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| | issue date = 02/01/2011 | | | issue date = 02/01/2011 |
| | title = Final Significance Determination for a Security-Related Green Finding (NRC Inspection Report Nos. 05000336/2011403; 05000423/2011403) - Millstone Nuclear Power Station | | | title = Final Significance Determination for a Security-Related Green Finding (NRC Inspection Report Nos. 05000336/2011403; 05000423/2011403) - Millstone Nuclear Power Station |
| | author name = Kennedy S R | | | author name = Kennedy S |
| | author affiliation = NRC/RGN-I/DRS/PSB1 | | | author affiliation = NRC/RGN-I/DRS/PSB1 |
| | addressee name = Heacock D | | | addressee name = Heacock D |
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| =Text= | | =Text= |
| {{#Wiki_filter:SAFEGU \RDS I N FORMATION February 1,2011 EA-10-214 Mr. David Heacock President and Chief Nuclear Officer Dominion Nuclear, Connecticut, Inc.Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060 | | {{#Wiki_filter:==SUBJECT:== |
| | | FINAL SIGNIFICANCE DETERMINATION FOR A SECURITY-RELATED GREEN FTNDlNG INRC TNSPECTTON REPORT NOS. 0500033612011403; 050004231201 1 4031 - M I LLSTON E N U CLEAR POWER STATl ON |
| SUBJECT: FINAL SIGNIFICANCE DETERMINATION FOR A SECURITY-RELATED GREEN FTNDlNG INRC TNSPECTTON REPORT NOS. 0500033612011403; 050004231201 1 4031 - M I LLSTON E N U CLEAR POWER STATl ON | |
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| ==Dear Mr. Heacock:== | | ==Dear Mr. Heacock:== |
| This letter provides you with the U.S. Nuclear Regulatory Commission's (NRC's) final significance determination for a finding that was preliminarily determined to be of at least low to moderate security significance (Greater than Green). The finding was identified during an NRC inspection conducted at the Millstone Nuclear Power Station (Millstone) | | This letter provides you with the U.S. Nuclear Regulatory Commission's (NRC's) final significance determination for a finding that was preliminarily determined to be of at least low to moderate security significance (Greater than Green). The finding was identified during an NRC inspection conducted at the Millstone Nuclear Power Station (Millstone) from August 16, 2010 - |
| from August 16, 2010 -September 28, 2010, and was presented at an exit meeting held on September 28, 2010. The finding was discussed in detail in the subject inspection report issued on November 9,2Q10.Dominion Nuclear Connecticut, lnc. (Dominion) | | September 28, 2010, and was presented at an exit meeting held on September 28, 2010. The finding was discussed in detail in the subject inspection report issued on November 9,2Q10. |
| has taken immediate corrective actions to address any security-related vulnerability.
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| The nature of the security-related finding, and the corrective actions taken to address the issue, are considered safeguards information (SGl) and are not included in this letter, but are described in the non-public enclosure.
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| Our November 9, 2010,letter also offered Dominion the opportunity to attend a Regulatory Conference or reply in writing to provide its position on the facts and assumptions the NRC used to arrive at the finding and its security significance.
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| At Dominion's request, a Regulatory Conference was held on January 6, 2011, at the NRC's Region I office in King of Prussia, Pennsylvania with Leslie Hart, Vice President Nuclear Support Services, and other members of your staff. During the meeting, Dominion staff described Dominion's assessment of the significance of the finding and the corrective actions taken to resolve the issue. Dominion disagreed with the proposed significance of the issue, and presented new information to support Dominion's position.After further consideration of the information developed during the inspection, and the additional information your staff provided at the conference, the NRC has concluded that the inspection finding is of very low security significance and should be characterized as Green. The NRC has also determined that the finding is associated with a violation of NRC requirements.
