRE - - - - - - - - - t~
^
R-A(L -' 101092-. ;i1:^r, 151 R1.20 - W-7 Pipe-to-Elbow AUG 2 RHR Service Water OWN (I PRE Printed 314/2005
C C 4th Interval ISI Plan (Rev.3) .-
,C Page 211 of 332 Monticello Nuclear Generating Plant ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012)
- Period 1 . . Period 2 Period 3 Category, Iso No.
ItemNO, Comp. Desc. Class . Summary / CompiD I System . -.- . -. Scope / Method / Procedure. . .. Code Case- - 1.. 2 3 4 1- 2 3 4 1.2 23 4 R-A(L) 101093 - ISI-1314248-B ISI - R1.20 W- 8 Elbow-to-Pipe AUG 2 -* RHR Service Water OWN PRE-R-A(L) 101094 IS--13142-48-B IS- BISI R1.20 W- 9 Pipe-to-Elbow AUG - - - 2 . RHR Service Waler -. OWN
..... ... *- -*-----PRE--- --
R-A(L) 101095 - ISI-13142-48-B ISI!. R1.20 W-10 Elbow-to-Pipe AUG 2 RHR Service Water OWN _ ..... .... ._ . - ----- PRE -- R-A(L) 101096 ISI-13142-48-B ISI R1.20 W-11 Pipe-to-Elbow AUG 2 - RHR Service Water OWN
-.-.- PRE -
R-A(L) 101097 - ISI-13142-48-B ISI R1.20 W-12 Elbow-to-Pipe AUG 2 - RHR Service Water . OWN -- '- -
....- ~~PRE~-----
R-A(L) 101098. ISI-13142-48-B 15ISI - . R1.20 W-13 Pipe-to-Elbow AUG 2 RHR Service Water - .OWN
.- --- PRE------.
R-A(L) 101099 ISI-13142-48-B ISI - - - - - - - - - - R1.20 W-14 Elbow-to-Pipe AUG 2 RHR Service Water OWN PRE R-A(L) 101100 ISI-13142-48-B ISI . . . R1.20 W-15 Pipe-to-Elbow AUG 2 RHR Service Water OWN .- , . PRE R-A(L) ,101101 ISI-13142-48-B ISI R1.20 W-16 Elbow-to-Pipe . AUG I o , I .- 2 RHR Service Water OWN PRE Printed 3/4/2005
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 212 of 332 ASME Section Xi (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 B I IsI R1.20 W-17 Pipe-to-Elbow AUG 2 RHR Service Water OWN PRE R-AtL) 101103 ISI-13142-48-B ISI - - . R1.20 W-18 Elbow-to-Pipe AUG 2 RHR Service Water OWN - - - - - - - . PRE R-A(L) 101115 ISI-13142-49-A ISI R1.20 W- 1 Valve-to-Elbow AUG 2 RHR Suction A OWN PRE R-A(L) 101116 ISI-13142-49-A ISI R1.20 W-2 Elbow-to-Pipe AUG 2 RHR Suction A OWN PRE R-A(L) 101117 ISI-13142-49-A ISI R1.20 W- 3 Pipe-to-Elbow AUG 2 RHR Suction A OWN PRE R-A(L) 101118 ISI-13142-49-A ISI R1.20 W- 4 Elbow-to-Pipe AUG 2 RHR Suction A OWN PRE R-A(L) 101119 ISI-1314249-A ISI R1.20 W- 5 Elbow-to-Pipe AUG 2 RHR Suction A OWN PRE.- R-A(L) 101120 ISI-13142-49-A ISI R1.20 W- 6 Pipe-to-Elbow AUG 2 RHR Suction A OWN PRE R-A(L) 101121 ISI-1314249-A ISI Ri .20 W-7 Pipe-to-Branch AUG (HR Suction A OWN
-C 2
C. PRE Prinlad 1 4t12005
C C- .C
- Monticello Nuclear Generating Plant 4th Interval 151 Plan (Rev.3) Page 213 of 332
~--ASME Section XI (1995 Edition, 1996 Addenda) (May 1,2003 to May 31, 2012)
