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| | number = ML12159A395 | | | number = ML12159A395 |
| | issue date = 06/08/2012 | | | issue date = 06/08/2012 |
| | title = County, Units 1 & 2, Limerick, Units 1 & 2, Oyster Creek, Peach Bottom, Units 2 & 3, Quad Cities, Units 1 & 2, Three Mile, Unit 1-Review of 60-Day Response To.. | | | title = Three Mile, Unit 1-Review of 60-Day Response To.. |
| | author name = Wiebe J S | | | author name = Wiebe J |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000219, 05000237, 05000249, 05000265, 05000277, 05000278, 05000289, 05000352, 05000353, 05000373, 05000374, 05000454, 05000455, 05000456, 05000457, 05000461 | | | docket = 05000219, 05000237, 05000249, 05000265, 05000277, 05000278, 05000289, 05000352, 05000353, 05000373, 05000374, 05000454, 05000455, 05000456, 05000457, 05000461 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 8, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO.1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2, AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 REVIEW OF 60-DAY RESPONSE TO REQUEST FOR INFORMATION REGARDING RECOMMENDATION 9.3, OF THE NEAR-TERM TASK FORCE RELATED TO THE FUKUSHIMA DAIICHI NUCLEAR POWER PLANT ACCIDENT (TAC NOS. ME8623, ME8624, ME8625, ME8626, ME8627, ME8628, ME8629, ME8630, ME8631, ME8632, ME8633, ME8634, ME8635, ME8636, ME8637, ME8638, AND ME8639) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 8, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
| | |
| | ==SUBJECT:== |
| | BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO.1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2, AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 REVIEW OF 60-DAY RESPONSE TO REQUEST FOR INFORMATION REGARDING RECOMMENDATION 9.3, OF THE NEAR-TERM TASK FORCE RELATED TO THE FUKUSHIMA DAIICHI NUCLEAR POWER PLANT ACCIDENT (TAC NOS. ME8623, ME8624, ME8625, ME8626, ME8627, ME8628, ME8629, ME8630, ME8631, ME8632, ME8633, ME8634, ME8635, ME8636, ME8637, ME8638, AND ME8639) |
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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f) which included the Near Term Task Force (NTTF) Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date. By letter dated May 10, 2012, Exelon Generation Company, LLC submitted its 60-day response proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. As discussed in the enclosed NRC staff evaluation, the licensee's alternative approach outlined in its 60-day response letter is consistent with the guidance of industry document Nuclear Energy Institute (NEI) 12-01, "Guidance for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities,,,1 and the direction of the Commission.
| |
| 1 NRC staff determined NEI 12-01 to be an acceptable approach in letter dated May 15, 2012 (ADAMS Accession No. ML12131A043).
| |
| -2 In addition, the NRC staff concludes that the licensee provided an adequate basis for its proposed alternative to responding to the 50.54(f) Request for Information regarding communications and staffing for NTTF Recommendation 9.3. If you have any questions, please contact me at 301-415-6606 or via e-mail at JoeI.Wiebe@nrc.gov. Joel S. Wiebe, Senior proieut Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455. 50-461, 50-237, 50-249,50-373,50-374,50-352, 50-353, 50-219, 50-277,50-278,50-254,50-265, and 50-289 Staff cc w/encl: Distribution via NUCLEAR REGULATORY COMMISSION STAFF EVALUATION INFORMATION REQUEST MADE UNDER 10 CFR 50.54(f) REGARDING NEAR-TERM TASK FORCE RECOMMENDATION
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| ===9.3 EXELON===
| | By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f) which included the Near Term Task Force (NTTF) Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date. |
| GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNITS 1 AND 2; CLINTON POWER STATION, UNIT 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461,50-237,50-249, 50-373,50-374,50-352,50-353,50-219,50-277, 50-278; 50-254, 50-265, AND 50-289 By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12073A348), the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.54{f) which included the Near-Term Task Force (NTTF) Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date. By letter dated May 3,2012 (ADAMS Accession No. ML 12125A410), the Nuclear Energy Institute (NEI) submitted NEI12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities," Revision 0, May 2012. The NRC staff reviewed NEI 12-01 and found it to be an acceptable method for licensees to use when responding to the NRC's 10 CFR 50.54{f) Request for Information regarding communications and staffing for EP. This staff evaluation is focused specifically on the licensee's response to the 10 CFR 50.54{f) letters and not on the associated Orders. By letter dated May 10, 2012 (ADAMS Accession No. ML 12135A391), Exelon Generation Company, LLC submitted its 60-day response to the 10 CFR 50.54{f) Request for Information Enclosure
| | By letter dated May 10, 2012, Exelon Generation Company, LLC submitted its 60-day response proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. As discussed in the enclosed NRC staff evaluation, the licensee's alternative approach outlined in its 60-day response letter is consistent with the guidance of industry document Nuclear Energy Institute (NEI) 12-01, "Guidance for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities,,,1 and the direction of the Commission. |
| -2 proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. The NRC staff reviewed the licensee's proposed alternative against the guidance contained in NEI 12-01. In addition, the NRC staff also considered the direction given by the Commission in the Staff Requirements Memorandum to SECY 12-0025, "Proposed Orders and Requests for Information in Response to Lessons Learned from Japan's March 11, 2011, Great Tohoku Earthquake and Tsunami," dated March 9,2012 (ADAMS Accession No. ML 120690347).