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| The NRC is treating the issue as a non-cited violation in accordance with Section 2.3.2.a of the NRC Enforcement Policy because: 1) the violation was of very low security significance; 2) comptiance was restored immediately upon identification of the issue; 3) the violation was When separated from its Enclosure, this document is DECONTROLLED.
| | Dominion Nuclear Connecticut, lnc. (Dominion) has taken immediate corrective actions to address any security-related vulnerability. The nature of the security-related finding, and the corrective actions taken to address the issue, are considered safeguards information (SGl) and are not included in this letter, but are described in the non-public enclosure. |
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| SAFECUARDS lNFORlv[ TION l=SAFECUNRDS I NFORMNTION entered into your corrective action program; and, 4) the violation was determined to be neither repetitive nor willful. The basis for the NRC's significance determination and discussion of the violation are provided in the attached Enclosure, which also contains SGI and, therefore, is non-public.ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the Publicly-Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC website at http://www.nrc.qov/readino-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 73.22, a copy of this letter's enclosure will not be available for public inspection.
| | Our November 9, 2010,letter also offered Dominion the opportunity to attend a Regulatory Conference or reply in writing to provide its position on the facts and assumptions the NRC used to arrive at the finding and its security significance. At Dominion's request, a Regulatory Conference was held on January 6, 2011, at the NRC's Region I office in King of Prussia, Pennsylvania with Leslie Hart, Vice President Nuclear Support Services, and other members of your staff. During the meeting, Dominion staff described Dominion's assessment of the significance of the finding and the corrective actions taken to resolve the issue. Dominion disagreed with the proposed significance of the issue, and presented new information to support Dominion's position. |
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| In addition, the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response, if you choose to provide one, will not be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. lf Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Othenruise, mark your entire response, "Security-
| | After further consideration of the information developed during the inspection, and the additional information your staff provided at the conference, the NRC has concluded that the inspection finding is of very low security significance and should be characterized as Green. The NRC has also determined that the finding is associated with a violation of NRC requirements. The NRC is treating the issue as a non-cited violation in accordance with Section 2.3.2.a of the NRC Enforcement Policy because: 1) the violation was of very low security significance; 2) comptiance was restored immediately upon identification of the issue; 3) the violation was When separated from its Enclosure, this document is DECONTROLLED. |
| Related Information - Withhold Under 10 CFR 2.390," and follow the instructions for withholding in 10 CFR 2.391(bX1).
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| Sincerely,/RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety DocketNos.
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| 50-336;50-243 License Nos. DPR-65; NPF-49
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| | SAFECUNRDS I NFORMNTION D. Heacock 2 entered into your corrective action program; and, 4) the violation was determined to be neither repetitive nor willful. The basis for the NRC's significance determination and discussion of the violation are provided in the attached Enclosure, which also contains SGI and, therefore, is non-public. |
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| ===Enclosure:===
| | ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the Publicly-Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC website at http://www.nrc.qov/readino-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 73.22, a copy of this letter's enclosure will not be available for public inspection. In addition, the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response, if you choose to provide one, will not be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. lf Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Othenruise, mark your entire response, "Security-Related Information - Withhold Under 10 CFR 2.390," and follow the instructions for withholding in 10 CFR 2.391(bX1). |
| As Described (CONTAINS SAFEGUARDS INFORMATION (SGl))cc wlencl: wlSGl: J. Curling, Acting Security Department Manager F. Murray, President and CEO, NYSERDA, State of New York R. Frazier, New York State Office of Homeland Security E. Wilds, Jr., PH.D., State Liaison Officer, State of Connecticut cc w/o encl:w/o OUO-SRI: Distribution via ListServ SNFEGUNRDS I NFERMATION entered into your corrective action program; and, 4) the violation was determined to be neither repetitive nor willful. The basis for the NRC's significance determination and discussion of the violation are provided in the attached Enclosure, which also contains SGI and, therefore, is non-public.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the Publicly-Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC website at http:/lwww.nrc.gov/readinq-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 73.22, a copy of this letter's enclosure will not be available for public inspection.
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| In addition, the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response, if you choose to provide one, will not be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. lf Safeguards lnformation is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response, "Security-
| | Sincerely, |
| Related Information - Withhold Under 10 CFR 2.390," and follow the instructions for withholding in 10 CFR 2.391(bX1).
