05000313/LER-2002-003, For Arkansas Unit 1 Reactor Coolant System Pressure Boundary Leakage from a Crack in a Control Rod Drive Mechanism Nozzle Reactor Vessel Head Penetration Weld Due to Previous Weld Repair Method
05000270/LER-2002-002, Reactor Pressure Vessel Head Leakage Due to Primary Water Stress Corrosion Cracking of Alloy 600 Control Rod Drive Nozzles
Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head
LIC-15-0070, Response to NRC Request for Additional Information Regarding Relief Request RR-14
LIC-15-0069, Response to NRC Request for Additional Information Regarding Relief Request RR-14
AEP-NRC-2014-99, Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code N-729-1 Request Number Isir 04-02
RC-12-0154, Reactor Vessel Head Penetration Weld Repair Under WCAP-15987
AEP-NRC-2011-39, License Renewal Submittal - Alloy 600 Aging Management Program
AEP-NRC-2018-20, Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 1
DCL-10-158, CFR 54.21(b) Annual Update to the DCPP License Renewal Application and Amendment No. 34
L-02-002, G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse
NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal
AEP-NRC-2008-12, Inservice Inspection Summary Report for Period of 11/14/2006 Through 04/29/2008
AEP-NRC-2018-50, Unit 2 - Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4
L-07-082, Cynthia Carpenter Ltr. Response to Demand for Information (DFI)
NL-07-0355, Examination and Mitigation of Alloy 82/182 Pressurizer Butt Welds
CPSES-200700169, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds
RS-07-015, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
RS-06-039, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
2CAN040602, Arkansas, Unit 2 - Request for Relaxation to NRC Order EA 03-09 Regarding Bare Metal Visual Inspection on the ANO-2 Reactor Vessel Hand
L-05-067, Letter Transmitting Firstenergy Corp. 2004 Annual Report
CNL-19-012, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISI-1
NL-03-098, Reactor Vessel Head Inspection Results, Spring 2003 Refueling Outage
LIC-05-0057, Revised Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
LIC-05-0048, Additional Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
LIC-05-0043, Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
L-2007-013, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds
L-2004-160, NRC Bulletin 2004-01 Inspection of Alloy 821182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors
RNP-RA/04-0086, Results of Inspections Conducted in Accordance with the First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
CPSES-200401627, Day Response Regarding NRC Bulletin 2003-02 and NRC Order EA-03-009
LR-N04-0199, Response to Request for Additional Information Regarding Relief Request S1-RR-13-B21 NRC Order EA-03-009 on Reactor Pressure Vessel Head Inspections
Press Release-III-04-011, NRC Approves Davis-Besse Restart
RC-03-0254, Response to NRC Bulletin 2002-02 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs
NRC 2003-0112, Supplemental Response to NRC Bulletin 2001-01, 2002-01, and 2002-02 for Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Findings
DCL-03-151, 90-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
L-03-138, Response to NRC Bulletin 2003-02
RNP-RA/03-0075, Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6
L-PI-03-071, Supplemental Response to NRC Bulletins 2001-01 & 2002-01
2CAN060308, Response to Request for Additional Information on the ANO-2 Relaxation from Performing a Bare Metal Visual Inspection from the February 11, 2003 Reactor Pressure Vessel Head Order
2CAN050301, Request for Relaxation from Section IV.C(1)(a) of the Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads
RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504
DCL-03-045, 30-Day Response to NRC Bulletins 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles & 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response to N
NL-03-0815, Responses to NRC Questions on Relaxation Request to Order EA-03-009
L-03-057, Reply to Request for Additional Information Regarding Order EA-03-009 Relaxation Request
NL-03-0684, ASME Section XI Requests for Relief Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head
L-03-010, Proposed Alternatives to Gas-Tungsten Arc Welding (Relief Request BV3-RV-03)
LIC-02-0106, Revised Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head Degradation & Vessel Head Penetration Nozzle Inspection Programs
3F0103-03, Response to Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Degradation & Reactor Coolant Pressure Boundary Integrity
NRC 2004-0052, Letter from G. D Van Middlesworth, NMC, to NRC NRC Order EA-03-009 Relaxation Request Supplement
ULNRC-04799, Response to Request for Additional Information - NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
W3F1-2003-0005, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
DCL-03-008, Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
RNP-RA/03-0001, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
L-PI-03-007, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-day Response for Prairie Island Nuclear Generating Plant, Request for Additional Information
NL-03-020, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01
NRC 2003-0006, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567)
HNP-02-164, Letter from James Scarola, Harris Nuclear Plant - - Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
L-02-121, Updated Information Regarding Bulletin 2001-01 & Bulletin 2002-01
CPSES-200300054, 30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
