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Line 29: |
Line 29: |
| The Enclosure should have been marked to be withheld from public disclosure due to security 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. | | 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 | | 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. | | : 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 | | 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. 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. | | : 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 | | 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 | | : 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. | | : 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. | | 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. |
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 type:PLA
MONTHYEARPLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) 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) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) 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-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-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 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-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 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) 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) PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan 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 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) PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8039, Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information2022-12-22022 December 2022 Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information PLA-8038, Notification of Petition for Bankruptcy (PLA-8038)2022-12-14014 December 2022 Notification of Petition for Bankruptcy (PLA-8038) PLA-8036, Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-80362022-11-30030 November 2022 Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-8036 PLA-8035, Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-80352022-11-0808 November 2022 Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-8035 PLA-8031, Emergency Plan Revision 66 (PLA-8031)2022-11-0707 November 2022 Emergency Plan Revision 66 (PLA-8031) PLA-8032, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032)2022-10-28028 October 2022 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032) PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-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 PLA-8030, Evacuation Time Estimate Report PLA-80302022-09-15015 September 2022 Evacuation Time Estimate Report PLA-8030 2024-07-23
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Text
\ 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.