| | /RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety DocketNos. 50-336;50-243 License Nos. DPR-65; NPF-49 Enclosure: As Described (CONTAINS (SGl)) |
| | cc wlencl: wlSGl: |
| | J. Curling, Acting Security Department Manager F. Murray, President and CEO, NYSERDA, State of New York R. Frazier, New York State Office of Homeland Security E. Wilds, Jr., PH.D., State Liaison Officer, State of Connecticut cc w/o encl:w/o OUO-SRI: Distribution via ListServ SNFEGUNRDS I NFERMATION entered into your corrective action program; and, 4) the violation was determined to be neither repetitive nor willful. The basis for the NRC's significance determination and discussion of the violation are provided in the attached Enclosure, which also contains SGI and, therefore, is non-public. |
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| Sincerely,/RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-336; 50-243 License Nos. DPR-65: NPF-49
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the Publicly-Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC website at http:/lwww.nrc.gov/readinq-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 73.22, a copy of this letter's enclosure will not be available for public inspection. In addition, the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response, if you choose to provide one, will not be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. lf Safeguards lnformation is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response, "Security-Related Information - Withhold Under 10 CFR 2.390," and follow the instructions for withholding in 10 CFR 2.391(bX1). |
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| ===Enclosure:===
| | Sincerely, |
| As Described (CONTAINS SAFEGUARDS INFORMATION (SGl))cc w/encl: w/SGl: J. Curling, Acting Security Department Manager F. Murray, President and CEO, NYSERDA, State of New York R. Frazier, New York State Office of Homeland Security E. Wilds, Jr., PH.D., State Liaison Officer, State of Connecticut cc w/o encl: w/o OUO-SRI: Distribution via ListServ SUNSI Review Complete: | | /RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-336; 50-243 License Nos. DPR-65: NPF-49 Enclosure: As Described (CONTAINS (SGl)) |
| MMM (Reviewer's Initials)DOCUMENT NAME: S:\Enf-allg\Enforcement\Proposed-Actions\Regionl\EA-10-214 Millstone Security (public ltr) FlNAL.docx qfterdeclaringthisdocument"AnOfficial AgencyRecord"thedocumentgllllgreleasedtothePublic. | | cc w/encl: w/SGl: |
| | J. Curling, Acting Security Department Manager F. Murray, President and CEO, NYSERDA, State of New York R. Frazier, New York State Office of Homeland Security E. Wilds, Jr., PH.D., State Liaison Officer, State of Connecticut cc w/o encl: w/o OUO-SRI: Distribution via ListServ SUNSI Review Complete: MMM (Reviewer's Initials) |
| | DOCUMENT NAME: S:\Enf-allg\Enforcement\Proposed-Actions\Regionl\EA-10-214 Millstone Security (public ltr) FlNAL.docx qfterdeclaringthisdocument"AnOfficial AgencyRecord"thedocumentgllllgreleasedtothePublic. ADAMSAccessionNo.: ML110330330 r indicate in the box: "C" = Coov without "E" = CopV with =No MMcLaughlin/MMM' |
| | RI/ DRS |
| | 'See Previous Concurrence Page |
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| ADAMSAccessionNo.:
| | SAFECUARDS IN FERMNTION Distribution w/o encl: w/o SGI: (via email) |
| ML110330330 r indicate in the box: "C" = Coov without"E" = CopV with=No MMcLaughlin/MMM'
| | R Zimmerman, OE N Hilton, OE M Ashley, NRR W Dean, RA D Lew, DRA J Clifford, DRP D Roberts, DRP P Wilson, DRS L Doerflein, DRS D Jackson, DRP T Setzer, DRP D Dodson, DRP B Haagensen, DRP, Rl J Krafty, DRP, Rl D Holody, Rl M Mclaughlin, ORA A DeFrancisco, ORA C ODaniell, Rl K Farrar, Rl D Screnci/ N Sheehan, Rl Distribution w/encl: w/SGl S Kennedy, DRS S Shaffer, DRP, SRI D Caron, DRS J Cherubini, DRS S Coker, NSIR D Furst. OE SAFEGUNRDS I NFORMNTION |
| RI/ DRS'See Previous Concurrence Page Distribution w/o encl: w/o SGI: R Zimmerman, OE N Hilton, OE M Ashley, NRR W Dean, RA D Lew, DRA J Clifford, DRP D Roberts, DRP P Wilson, DRS L Doerflein, DRS D Jackson, DRP T Setzer, DRP D Dodson, DRP B Haagensen, DRP, Rl J Krafty, DRP, Rl D Holody, Rl M Mclaughlin, ORA A DeFrancisco, ORA C ODaniell, Rl K Farrar, Rl D Screnci/ N Sheehan, Rl Distribution w/encl: w/SGl S Kennedy, DRS S Shaffer, DRP, SRI D Caron, DRS J Cherubini, DRS S Coker, NSIR D Furst. OE SAFECUARDS IN FERMNTION 3 (via email)SAFEGUNRDS I NFORMNTION
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Category:Inspection Report
