Letter Sequence Approval |
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MONTHYEARML0209903052002-04-0909 April 2002
Request for Additional Information, Proposed Use of the New Design Mechanical Nozzle Seal Assembly (MNSA-2)
Project stage: RAI
CNRO-2002-00023, Response to NRC Request for Additional Regarding Proposed Use of the New Mechanical Nozzle Seal Assembly (MNSA-2)2002-04-11011 April 2002
Response to NRC Request for Additional Regarding Proposed Use of the New Mechanical Nozzle Seal Assembly (MNSA-2)
Project stage: Request
ML0218406752002-07-0303 July 2002
Relief, Mechanical Nozzle Seal Assembly
Project stage: Other
ML0220508222002-07-22022 July 2002
Correction to Authorization of Relief Request Request for Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Concerning Authorization to Use New Design Of..
Project stage: Approval
CNRO-2004-00010, Arkansas, Unit 1 - Pre-Application Review, ASME Request for Alternative ANO1-R&R-007, Use of Mechanical Nozzle Seal Assemblies on Reactor Vessel Bottom Mounted Instrumentation Nozzles2004-02-0505 February 2004
Arkansas, Unit 1 - Pre-Application Review, ASME Request for Alternative ANO1-R&R-007, Use of Mechanical Nozzle Seal Assemblies on Reactor Vessel Bottom Mounted Instrumentation Nozzles
Project stage: Request
CNRO-2004-00016, Request for Alternative ANO2-R&R-002, Rev. 1 - Use of Mechanical Nozzle Seal Assemblies2004-03-11011 March 2004
Request for Alternative ANO2-R&R-002, Rev. 1 - Use of Mechanical Nozzle Seal Assemblies
Project stage: Request
2002-07-22
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Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024
Comprehensive Engineering Team Inspection Report 05000382/2023010
IR 05000382/20230032024-01-23023 January 2024
Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003
ML24012A1962024-01-12012 January 2024
Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and
ML23340A2292023-12-28028 December 2023
Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR
ML23349A1672023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
ML23333A1362023-11-29029 November 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23325A1442023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23312A1832023-11-14014 November 2023
Integrated Inspection Report 05000382/2023003 and Notice of Violation
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
IR 05000382/20234012023-10-0404 October 2023
Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only)
IR 05000382/20230052023-08-21021 August 2023
Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005)
IR 05000382/20233012023-08-15015 August 2023
NRC Initial Operator Licensing Examination Approval 05000382/2023301
IR 05000382/20230022023-08-0808 August 2023
Integrated Inspection Report 05000382/2023002
IR 05000382/20234022023-08-0707 August 2023
NRC Security Inspection Report 05000382/2023402 (Full Report)
IR 05000382/20230402023-07-12012 July 2023
Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter
ML23191A4562023-07-10010 July 2023
Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information
ML23158A1042023-06-0808 June 2023
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401
ML23145A2272023-06-0202 June 2023
95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion
ML23130A2732023-05-10010 May 2023
and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
IR 05000382/20230012023-04-24024 April 2023
Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion
ML23111A2132023-04-21021 April 2023
Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities
ML23110A1122023-04-20020 April 2023
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
ML23108A2542023-04-18018 April 2023
WCGS Information Request, Security IR 2023401
IR 05000382/20234032023-04-17017 April 2023
Security Baseline Inspection Report 05000382/2023403
ML23093A2122023-04-0303 April 2023
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022
ML23089A0602023-03-30030 March 2023
Entergy Operations, Inc. - Fleet Project Manager Assignment
ML23088A3922023-03-29029 March 2023
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
ML23080A2882023-03-21021 March 2023
Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc
ML23059A2592023-03-0707 March 2023
Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23065A2002023-03-0303 March 2023
EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors
ML23060A1092023-03-0101 March 2023
