Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations
Regulatory Guide 1.150# QUERYc5d7c1b9f83657d2a9120a19ef4f31fa
Regulatory Guide 1.150# QUERY6e8e6098e14870e6e2c4dfebdb64e5a9
Regulatory Guide 1.150# QUERY09eb28e512974639deab8b6e7166aafb
Regulatory Guide 1.150# QUERYc3d71bc3d0567166d422ca930681e2ff

Regulatory Guide 1.150# QUERY63d5ea34e6aa3a2e0bea4e8bf23559a9
Regulatory Guide 1.150# ERR1dd423a8697e32d6813ecd1a7aae482c
Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel
Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel
PLA-4011, Forwards Responses to Requests for Addl Info & 930520 Re First 10-Yr ISI Program Plan.Final Reconciliation of ISI Program Plan Will Be Completed Prior to 950601
RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
RS-15-156, Response to Request for Additional Information Regarding License Amendment Request to Utilize WCAP-16143-P, Revision 1, as an Analytical Method to Determine the Reactor Coolant System Pressure And.
WO 14-0002, Operating Corporation - 10 CFR 50.55a Requests 13R-08 and 13R-09 for the Third Inservice Inspection Program Interval
RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests
TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval
RS-11-015, Response to Request for Additional Information Related to Relief Requests
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 4 Through Chapter 5
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems
NOC-AE-100025, Submittal of Updated Final Safety Analysis Report Revision 15
W3F1-2010-0014, Response to NRC Request for Additional Information Dated January 6, 2010 Waterford 3 Steam Electric Station, Unit 3 - Requests for Relief from ASME Section XI Volumetric Examination Requirements - Second 10-Year Inservice Inspection I
2CAN100902, Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations
TMI-09-142, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02
CP-200901227, Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Informatio
NRC-09-0038, Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities
CP-200900009, Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses
HNP-08-045, Second Ten-Year Interval Inservice Inspection Program-Final Documentation Including Requests for Relief in Accordance with 10 CFR 50.55a
NL-08-177, Response to Request for Additional Information on Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment
W3F1-2008-0060, . Request for Alternative W3-ISI-006 and Proposed Alternative to Extend the Second 10-Year Inservice Inspection Interval for Reactor Vessel Internal Weld Examinations
NL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses
1CAN050807, Inservice Inspection Plan for the Fourth 10 - Year Interval
1CAN010801, Request for Relief from ASME Section XI, Table IWB-2500-1 Requirements
NRC 2007-0093, Response to Request for Additional Information 10 CFR 50.55a Requests Relief Request RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval
CNRO-2007-00020, Request for Alternative W3-ISI-003, Proposed Alternative to Extend the Second 10 - Year Inservice Inspection Interval for Reactor Vessel Internal Weld Examinations
NRC 2007-0020, 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval
L-06-111, Response to Request for Additional Information Regarding Relief Request No. BV3-RV-1
NL-06-1305, Inservice Inspection Alternatives for Reactor Pressure Vessel Examinations
CNRO-2006-00024, Request for Alternative ANO-ISI-005, Proposed Alternative to Extend the Third Inservice Inspection Interval for Reactor Vessel Inservice Examinations
L-06-042, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Examination Requirements