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) IR 05000336/20230042024-02-14014 February 2024 Integrated Inspection Report 05000336/2023004 and 05000423/2023004 IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 IR 05000336/20230012023-05-0808 May 2023 Integrated Inspection Report 05000336/2023001 and 05000423/2023001 IR 05000336/20234032023-05-0202 May 2023 Public - Millstone Power Station, Units 2 and 3 – Final Significance Determination of Green Finding; Inspection Report 05000336/2023403 and 05000423/2023403 IR 05000336/20233022023-03-0707 March 2023 Operator Licensing Retake Examination Report 05000336/2023302 IR 05000336/20220062023-03-0101 March 2023 Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2022006 and 05000423/2022006) IR 05000336/20220042023-02-13013 February 2023 Integrated Inspection Report 05000336/2022004 and 05000423/2022004 IR 05000336/20224012023-01-26026 January 2023 Security Baseline Inspection Report 05000336/2022401 and 05000423/2022401 and Preliminary Finding(S) of Greater than Very Low Significance and Apparent Violation(S) (Cover Letter Only) IR 05000245/20220012023-01-0909 January 2023 – Safstor Inspection Report 05000245/2022001 IR 05000336/20224032023-01-0505 January 2023 Cyber Security Inspection Report 05000336/2022403 and 05000423/2022403 IR 05000336/20225012022-12-14014 December 2022 Reissued Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501 IR 05000336/20223012022-11-22022 November 2022 Initial Operator Licensing Examination Report 05000336/2022301 ML22325A1042022-11-21021 November 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501 IR 05000336/20220032022-11-14014 November 2022 Integrated Inspection Report 05000336/2022003 and 05000423/2022003 IR 05000336/20220102022-11-0101 November 2022 Biennial Problem Identification and Resolution Inspection Report 05000336/2022010 and 05000423/2022010 IR 05000336/20220112022-09-0808 September 2022 Triennial Fire Protection Inspection Report 05000336/2022011 and 05000423/2022011 IR 05000336/20220052022-08-31031 August 2022 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2022005 and 05000423/2022005) IR 05000336/20220022022-08-11011 August 2022 Integrated Inspection Report 05000336/2022002 and 05000423/2022002 IR 05000336/20224022022-05-23023 May 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000336/2022402 and 05000423/2022402 IR 05000336/20220012022-05-10010 May 2022 Integrated Inspection Report 05000336/2022001 and 05000423/2022001 IR 05000423/20223022022-03-0707 March 2022 Operator Licensing Retake Examination Report 05000423/2022302 IR 05000336/20210062022-03-0202 March 2022 Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2021006 and 05000423/2021006) IR 05000336/20210042022-02-10010 February 2022 Integrated Inspection Report 05000336/2021004 and 05000423/2021004 IR 05000336/20210112022-01-20020 January 2022 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000336/2021011 IR 05000336/20210032021-11-12012 November 2021 Integrated Inspection Report 05000336/2021003 and 05000423/2021003 IR 05000423/20213012021-11-10010 November 2021 Initial Operator Licensing Examination Report 05000423/2021301 2024-08-06
[Table view] Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
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SUBJECT:
FINAL SIGNIFICANCE DETERMINATION FOR A SECURITY-RELATED GREEN FTNDlNG INRC TNSPECTTON REPORT NOS. 0500033612011403; 050004231201 1 4031 - M I LLSTON E N U CLEAR POWER STATl ON
Dear Mr. Heacock:
This letter provides you with the U.S. Nuclear Regulatory Commission's (NRC's) final significance determination for a finding that was preliminarily determined to be of at least low to moderate security significance (Greater than Green). The finding was identified during an NRC inspection conducted at the Millstone Nuclear Power Station (Millstone) from August 16, 2010 -
September 28, 2010, and was presented at an exit meeting held on September 28, 2010. The finding was discussed in detail in the subject inspection report issued on November 9,2Q10.
Dominion Nuclear Connecticut, lnc. (Dominion) has taken immediate corrective actions to address any security-related vulnerability. The nature of the security-related finding, and the corrective actions taken to address the issue, are considered safeguards information (SGl) and are not included in this letter, but are described in the non-public enclosure.
Our November 9, 2010,letter also offered Dominion the opportunity to attend a Regulatory Conference or reply in writing to provide its position on the facts and assumptions the NRC used to arrive at the finding and its security significance. At Dominion's request, a Regulatory Conference was held on January 6, 2011, at the NRC's Region I office in King of Prussia, Pennsylvania with Leslie Hart, Vice President Nuclear Support Services, and other members of your staff. During the meeting, Dominion staff described Dominion's assessment of the significance of the finding and the corrective actions taken to resolve the issue. Dominion disagreed with the proposed significance of the issue, and presented new information to support Dominion's position.
