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Category:Letter
MONTHYEARIR 05000324/20253012024-10-17017 October 2024 Notification of Licensed Operator Initial Examination 05000325/2025301 and 05000324/2025301 IR 05000324/20244012024-10-15015 October 2024 Security Baseline Inspection Report 05000324/2024401 and 05000325/2024401 ML24297A6262024-10-11011 October 2024 PCA Letter to NRC Brunswick Potential Tropical Storm Eight IR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 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. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 05000325/LER-2024-002, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-10010 April 2024 Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 – Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20243012023-07-25025 July 2023 – Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 05000324/LER-2023-001, Two Main Steam Line Safety Relief Valves Inoperable2023-07-17017 July 2023 Two Main Steam Line Safety Relief Valves Inoperable 05000325/LER-2023-001, Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram2023-06-15015 June 2023 Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material 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 2024-09-04
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML23297A0262023-11-27027 November 2023 – Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 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 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 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 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 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 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21343A2002021-12-20020 December 2021 Authorization and Safety Evaluation for Alternative from Certain Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code of Buried Service Water Piping (EPID L-2021-LLR-0014) (Non-Proprieta ML21281A1382021-12-14014 December 2021 Issuance of Amendment Nos. 306 and 334 to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21067A2242021-04-30030 April 2021 Issuance of Amendment Nos. 305 and 333 to Revise License Conditions to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20309A7842021-03-18018 March 2021 Issuance of Amendment Nos. 304 and 332 Revise Technical Specification 3.4.7 and 3.4.8 to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20253A3212021-01-26026 January 2021 Issuance of Amendment Nos. 302 and 330 Revise Technical Specification 3.6.3.1 to Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20310A4102020-12-18018 December 2020 Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20269A3052020-09-29029 September 2020 Issuance of Amendment Nos. 301 and 329 to Revise Technical Specifications to Adopt TSTF-564 (EPID L-2020-LLA-0043) (Non-Proprietary) ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20073F1862020-03-0606 March 2020 Issuance of Amendment Nos. 299 and 327 to Revise Technical Specification 5.6.5b to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2018-LLA-0273) (Redacted) ML19346C7922020-02-0606 February 2020 Issuance of Amendments Nos. 298 and 326 to Modify Technical Specification to Extend Containment Leakage Test Intervals ML19316B0572020-01-0808 January 2020 Issuance of Amendment Nos. 297 and 325 to Modify Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.11 Safety Relief Valves ML19284C8332019-11-21021 November 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19281A3302019-11-21021 November 2019 Issuance of Amendment Nos. 296 and 324 to Adopt Technical Specification Task Force Traveler TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification ML19268A0542019-10-31031 October 2019 Units 1 and 2 - Issuance of Amendment Nos. 295 and 323 to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML19254E0762019-10-25025 October 2019 Issuance of Amendment Nos. 294 and 322 to Revise Technical Specification 3.7.4 for Control Room Air Conditioning Subsystems ML19233A0732019-09-23023 September 2019 Issuance of Amendment Nos. 293 and 321 to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19149A4712019-09-17017 September 2019 Issuance of Amendment Nos. 292 and 320, Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19018A2062019-05-0606 May 2019 Issuance of Amendment Nos. 290 and 318 to Revise Note on Brunswick TS 3.8.3 for One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML19035A0062019-04-22022 April 2019 Issuance of Amendment Nos. 289 and 317 to Relocate the Pressure-Temperature Limits in the Technical Specifications to the Pressure-Temperature Limits Report ML18291B3222019-01-0909 January 2019 Issuance of Amendment Nos. 288 and 316 to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 ML18264A2602019-01-0707 January 2019 Issuance of Amendment Nos. 287 and 315 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML18243A2982018-09-27027 September 2018 Issuance of Amendment to Modify DC Sources Technical Specification Surveillance Requirement 3.8.4.5 ML18172A2582018-09-18018 September 2018 Non-Proprietary, Issuance of Amendment Regarding Core Flow Operating Range Expansion (Mellla+) ML18197A4302018-08-0909 August 2018 Relief Request ISI-10 to Regarding Alternate Repair of Feedwater Nozzle Dissimilar Metal Welds ML18106B1692018-07-0606 July 2018 Issuance of Amendment Nos. 284 and 312 Regarding Request to Allow Performance-Based Fire Protection Alternative for Thermal Insulation Material ML18124A3052018-05-0909 May 2018 Alternative for ISI-09 Regarding Reactor Pressure Vessel Shell Welds Fourth Ten-Year Inservice Inspection Interval ML18122A2032018-05-0707 May 2018 Relief from the Requirements of the ASME Code, Section XI, ISI-11 Regarding System Leakage Test of Class 1 Piping ML18117A1912018-05-0404 May 2018 Proposed Alternative to Defer Inspection of Reactor Vessel Instrumentation Nozzle 2B11-RPV-N11B Until the First Period in the 5th 10-Year ISI Interval ML18039A4442018-04-13013 April 2018 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control Revision 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads 2024-07-12
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Text
March 15, 2002 Mr. J. S. Keenan Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 - REQUEST FOR RELIEF FROM ASME CODE REPAIR REQUIREMENTS FOR ASME CLASS 3 SERVICE WATER SYSTEM PIPING (TAC NO. MB3498)
Dear Mr. Keenan:
In a letter dated November 28, 2001, as supplemented January 18, 2002, Carolina Power &
Light Company (CP&L) requested relief from American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the Brunswick Steam Electric Plant, Unit 2. Specifically, CP&L requested relief from the requirements of subparagraph IWA-4000(a) regarding the repair of a through-wall leak identified on Service Water System line 2-SW-103-24-157. The request for relief was requested according to the guidance in Generic Letter (GL) 90-05. Based on the enclosed Safety Evaluation, the Nuclear Regulatory Commission (NRC) finds the requested relief acceptable.