GO2-05-196, Submittal of the Third Ten-Year Interval Inservice Inspection Program Plan and 10 CFR 50.55a Requests 3ISI-01 Through 3ISI-07
NRC Generic Letter 83-15, Implement. of Reg. Guide 1.150, "Ultrasonic Testing of RX Vessel Welds During Preservice & Inservice Examinations, REV.1
HNP-05-130, Relief Requests No 2R1-016 Request for Relief from Inservice Inspection Requirements for Pressure Retaining Dissimilar Metal Welds and No 2R1-017 Request for Relief from Inservice Inspection Program Requirements for Reactor Vessel
L-PI-05-082, Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program
L-PI-05-083, Request for Relief No. 2-RR-4-6, for the Unit 2 4th 10-Year Interval Inservice Inspection Program
NL-05-0720, Request for Relief to Extend the Third 10-Year Inservice Inspection Interval for the Reactor Vessel Weld Examination
WM 05-0013, 10CFR50.55a Requests Regarding Implementation of ASME Section XI Requirements for Examination of the Reactor Pressure Vessel and Connecting Loop Piping Welds; 10CFR50.55a Requests 12R-29, 12R-30, 12R-31, and 12R-32
L-PI-05-012, Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program
L-MT-04-050, Fourth Interval Inservice Inspection Examination Plan, Revision 2
NL-04-100, Reply to Supplemental Request for Additional Information Regarding Stretch Power Uprate
L-PI-04-070, Reply to Request for Additional Information on Third Ten Year 10-Year Inservice Inspection Interval Request for Relief No. 16
NL-04-045, Reply to RAI Regarding Relief Requests to Use ASME Code Case N-613-1; Reactor Vessel Nozzle-to-Vessel Weld Inspections
GNRO-2004/00019, Transmittal of Inservice Inspection Summary Reports
RNP-RA/03-0160, Response to RAI for Relief Request Pertaining to Examination Coverage Less than Essentially 100 Percent (Relief Request No. 34)
L-PI-04-005, Request for Relief No. 16, Revision 0 for the Third 10-Year Interval Inservice Inspection Program
NL-03-188, Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection
L-PI-03-118, Request for Relief No. 14, Revision 1 for the Third 10-Year Interval Inservice Inspection Program
RC-03-0223, Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-15, RR-II-18 (0-C-03-0262)
RC-03-0196, Resubmittal of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI (C-03-0262), RR-II-15, RR-II-16, RR-II-17, RR-II-19
ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements
NL-09-2057, FNP-ISI-ALT-09, Version 1.0, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
RC-03-0142, Request for Use Alternatives to ASME Boiler & Pressure Vessel Code, Section XI, RR-II-15, RR-11-15, RR-II-17, RR-II-18, RR-II-19, RR-II-20 and RR-II-21
LIC-94-0078, Forwards Documentation from 1992 ISI of Reactor Pressure Vessel Welds in Beltline Region in Response to Request for Addl Info Re Third 10-yr Interval ISI Program Plan & Associated Relief Requests
L-MT-03-004, Change to Inservice Program Plan & Inservice Inspection Examination Plan 10-Year Intervals
CPSES-200203345, Relief Requests A-3, A-4 Rev 1, & A-5 Rev 1 to the Inservice Inspection (ISI) from 1986 Edition of ASME Code, Section XI, No Addenda (Interval Start Date: August 13, 2000, Second Interval)
U-603571, Day Post-Outage Inservice Inspection (ISI) Summary Report
CPSES-200202752, Relief Request A-3, A-4, and A-5 to ASME Code, Section XI, No Addenda (Interval Start Date: August 13, 2000, Second Interval)
CPSES-200200025, Relief Requests from 1986 Edition of ASME Code, Section XI, No Addenda, Inservice Inspection (ISI) A-4 Through A-8
ET 02-0002, Inservice Inspection Program Alternative for Limited Examination on Closure Head to Flange Weld on the Reactor Pressure Vessel, Relief Request l2R-25