IPeriod 1 PerIod 2 Period 3 Category, Iso No. 1temNO, - Comp. Dese. CompiD ISy'stem -r. .Scope!I Method I Procedure Code Case'" 1 23 4 I 2 34 1 23 4 Class'.. . -Summnary! . ISI-1 3142-49-A S - - - - - - - - - - - - R.A(L) 1-01122 Pipe-to-Pipe AUG R20 W OWN 2 RHR Suction A PR. ISI-13142-49-A isl R-A(L) 101123 Pipe-to-Elbow AUG RI.20 W9 OWN - - - - - - - - - - - 2 RHR Suction A . ISI-131 42-49-A IS[,t R-A(L) 101124 - Elbow-to-Pipe AUG - - - - - - - - - - - Rl.20 W-10 OWN - - - - - - - - - - - - 2 RHR Suction A
.~PRE ISI - - - - - - - - - - - -
R-A(L) 101125 .ISI-13142-49-A Pipe-to-Elbow AUG - - - - - - - - - - - - R1.20 W-1 1 OWN - - - - - - - - - - - - 2%RH R Suction A
-PRE 9A s R-A(L) 101 126IS134 Elbow-to-Tee AUG - - - - - - - - - -
R1.20 W-12 OWN - - - - - - - - - - 2 RHR Suction A
.PRE-"-
ISI-13142-49-A ISI R-A(L) 101127 Tee-to-Pipe AUG - - - - - - - - - - - - R1.20 W-13 OWN - - - - - - - - - - - - 2- RHR Suction A PRE -- 101128 ISI-13142-49-A Isi R-A(L) - - - - - - Pipe-to-Elbow AUG - - - - - - R1.20 W-14 OWN - - - - - - - - - - - - 2 RHR Suction A RE - - -- - - - - - - - - -
.O.
ISI-13142-49-A ISI R-A(L) 101129 AUG . . . . . . . . . . . . R12 . W 15Elbow-to-Pipe - - OWN - - - 2 RHR Suction A rtA % a d aPRE IUI IOU - . I .ISI-1 31 42-49-A ISI R1.20 W-16 , ,- ... . a ,-Tee-to-Elbow. AUG 2 RHR Suction 8 OWN PRE Prifn'f IP2 0 9~
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 214 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003.to May.31, 2012) Period I Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 101131 ISI-13142-49-A ISI R1.20 W-17 Elbow-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 101132 ISI-13142-49-A ISI Ri.20 W-18 Pipe-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 101133 ISI-13142-49-A ISI R1.20 W-19 Pipe-to-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 101134 ISI-13142-49-A ISI R1.20 W-20 Pipe-to-Elbow AUG 2 RHR Suction B OWN PRE R-A(L) 101135 ISI-13142-49-A IS1 R1.20 W-21 Elbow-to-Pipe AUG 2 - RHR Suction B OWN PRE R-A(L) 101136 ISI-13142-49-A ISI R1.20 W-22 Pipe-to-Elbow AUG 2 RHR Suction B OWN PRE R-A(L) 101137 ISI-13142-49-A ISI R1.20 W-23 Elbow-lo-Pipe AUG 2 RHR Suction B OWN PRE R-A(L) 101138 ISI-13142-49-A ISI R1.20 W-24 Pipe-to-Valve AUG 2 RHR Suction B OWN PRE R-A(L) 101140. ISI-13142-51-A 5lS R1 .20 W-1 Pump-to-Reducer AUG 2 RHR A OWN Q PRE Printed 3/4/2005
( C (C Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 215 of 332 ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class,, , Summary I ComplD I System, - Scope I Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 101141 ISI-13142-51-A ISI . R1.20 W-2 Reducer-to-Valve AUG 2 RHRA - OWN - - - .
* . - . . ~~. -.- - ~P R E- - - - . . '
R-A(L) 101142 ISI-13142-51-A 181 R1.20 W- 3 Valve-to-Elbow AUG
- 2. , RHR A . OWN .