| | 1 NRC staff determined NEI 12-01 to be an acceptable approach in letter dated May 15, 2012 (ADAMS Accession No. ML12131A043). |
| This guidance stated, in part, that Completing implementation activities associated with the rule we have already promulgated has greater safety significance and also involves the coordinated actions of our partners in State and local governments.
| | |
| Substantial public credibility benefits accrue from continuing these activities as a priority.
| | -2 In addition, the NRC staff concludes that the licensee provided an adequate basis for its proposed alternative to responding to the 50.54(f) Request for Information regarding communications and staffing for NTTF Recommendation 9.3. |
| The NRC staff considers the existing EP framework and regulations provide reasonable assurance of adequate protection of public health and safety in the event of a radiological emergency.
| | If you have any questions, please contact me at 301-415-6606 or via e-mail at JoeI.Wiebe@nrc.gov. |
| The revised EP rule that was promulgated on November 23, 2011, initiated a number of activities that will enhance EP programs, including conducting a staffing analysis and enhancing public notification systems. The implementation of the EP rule was given priority by the Commission and the NTTF recommendations should not displace ongoing work that has greater safety benefit, higher priority, or is necessary for continued safe operation of nuclear power plants. The NTTF Report concluded that continued operation and continued licensing activities do not pose an imminent risk to the public health and safety and are not inimical to the common defense and security.
| | ~Jk;: ~~D Joel S. Wiebe, Senior p r o i e u t Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455. 50-461, 50-237, 50-249,50-373,50-374,50-352, 50-353, 50-219, 50-277,50-278,50-254,50-265, and 50-289 |
| The phased approach to responding to the 10 CFR 50.54(f) letters, combined with the definition of new response requirements associated with Fukushima NTTF Recommendation 4.2, as subsequently modified by the NRC staff and issued as NRC Order EA-12-049 (ADAMS Accession No. ML 12054A736) will ensure that enhancements will be made to staffing and communications by licensees. | | |
| It should be noted that the 10 CFR 50.54(f) letter and implementation of the Order includes completion of actions related to response assignments, staffing changes, issuance of new or revised procedures or guidelines, and training.
| | ==Enclosure:== |
| Activities are ongOing by both the NRC and industry to initiate interim actions as a result of lessons learned from the events which will be provided in the 90-day response such as: Methods to access the site Notification of Interim actions taken to Given the above and that the licensee's approach was found to be consistent with the guidance of NEI 12-01 and the direction of the Commission, the NRC staff concludes that the licensee has provided an adequate basis for its proposed alternative responding to the 10 CFR 50.54(f) letters regarding communications and staffing for Recommendation 9.3.
| | |
| -2 In addition, the NRC staff concludes that the licensee provided an adequate basis for its proposed alternative to responding to the 50.54(f) Request for Information regarding communications and staffing for NTTF Recommendation 9.3. If you have any questions, please contact me at 301-415-6606 or via e-mail at Joel.Wiebe@nrc.gov.