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
HL-5250, Requests NRC Authorization of Alternative Exam Per Provisions of 10CFR50.55(g)(6)(ii)(A)(5) for Shell Welds on Plant,Unit 2
NG-96-2088, Forwards Revs to Relief Reqests HT-014 & NDE-020 Re Third Ten Yr Interval Inservice Insp Plan.Util Has Withdrawn Relief Request NDE-R022
NRC-99-0038, Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)
NRC-99-0041, Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl
NRC-98-0093, Provides Detailed Response to Request for Addl Info Re Relief Request Update for First 10-yr ISI NDE Program
1CAN109705, Requests Relief from Requirements of 10CFR50.55(a)(g)(ii)(A) Augmented Reactor Vessel Shell Weld Insp.Util Was Unable to Examine Greater than 90% of Four Rv Welds Due to Rv Interferences.Relief Request,Encl
LR-N970558, Requests Approval of Attached Relief Request RR-A4 to First Ten Yr ISI Program.Details & Justification for Relief Explained Further in Attached Relief Request
SVP-97-202, Provides RPV Shell Weld Exam Results & Proposed Alternative Exam Requirements
A97010, Requests Authorization for Alternative to One Time Augmented Insp of RPV Shell Welds Set Forth in 10CFR50.55a(g)(6)(ii) (A)(2) Per 10CFR50.55a(g)(6)(ii)(A)(5).Authorization to Use Partial Insp Coverage Requested
B12512, Forwards Relief Request 2.0,requesting Relief from Performing Inservice Surface Exam of Eight nozzle-to-safe End Butt Welds for Inservice Insp Program,Code Category B-F, Item B5.10.Relief Requested by 870615.Fee Paid
LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds
1CAN059902, Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program
SVP-99-063, Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval
B16647, Requests Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Section XI for Unit 3
B17468, Requests Relief from Performing Inservice Volumetric Exams of Inaccessible Portions of RPV flange-to-shell Weld,Per 10CFR50.55a(g)
B12819, Responds to 880205 Request for Addl Info Re Reactor Protection Sys Upgrade.Meeting Arranged W/Nrc on 880210 at White Flint Ofcs.Util Maintains RPS Upgrade Meets 10CFR50.59 Requirements & Does Not Need Prior Approval
L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2
NG-96-2574, Responds to 961118 Telcon RAI Re Inservice Insp Relief Requests NDE-020 & NDE-R011.Ultrasonic Calibr Data,Provided
AECM-87-0198, Provides Rev to 10-yr Inservice Insp Plan Relief Request I-00015 Submitted by .Rev Provides New Figure for Reactor Pressure Vessel Seam Ba,Demonstrating Geometric Limitation of Performing Required Volumetric Insp
NOC-AE-000197, Requests Relief from Performing ISI Nondestructive Examination on Essentially 100% of Weld Length of Two RPV Welds in Unit 1 & Three RPV Welds in Unit 2
ST-HL-AE-2274, Forwards Scan Plan for Mechanized Ultrasonic Exam of Selected Areas of South Texas Project Electric Generating Station,Unit 2, Vols I-IV.Plan Suppls STPEGS-2 Preservice Insp Exam Plan Transmitted on 870514
ST-HL-AE-1837, Forwards Requests for Relief RR-ENG-02,03,04 & 05 from ASME Section XI Inservice Insp Requirements.Submittals Identify Section XI Preservice Insp Exam Requirements Impractical to Perform & Provide Supporting Justification for Each Requ
AECM-87-0112, Forwards Revs to Relief Requests I-00004,I-00009 & I-00010 & Relief Requests I-00014 & I-00015.Relief Necessary Due to Exam Limitations Identified in First Refueling Outage at Unit 1.Expeditious Review & Approval Requested.Fee Paid
ST-HL-AE-2821, Forwards Revised Pages to 880810 Relief Request RR-ENG-07 Re Preservice Insp Program,Per 880908 Telcon
NPL-98-0931, Requests Relief from Section XI of ASME Boiler & Pressure Vessel Code, Rules for Inservice Exam of Nuclear Power Plant Components, 1986 Edition,No Addenda
