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| #REDIRECT [[IR 05000325/2011004]]
| | {{Adams |
| | | number = ML12326A721 |
| | | issue date = 11/20/2012 |
| | | title = IR 05000325-11-004, 05000325-11-004, on 12/14/2011 and 11/14/2011, Response to Disputed Non-Cited Violation - Brunswick Steam Electric Plant - NRC Integrated Inspection |
| | | author name = Croteau R P |
| | | author affiliation = NRC/RGN-II/DRP |
| | | addressee name = Annacone M |
| | | addressee affiliation = Carolina Power & Light Co |
| | | docket = 05000324, 05000325 |
| | | license number = DPR-062, DPR-071 |
| | | contact person = |
| | | document report number = IR-11-004 |
| | | document type = Inspection Report, Letter |
| | | page count = 9 |
| | }} |
| | See also: [[followed by::IR 05000325/2011004]] |
| | |
| | =Text= |
| | {{#Wiki_filter: |
| | [[Issue date::November 20, 2012]] |
| | |
| | Mr. Michael Annacone Vice President Carolina Power and Light Company Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461 |
| | |
| | SUBJECT: RESPONSE TO DISPUTED NON-CITED VIOLATION - BRUNSWICK STEAM ELECTRIC PLANT - NRC INTEGRATED INSPECTION REPORT NOS.: 05000325/2011004 AND 05000324/2011004 DATED NOVEMBER 14, 2011 |
| | |
| | ==Dear Mr. Annacone:== |
| | Thank you for your reply dated December 14, 2011, to the licensee identified violation (LIV) issued on November 14, 2011, concerning activities conducted at your facility. |
| | |
| | In your reply, you disputed the LIV, concerning Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, discussed in section 4OA7 of Integrated Inspection Report 05000325,324/2011004 based on the following: The incorrectly installed flow element did not render the reactor water clean-up (RWCU) Differential Flow - High instrumentation (Function 5.a of TS Table 3.3.6.1-1) inoperable. Operability of the RWCU Differential Flow- |
| | High instrumentation is dependent upon: meeting the TS required allowable value of equal to or less than 73 gallons per minutes (gpm); and the overall ability of the instrument loop to perform its intended safety function. The flow element installation error did not affect the transmitter or trip device and, as such, did not prevent the RWCU Differential Flow - High instrumentation to meet the TS allowable value of equal to or less than 73 gpm. The amount of uncertainty introduced by this condition was not sufficient to render the instrument loop incapable of performing its intended safety function (assuring that the 300 gpm analytical limit would not be exceeded). Therefore, a violation of TS 3.3.6.1 did not occur. |
| | |
| | After consideration of your reply, the Nuclear Regulatory Commission (NRC) has concluded that, for the reasons presented in the enclosure to this letter, the LIV occurred as stated in section 4OA7 of Integrated Inspection Report 05000325, 324/2011004 dated November 14, 2011. This matter was the subject of a Task Interface Agreement (TIA) dated November 9, 2012, which is an attachment to this letter. No additional written response is required from you at this time. We will review your corrective actions for this violation during routine baseline inspections. |
| | |
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document systems (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/readingrm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. |
| | |
| | Should you have any questions concerning this letter, please contact Mr. Randall A. Musser, at (404) 997-4603. |
| | |
| | Sincerely,/William Jones RA for/ |
| | Richard P. Croteau, Director Division of Reactor Projects Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62 |
| | |
| | ===Enclosure:=== |
| | Evaluation and Conclusion |
| | |
| | ===w/Attachment:=== |
| | Task Interface Agreement dated November 9, 2012. |
| | |
| | cc w/encl: (See page 3) |
| | }} |
Revision as of 04:20, 23 February 2018
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Category:Inspection Report
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[Table view] Category:Letter
MONTHYEARIR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. 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Engine Systems Inc and Brunswick ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) ML22230D0692022-08-22022 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident IR 05000324/20220022022-08-0505 August 2022 Integrated Inspection Report 05000324/2022002 and 05000325/2022002 IR 05000324/20220102022-06-27027 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000324 2022010 and 05000325 2022010 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 IR 05000324/20220012022-05-10010 May 2022 Integrated Inspection Report 05000324/2022001 and 05000325/2022001 ML22119A1352022-05-0909 May 2022 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000325/2022403; 05000324/2022403 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22102A0502022-04-11011 April 2022 301 Corporate Notification Letter IR 05000324/20224012022-03-16016 March 2022 Security Baseline Inspection Report 05000324/2022401 and 05000325/2022401 2024-08-05
[Table view] |
See also: IR 05000325/2011004
Text
November 20, 2012
Mr. Michael Annacone Vice President Carolina Power and Light Company Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461
SUBJECT: RESPONSE TO DISPUTED NON-CITED VIOLATION - BRUNSWICK STEAM ELECTRIC PLANT - NRC INTEGRATED INSPECTION REPORT NOS.: 05000325/2011004 AND 05000324/2011004 DATED NOVEMBER 14, 2011
Dear Mr. Annacone:
Thank you for your reply dated December 14, 2011, to the licensee identified violation (LIV) issued on November 14, 2011, concerning activities conducted at your facility.
In your reply, you disputed the LIV, concerning Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, discussed in section 4OA7 of Integrated Inspection Report 05000325,324/2011004 based on the following: The incorrectly installed flow element did not render the reactor water clean-up (RWCU) Differential Flow - High instrumentation (Function 5.a of TS Table 3.3.6.1-1) inoperable. Operability of the RWCU Differential Flow-
High instrumentation is dependent upon: meeting the TS required allowable value of equal to or less than 73 gallons per minutes (gpm); and the overall ability of the instrument loop to perform its intended safety function. The flow element installation error did not affect the transmitter or trip device and, as such, did not prevent the RWCU Differential Flow - High instrumentation to meet the TS allowable value of equal to or less than 73 gpm. The amount of uncertainty introduced by this condition was not sufficient to render the instrument loop incapable of performing its intended safety function (assuring that the 300 gpm analytical limit would not be exceeded). Therefore, a violation of TS 3.3.6.1 did not occur.
After consideration of your reply, the Nuclear Regulatory Commission (NRC) has concluded that, for the reasons presented in the enclosure to this letter, the LIV occurred as stated in section 4OA7 of Integrated Inspection Report 05000325, 324/2011004 dated November 14, 2011. This matter was the subject of a Task Interface Agreement (TIA) dated November 9, 2012, which is an attachment to this letter. No additional written response is required from you at this time. We will review your corrective actions for this violation during routine baseline inspections.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document systems (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/readingrm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction.
Should you have any questions concerning this letter, please contact Mr. Randall A. Musser, at (404) 997-4603.
Sincerely,/William Jones RA for/
Richard P. Croteau, Director Division of Reactor Projects Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62
Enclosure:
Evaluation and Conclusion
w/Attachment:
Task Interface Agreement dated November 9, 2012.
cc w/encl: (See page 3)