| | Staff Evaluation cc w/encl: Distribution via Listserv |
| Sincerely, I RAJ Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461, 50-237, 50-249,50-373,50-374, 50-352, 50-353, 50-219, 50-277,50-278, 50-254, 50-265, and 50-289 Staff cc w/encl: Distribution via DISTRIBUTION:
| | |
| PUBLIC RidsRg n 1 MailCenter Resource LPL3-2 R/F RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsOgcRp Resource RidsNrrPMBraidwood Resource RidsNrrPMByron Resource LPL 1-2 R/F RidsNrrPMClinton Resource RidsNrrLaSalie Resource CMurray, NSIR RidsNrrPMDresden Resource RidsNrrPMQuadCities Resource JShea, NRR/JLD RidsNrrPMPeachBottom Resource RidsNrrPMThreeMilelsland Resource RidsNrrPM Limerick Resource RidsAcrsAcnw&mMailCenter Resource RidsNrrLASRohrer Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resource RidsNsirDpr Resource JKratchman, NRR/JLD ADAMS Accession No. ML 12159A395
| | NUCLEAR REGULATORY COMMISSION STAFF EVALUATION INFORMATION REQUEST MADE UNDER 10 CFR 50.54(f) |
| *concurrence via email OFFICE i NRR/DORLlLPL3-2/PM N RR/DORLlLPL3-2/LA I NSIR/DPR/DDEP/NRLB/BC NAME JWiebe SRohrer i KWiliiams*
| | REGARDING NEAR-TERM TASK FORCE RECOMMENDATION 9.3 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNITS 1 AND 2; CLINTON POWER STATION, UNIT 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461,50-237,50-249, 50-373,50-374,50-352,50-353,50-219,50-277, 50-278; 50-254, 50-265, AND 50-289 By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12073A348), the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.54{f) which included the Near-Term Task Force (NTTF) |
| DATE 6/7/12 6/7/12 6/6/12 ,OFFICE NRR/JLD/PMB/BC NRR/DORLlLPL 1-2/BC N RR/DO R LlLPL3-2/BC ATE RPascarelli 6/7/12 J MKhanna 6/08 112 Jlimmerman 16/08 112 OFFICIAL RECORD COPY}} | | Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date. |
| | By letter dated May 3,2012 (ADAMS Accession No. ML12125A410), the Nuclear Energy Institute (NEI) submitted NEI12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities," Revision 0, May 2012. The NRC staff reviewed NEI 12-01 and found it to be an acceptable method for licensees to use when responding to the NRC's 10 CFR 50.54{f) Request for Information regarding communications and staffing for EP. This staff evaluation is focused specifically on the licensee's response to the 10 CFR 50.54{f) letters and not on the associated Orders. |
| | By letter dated May 10, 2012 (ADAMS Accession No. ML12135A391), Exelon Generation Company, LLC submitted its 60-day response to the 10 CFR 50.54{f) Request for Information Enclosure |
| | |
| | -2 proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. The NRC staff reviewed the licensee's proposed alternative against the guidance contained in NEI 12-01. In addition, the NRC staff also considered the direction given by the Commission in the Staff Requirements Memorandum to SECY 12-0025, "Proposed Orders and Requests for Information in Response to Lessons Learned from Japan's March 11, 2011, Great Tohoku Earthquake and Tsunami," dated March 9,2012 (ADAMS Accession No. ML120690347). This guidance stated, in part, that Completing implementation activities associated with the rule we have already promulgated has greater safety significance and also involves the coordinated actions of our partners in State and local governments. Substantial public credibility benefits accrue from continuing these activities as a priority. |
| | The NRC staff considers the existing EP framework and regulations provide reasonable assurance of adequate protection of public health and safety in the event of a radiological emergency. The revised EP rule that was promulgated on November 23, 2011, initiated a number of activities that will enhance EP programs, including conducting a staffing analysis and enhancing public notification systems. The implementation of the EP rule was given priority by the Commission and the NTTF recommendations should not displace ongoing work that has greater safety benefit, higher priority, or is necessary for continued safe operation of nuclear power plants. The NTTF Report concluded that continued operation and continued licensing activities do not pose an imminent risk to the public health and safety and are not inimical to the common defense and security. |
| | The phased approach to responding to the 10 CFR 50.54(f) letters, combined with the definition of new response requirements associated with Fukushima NTTF Recommendation 4.2, as subsequently modified by the NRC staff and issued as NRC Order EA-12-049 (ADAMS Accession No. ML12054A736) will ensure that enhancements will be made to staffing and communications by licensees. It should be noted that the 10 CFR 50.54(f) letter and implementation of the Order includes completion of actions related to response assignments, staffing changes, issuance of new or revised procedures or guidelines, and training. Activities are ongOing by both the NRC and industry to initiate interim actions as a result of lessons learned from the events which will be provided in the 90-day response such as: |