NOC-AE-02001437, STP Unit 2 Reactor Pressure Vessel Head Inspection Results in Response to Bulletin 2001-01, Bulletin 2002-01 and Bulletin 2002-02
ULNRC-04783, Response to Information Requested 30 Days After the Next Refueling Outage by NRC Bulletins 2001-01, 2002,01, & 2002-02
NL-02-162, Reactor Vessel Head Inspection Results; Indian Point 2, Fall 2002 Refueling Outage
1CAN120205, 30-Day Post Outage Response to NRC Bulletins 2001-01, 2002-01 & 2002-02 for ANO-1
RNP-RA/02-0182, Submittal of 30-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
RNP-RA/02-0175, Submittal of Results of Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspections Performed During Refueling Outage 21
L-2002-233, Westinghouse Report WCAP-15945-NP, Rev. 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: St. Lucie Unit 1
1CAN100203, Supplemental Response to NRC Bulletin 2002-02 for Arkansas Nuclear One, Unit 1
BYRON 2002-0109, Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Head Penetration Nozzles
L-01-002, NRC Bulletin 2001-01: Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles - Updated Response
B18790, Inservice Inspection Program - Owners Activity Reports
NL-03-178, Day Response to NRC Bulletin 2003-02 Regarding Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
CNRO-2002-00048, Arkansas Units 1 & 2, Waterford Unit 3 Proposed Alternatives to ASME Requirements for Weld Repairs
ULNRC-04731, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
CPSES-200203264, Day Response to Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
NRC 2002-0082, Day Response to NRC Bulletin 2002-02: Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs
RS-02-154, Exelon/Amergen Thirty-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
ET 02-0037, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
DCL-02-109, Day Response to NRC Bulletins 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
LR-N02-0297, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs for Salem Units 1 & 2
NOC-AE-02001386, Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
RC-02-0160, Response to NRC Bulletin 2002-02 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs
NL-02-119, Letter from John Herron Re 30 Day Response to NRC Bulletin 2002-02
L-2002-185, Response to NRC Bulletin 2002-02 - Reactor Pressure Vessel Head Penetration Nozzle Inspection Programs
RNP-RA/02-0126, Submittal of Information Requested by NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
NRC 2002-0069, Filing of Owners Inservice Inspection Summary Report
NL-02-114, ASME Code Relief Requests to Use Alternative Repair Methods and NDE Techniques for Reactor Vessel Head Penetration Nozzles
3F0802-07, Response to NRC Bulletin 2002-02 Re Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Program from Florida Power Corp
W3F1-2002-0080, Day Response to Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs
CNRO-2002-00022, Arkansas Units 1 & 2 & Waterford Unit 3, Response to NRC Request for Additional Information Regarding Proposed Alternatives to ASME Requirements for Weld Repairs
RNP-RA/02-0122, Reactor Vessel Head Inspection Plan for Refueling Outage 21
NL-02-104, ASME Code Relief Requests to Use Alternative to Temper Bead Welding for Contingency Repairs on Reactor Vessel Head Penetration Nozzles
RNP-RA/02-0104, License No. DPR-23, Response to Requests for Additional Information on Amendment Request to Increase Authorized Reactor Power Level
NL-02-101, Letter Providing Additional Details Re Reactor Vessel Head Inspections to Be Performed at Indian Point Unit No. 2 During Next Refueling Outage (2R15)
NL-02-099, Submittal of Supplement to 15-day Response for NRC Bulletin 2002-01 from Entergy Nuclear Northeast
CNRO-2002-00041, Response to NRC Request for Additional Information Regarding Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations from Entergy Operations, Inc
CNRO-2002-00040, Arkansas Unit 1 Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations
RC-02-0115, Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity from Virgil C. Summer
CPSES-200202442, 30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
CPSES-200202322, Comanche Peak'S 30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
LIC-02-0070, Station'S (FCS) Clarifications to FCS Response to Bulletin 2002-01
LR-N02-0178, Response to NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
LR-N02-0180, Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Vessel Head Penetration Nozzles and Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, Salem Generating Statio
ET 02-0023, 30-Day Response for NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.
NRC 2002-0038, Supplement to Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.
L-02-055, 60-Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
RC-02-0091, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
NL-02-074, Submittal of 60-Day Response to NRC Bulletin 2002-01
L-02-054, Reply to Request for Information Concerning Beaver Valley Power Station Responses to NRC Bulletins 2001-01 & 2002-01
BYRON 2002-0050, Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.
NRC 2002-0029, Revised Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
W3F1-2002-0037, 30 Day Response to NRC Bulletins 2001-01 and 2002-01 for Vessel Head Inspection Findings
L-02-040, Supplemental Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
CNRO-2002-00021, Entergy Operations, Inc., Proposed Alternative to ASME Examination Requirements Performed on Reactor Vessel Head Penetrations
NL-02-050, Submittal of 15 Day Response to NRC Bulletin 2002-01.