Proof of Financial Protection (10 CFR 140.15)
IR 05000382/20220062023-03-0101 March 2023
Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006)
ML22322A1092023-02-17017 February 2023
Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
IR 05000382/20230902023-02-0101 February 2023
Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090
ML23032A5062023-02-0101 February 2023
Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022
ML23030A6642023-01-27027 January 2023
Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors
IR 05000382/20220042023-01-26026 January 2023
Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001
ML23024A0822023-01-20020 January 2023
Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection
ML23018A2202023-01-18018 January 2023
Quality Assurance Program Manual Reduction in Commitment
IR 05000382/20220912023-01-12012 January 2023
Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation
IR 05000382/20220032023-01-0505 January 2023
Revised Integrated Inspection Report 05000382/2022003
ML22342B1402022-12-0202 December 2022
56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors
ML22300A2082022-11-30030 November 2022
Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22332A5292022-11-29029 November 2022
Notification of NRC Initial Operator Licensing Examination 05000382/2023301
IR 05000382/20220132022-11-28028 November 2022
Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013
IR 05000382/20220022022-11-0101 November 2022
Revised Integrated Inspection Report 05000382/2022002
2024-01-31
[Table view] |
Text
July 22, 2002 Mr. Michael Krupa Director, Nuclear and Safety Engineering Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8293
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO AUTHORIZATION OF RELIEF REQUEST RE: REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) BOILER AND PRESSURE VESSEL CODE (CODE)
CONCERNING AUTHORIZATION TO USE NEW DESIGN OF MECHANICAL NOZZLE SEAL ASSEMBLY (MNSA) (TAC NO. MB4272)
Dear Mr. Krupa:
By letter dated March 1, 2002, as supplemented by letters dated March 6, March 29, April 11, and May 1, 2002, Entergy Operations, Inc. (Entergy), requested relief from ASME Code,Section XI, requirements for IWA-4170 required repairs. Entergy requested Nuclear Regulatory Commission (NRC) staff approval to use the new design of the MNSA in temporary applications on locations in the reactor coolant system that exhibit leakage due to primary water stress corrosion cracking at Waterford Steam Electric Station, Unit 3.
The staff evaluated the information provided in the submittal and determined that the proposed alternative would provide an acceptable level of quality and safety for the requested two cycles.
Therefore, by letter dated July 3, 2002, NRC authorized Entergys proposed alternative pursuant to 10 CFR 50.55a(a)(3)(i). A copy of our related Safety Evaluation (SE) was also enclosed.
Errors were discovered on page 2 of the cover letter and page 8 of the SE (Section 4.0, "CONCLUSION"). Revised sheets of these two pages are enclosed with the corrections identified by a marginal vertical bar. Please replace page 2 of the cover letter and page 8 of the SE of the previous submittal with the enclosed, revised sheets.
Mr. M. Krupa Please call N. Kalyanam, at (301) 415-1480, with any questions you may have.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Page 2 of the cover letter, Page 8 of the SE cc w/encls: See next page
M. Krupa Please call N. Kalyanam, at (301) 415-1480, with any questions you may have.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Page 2 of the cover letter, Page 8 of the SE cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsOgcRp PDIV-1 Reading RidsAcrsAcnwMailCenter RidsNrrDlpmLpdiv (WRuland) GHill (2)
RidsNrrDlpmLpdiv1 (RGramm) TBloomer/SCoffin MHartzman/KManoly RidsNrrPMNKalyanam SMorris, R.V. Plants (SAM1) RidsNrrLADJohnson RidsRgn4MailCenter (KBrockman) LHurley Accession No.: ML02 OFFICE PDIV-1/PM PDIV-1/LA PDIV-1/SC NAME NKalyanam DJohnson RGramm DATE 07/15/02 07/15/02 07/22 /02 OFFICIAL RECORD COPY
Mr. M. Krupa for additional clarifying information from Waterford 3, if the relief request was intended for a period exceeding two operating cycles. These aspects, however, are less significant when the use of the MNSA-2s is limited to two operating cycles. The staff did not review the design stress reports with respect to use of the MNSAs beyond a time period of two operating cycles.