| | * Methods to access the site |
| | * Notification of staff Interim actions taken to date Given the above and that the licensee's approach was found to be consistent with the guidance of NEI 12-01 and the direction of the Commission, the NRC staff concludes that the licensee has provided an adequate basis for its proposed alternative responding to the 10 CFR 50.54(f) letters regarding communications and staffing for Recommendation 9.3. |
| | |
| | ML12159A395 *concurrence via email OFFICE i NRR/DORLlLPL3-2/PM N RR/DORLlLPL3-2/LA I NSIR/DPR/DDEP/NRLB/BC NAME JWiebe SRohrer i KWiliiams* |
| | DATE 6/7/12 6/7/12 6/6/12 |
| | ,OFFICE NRR/JLD/PMB/BC NRR/DORLlLPL1-2/BC N RR/DO R LlLPL3-2/BC |
| | ~E ATE RPascarelli 6/7/12 J MKhanna 6/08 112 Jlimmerman 16/08 112}} |
Letter Sequence Approval |
|---|
TAC:ME8623, (Approved, Closed) TAC:ME8624, (Approved, Closed) TAC:ME8625, (Approved, Closed) TAC:ME8626, (Approved, Closed) TAC:ME8627, (Approved, Closed) TAC:ME8628, (Approved, Closed) TAC:ME8629, (Approved, Closed) TAC:ME8630, (Approved, Closed) TAC:ME8631, (Approved, Closed) TAC:ME8633, (Approved, Closed) TAC:ME8634, (Approved, Closed) TAC:ME8635, (Approved, Closed) TAC:ME8636, (Approved, Closed) TAC:ME8637, (Approved, Closed) TAC:ME8638, (Approved, Closed) TAC:ME8639, (Approved, Closed) |
|
MONTHYEARML0726804681954-12-31031 December 1954
New Jersey Department of Environmental Protection, Division of Parks and Forestry, State Forest Service, New Jersey'S Big Trees
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ML0726705561963-01-31031 January 1963
Us Fish and Wildlife Service, 1963. Distribution of Shellfish Resources in Relation to the New Jersey Intracoastal Waterway -- Manasquan Inlet to Little Egg Harbor. Boston, Ma. January
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ML20260G1161965-06-17017 June 1965
Fuel Storage Building Sections & Details. Sheet 1
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ML20260G1231965-08-20020 August 1965
Fuel Storage Building Section & Details. Sheet 7.Field Change Request & Drawing Change Notices Encl
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ML20260G1201967-01-31031 January 1967
Fuel Storage Building Sections & Details. Sheet 4
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ML0725407921968-06-0404 June 1968
Drawing 11D-190, 6 Inch Roof Vent.
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ML20264B5281971-04-0101 April 1971
Reactor Protection System. Sheet 5 of 13
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ML20206K6391972-05-31031 May 1972
Ack Receipt of Re Technical Basis for Accepting Weld Surface Area W/Bluish Tint.No Further Questions
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ML20263J0711972-07-10010 July 1972
Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly D (48 of 50), as-built
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ML20263J0731972-07-10010 July 1972
Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly a, as-built
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ML20263J0781972-07-10010 July 1972
Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly C
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ML20263J0751972-07-18018 July 1972
Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly B (46 of 50), as-built
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ML19326C1141972-07-19019 July 1972
SLR Tech Specs from Authority File
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ML0726405941972-11-17017 November 1972
Jersey Central Power & Light Company, Oyster Creek Nuclear Generating Station Environmental Report, Amendment 2
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ML20263N4591973-01-14014 January 1973
Auxiliary Building Unit 1 Spent Fuel Pool Sections Reinforcing. Sheet 4
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ML20262H5581973-12-14014 December 1973
Details:1,2,17 & 21 Thru 27,32,33 & 34. Sheet 2 of 3
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ML20262H5611973-12-14014 December 1973
Details:3,13,19,24,28,35 & 36. Sheet 3 of 3
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ML20262H5551973-12-14014 December 1973
Watertight Door Assy. Sheet 1 of 3
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ML20263T0291974-04-0909 April 1974
Shore Line Contours. Sheet 3 of 4
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ML20263N4901974-07-15015 July 1974
Auxiliary Building Unit 1 Spent Fuel Pool Plan and Sections Concrete. Sheet 1
Project stage: Other
ML20235X2491974-07-16016 July 1974
Forwards Revised Operator Requalification Program for Plant, Per Recipient 740618 Request
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ML20263N4981974-10-10010 October 1974
Auxiliary Building Unit 2 Spent Fuel Pool Sections Concrete. Sheet 2
Project stage: Other
ML20263N4751974-10-11011 October 1974
Auxiliary Building Unit 2 Spent Fuel Pool Sections Reinforcing. Sheet 2
Project stage: Other
ML0725408181974-10-22022 October 1974
Drawing M-79, Rev. 3, Main Steam Relief Valve Discharge Stack Modification.