.... ~~PR E -- - - -
R-A(L) 101143 ISI-13142-51-A SiS l R1.20 W- 4 Elbow-to-Elbow AUG 2 . RHR A OWN
. .. .- -..... PRE -
R-A(L) 101144 ISI-13142-51-A iSi - . R1.20 W- 5 Elbow-to-Valve AUG 2.. RHR A , , ,. OWN 2 , , ,, OWN. - .- ..,- ....- - -. -. -- - - - -------------- PE.----
.-.- . -PRE R-A(L) 101145 ISI-13142-51-A ISl7-R1.20 W-6 Valve-to-Pipe , AUG 2 ,., RHRA A, ,, ,, OWN
.OWN.-.- ---- --- - -R- 7-7 R-A(L) 101146 ISI-13142-51-A iSI .
R1.20 W 7 Pipe-to-Elbow AUG 2 . RHR A OWN
...-.. PRE -
R-A(L) 101147 ISI-13142-51-A IS1 R1.20 W- 8 Elbow-to-Reducer AUG 2 RHR A OWN PRE . . R-A(L) 101148 ISI-13142-51-A ISI : R1.20 W- 9 Reducer-to-Tee AUG 2 RHR A OWN - PRE R-A(L) ,. ; 101149 -. , - -11 I !. 1-- .. I , ., ., . . . ISI-13142-51-A ISI R1.20 ;W-10 ., Pump-to-Reducer AUG 2 RHR A OWN PRE Prinfnrf ibmo()
Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 216 of 332 ASME Section XI (1995 Edition, 1996 Addenda) (May 1. 2003 to May 31, 2012) Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD / System Scope / Method / Procedure Code Case 1 2 3 4 1 2 3 4 1 2 3 4 R-A(L) 101150 ISI-13142-51-A IS1 R1.20 W-11 Reducer-to-Elbow AUG 2 RHR A OWN PRE R-A(L) 101151 ISI-13142-51-A IS1 R1.20 W-12 Elbow-to-Pipe AUG 2 RHR A. OWN PRE-R-A(L) 101152 ISI-13142-51-A ISI R1.20 W-13 Pipe-to-Elbow AUG 2 RHR A OWN PRE R-A(L) 101153 ISI-13142-51-A ISI R1.20 W-14 Elbow-to-Valve AUG 2 RHR A OWN PRE R-A(L) 101154 151-13142-51-A ISI R1.20 W-15 Valve-to-Pipe AUG 2 RHR A OWN
- PRE R-A(L) 101155 151-13142-51-A ISI R1.20 W-16 Pipe-to-Elbow AUG 2 RHR A OWN PRE R-A(L) 101156 151-13142-51-A ISI R1.20 W-17 Elbow-to-Valve AUG 2 RHR A OWN PRE R-A(L) 101157 ISI-13142-51-A ISI R1.20 W-18 Valve-to-Pipe AUG 2 RHR A OWN PRE R-A(L) 101158 ISI-131 42-51-A IS1 R1.20 W-19 Pipe-to-Tee AUG 2 RHR A OWN
( PRE
-C -
Printed 3/4/2005
C C C2 Monticello Nuclear Generating Plant 4th Interval ISI Plan (Rev.3) Page 217 of 332. ASME Section Xl (1995 Edition, 1996 Addenda) (May 1, 2003 to May.31, 2012) Period 1 i Period 2 Period 3 Category, Iso No. ItemNO, I* Comp. Desc. Class- - Summary I CompiD I System - . - Scope I Method I Procedure .. Code Case: 1 .2 3 4 1..2 .3. 4 1. 2 3 4 R-A(L) 101159 ISI-13142-51-A ISI . . . . . . . . . . . . R1.20 W-20 Tee-to-Pipe AUG . . . . . . . . . . . . 2 RHR A OWN - - - - - - - - - - - -
-""PRE R-A(L) 101160 ISI-13142-51-A I-S---. - - - - - - - - - - -
R1.20 W-21 Pipe-to-Elbow AUG - ....}}