After further consideration of the information developed during the inspection, and the additional information your staff provided at the conference, the NRC has concluded that the inspection finding is of very low security significance and should be characterized as Green. The NRC has also determined that the finding is associated with a violation of NRC requirements. The NRC is treating the issue as a non-cited violation in accordance with Section 2.3.2.a of the NRC Enforcement Policy because: 1) the violation was of very low security significance; 2) comptiance was restored immediately upon identification of the issue; 3) the violation was When separated from its Enclosure, this document is DECONTROLLED.
SAFECUARDS lNFORlv[ TION
l=
SAFECUNRDS I NFORMNTION D. Heacock 2 entered into your corrective action program; and, 4) the violation was determined to be neither repetitive nor willful. The basis for the NRC's significance determination and discussion of the violation are provided in the attached Enclosure, which also contains SGI and, therefore, is non-public.
ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the Publicly-Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC website at http://www.nrc.qov/readino-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 73.22, a copy of this letter's enclosure will not be available for public inspection. In addition, the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response, if you choose to provide one, will not be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. lf Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Othenruise, mark your entire response, "Security-Related Information - Withhold Under 10 CFR 2.390," and follow the instructions for withholding in 10 CFR 2.391(bX1).
Sincerely,
/RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety DocketNos. 50-336;50-243 License Nos. DPR-65; NPF-49 Enclosure: As Described (CONTAINS (SGl))
cc wlencl: wlSGl:
J. Curling, Acting Security Department Manager F. Murray, President and CEO, NYSERDA, State of New York R. Frazier, New York State Office of Homeland Security E. Wilds, Jr., PH.D., State Liaison Officer, State of Connecticut cc w/o encl:w/o OUO-SRI: Distribution via ListServ SNFEGUNRDS I NFERMATION entered into your corrective action program; and, 4) the violation was determined to be neither repetitive nor willful. The basis for the NRC's significance determination and discussion of the violation are provided in the attached Enclosure, which also contains SGI and, therefore, is non-public.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the Publicly-Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC website at http:/lwww.nrc.gov/readinq-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 73.22, a copy of this letter's enclosure will not be available for public inspection. In addition, the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response, if you choose to provide one, will not be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. lf Safeguards lnformation is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response, "Security-Related Information - Withhold Under 10 CFR 2.390," and follow the instructions for withholding in 10 CFR 2.391(bX1).
Sincerely,
/RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-336; 50-243 License Nos. DPR-65: NPF-49 Enclosure: As Described (CONTAINS (SGl))
cc w/encl: w/SGl:
J. Curling, Acting Security Department Manager F. Murray, President and CEO, NYSERDA, State of New York R. Frazier, New York State Office of Homeland Security E. Wilds, Jr., PH.D., State Liaison Officer, State of Connecticut cc w/o encl: w/o OUO-SRI: Distribution via ListServ SUNSI Review Complete: MMM (Reviewer's Initials)
DOCUMENT NAME: S:\Enf-allg\Enforcement\Proposed-Actions\Regionl\EA-10-214 Millstone Security (public ltr) FlNAL.docx qfterdeclaringthisdocument"AnOfficial AgencyRecord"thedocumentgllllgreleasedtothePublic. ADAMSAccessionNo.: ML110330330 r indicate in the box: "C" = Coov without "E" = CopV with =No MMcLaughlin/MMM'
RI/ DRS
'See Previous Concurrence Page
SAFECUARDS IN FERMNTION Distribution w/o encl: w/o SGI: (via email)
R Zimmerman, OE N Hilton, OE M Ashley, NRR W Dean, RA D Lew, DRA J Clifford, DRP D Roberts, DRP P Wilson, DRS L Doerflein, DRS D Jackson, DRP T Setzer, DRP D Dodson, DRP B Haagensen, DRP, Rl J Krafty, DRP, Rl D Holody, Rl M Mclaughlin, ORA A DeFrancisco, ORA C ODaniell, Rl K Farrar, Rl D Screnci/ N Sheehan, Rl Distribution w/encl: w/SGl S Kennedy, DRS S Shaffer, DRP, SRI D Caron, DRS J Cherubini, DRS S Coker, NSIR D Furst. OE SAFEGUNRDS I NFORMNTION