Letter Sequence Other |
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Results
Other: GNRO-2013/00014, Entergy'S Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3, GNRO-2016/00010, Entergy Update to Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3, ML13057A116, ML13058A066, ML13127A146, NLS2013028, Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3, PLA-7034, Response to Follow-Up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals
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MONTHYEARNOC-AE-12002867, Revised 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-06-0404 June 2012 Revised 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI NOC-AE-12002859, Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-06-0404 June 2012 Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident Project stage: Response to RAI GNRO-2012/00052, Entergy'S 90-Day Response to the March 12, 2012, Information Request, Action Plan for Completing Emergency Communication and Staffing Assessments2012-06-0808 June 2012 Entergy'S 90-Day Response to the March 12, 2012, Information Request, Action Plan for Completing Emergency Communication and Staffing Assessments Project stage: Request ML12311A0282012-10-31031 October 2012 Emergency Preparedness Information Requested by NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1,... Project stage: Request NOC-AE-13002958, STPNOC Response to January 23, 2013, Request for Additional Information Related to the Near-Term Task Force Recommendation 9.3 on Communications2013-02-21021 February 2013 STPNOC Response to January 23, 2013, Request for Additional Information Related to the Near-Term Task Force Recommendation 9.3 on Communications Project stage: Request NLS2013028, Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.32013-02-21021 February 2013 Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3 Project stage: Other GNRO-2013/00014, Entergy'S Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.32013-02-21021 February 2013 Entergy'S Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3 Project stage: Other ML13057A1162013-02-22022 February 2013 Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3 Project stage: Other ML13058A0662013-02-22022 February 2013 Response to NRC Follow-up Letter on Technical Issues for Resolution Regarding Licensee Communication Associated with Near-Term Task Force Recommendation 9.3 Project stage: Other ML13057A5932013-02-22022 February 2013 Response to Follow-up Letter on Technical Issues for Resolution Regarding Licenses Communication Submittals Project stage: Request L-13-047, Supplement to Response to NRC Letter, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-02-22022 February 2013 Supplement to Response to NRC Letter, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Supplement ML13127A1462013-05-0606 May 2013 Email Table 2 Response Question Project stage: Other PLA-6978, Response to Follow-Up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals2013-06-0303 June 2013 Response to Follow-Up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals Project stage: Request PLA-7034, Response to Follow-Up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals2013-06-28028 June 2013 Response to Follow-Up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals Project stage: Other GNRO-2016/00010, Entergy Update to Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.32016-08-24024 August 2016 Entergy Update to Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3 Project stage: Other 2013-02-22
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Category:Letter
MONTHYEARPLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8123, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) ML24092A4022024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8088, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088)2023-12-0505 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088) PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 2024-09-06
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\ I I Timothy S. Rausch Senior Vice President
& Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3345 Fax 570.542.1504 tsrausch @pplweb.com \ ' I I I ' t If # , *****l *' . . *' JUN 2 8 2 0t U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington , DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO FOLLOW-UP LETTER ON TECHNICAL ISSUES FOR RESOLUTION REGARDING LICENSEES COMMUNICATION SUBMITTALS PLA-7034 Docket Nos. 50-387 and 50-388
References:
- 1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," dated March 12, 2012. 2. PLA-6852, "60-Day Response to NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(!) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, dated March 12 , 2012," dated May 11, 2012. 3. PLA-6866, "Emergency Preparedness Information Requested by NRC Letter ," dated June 11, 2012. 4. PLA-6927, "Requested Communications Assessment Results and Implementation Schedule per References 1 and 2," dated October 31, 2012. 5. NRC Letter, "Follow-Up Letter on Technical Issues for Resolution Regarding Licensee Communication Submittals associated with Near-Term Task Force Recommendation 9.3 (TAC NO. M£7951)," dated January 23, 2013. 6. PLA-6978, "Response to Follow-up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals , dated February 22 , 2013." (ML13057 A593) 7. PLA-6978 , "Response to Follow-up Letter on Technical Issues for Resolution Regarding Licensees Communication Submittals, dated June 3, 2013." (ML13156A058)
The purpose of this letter is to supersede References 6 (PLA-6978, dated February 22, 2013, ML13057A593) and 7 (PLA-6978, dated June 3, 2013, ML13156A058) in their entirety.