Project stage: Other
ML20263N4621974-11-0505 November 1974
Auxiliary Building Unit 1 Spent Fuel Pool - Sections Reinforcing. Sheet 2
Project stage: Other
ML20263N4671974-11-0505 November 1974
Auxiliary Building Unit 1 Spent Fuel Pool Plan and Sections Reinforcing. Sheet 1
Project stage: Other
ML20263N4741974-11-0505 November 1974
Auxiliary Building Unit 2 Spent Fuel Pool Sections Reinforcing. Sheet 3
Project stage: Other
ML20235X2331974-12-10010 December 1974
Discusses 741206 Meeting W/Util to Review Responsibilities & Outline Scope of Exam for Fuel Handling & Senior Operators at Facility.Addl Info to Develop Written & Operating Test Needed
Project stage: Meeting
ML20263N4561974-12-13013 December 1974
Auxiliary Building Spent Fuel Pool - Unit 1 Plan and Sections Reinforcing. Sheet 4
Project stage: Other
ML20263N4711974-12-13013 December 1974
Auxiliary Building Spent Fuel Pool - Unit 2 Plan and Sections Reinforcing. Sheet 4
Project stage: Other
ML20264B5261975-04-24024 April 1975
Single Line Diagram:125 Volt D-C System
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ML0607202531975-05-23023 May 1975
May 23, 1975 - Final Summary Report Unit 2 Startup
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ML0606805861975-05-23023 May 1975
May 23, 1975 - Final Summary Report Startup, Enclosure 4
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ML20140F9811975-06-16016 June 1975
Forwards Request for Info Re Ebasco Containment Structures Design Rept,Per 750530 Request.Info for Assessing Design Adequacy of Piping & Mechanical Components Affected by Suppression Pool Dynamic Loadings Needed
Project stage: Other
ML20235Z6961975-06-17017 June 1975
Requests Listed Info Re Application for Permit to Const Plant,Including Necessary Info to Evaluate Means Employed for Keeping Radioactivity in Effluents to Unrestricted Areas as Low as Practicable,Within 12 Months from 750604
Project stage: Other
ML20262H5711975-06-18018 June 1975
Details 2,3,4 & 5. Sheet 3 of 3
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ML20262H5691975-06-18018 June 1975
Details 1 & 6. Sheet 2 of 3
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ML20262H5671975-06-18018 June 1975
4 Ft X 8 Ft Opening Lhrb Door & Frame Assembly. Sheet 1 of 3
Project stage: Other
ML20263N4791975-08-15015 August 1975
Auxiliary Building Unit 2 Spent Fuel Pool Plans and Sections Reinforcing. Sheet 1
Project stage: Other
ML20236A0651975-10-15015 October 1975
Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days
Project stage: Other
ML20263N4651975-11-18018 November 1975
Auxiliary Building Spent Fuel Pool - Unit 2 Plan and Sections Reinforcing. Sheet 5
Project stage: Other
ML20155J7791976-01-0505 January 1976
Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl
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ML20262D8641976-03-26026 March 1976
Piping & Instrumentation Diagram: Type Gs,Oil Piping Diagram
Project stage: Other
ML20148F2811976-06-0707 June 1976
Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads
Project stage: RAI
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
Project stage: Meeting
ML20205H9841976-07-0606 July 1976
Forwards Draft Amends 18 & 23 to Licenses DPR-24 & DPR-27, Respectively, & Safety Evaluation.Amends Revise Tech Specs to Add Surveillance Requirements & Place Limit on Max Weight of Spent Fuel Shipping Cask Used
Project stage: Draft Approval
ML20245C3281976-07-0909 July 1976
Requests Amend to Fsar,Describing Rupture Discs & Administrative Controls,Tests & Surveillance That Recipient Has or Intends to Have Over Discs,Within 30 Days of Ltr Receipt.Listed Items Should Be in Tech Spec Format
Project stage: Other
ML20236C3041976-09-14014 September 1976
Notification of 760928 Meeting W/Util in Bethesda,Md to Discuss Util Concepts for Proposed Neutron Shield for Plant. Summary of Neutron Streaming Problem Encl
Project stage: Meeting
ML20265C7261976-09-17017 September 1976
Elementary Wiring Diagram:Reactor Cooling System Przr Heater
Project stage: Other
ML20070J8961976-09-29029 September 1976
RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated
Project stage: Other
1974-12-13 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:TAC:ME8623]] OR [[:TAC:ME8624]] OR [[:TAC:ME8625]] OR [[:TAC:ME8626]] OR [[:TAC:ME8627]] OR [[:TAC:ME8628]] OR [[:TAC:ME8629]] OR [[:TAC:ME8630]] OR [[:TAC:ME8631]] OR [[:TAC:ME8633]] OR [[:TAC:ME8634]] OR [[:TAC:ME8635]] OR [[:TAC:ME8636]] OR [[:TAC:ME8637]] OR [[:TAC:ME8638]] OR [[:TAC:ME8639]] </code>.