The following regulatory commitments were made in CP&Ls November 28, 2001, letter.
Commitment Committed date or outage
- 1. Assess the integrity of the defect area located on Service At least once every three Water System line number 2-SW-103-24-157 between months until completion valves 2-SW-V104 and 2-SW-V105, in accordance with of a code repair.
NRC GL 90-05, using a examination technique.
- 2. Perform a qualitative assessment of leakage through the At least once every week defect located on line number 2-SW-103-24-157 between until completion of a code valves 2-SW-SW104 and 2-SW-V105, to identify any repair.
degradation of structural integrity.
- 3. Perform a repair, in accordance with the ASME B&PV Next scheduled outage Code Section XI, of the defect area on line number exceeding 30 days 2-SW-103-24-157 between valves 2-SW-SW104 and duration, but no later than 2-SW-V105. Refueling Outage 15.
If you have any questions, please contact Allen Hansen at 301-415-1390.
Sincerely,
/RA/
Richard P. Correia, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-324
Enclosure:
Safety Evaluation cc w/enclosure: See next page
ML020740605 OFFICE PD-II/PM PD-II/LA OGC(NLO) PD-II/SC NAME JGoshen for EDunnington RHoefling RCorreia AHansen DATE 02/28/02 02/28/02 03/06/02 03/06/02 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM ASME CODE REPAIR REQUIREMENTS FOR ASME CODE CLASS 3 PIPING SERVICE WATER SYSTEM LINE 2-SW-103-24-157 BRUNSWICK UNIT NO. 2 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324
1.0 INTRODUCTION
By letter dated November 28, 2001, as supplemented January 18, 2002, Carolina Power &
Light Company (CP&L, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the Code),Section XI requirements regarding repair to a leak in a Class 3, moderate energy pipe at Brunswick Steam Electric Plant (BSEP), Unit 2. The leak was detected in a 24-inch nominal pipe size service water (SW) system line 2-SW-103-24-157, which provides suction supply to booster pumps for supplying cooling water to residual heat removal (RHR) heat exchangers. The SW system has a design temperature of 105-F and pressure of 150 psig. The pipe material is carbon steel, and the nominal wall thickness of the pipe is 0.375 inch.
An ultrasonic (UT) examination at the leak location revealed that the flaw is a through-wall pinhole about 0.2 inch surrounded by a degraded area approximately 1.0 inches in diameter and 0.12 inch in thickness (tmin). The licensee currently attributed the leak to a local failure of the cement liner on the inside of the pipe that has allowed salt water to come into contact with the carbon steel pipe.
Although the flaw can be isolated, the Code repair cannot be completed with the applicable limiting condition for operation action statement completion time. Therefore, the licensee considered the on-line repair of the SW piping not practical.
Based upon the above, the licensee submitted a relief request in accordance with the provisions of Nuclear Regulatory Commission (NRC) Generic Letter (GL) 90-05, "Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping. The licensee requests relief until a Code repair can be performed during the next refueling outage scheduled to begin in March 2003.
2.0 DISCUSSION AND EVALUATION Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g), requires nuclear power facility piping and components to meet the applicable requirements of Section XI of the Code. This section of the Code specifies Code-acceptable repair methods for flaws that exceed Code acceptance limits in piping that is in service. A Code repair is required to restore the structural integrity of flawed Code piping, independent of the operational mode of the plant when the flaw is detected. Those repairs not in compliance with Section XI of the Code are non-Code repairs.
In some circumstances, the required Code repair may be impractical unless the facility is shut down. In such cases, the NRC may evaluate determinations of impracticality and may grant relief and impose alternative requirements pursuant to 10 CFR 50.55a(g)(6)(i). GL 90-05 provides guidance to the staff for evaluating relief requests submitted by licensees for temporary non-Code repairs to Code class 3 piping.