Therefore, if an application for extended operation, i.e., beyond the approved two operating cycles, is submitted, the staff will need to evaluate all current and any new data, including stress and fatigue calculations, that may pertain to long-term usage before approval is granted for extended operation.
This authorization is valid for two operating cycles of the current inspection interval, which ends in June 30, 2007.
The staffs safety evaluation is enclosed.
Sincerely,
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Safety Evaluation cc: w/encl: See next page
(2) Entergy has used minimum wall thickness in its reinforcement calculations to assure that the pressurizer shell thickness is adequate.
(3) Entergy will evaluate the area surrounding the leaking nozzles or heater sleeves during the counterbore machining process to verify that no significant degradation of the pressurizer wall annulus region has occurred.
(4) If the MNSA-2 device leaks, the bolts may be exposed to borated water or steam under conditions in which deposits or slurries develop. Under these conditions and at stress levels present in the MNSA-2 application, the bolts will operate satisfactorily for at least one fuel cycle. Should a leaking MNSA-2 be discovered, it shall be repaired/replaced as part of the walkdown inspections performed in response to Generic Letter 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants." These walkdown inspections are performed prior to entering unit outages.
Therefore, the existence of leaking MNSA conditions would be limited to one cycle.
(5) As required by IWA-4820, a VT-1 preservice inspection will be performed on all MNSA-2 installations in accordance with IWB-2200.
(6) During plant startup (Mode 3) after initial MNSA-2 installation and during subsequent plant restarts following scheduled outages, the MNSA-2 will be pressure tested and inspected for leakage. To ensure quality of installation and continued operation with the absence of leakage, a pressure test with visual inspection will be performed on each of the installed MNSA-2s with any insulation removed. The test will be performed as part of plant restart and will be conducted at normal operating pressure, with the test temperature determined in accordance with the Waterford 3 P-T Limits, as stated in the Waterford 3 Technical Specifications. Additionally, VT-2 examination of the external edge of the counterbore region will be performed to verify no leakage is present that would not be detected by the leakoff nozzle.
The NRC staff has reviewed the proposed licensee actions and limitations noted above, and concludes that they are sufficient to assure proper installation and operation of the MNSA-2 for their intended use and duration.
4.0 CONCLUSION
The NRC staff concludes that, pursuant to 10 CFR 50.55a(a)(3)(i), the use of MNSA-2s as an alternative to an ASME Code Section XI repair on any leaking nozzles or heater sleeves of the type described above, may be authorized for a period not to exceed two operating cycles, since it is found to provide an acceptable level of quality and safety. This authorization is valid for two operating cycles of the current ISI interval applicable for Waterford 3, which ends on June 30, 2007.
Principle Contributors: T. Bloomer, M. Hartzman Date: July 3, 2002
Waterford Generating Station 3 cc:
Mr. Michael E. Henry, Administrator Regional Administrator, Region IV and State Liaison Officer U. S. Nuclear Regulatory Commission Department of Environmental Quality 611 Ryan Plaza Drive, Suite 1000 P. O. Box 82135 Arlington, TX 76011 Baton Rouge, LA 70884-2135 Parish President Council Vice President, Operations Support St. Charles Parish Entergy Operations, Inc. P. O. Box 302 P. O. Box 31995 Hahnville, LA 70057 Jackson, MS 39286-1995 Executive Vice President Director & Chief Operating Officer Nuclear Safety Assurance Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 17265 River Road Jackson, MS 39286-1995 Killona, LA 70066-0751 Chairman Wise, Carter, Child & Caraway Louisiana Public Services Commission P. O. Box 651 P.O. Box 91154 Jackson, MS 39205 Baton Rouge, LA 70825-1697 General Manager Plant Operations Mr. Joseph E. Venable Waterford 3 SES Vice President Operations Entergy Operations, Inc. Entergy Operations, Inc.
17265 River Road 17265 River Road Killona, LA 70066-0751 Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Resident Inspector/Waterford NPS P. O. Box 822 Killona, LA 70066-0751 January 2002