[Table View]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:TAC:ME8623]] OR [[:TAC:ME8624]] OR [[:TAC:ME8625]] OR [[:TAC:ME8626]] OR [[:TAC:ME8627]] OR [[:TAC:ME8628]] OR [[:TAC:ME8629]] OR [[:TAC:ME8630]] OR [[:TAC:ME8631]] OR [[:TAC:ME8633]] OR [[:TAC:ME8634]] OR [[:TAC:ME8635]] OR [[:TAC:ME8636]] OR [[:TAC:ME8637]] OR [[:TAC:ME8638]] OR [[:TAC:ME8639]] </code>. |
Three Mile, Unit 1-Review of 60-Day Response To..| ML12159A395 |
| Person / Time |
|---|
| Site: |
Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, LaSalle |
|---|
| Issue date: |
06/08/2012 |
|---|
| From: |
Joel Wiebe
Plant Licensing Branch III |
|---|
| To: |
Pacilio M
Exelon Nuclear |
|---|
| References |
|---|
| TAC ME8623, TAC ME8624, TAC ME8625, TAC ME8626, TAC ME8627, TAC ME8628, TAC ME8629, TAC ME8631, TAC ME8633, TAC ME8634, TAC ME8635, TAC ME8636, TAC ME8637, TAC ME8638, TAC ME8639, TAC ME8630 |
| Download: ML12159A395 (5) |
|
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|---|
Category:Letter
MONTHYEARML24285A1452024-10-24024 October 2024
Ltr. to Gail Cheatham, Kickapoo Tribe of Indians of the Kickapoo Reservation in Ks Re CPS Sect 106 Consult
ML24285A1472024-10-24024 October 2024
Ltr. to Geoffrey M. Standing Bear, Principal Chief, Osage Nation Re CPS Section 106 Consultation
ML24285A1422024-10-24024 October 2024
Ltr. to Darwin Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Re CPS Section 106 Consultation
ML24285A1442024-10-24024 October 2024
Ltr. to Estavio Elizondo, Sr., Chairman, Kickapoo Traditional Tribe of Texas Re CPS Section 106 Consultation
ML24285A1462024-10-24024 October 2024
Ltr. to Gena Kakkak, Chairwoman, Menominee Indian Tribe of Wisconsin Re CPS Section 106 Consultation
ML24285A1482024-10-24024 October 2024
Ltr. to Joseph Rupnick, Chairman, Prairie Band Potawatomi Nation Re CPS Section 106 Consultation
ML24285A1432024-10-21021 October 2024
Ltr. to Douglas Lankford, Chief, Miami Tribe of Oklahoma Re CPS Section 106 Consultation
ML24285A1412024-10-21021 October 2024
Ltr. to Craig Harper, Chief, Peoria Tribe of Oklahoma Re CPS Section 106 Consultation
IR 05000352/20240122024-10-17017 October 2024
Commercial Grade Dedication Inspection Report 05000352/2024012 and 05000353/2024012
IR 05000277/20244012024-10-17017 October 2024
Security Baseline Inspection Report 05000277/2024401 and 05000278/2024401 (Cover Letter Only)
ML24291A0012024-10-17017 October 2024
Submittal of Core Operating Limits Report, Cycle 25
RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024
Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024
Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals
ML24284A1972024-10-10010 October 2024
Cover Letter Oyster Creek, License Termination Plan Acceptance Review
ML24284A2842024-10-10010 October 2024
(Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP)
05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024
Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate
ML24281A1012024-10-0707 October 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML24274A2372024-10-0707 October 2024
– Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications
ML24281A1502024-10-0707 October 2024
Request for Information for NRC Commercial Grade Dedication Inspection Report 05000454/2025010 and 05000455/2025010
ML24269A0462024-10-0404 October 2024
Cover Letter for Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Acceptance Review Request for Additional Information
ML24278A3022024-10-0404 October 2024
Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec
ML24256A0422024-10-0404 October 2024
Updated Post-Shutdown Decommissioning Activities Report, Rev. 6
SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024
Correction to Registration of Use of Casks to Store Spent Fuel
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24247A1642024-09-30030 September 2024
Alternative Request RP-01
IR 05000373/20244012024-09-27027 September 2024
County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401
ML24263A0032024-09-27027 September 2024
