|
---|
Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 2024-02-02
[Table view] |
Text
December 2, 2007 Mr. Frank Barber
[HOME ADDRESS DELETED UNDER 10 CFR 2.390(A)]
Dear Mr. Barber,
I was very pleased to speak with you at the Braidwood Community Information Night on November 8, 2007, and in our subsequent telephone conversation on November 14, 2007. I understand your questions and concerns related to the tritium groundwater contamination at the Braidwood and Dresden nuclear plants, and I hope that our discussions were helpful in furthering your understanding of the issues and the NRCs response to the issues.
The purpose of this letter is to provide you with the additional information that you requested during our discussions.
Question: You indicated that about 40 people living near the Dresden nuclear plant were offered water testing for tritium. Only 19 or 20 requested the testing. You questioned: (1) How close were they located to the Dresden Plant? (2) What were the tritium levels that were measured? and (3) When were they sampled?
Answer: During our inspections at the Dresden station, we reviewed Exelons results. The Dresden staff or its contractor collected samples from 18 private wells located in the community immediately south of the plant and just west of the Kankakee River. One of these private wells is routinely sampled as part of the licensees Radiological Environmental Monitoring Program (REMP) required by the NRC.
Samples from the private wells were collected between November 2004 and September 2005, and were analyzed by the licensees contract laboratory. Samples were split with the Illinois Emergency Management Agency. Four of the 18 private wells showed concentrations of tritium above the contract laboratorys lower limit of detection of about 200 picocuries/liter (pCi/L).
Tritium concentrations in the four wells ranged from 368 to 830 pCi/L. The private well having the highest concentration of tritium was the well that is routinely sampled as part of the licensees REMP. The REMP required well is located approximately one-quarter mile west of the river while the other three private wells that showed positive results are located on/near the westerly bank of the Kankakee River. The tritium levels in the wells were well below the U.S.
Environmental Protection Agencys drinking water standard of 20,000 pCi/L and were well below NRC limits for dose to a member of the public. Consequently, we do not consider the levels to be a health or safety hazard.
F. Barber Question: How deep are the monitoring wells that are on the Dresden plant site?
Answer: Exelon provided to the NRC the results of its onsite monitoring program at Dresden in a report that was provided to the NRC in September of 2006. A copy of that report is available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room) (ADAMS Accession No. ML062760005). For your convenience, we have enclosed Table 4.1 from that report, which contains the specifications for a number of the onsite monitoring wells. Generally, the wells were screened at depths of 5 to 50 feet below ground surface, which represents the saturation zone closest to the surface. That zone contains the groundwater that is most likely to be affected by any leaks or spills that may originate from the facility.
Question: How deep are the test wells at the Braidwood nuclear plant?
Answer: During 2006, Exelon provided the NRC two documents that contained groundwater sampling results for the Braidwood nuclear plant. In March 2006, Exelon completed its groundwater characterization report that assessed the impact of leakage from the circulating water vacuum breaker valves. Additionally, Exelon provided the NRC the results of its onsite monitoring program at Braidwood in a report that was provided to the NRC in September of 2006. Copies of those reports are available electronically for public inspection in the NRC Public Document Room or from the PARS component of ADAMS (ADAMS Accession Nos.
ML062640270/062740279 and ML062760004, respectively). For your convenience, we have enclosed copies of Table 4.1 from both of the reports, which contain the specifications for a number of the monitoring wells. Generally, the wells were screened at depths of 2 to 100 feet below ground surface, which represents the saturation zone closest to the surface. That zone contains the groundwater that is most likely to be affected by any leaks or spills that originate from the facility.
We have also enclosed a copy of the 2006 Annual Radiological Environmental Operating Report for the Dresden nuclear plant that you requested during our discussions. That report contains the results of tritium measurements in water near the Dresden facility. In particular, Figures C-3, C-4, and C-5 provide trends of tritium measurements for surface and groundwater.
I hope that you find this information useful in your review of the issues at these two facilities. I assure you that the NRC is committed to ensuring that these facilities are operated safely and within NRC requirements.
F. Barber In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter with the address redacted will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
If you have any additional questions, please feel free to contact me at (630) 829-9827.
Sincerely,
/RA/
Steven K. Orth, Health Physics Program Manager Division of Reactor Safety
Enclosures:
- 1. Table 4.1 from Revision 1 to "Hydrogeologic Investigation Report, Fleetwide Assessment, Dresden Generating Station (ADAMS ML062760005)
- 2. Table 4.1 from Tritium Investigation Report, March 2006 (ADAMS ML062640270 and ML062640279)
- 3. Table 4.1 from Revision 1 to "Hydrogeologic Investigation Report, Fleetwide Assessment, Braidwood Generating Station (ADAMS ML062760004)
- 4. 2006 Annual Radiological Environmental Operating Report (ADAMS ML071380245, ML071380246, and ML071380248)
F. Barber In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter with the address redacted will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
If you have any additional questions, please feel free to contact me at (630) 829-9827.
Sincerely,
/RA/
Steven K. Orth, Health Physics Program Manager Division of Reactor Safety
Enclosures:
- 1. Table 4.1 from Revision 1 to "Hydrogeologic Investigation Report, Fleetwide Assessment, Dresden Generating Station (ADAMS ML062760005)
- 2. Table 4.1 from Tritium Investigation Report, March 2006 (ADAMS ML062640270 and ML062640279)
- 3. Table 4.1 from Revision 1 to "Hydrogeologic Investigation Report, Fleetwide Assessment, Braidwood Generating Station (ADAMS ML062760004)
- 4. 2006 Annual Radiological Environmental Operating Report (ADAMS ML071380245, ML071380246, and ML071380248)
DOCUMENT NAME:
G Publicly Available G Non-Publicly Available G Sensitive G Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME SOrth:jb VMitlyng ABoland DATE 12/02/07 11/28/07 11/30/07 OFFICIAL RECORD COPY