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Category:General FR Notice Comment Letter type:NRC
MONTHYEARNRC-2023-0152, Comment (1) of Pamela Greenlaw on Notice of Intent to Conduct Scoping Process and Prepare Environmental Impact Statement; Dominionenergy South Carolina, Inc.; Virgil C. Summer Nuclear Station, Unit 12023-12-0404 December 2023
Comment (1) of Pamela Greenlaw on Notice of Intent to Conduct Scoping Process and Prepare Environmental Impact Statement; Dominionenergy South Carolina, Inc.; Virgil C. Summer Nuclear Station, Unit 1
NRC-2018-0198, Comment (1) of Anonymous Individual on Virgil C. Summer Nuclear Station, Unit 12018-09-24024 September 2018
Comment (1) of Anonymous Individual on Virgil C. Summer Nuclear Station, Unit 1
NRC-2016-0233, Comment (4) of Anonymous Individual on Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents2017-04-14014 April 2017
Comment (4) of Anonymous Individual on Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents
NRC-2016-0224, Comment (5) of T. Stewart on Behalf of Virgil C. Summer Nuclear Station Unit 1 on Restart of a Nuclear Power Plant Shut Down by a Seismic Event2017-02-28028 February 2017
Comment (5) of T. Stewart on Behalf of Virgil C. Summer Nuclear Station Unit 1 on Restart of a Nuclear Power Plant Shut Down by a Seismic Event
NRC-2015-0172, Comment (6) of Unknown Individual on Clarification of Reporting Requirements2015-09-14014 September 2015
Comment (6) of Unknown Individual on Clarification of Reporting Requirements
NRC-2015-0136, Comment (0001) of Damon Bryson on Information Collection: NRC Generic Letter 2015-XX, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools2015-07-0808 July 2015
Comment (0001) of Damon Bryson on Information Collection: NRC Generic Letter 2015-XX, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools
NRC-2015-0095, Comment (5) of Scott A. Bauer, on Behalf of Stars Alliance LLC, on NRC Draft Regulatory Guide DG-1322, Alternate Risk-Informed Approach for Addressing He Effects of Debris on Post-Accident Long-Term Cooling2015-07-0202 July 2015
Comment (5) of Scott A. Bauer, on Behalf of Stars Alliance LLC, on NRC Draft Regulatory Guide DG-1322, Alternate Risk-Informed Approach for Addressing He Effects of Debris on Post-Accident Long-Term Cooling
NRC-2011-0011, Comment (1) of Susan Reese on Design and Inspection Criteria for Water-Control Structures Associated with Nuclear Power Plants; Request for Comment on Draft Regulatory Guide2015-03-18018 March 2015
Comment (1) of Susan Reese on Design and Inspection Criteria for Water-Control Structures Associated with Nuclear Power Plants; Request for Comment on Draft Regulatory Guide
NRC-2014-0276, Comment (5) of Thomas Collins on General Use of Locks in Protection and Control of Facilities and Special Nuclear Materials, Classified Matter and Safeguards Information2015-02-27027 February 2015
Comment (5) of Thomas Collins on General Use of Locks in Protection and Control of Facilities and Special Nuclear Materials, Classified Matter and Safeguards Information
NRC-2014-0071, Comment (7) of Bruce Thompson on Behalf of V.C. Summer, Unit 1 on Tornado Missile Protection; Extension of Comment Period2014-06-19019 June 2014
Comment (7) of Bruce Thompson on Behalf of V.C. Summer, Unit 1 on Tornado Missile Protection; Extension of Comment Period
NRC-2014-0040, Comment (7) of Tracey Stewart on Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2014-05-12012 May 2014
Comment (7) of Tracey Stewart on Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
NRC-2010-0148, Comment (2) of Susan Reese, on Behalf of South Carolina Electric & Gas, on NRC-2010-0148-0001, Draft Regulatory Guide: Issuance; Availability2010-06-0303 June 2010
Comment (2) of Susan Reese, on Behalf of South Carolina Electric & Gas, on NRC-2010-0148-0001, Draft Regulatory Guide: Issuance; Availability
NRC-2009-0520, Comment (4) of Bruce Thompson on Behalf of South Carolina Electric & Gas Supporting Nuclear Regulatory Commission Federal Register Notice NRC 2009-0520 on the Blending of Low-Level Radioactive Waste2010-01-28028 January 2010
Comment (4) of Bruce Thompson on Behalf of South Carolina Electric & Gas Supporting Nuclear Regulatory Commission Federal Register Notice NRC 2009-0520 on the Blending of Low-Level Radioactive Waste
2023-12-04
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'Z>l7 Received: April 14, 2017 PUBLIC SUBMISSIONt ti.r~ ! 7 i.tt 10: :,o Status: Pending_Post Tracking No. lkl-8vtu-n8fj Comments Due: April 21, 2017 Submission Type: Web Docket: NRC-2016,-0233
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Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents Comment On: NRC-2016-0233-0003 Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents; Extension of Comment Period Document: NRC-20 l 6""023 3-DRAFT-0005 Comment on FR Doc# 2017-02073
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Name: Anonymous Anonymous General Comment 0 / ,f-.
Virgil C. Summer Nuclear Station Unit 1 is providing the following comments concerning its review of Draft Regulatory Guide (DG) 1327.
Section 2.1.3: Please clarify what kind of manufacturing tolerances are referred to here. Does this require a statistical analysis with 95/95 uncertainty?
Section 2.2.3: Given that a large majority of the time each reactor spends at power is near 100%, can low power conditions be excluded from the analysis? Many transient analyses are perfofll1ed at zero power .and full power based on probability. It would be very time-consuming to determine if intermediate power levels are more limiting at each bumup interval. It would seem that even for a load-following plant, examinations of 0, 80%, 90%, and 100% would be sufficient to cover 99% of the probability distribution.
Section 2.5.1: For control rod ejection (CRE), since.the reactivity-initiated accident (RIA) transient is caused by the pressure boundary breach, the analysis should be able to credit the pressure boundary breach in the peak RCS pressure analysis.
Section 4: This section should be removed from DG-1327. Information related to the performance of radiological consequence analyses should remain in RG 1.183.
Section 6: The reactor coolant peak pressure acceptance criterion is already defined in a plant's Final Safety Analysis Report and may differ from the limit defined in DG-1327. The Regulatory Guide should not override existing license~ limits._ _ ~-~=?>S-:::::- /}!JiLt-tJ 3 Su.UST ~:1e~~c=;~ ~<--~/!t!/~C/N~ 3)
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https://www.fdms.govIfdms/getcontent?objectld=09000064825 56dce&format=xml&showorig=false 04/ 17/2017