Per discussions with our NRC Project Manager , Enclosure 1 to Reference 6 was incorrectly marked as being withheld from public disclosure due to proprietary information.
The Enclosure should have been marked to be withheld from public disclosure due to security information.
Reference 7 was generated to correct the reason for withholding the information from public disclosure; however, an ' TM Document Control Desk PLA-7034 incorrect version of Enclosure 1 was submitted.
Except for the deletion of any reference to an affidavit and the correction to the request to withhold the information in Enclosure 1, the information in this letter is identical to that submitted in Reference
- 6. In addition, the following commitment has been completed since Reference 6 was issued: "SSES will revise EP-RM-008, "Emergency Telephone to include satellite phone usage instructions." On March 12, 2012, the Nuclear Regulatory Commission (NRC) staff issued a letter entitled "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," (Reference 1). Enclosure 5 of Reference 1 contains specific Requested Actions and Requested Information associated with Recommendation 9.3 for Emergency Preparedness (EP) programs.
In accordance with 10 CFR 50.54, "Conditions of licenses," paragraph (f), addressees were requested to submit a written response to the information request within 90 days from the date of letter. Reference 1 also states that if an addressee cannot meet the requested response date, the addressee must provide a response within 60 days of the date of the letter and describe the alternative course of action that it proposes to take, including the basis of the acceptability of the proposed alternative course of action and estimated completion date. After a carefqJ review of the requested actions and information, PPL Susquehanna, LLC (PPL) opted to take an alternative course of action as described in Enclosure 1 of Reference
- 2. The basis for PPL's alternative course of action was documented in Enclosure 2 of Reference
- 2. This alternative course of action was based on the industry standard guidance developed with the Nuclear Energy Institute (NEI). Reference 4 provided PPL's Communications Assessment Results and Implementation Schedule for planned changes. Enclosure 1 to Reference 3 contains the results of the Communications Assessment in the format presented in NEI 12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities." Enclosure 2 of Reference 4 contains a list of regulatory commitments regarding the changes PPL planned to make as a result of the Communications Assessment.
In Reference 5, the NRC identified eight (8) generic technical issues needing resolution to determine the licensee's communications capability regarding a multi-unit station blackout event. The NRC requested a response be provided within 30 days from the date of the letter. The purpose of this letter and associated Enclosure 1 is to provide PPL' s response to Reference
- 5. PPL's response in Enclosure 1 is in a tabular format with three columns. The table presents the NRC's Generic Technical Issues in the left hand column. Document Control Desk PLA-7034 Information from PPL's Communications Assessment submittal (Reference
- 4) is presented in the center column. The right hand column provides additional information to fully respond to the NRC's Generic Technical Issues and augments PPL's original response (Reference 4). PPL requests that Enclosure 1 to this letter be withheld from public disclosure.
The information represents Security-Related information as defined by 10 CPR 2.390. Enclosure 2 to this letter contains a list of new regulatory commitments.
If you have any questions regarding the information contained in this letter, please contact Mr. John L. Tripoli, Manager, Nuclear Regulatory Affairs, at (570) 542-3100.
I declare under penalty of perjury that the foregoing is true and correct. Executed on: Senior Vice President
& Chief Nuclear Officer
Enclosures:
- 1. PPL' s Response to the NRC's 8 Generic Technical Issues for RFI 9.3 Communications Assessment
-Security-Related Information
-Withhold in Accordance with 10 CPR 2.390 2. List of Regulatory Commitments Copy: Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP Region I Administrator, NRC Enclosure 2 to PLA -7034 List of Regulatory Commitments Enclosure 2 to PLA-7034 List of Regulatory Commitments Item Description Due Date Tracking # 1 SSES will revise EP-RM-008, Complete 1671371 "Emergency Telephone Directory" to include satellite phone usage instructions.
2 NDAP-QA-0777, "PPL Susquehanna Complete 1499071 Emergency Preparedness Program" will be revised to include the "self-activation" expectation and guidance that SSES' NERO personnel have already been trained on.