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| | {{#Wiki_filter:Timothy S. Rausch Senior Vice President |
| | & Chief Nuclear Officer FEB 2 2 2013 U.S. Nuclear Regulatory Commission Attention: |
| | Document Control Desk Washington, DC 20555-0001 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, P A 18603 Tel. 570.542.3345 Fax 570.542.1504 tsrausch @pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO FOLLOW-UP LETTER ON TECHNICAL ISSUES FOR RESOLUTION REGARDING LICENSEES COMMUNICATION SUBMITTALS Docket Nos. 50-387 and 50-388 PLA-6978 |
| | |
| | ==References:== |
| | : 1. 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. 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. ME7951)," dated January 23, 2013. 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 Document Control Desk PLA-6978 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 careful 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) eight 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. 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 proprietary, confidential, and Security sensitive material 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. Document Control Desk PLA-6978 I declare under penalty of perjury that the foregoing is true and correct. Executed on 7-('2..-z-I IS '2013. 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-Withhold from Public Disclosure in Accordance with 10 CFR 2.390 2. List of Regulatory Commitments |
| | : 3. Affidavit Copy: Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PADEP/BRP Region I Administrator, NRC Enclosure 2 to PLA-6978 List of Regulatory Commitments Enclosure 2 to PLA-6978 List of Regulatory Commitments Item Description Due Date Tracking # 1 SSES will revise EP-RM -008, 06/28/2013 1671371 "Emergency Telephone Directory" to include satellite phone usage instructions. |
| | 2 NDAP-QA-0777, "PPL Susquehanna 05/24/2013 1499071 Emergency Preparedness Program" will be revised to include the "self-activation" expectation and guidance that SSES' NERO personnel have already been trained on. |
| | Enclosure 3 to PLA -6978 Affidavit AFFIDAVIT OF TIMOTHY S. RAUSCH I, Timothy S. Rausch, Senior Vice President and Chief Nuclear Officer, PPL Susquehanna, LLC, do hereby affirm and state: 1. I am authorized to execute this affidavit on behalf of PPL Susquehanna, LLC (hereinafter referred to as .. PPL .. ). 2. PPL requests that the document enclosed hereto ("Enclosure 1 11) be withheld from public disclosure under the provisions of 10 C.F.R. 2.390(a)(4) and 2.390(d)(1 |
| | ). 3. The PPL Document contains confidential commercial information, the disclosure of which would adversely affect PPL. 4. This information has been held in confidence by PPL. To the extent that PPL has shared this information with others, it has done so on a confidential basis. 5. PPL customarily keeps such information in confidence and there is a rational basis for holding such information in confidence. |
| | The information is not available from public sources and could not be gathered readily from other publicly available information. |
| | : 6. Public disclosure of this information would cause substantial harm to the competitive position of PPL, because such information has significant commercial value to PPL. 7. PPL requests that the information identified in paragraph (2) above be classified as proprietary commercial information because it details results of an assessment performed to assess PPL's communications capabilities during an extended loss of AC power. The results and the conditions under which it was collected constitutes a major PPL asset. 8. This information is of a type that is held in confidence by PPL, and there is a rational basis for doing so because the information contains sensitive commercial information concerning the physical protection of PPL*s facility. |
| | 1 Commonwealth of Pennsylvania County of ) Subscribed and sworn before me, a Notary Public in and for the Commonwealth of Pennsylvania This J.. 1.. day of , 2013 NOTARIAL SEAL JACQUELINE M. JACOB Notary Public ALLENTOWN. |
| | CITY, LEHIGH COUNTY My Commilllon Expires Mar 20, 2016 PPL SUSQUEHANNA, LLC 2}} |
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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
MONTHYEARIR 05000387/20245012024-11-13013 November 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2024501 and 05000388/2024501 IR 05000387/20240102024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000387/2024010 and 05000388/2024010 IR 05000387/20240032024-11-12012 November 2024 Integrated Inspection Report 05000387/2024003 and 05000388/2024003 PLA-8135, Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-81352024-11-0101 November 2024 Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135 ML24289A1252024-10-22022 October 2024 – Authorized Alternative to Requirements of the ASME OM Code PLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-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-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, 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 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 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 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) 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) 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage 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 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-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 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes 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) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8098, Annual Financial Report (PLA-8098)2024-04-0101 April 2024 Annual Financial Report (PLA-8098) 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 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-0909 January 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 2024-09-06
[Table view] Category:Legal-Affidavit