HL-5728, Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures
NG-97-0078, Submits Clarification & Justification Re ISI Alternative Exam Requests NDE-020 & NDE-R011.GENE 955-009-0197 Rept Encl
NG-96-1807, Responds to RAI on Third 10-yr Interval ISI Program Plan & Associated Requests for Relief
BVY-96-105, Provides Util Plans for Insp of RPV Shell Welds at Plant During Refueling Outage on 960906
U-602566, Forwards Requests for Relief from Requirements of Section XI of ASME Boiler & Pressure Vessel Code,1980 Edition Through Winter 1981 Addenda,W/Re Performance of non-destructive Exam of Welds
2CAN089210, Forwards Response to NRC 910910 Request for Addl Info Re First 10-yr Inservice Insp Relief Requests,Per 911210 & 920603 Telcons.Under Current Code Rules,Indentification Tag Would Not Cause Exam Limitation
RBG-19-359, Forwards Response to SER Open Item 4 Inservice Test Program & Open Item 6 Preservice Insp Program. Encl Preservice Insp Plan & Pump & Valve Plan Will Be Updated as Design & Const Completed
L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2
JPN-92-036, Provides Results of Reactor Vessel Head Weld Insp Conducted During 1992 Refueling Outage
1CAN039606, Forwards Request for Addl Info Re Relief Request 95-001.Rev 0 to SIR-96-022 & Rev 0 to SIR-95-017 Repts Encl
3F0396-08, Submits ISI Program Relief Request 95-030,Suppl 2,revising Response to RAI Re Reactor Vessel Stress in Structural Integrity Rept SIR-95-135
2CAN049208, Forwards Addl Info to Support 890831 Relief Requests from First 10-yr Inservice Insp Interval Consisting of Listing of Limited Inservice Insp Exam Coverage Estimates for First Insp Interval
L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1
3F0296-07, Forwards Suppl 1 to ISI Relief Request 95-030,consisting of Rev to Code of Ref Previously Provided to Reflect Correct Code.Correct Code ASME B&PV Code,Section XI,1983 Edition Through Summer 1983 Addenda
2CAN079211, Forwards Arkansas Nuclear One Unit 2,Inservice Insp Program Plan,Second Insp Interval. Program Plan Modified by Applying 7.5% Required Code Sampling Across Board for Class 2 Piping Sys Regardless of Nominal Wall Thickness
SNRC-1051, Forwards Summary of Disposition of Generic Ltrs for CY83
3F0995-03, Requests Review & Approval of Encl ISI Program Relief Requests 95-010,95-020,95-030 & 95-040,for Implementation by Next Refueling Outage Scheduled for Feb 1996
NRC-84-0095, Forwards Rev 15 to Fsar.Rev Includes Only Changes Consistent W/Basis for Issuance of Callaway License
B15266, Notifies NRC of Inability to Completely Satisfy Requirements for Second 10-yr ISI Augmented Exam of Reactor Pressure Vessel at Millstone Unit 2 & Requests Authorization to Not Perform Any Addl or Alternative Exams
B11165, Forwards Response to Matls Engineering Branch Draft SER Open Item Mteb 250.9 Re Compliance W/Reg Guide 1.50, Ultrasonic Testing of Reactor Vessels During Preservice & Inservice Insp
3F0691-01, Responds to NRC 910425 Request for Addl Info Re Inservice Insp Program Plan.Listed Relief Requests Re Class 2 Piping & Recertification of Level III Personnel by Exam on Triennial Basis Already Submitted
LIC-95-0063, Provides Response to Request for Addl Info Re ISI Program Plan.Rev 2 to SEI-27, ISI & Test Program, Encl. W/Five Oversize Drawings
BVY-94-124, Forwards Util Response to NRC RAI Re Plant Third ISI Program & Associated Relief Requests
JPN-95-005, Submits Results of Reactor Vessel Head Weld Inspections Conducted During 1995 Refueling Outage.Insp Data Shows No Changes from 1992 Insp Data