CNRO-2002-00020, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations
CPSES-200200917, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
0CAN040201, Day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
DCL-02-033, Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
ET 02-0018, Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
CNRO-2002-00017, Proposed Alternative to ASME Code Requirements for Weld Repairs
W3F1-2002-0032, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
LR-N02-0108, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
NOC-AE-02001290, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
RC-02-0055, Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
HNP-02-052, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
LIC-02-0034, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
CNRO-2002-00013, Arkansas Units 1 & 2, Waterford Unit 3, Use of Electrical Discharge Machining
L-02-021, Bulletin 2001-01 Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
CNRO-2002-00006, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations
CNRO-2002-00008, Proposed Alternative to ASME Code Requirements for Weld Repairs
CNRO-2002-00007, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations
L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424
L-2002-023, Request for Approval of Relief Requests 30 & 31, Reactor Vessel Closure Head Repair
HNP-02-009, Supplemental Response to NRC Bulletin 2002-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
2CAN020203, Response to Request for Additional Information on Vessel Head Penetration Nozzles Re the ANO-2 Power Uprate License Application
CNRO-2002-00001, Letter of Intent Re Proposed Alternatives to ASME Code Requirements
ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138)
NRC-83-0058, Final Significant Deficiency Rept 83-11 Re Failures in Pacific Scientific Co Snubber Spring Assemblies.Initially Reported to Regions IV & III on 830913 & 16,respectively. Springs Will Be Replaced.Also Reportable Per 10CFR21
ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
CP-201500430, Relief Request lB3-4 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Head Penetration Weld Inspection
IA-05-054, Perry Nuclear Power Plant, Atomic Safety and Licensing Board Order (Approving Proposed Settlement and Dismissing Proceeding) (ASLBP No. 06-847-03)
NL-06-1217, WCAP-16493-NP, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Vogtle Units 1 & 2
05000287/LER-2001-001-01, Regarding Reactor Pressure Vessel Head Leakage Due to Stress Corrosion Cracks Found in Nine Control Rod Drive Nozzle Penetrations
B19004, Response to Request for Additional Information on RR-89-48 for the Nozzle Inspection Ultrasonic Test Coverage Requirements in Order EA-03-009
B18853, Request for Relaxation from Section IV.C(a)(1) of the Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads
L-2003-070, Enclosure 1 - St. Lucie License Renewal Safety Evaluation Report Open Item and Confirmatory Item Responses and Revised License Renewal Application Appendix a
B18815, Reply to Request for Additional Information Related to NRC Bulletin 2002-01
B18811, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs
B18802, Supplemental Response to NRC Bulletin 2001-01 Re Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
B18792, Response to NRC Bulletins Regarding Reactor Pressure Vessel Head Inspections
B18735, Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs
1CAN090202, Entergys 30-day Response to NRC Bulletin 2002-02, for Arkansas Nuclear One, Unit 1
B18740, Day Response to NRC Bulletin 2002-02 Reactor Pressure Vessel Heat Penetration Nozzle Inspection Programs
B18640, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
B18662, Reply to Request for Additional Information Related to NRC Bulletin 2001-01
05000269/LER-2002-003, Re Minor Reactor Pressure Vessel Head Leakage Due to Primary Water Stress Corrosion Cracking of an Alloy 600 Control Rod Drive Nozzle
B18637, Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
05000336/LER-2002-001, Two Reactor Coolant System Pressure Boundary Leakage Events on 02/19/2002 and 02/22/202
05000346/LER-2002-002, Reactor Coolant System Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism Nozzles and Reactor Pressure Vessel Head Degradation
B18621, Response to NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
RS-02-061, Exelon/Amergen Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
B18601, ASME Section XI Request, Use of Alternative to Weld Repair Requirements and Relief Request, Characterization and Successive Examinations of Remaining Flaws in Reactor Vessel Head Penetrations
B18590, Millstone. Unit 2 - Request to Use an Alternative to ASME Code Section XI Repair Welding Requirements by Employing Temper Bead Techniques
B18586, Supplemental Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
B18580, Supplemental Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
RNP-RA/02-0041, Submittal of Information Requested by NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
PNO-III-02-006, Significant Metal Loss Observed in Reactor Vessel Head
05000339/LER-2001-003, Reactor Vessel Head Nozzle Through-Wall Leakage Due to Lack of Weld Fusion During Original Fabrication
05000287/LER-2001-003, Minor Reactor Pressure Vessel Head Leakage from Several Control Rod Drive Nozzle Penetrations Due to Primary Water Stress Corrosion Cracking
NRC-2002-0002, Revised Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
SECY-02-0155, Weekly Information Report - Week Ending 08/09/02
NL-04-0617, Application for License Renewal - Requests for Additional Information
NL-03-1958, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity.
RC-02-0114, Response to NRC Bulletin 2001-01 Re Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles
RNP-RA/02-0072, Submittal of 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.