NOC-AE-17003459, Supplement to the License Renewal Application Re Aging Management Programs
NOC-AE-16003348, Response to Request for Additional Information for License Renewal Application 2014 Annual Update (Tac. Nos. ME4936 and ME4937)
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion.
Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head
3F0514-08, NRC Commitment Change Report - May 2014
ULNRC-05863, Cycle 18 Commitment Change Summer Report
DCL-10-076, Response to NRC Letter Dated June 29, 2010, Request for Additional Information (Set 6) for License Renewal Application
ULNRC-05425, Facility Operating License NPF-030 Cycle 15 Commitment Change Summary
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants
RS-03-007, Exelon/Amergen Response to Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
NL-02-074, Submittal of 60-Day Response to NRC Bulletin 2002-01
B11820, Forwards Reviews for Integrated Safety Assessment Program Topics 1.40, Bolting Degradation or Failure & 1.49, Reactor Vessel Surveillance Program, Per . Departmental Instruction 1-MPM-12.17 Also Encl
L-84-159, Informs of Completion of Balance of Actions Requested in IE Bulletin 82-02.Rept Requested in Action Item 4 Encl
3F0684-06, Forwards Response to IE Bulletin 82-02,Action Items 1,2 & 4 Re Threaded Fastener Practices.Flange at Location P-6 Showed Definite Signs of Leakage During Refuel III Insp
2CAN128218, Provides Info to Satisfy Requirements of IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants, Action Item 4.No Indication of stress-corrosion Cracking Found
1CAN078310, Responds to IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants, Action Item 4.Commitments Re Future Insps Withdrawn.Insp Will Continue as Appropriate Under Applicable Codes & Stds
L-83-411, Informs That Util Completed Balance of Actions Requested in Action Item 4 of IE Bulletin 82-02 Re Maint Procedures for Threaded Fasteners
0CAN088201, Submits Initial Responses to 820602 IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants. Action Items Re Plant Shielding & post-accident Sampling Addressed
2CAN038305, Advises That Addl Info in Response to IE Bulletin 82-02 Will Be Provided by 830324
0CAN118209, Forwards Addl Info Re IE Bulletin 82-02,clarifying 820929 Commitments.Results of Matl Review to Determine Number of Leaks on Bolted Closures Listed
2CAN038312, Responds to Re QA for Threaded Fasteners.Review of Relationship,Procurement & Application of Threaded Fastener Lubricants & Injection Sealant Compounds,Per IE Bulletin 82-02,will Be Completed by 830415
0CAN098210, Suppl 820802 Response to IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants. Bolted Closure Leaks Not Complete.Results of Review Will Be Provided by 821108
L-82-326, Forwards Info in Response to IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants. Control Rod Drive Flanges Have Omega Seal Weld Design.No Injection Sealant Matl Used
L-82-322, Submits Evaluation of IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants. Two RCPB Bolted Closures Have Experienced Leakage.Injection Sealant Matls Not Used in RCPB Closures
NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants
L-88-005, Response to Generic Letter 88-05 Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants
05000316/LER-1984-035-01, :on 841226,containment Insp Revealed body-to-bonnet Leakage on RCS Valve 2-RC-107 Loop 4.Caused by Carbon Steel body-to-bonnet Studs Severely Wasted Due to Corrosive Erosion.Studs Replaced
05000338/LER-1983-079-03, /03l-0:on 831020,leakage Observed from body-to- Bonnet Region of Loop Isolation Valve 1-RC-87.Caused by Excessive Boric Acid Corrosion in Studs.Valve Reparied & RCS Pressure Reduced to 2,235 Psig
05000313/LER-1982-027-03, /03L-0:on 820714,RCS Leak Rate Calculated at 3.4 Gpm,In Excess of Tech Spec.Caused by Low Breakway Torque Valves,Deteriorated Gasket & Eroded Manway Cover.All Defective Parts Repaired or Replaced
2CAN048308, Forwards List of Addl Procedures Controlling QA Measures for Threaded Fastener Lubricants to Minimize Fastener Susceptibility to Stress Corrosion Cracking
LR-N980601, Submits List of Fourteen Changes to Be Incorporated Into Salem,Unit 1 Inservice Insp Program as Rev 1B.Rev Deletes Requirement That Program Be Revised at End of Each Insp Period as Stated
L-84-340, Forwards Response to 840914 Request for Addl Info Re Inservice Insp Program.Drawings Undergoing General Rev for Incorporation of as-built Field Changes & Clarification
ET 07-0020, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion
NRC 2005-0002, Response to Request for Additional Information Regarding the Point Beach Nuclear Plant, Units 1 and 2, License Renewal Application
NL-04-0924, Application for License Renewal Errata and Responses to Follow-up Questions
NL-04-0800, Application for License Renewal - Request for Additional Information Response
L-2002-157, Response to NRC Request for Additional Information for Review of the License Renewal Application
L-2002-159, Response to NRC Request for Additional Information for Review of the License Renewal Application
NL-04-0473, Application for License Renewal - Requests for Additional Information (Rais)
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative