Letter Sequence Request |
---|
|
|
MONTHYEARJAFP-05-0151, Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection2005-10-0707 October 2005 Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection Project stage: Request ML0603907362006-02-0909 February 2006 Request for Additional Information Regarding Relief Request RR-39, Implementation of BWRVIP Guidelines Project stage: RAI JAFP-06-0059, Response to Request for Additional Information, Regarding Request for Approval of Relief Request No. 39, Section XI Code2006-04-0303 April 2006 Response to Request for Additional Information, Regarding Request for Approval of Relief Request No. 39, Section XI Code Project stage: Response to RAI JAFP-06-0085, Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspect2006-05-31031 May 2006 Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection Project stage: Request ML0622002262006-08-30030 August 2006 Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection Project stage: Other 2006-04-03
[Table View] |
|
---|
Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
[Table view] |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP 7 --Entergy P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 JAFP-06-0085 May 31, 2006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-000 1
SUBJECT:
Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Revision to Response to Request for Additional Information (RAI) Reearding Request for Approval of Relief Request No.
39, Implementation of BWRVIiP Guidelines in lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection (TAC No. MC 8587)
REFERENCES:
- 1. Telecom dated May 11, 2006 between NRC Staff and JAF Regarding Clarification on Use of BWvRVIP Guidelines.
- 2. Entergy Nuclear Operations, Inc. letter to USNRC (JAFP-06-0059), Response to RAI Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection (TAC No. MC 8587) dated April 3, 2006.
- 3. USNRC letter to Entergy Nuclear Operations, Inc., Request for Additional Information (RAI) Regarding Relief Request RR-39, Implementation of BWRVIP Guidelines, (TAC No.
MC8587) dated February 9, 2006.
- 4. Entergy Nuclear Operations, Inc. letter to USNRC (JAFP-05 -015 1), Request for Approval of Relief Request No. 39, dated October 7, 2005.
Dear Sir:
On May 11, 2006, a telecom (Reference 1) was held with your Staff to discuss Entergy Nuclear Operation, Inc.'s response (Reference 2) to an NRC Request for Additional Information (RAI) (Reference 3).
404-7
This letter contains the revised information as discussed in the May 11, 2006 telecom.
This response does not change the conclusions in the original Relief Request (Reference 4). However, the scope of the original Relief Request has been revised to no longer include BWVRVIP-25, "B WRVIP Core Plate Inspection and Flaw Evaluation Guidelines" as a proposed alternative inspection program for the Core Plate Rim Hold-Down Bolts.
There are no commitments contained in this letter.
Sincerely, _ __
Regulatory Compliance Manager JC:GB:gb
Attachment:
Revised Reactor Vessel Internals Inspection Five (5) Cycle Look-Ahead cc:
Regional Administrator, Region 1 Resident Inspector's Office U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission 475 Allendale Road James A. FitzPatrick Nuclear Power Plant King of Prussia, PA 19406-1415 P0 Box 136 Lycoming, NY 13093 Mr. John Boska, Project Manager Plant Licensing Branch I-1 Mr. Paul Eddy Division of Operating Reactor Licensing New York State Dept. of Public Service Office of Nuclear Reactor'Regulation 3 Empire State Plaza U. S. Nuclear Regulatory Commission Albany,ý NY 12223-1350 Mail Stop O-8-C2 Washington, DC 20555 Mr. Peter R. Smith, President New York State Energy, Research,
& Development Authority 17 Columbia Circle Albany, NY 12203-6399
Attachment 1 to JAFP-06-0085 Entergy Nuclear Operations, Inc. - FitzPatrick Docket No. 50-333 Reactor Vessel Internals Inspection Five (5) Cycle Look-Ahead Reactor Internal Comp onent Inspection Bowes R07 2006 R018O 12008)L R020(0 1 L2) O~L Control Rod Drive Guide Tube Body Welds BWRVIP-47-A, Table 3-3 EVT-l EVT-l(In) _____ EVT-I Control Rod Drive Guide Tube Lug and Pin BWRVIP-47-A, Table 3-3 VT-3 VT-3(!n) _____ VT-3 Core Plate Rim Hold-Down Bolts (OTE 1)___________
Core Shroud Vertical & Bing Segent Welds BWRVIP-76, Figure 3-3 & 3-4 EVT-l/UT EVT-1(IN) EVT-l(N EVT-l EVT-l Core Shroud Tie-Rod Repair BWRVIP-76, Section 3.5 VT-3/EVT-l(10) VT-3/EVT-1(6) ______
Core Shroud Supprt Welds (H9) (OTE 3) BWRVIP-38, Figure 3-5 EVT-l EVT-l _____ EVT-1 Core Shroud Gusset Welds BWRVIP-38, Figure 3-2 and EVT-l EVT-l EVT-l BWRVIP-76,_Section 3.6 _____ ______
Core Spray Thermal Sleeve Welds (idden) (OTE 2) BWRVIP-1 8-A, Section 3.2.4 UT ()UT (IN) UTU UT (IN)
Core Spray Piping Welds BWRVIP-18-A, Table 3-5 EVT-1 -EVT-1 EVT-1 EVT-l EVT-1 Core Spray Sparer Lre Circ Welds BWRVIP-18-A, Table 3-5 EVT-1 EVT-l EVT-1 Core Spray Spaer Nozzle Welds BWRVIP-1 8-A, Table 3-5 ______ VT-I Ti(0)(50%) ______ Tl(0%)
Core Spa Piping Brackets BWRVIP-18-A, Table 3-5 EVT-l _____ EVT-l Core Spray Sparer Brackets BWRVIP-18-A, Table 3-5 VT-I _____ VT-I VT-i Feedwater Sparger Tee Welds NUREG 0619 _ ________ VT-i_____
Feedwater Sparer Bracket Attachment BWRVIP-48-A, Table 3-2 _ ________ EVT-l ________
Feedwater Sparer Assembly NUREG 0619 _ ___ ____ VT-3_____
Jet Pump Beams BWRVIP-41, Rev.l1, Table 3.3-1 and UT UT
/ ~~~BWRVIP-13S, Section 6.4 ____________ _____ ______
Jet Pump Thermal Sleeve Welds (idden) O 2) BWRVIP-41, Rev. 1, Table 3.3-1 _____ UT*M ~ UT(N T(N T(N Jet Pump Assembly (igh Priorit Welds) BWRVIP-41, Rev.l1, Table 3.3-1 UT/EVT-l ____________ EVT-1 (50%) ______
Jet Pump Assembly (Medium & Low Priorit Welds) BWRVIP-4 1, Rev.l1, Table 3.3-1 EVT-I ____ ____ EVT-l (25%0/) _ ___
Jet Pump Riser Brace Welds BWRVIP-4 1, Rev.l1, Table 3.3-1 EVT-l I____ ____ EVT-l (25%) _ ___
Jet Pump Restrainer Wedges BWRVEP-4 1, Rev.l1, Table 3.3-1 VT-I I____ ____ VT..l(50-%') ____
Lower Plenum BWRVIP-47-A, Section 3.2 _____WHNACCESSIBLE _____
Miscellaneous Vessel Internal Attachments BWRVIP-48-A, Table 3-2 VT-3 _________JVT..3/EVT-1 Orificed Fuel Supprt Castings (Sampling BWRVIP-47-A, Table 3.2-I VT-3 VT-3 VT-3 VT-3 VT-3 SLC Nozzle-to-Safe End Weld (OTE 2) BWRVIP-27-A, Section 3.3.1 PT or EVT-2* EVT-2* (IN) PT or EVT-2* EVT-2* (IN) PT or EVT-2*
Top Guide Hold-down Assemblies BWRVIP-26-A, Table 3-2 VT-l (2) ___ _ ___ VT-1 _(2) _______ V-(2 Top Guide Grid Beams (Sampting BWRVIP-26-A, Section 3.2.2 VT-31 VT-1 _____
NOTES: (1) Inspection performed per ASME Code Section XI requirements (this component is excluded from Relief Request No. 39).
(2) Inspection of these welds to be performed when UT technology is available in accordance with BWRVIP requirements of the applicable BWRVIP document.
(3) For clarification purposes only: H12 weld does not apply to the FitzPatrick Plant.
Page 1 of 2
Attachment 1 to JAFP-06-0085 Entergy Nuclear Operations, Inc. - FitzPatrick Docket No. 50-333 Reactor Vessel Internals Inspection Five (5) Cycle Look-Ahead Table Key Standard Print = Inspections mandated by BWRVIP I & E Guidelines Italics = Inspections recommended for Risk-To-Generation purposes UT = Ultrasonic Testing planned UT M* =Ultrasonic Testing when the technique becomes available VT-3/VT-1(*) = Contingency examination subject to lower plenum access VT = Visual Testing planned EVT-1 = EVT-1; Enhanced Visual Test to look for cracking; 1/2 mil wire resolution with cleaning assessment EVT-2* =Enhanced Leakage Inspection (direct view of component during pressure test)
VT-I =VT-i; Visual Test to look for cracks, wear, corrosion, etc.; resolution required: 1/32" black line VT-3 =VT-3; Visual Test to determine general mechanical/structural condition; no resolution requirements PT = Surface examination (IN) = If necessary, to complete number of inspections not performed in previous outage(s)
(all, number, or %/) = Perform inspection on all or on remainder components, limited number (or percentage) of components, or just flawed components Page 2 of 2