Generation Station, Units 1 and 2 – Regulatory Audit Plan Supporting Review of the Component Interface Module System of the Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) (Redacted)
ML24225A2132024-09-26026 September 2024
Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
ML24274A0822024-09-25025 September 2024
Independent Spent Fuel Storage Installation Security Plan, Training Qualification Plan, Safeguards Contingency Plan, Revisions 1 and 2
05000461/LER-2023-002-01, Reactor Core Isolation Cooling Inoperable Prior to Mode Change2024-09-24024 September 2024
Reactor Core Isolation Cooling Inoperable Prior to Mode Change
ML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
ML24253A0942024-09-23023 September 2024
License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID L-2024-Sle-0002) (Docket Numbers: 50-237 and 50-249)
SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024
ISFSI Annual Effluent Release Report
ML24270A0332024-09-20020 September 2024
Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report
IR 05000237/20244022024-09-19019 September 2024
– Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public)
ML24243A0482024-09-19019 September 2024
Generation Station, Unit Nos. 1 and 2 - Schedule Update for License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System
BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024
Cycle 27 Core Operating Limits Report
ML24263A2062024-09-19019 September 2024
Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24215A4042024-09-18018 September 2024
Request for Withholding Information from Public Disclosure
IR 05000352/20244202024-09-16016 September 2024
– Security Baseline Inspection Report 05000352/2024420 and 05000353/2024420
ML24260A0492024-09-16016 September 2024
Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024
ML24260A2152024-09-16016 September 2024
Confirmation of Initial License Examination
RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024
Relief Requests Associated with the Fifth Inservice Inspection Interval
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
IR 05000254/20244022024-09-12012 September 2024
Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public)
IR 05000456/20240112024-09-12012 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011
ML24211A2302024-09-11011 September 2024
– Request for Partial Site Release for Facility Operating License No. NPF-62
SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024
Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds
2024-09-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 8, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO.1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2, AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 REVIEW OF 60-DAY RESPONSE TO REQUEST FOR INFORMATION REGARDING RECOMMENDATION 9.3, OF THE NEAR-TERM TASK FORCE RELATED TO THE FUKUSHIMA DAIICHI NUCLEAR POWER PLANT ACCIDENT (TAC NOS. ME8623, ME8624, ME8625, ME8626, ME8627, ME8628, ME8629, ME8630, ME8631, ME8632, ME8633, ME8634, ME8635, ME8636, ME8637, ME8638, AND ME8639)
Dear Mr. Pacilio:
By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f) which included the Near Term Task Force (NTTF) Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date.
By letter dated May 10, 2012, Exelon Generation Company, LLC submitted its 60-day response proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. As discussed in the enclosed NRC staff evaluation, the licensee's alternative approach outlined in its 60-day response letter is consistent with the guidance of industry document Nuclear Energy Institute (NEI) 12-01, "Guidance for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities,,,1 and the direction of the Commission.
1 NRC staff determined NEI 12-01 to be an acceptable approach in letter dated May 15, 2012 (ADAMS Accession No. ML12131A043).
-2 In addition, the NRC staff concludes that the licensee provided an adequate basis for its proposed alternative to responding to the 50.54(f) Request for Information regarding communications and staffing for NTTF Recommendation 9.3.
If you have any questions, please contact me at 301-415-6606 or via e-mail at JoeI.Wiebe@nrc.gov.