MONTHYEARPLA-8015, Application for Order Approving Indirect Transfer of Control of Licenses2022-09-29029 September 2022 Application for Order Approving Indirect Transfer of Control of Licenses ML20248H4702020-08-19019 August 2020 Submittal of Annual Financial Information Required by 10 CFR 50.71 PLA-7861, Submittal of Unit 2 Cycle 21 Reload Licensing Documents to Support License Amendment Requesting Application of Advanced Framatome Methodologies (PLA-7861)2020-04-0909 April 2020 Submittal of Unit 2 Cycle 21 Reload Licensing Documents to Support License Amendment Requesting Application of Advanced Framatome Methodologies (PLA-7861) PLA-7847, Submittal of Revised Topical Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies2020-03-0909 March 2020 Submittal of Revised Topical Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7841, Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies2020-02-0606 February 2020 Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7585, Annual Financial Information for the Years Ended December 31, 2105 and 20162017-04-13013 April 2017 Annual Financial Information for the Years Ended December 31, 2105 and 2016 PLA-7500, Affidavit of Timothy S. Rausch2016-06-29029 June 2016 Affidavit of Timothy S. Rausch PLA-7274, Response to Second Request for Additional Information Regarding Application for Approval of Indirect Transfer of Control PLA-72742015-01-0505 January 2015 Response to Second Request for Additional Information Regarding Application for Approval of Indirect Transfer of Control PLA-7274 ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow ML13057A5932013-02-22022 February 2013 Response to Follow-up Letter on Technical Issues for Resolution Regarding Licenses Communication Submittals ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML0808605052008-03-20020 March 2008 MD8079 - Susquehanna 1 and 2 - Meeting on March 18, 2008, Affidavit for Proprietary Presentation Material PLA-6236, Proposed License Amendments No. 285 & 253 for Units 1 & 2, Respectively Re Extended Power Uprate Application Supplement to Instrumentation and Controls & Balance-of-Plant Safety System2007-07-13013 July 2007 Proposed License Amendments No. 285 & 253 for Units 1 & 2, Respectively Re Extended Power Uprate Application Supplement to Instrumentation and Controls & Balance-of-Plant Safety System PLA-6203, Proposed License Amendment Extended Power Uprate Application Containment and Ventilation Technical Review Request for Additional Information Responses, PLA-62032007-06-0404 June 2007 Proposed License Amendment Extended Power Uprate Application Containment and Ventilation Technical Review Request for Additional Information Responses, PLA-6203 ML0629001612006-10-11011 October 2006 Supplemental Environmental Report for Extended Power Uprate. ML0629001622006-10-11011 October 2006 Extended Power Uprate Steam Dryer Evaluation. PLA-5979, Decommissioning Report of Financial Assurance, Supplemental Information2005-11-0707 November 2005 Decommissioning Report of Financial Assurance, Supplemental Information ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference PLA-5920, Transmittal of Susquehanna - Guarantee of Payment of Deferred Premiums - 10 CFR 140.212005-06-28028 June 2005 Transmittal of Susquehanna - Guarantee of Payment of Deferred Premiums - 10 CFR 140.21 ML19186A1231979-01-17017 January 1979 Amended Petition for Leave to Intervene ML18023A7421978-09-18018 September 1978 Letter Attaching an Affidavit of Service for Amendment No. 2 to Ses Operating License Application Containing Revision No. 2 to the Final Safety Analysis Report ML18024A1451978-09-18018 September 1978 Letter Enclosing an Affidavit of Service for Amendment No. 2 of Operating License Application ML19184A5341978-07-20020 July 1978 Affidavit of Service: Environmental Report - Operating License Stage 2022-09-29
[Table view] |
Text
Timothy S. Rausch Senior Vice President
& Chief Nuclear Officer FEB 2 2 2013 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, P A 18603 Tel. 570.542.3345 Fax 570.542.1504 tsrausch @pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO FOLLOW-UP LETTER ON TECHNICAL ISSUES FOR RESOLUTION REGARDING LICENSEES COMMUNICATION SUBMITTALS Docket Nos. 50-387 and 50-388 PLA-6978
References:
- 1. 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. 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. ME7951)," dated January 23, 2013. 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 Document Control Desk PLA-6978 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 careful 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) eight 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. 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 proprietary, confidential, and Security sensitive material 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. Document Control Desk PLA-6978 I declare under penalty of perjury that the foregoing is true and correct. Executed on 7-('2..-z-I IS '2013. 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-Withhold from Public Disclosure in Accordance with 10 CFR 2.390 2. List of Regulatory Commitments
- 3. Affidavit Copy: Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PADEP/BRP Region I Administrator, NRC Enclosure 2 to PLA-6978 List of Regulatory Commitments Enclosure 2 to PLA-6978 List of Regulatory Commitments Item Description Due Date Tracking # 1 SSES will revise EP-RM -008, 06/28/2013 1671371 "Emergency Telephone Directory" to include satellite phone usage instructions.
2 NDAP-QA-0777, "PPL Susquehanna 05/24/2013 1499071 Emergency Preparedness Program" will be revised to include the "self-activation" expectation and guidance that SSES' NERO personnel have already been trained on.
Enclosure 3 to PLA -6978 Affidavit AFFIDAVIT OF TIMOTHY S. RAUSCH I, Timothy S. Rausch, Senior Vice President and Chief Nuclear Officer, PPL Susquehanna, LLC, do hereby affirm and state: 1. I am authorized to execute this affidavit on behalf of PPL Susquehanna, LLC (hereinafter referred to as .. PPL .. ). 2. PPL requests that the document enclosed hereto ("Enclosure 1 11) be withheld from public disclosure under the provisions of 10 C.F.R. 2.390(a)(4) and 2.390(d)(1
). 3. The PPL Document contains confidential commercial information, the disclosure of which would adversely affect PPL. 4. This information has been held in confidence by PPL. To the extent that PPL has shared this information with others, it has done so on a confidential basis. 5. PPL customarily keeps such information in confidence and there is a rational basis for holding such information in confidence.
The information is not available from public sources and could not be gathered readily from other publicly available information.
- 6. Public disclosure of this information would cause substantial harm to the competitive position of PPL, because such information has significant commercial value to PPL. 7. PPL requests that the information identified in paragraph (2) above be classified as proprietary commercial information because it details results of an assessment performed to assess PPL's communications capabilities during an extended loss of AC power. The results and the conditions under which it was collected constitutes a major PPL asset. 8. This information is of a type that is held in confidence by PPL, and there is a rational basis for doing so because the information contains sensitive commercial information concerning the physical protection of PPL*s facility.
1 Commonwealth of Pennsylvania County of ) Subscribed and sworn before me, a Notary Public in and for the Commonwealth of Pennsylvania This J.. 1.. day of , 2013 NOTARIAL SEAL JACQUELINE M. JACOB Notary Public ALLENTOWN.
CITY, LEHIGH COUNTY My Commilllon Expires Mar 20, 2016 PPL SUSQUEHANNA, LLC 2