On November 7, 1991, the NRC issued GL 91-18, "Information to Licensees Regarding two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability." This GL and NRC Inspection Manual Part 9900 provided detailed discussions of specific operability determinations, one of which was operational leakage. In this regard, Section 6.15 of Part 9900 states the following:
"Upon discovery of leakage from a Class 1, 2, or 3 component pressure wall (i.e., pipe wall, valve body, pump casing, etc.) the licensee should declare the component inoperable. The only exception is Class 3 moderate energy piping as discussed in Generic Letter 90-05. For Class 3 moderate energy piping, the licensee may treat the system containing the through-wall flaw(s), evaluated and found to meet the acceptance criteria in Generic Letter 90-05, as operable until relief is obtained from the NRC."
The licensee has evaluated the flaw in accordance with GL 90-05. The licensee has used the "through-wall flaw" approach of the GL for the pinhole area of the SW pipe. The flaw is assumed to be 1.0 inch long, and the pipe wall is assumed conservatively to be 0.12 inch based on the UT data. The applied stress intensity factor due to the combination of deadweight, pressure, thermal expansion, and seismic loading was calculated to be 30.09 ksi/in. The fracture toughness was 35 ksi/in, the suggested value for ferric steel in GL 90-05. Since the applied stress intensity factor is less than the fracture toughness, the licensee concluded that the structural integrity of the SW system is adequate for continued operation of the unit until the next refueling outage scheduled to begin in March 2003. The staff has reviewed the licensees evaluation and confirmed that it is in accordance with GL 90-05 and satisfies the requirements of GL 90-05. Hence, the staff agrees with the licensees conclusion that the SW system is adequate for continued operation of the unit until the next refueling outage. A soft patch was installed over the hole using metal bands to stop the leakage from the SW pipe pinhole for housekeeping purposes. Further, the issues of flooding, water spraying on other equipment, and loss of flow were analyzed and found to be insignificant to the operation of the SW system.
The licensee has also performed an augmented UT inspection on five locations on SW piping having similar characteristics to the flawed line. This inspection did not reveal any other degraded areas. To monitor this non-Code repair, the licensee proposed to assess the integrity
of the degraded area using a non-destructive examination technique once every 3 months, and perform a qualitative assessment of leakage through the pinhole once every week in accordance with GL 90-05. The staff finds these commitments acceptable.
3.0 CONCLUSION
The staff has reviewed the licensee's request for relief and finds that the licensees analytical methods and results meet the requirements of GL 90-05. Further, the staff finds that performing a Code repair on the leaking SW system piping while the unit is operating is impractical. The staff concludes that the granting of relief where Code requirements are impractical and imposing alternative requirements is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest, given due consideration to the burden upon the licensee and facility that could result if the Code requirements were imposed on the facility. Pursuant to 10 CFR 50.55a(g)(6)(i) and consistent with the guidance in GL 90-05, relief is granted through the next refueling outage scheduled to start in March 2003.
Principle contributor: Simon Sheng Date: March 15, 2002
Mr. J. S. Keenan Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:
Mr. William D. Johnson Ms. Margaret A. Force Vice President and Corporate Secretary Assistant Attorney General Carolina Power & Light Company State of North Carolina Post Office Box 1551 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Donald E. Warren Mr. Robert P. Gruber Brunswick County Board of Commissioners Executive Director Post Office Box 249 Public Staff - NCUC Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Resident Inspector U.S. Nuclear Regulatory Commission Mr. C. J. Gannon 8470 River Road Director - Site Operations Southport, North Carolina 28461 Carolina Power & Light Company Brunswick Steam Electric Plant Mr. John H. ONeill, Jr. Post Office Box 10429 Shaw, Pittman, Potts & Trowbridge Southport, North Carolina 28461 2300 N Street, NW.
Washington, DC 20037-1128 Mr. Norman R. Holden, Mayor City of Southport Mr. Mel Fry, Director 201 East Moore Street Division of Radiation Protection Southport, North Carolina 28461 N.C. Department of Environment and Natural Resources Mr. Dan E. Summers 3825 Barrett Dr. Emergency Management Coordinator Raleigh, North Carolina 27609-7721 New Hanover County Department of Emergency Management Mr. W. C. Noll Post Office Box 1525 Plant Manager Wilmington, North Carolina 28402 Carolina Power & Light Company Brunswick Steam Electric Plant Mr. Terry C. Morton Post Office Box 10429 Manager Southport, North Carolina 28461 Performance Evaluation and Regulatory Affairs CPB 7 Public Service Commission Carolina Power & Light Company State of South Carolina Post Office Box 1551 Post Office Drawer 11649 Raleigh, North Carolina 27602-1551 Columbia, South Carolina 29211 Mr. Leonard R. Beller Manager - Regulatory Affairs Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10429 Southport, NC 28461