~Jk;: ~~D Joel S. Wiebe, Senior p r o i e u t Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455. 50-461, 50-237, 50-249,50-373,50-374,50-352, 50-353, 50-219, 50-277,50-278,50-254,50-265, and 50-289
Enclosure:
Staff Evaluation cc w/encl: Distribution via Listserv
NUCLEAR REGULATORY COMMISSION STAFF EVALUATION INFORMATION REQUEST MADE UNDER 10 CFR 50.54(f)
REGARDING NEAR-TERM TASK FORCE RECOMMENDATION 9.3 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNITS 1 AND 2; CLINTON POWER STATION, UNIT 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461,50-237,50-249, 50-373,50-374,50-352,50-353,50-219,50-277, 50-278; 50-254, 50-265, AND 50-289 By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12073A348), the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.54{f) which included the Near-Term Task Force (NTTF)
Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date.
By letter dated May 3,2012 (ADAMS Accession No. ML12125A410), the Nuclear Energy Institute (NEI) submitted NEI12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities," Revision 0, May 2012. The NRC staff reviewed NEI 12-01 and found it to be an acceptable method for licensees to use when responding to the NRC's 10 CFR 50.54{f) Request for Information regarding communications and staffing for EP. This staff evaluation is focused specifically on the licensee's response to the 10 CFR 50.54{f) letters and not on the associated Orders.
By letter dated May 10, 2012 (ADAMS Accession No. ML12135A391), Exelon Generation Company, LLC submitted its 60-day response to the 10 CFR 50.54{f) Request for Information Enclosure
-2 proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. The NRC staff reviewed the licensee's proposed alternative against the guidance contained in NEI 12-01. In addition, the NRC staff also considered the direction given by the Commission in the Staff Requirements Memorandum to SECY 12-0025, "Proposed Orders and Requests for Information in Response to Lessons Learned from Japan's March 11, 2011, Great Tohoku Earthquake and Tsunami," dated March 9,2012 (ADAMS Accession No. ML120690347). This guidance stated, in part, that Completing implementation activities associated with the rule we have already promulgated has greater safety significance and also involves the coordinated actions of our partners in State and local governments. Substantial public credibility benefits accrue from continuing these activities as a priority.
The NRC staff considers the existing EP framework and regulations provide reasonable assurance of adequate protection of public health and safety in the event of a radiological emergency. The revised EP rule that was promulgated on November 23, 2011, initiated a number of activities that will enhance EP programs, including conducting a staffing analysis and enhancing public notification systems. The implementation of the EP rule was given priority by the Commission and the NTTF recommendations should not displace ongoing work that has greater safety benefit, higher priority, or is necessary for continued safe operation of nuclear power plants. The NTTF Report concluded that continued operation and continued licensing activities do not pose an imminent risk to the public health and safety and are not inimical to the common defense and security.
The phased approach to responding to the 10 CFR 50.54(f) letters, combined with the definition of new response requirements associated with Fukushima NTTF Recommendation 4.2, as subsequently modified by the NRC staff and issued as NRC Order EA-12-049 (ADAMS Accession No. ML12054A736) will ensure that enhancements will be made to staffing and communications by licensees. It should be noted that the 10 CFR 50.54(f) letter and implementation of the Order includes completion of actions related to response assignments, staffing changes, issuance of new or revised procedures or guidelines, and training. Activities are ongOing by both the NRC and industry to initiate interim actions as a result of lessons learned from the events which will be provided in the 90-day response such as:
- Methods to access the site
- Notification of staff Interim actions taken to date Given the above and that the licensee's approach was found to be consistent with the guidance of NEI 12-01 and the direction of the Commission, the NRC staff concludes that the licensee has provided an adequate basis for its proposed alternative responding to the 10 CFR 50.54(f) letters regarding communications and staffing for Recommendation 9.3.
ML12159A395 *concurrence via email OFFICE i NRR/DORLlLPL3-2/PM N RR/DORLlLPL3-2/LA I NSIR/DPR/DDEP/NRLB/BC NAME JWiebe SRohrer i KWiliiams*
DATE 6/7/12 6/7/12 6/6/12
,OFFICE NRR/JLD/PMB/BC NRR/DORLlLPL1-2/BC N RR/DO R LlLPL3-2/BC
~E ATE RPascarelli 6/7/12 J MKhanna 6/08 112 Jlimmerman 16/08 112