B14906, Forwards Rev 1 to Request for Relief from Section XI of ASME Code Exam Requirements Re 10-yr ISI Program
PY-CEI-NRR-2210, Forwards Info to Support Determination for Relief Request IR-030 from Code & Augmented Exam Requirements for Circumferential Welds as Justified.Response Is Requested by 970918
PY-CEI-NRR-2219, Forwards Response to RAI Re 970828 Submittal for Relief Request IR-030 for Relief from Exam of Reactor Pressure Vessel Circumferential Shell Welds for Two Operating Cycles
BECO-LTR-96-010, Provides Suppl Info on Reactor Pressure Vessel Augmented Exam Requested by NRC in 951207 Telcon
BECO-LTR-95-099, Provides Shell Weld Exam Results to Address 950317 Commitment,Per Fr 57FR34666,dtd 920806 & Requests Relief from Exam of Certain Rv Shell Welds Per 10CFR50.55a(g)(6)(ii)(A)(5)
W3P83-0324, Forwards Status List of All Open & Confirmatory Items & Addl Items of Interest
TXX-3632, Advises of Reactor Vessel Preservice Insp in Early Apr 1983. Insp Will Consist of Std ASME Code Section XI Insp & Addl Insp of Beltline Region Welds Utilizing Westinghouse Shallow Angle near-surface Technique
TXX-3590, Discusses Intention to Perform Reactor Vessel Insp Per Westinghouse Contract W/O Implementation of Reg Guide 1.150 During Latter Part of First Quarter 1983
3F0509-08, Third Ten-Year Inservice Inspection (ISI) Interval Relief Request 09-003-II, Revision 1
3F0798-16, Submits Relief Requests 98-009-II,98-010-II & 98-011-II, Respectively.Relief Requests Seek Approval for Limited Volumetric & Surface Exams Performed During Plant Second ISI Interval.W/Two Oversize Drawings
L-90-012, Forwards Info Re code-rejectable Indications Found in Reactor Vessel Outlet nozzle-to-shell Welds,Per 900427 Telcon.List of Attendees from Telcon Encl
ST-HL-AE-1219, Forwards Responses to NRC 850211 Questions.Procedures & Sys Review Branch Questions Will Be Answered by Amend to FSAR Section 14.2 by 850601.W/22 Oversize Drawings.Aperture Cards Available in PDR
JPN-90-040, Forwards Structural Evaluation of Indications in Reactor Top Head at Ja Fitzpatrick Power Station, Based on Evaluation Analyses for Flaw Indications Identified During Routine Inservice Insps
1CAN118203, Submits Response to NRC 820223 & 0302 Ltrs Re Inservice Insp Relief Requests.Consolidated Response Will Keep Overall Program in Perspective
2CAN039012, Forwards ISI Program Vol 17, Seventh Refueling Outage Rept & Vol 18, Seventh Refueling Outage Exam Data. Hydrostatic Test of Main Steam/Secondary Sys Imcomplete
W3P82-0184, Forwards Latest Submittal Schedule for Remainder of SER Open Items
L-89-190, Forwards Addl Info Re Reactor Vessel Fracture Toughness,Per NRC 880531 SER Request.Extension of 30-day Submittal Date Granted by NRC
L-88-207, Responds to NRC 871030 Request for Licensee Plan for Complying w/10CFR50,App G,Section V.C Re Fracture Toughness Requirements & Recommendations That Util Surveillance Program Revised & Integrated Analysis Provided
GO2-93-166, Forwards Revised ISI Program Relief Requests 2-ISI-001 & 2-ISI-010 to Be Implemented During Third Insp Period of First Insp Interval.Ge Coverage Repts for R-8 & R-7 & Coverage Plot for N3 - Main Steam Also Encl
RA-14-105, Submittal of Fifth Ten-Year Interval Inservice Inspection Program Plan
RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures for
RS-04-142, Submittal of Proposed Relief Request CR-39 Regarding Inservice Inspection Program Examination Coverage for the Third Ten-Year Interval
RS-12-151, Fifth Interval Inservice Inspection Program Plan and Relief Requests
BECO-87-158, Responds to 870714 Request for Addl Info Re Second 10-yr Interval Inservice Insp Program Plan.Ref List of Calibr Blocks,Including Identifications,Matl Specs & Sizes Encl