|
---|
Category:Inspection Report
MONTHYEARIR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation RA-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 IR 05000269/20234012023-04-14014 April 2023 Security Baseline Inspection Report 05000269 2023401 and 05000270 2023401 and 05000287 2023401 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 IR 05000269/20220052022-08-26026 August 2022 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 - NRC Inspection Report 05000269/2022005, 05000270/2022005, and 05000287/2022005 IR 05000269/20224012022-08-26026 August 2022 Material Control and Accounting Program Inspection Report 05000269/2022401 and 05000270/2022401 and 05000287/2022401 (OUO Removed) IR 05000270/20220022022-07-29029 July 2022 Integrated Inspection Report 05000269/ 2022002 and 05000270/2022002 and 05000287/2022002 IR 05000269/20220102022-06-30030 June 2022 Triennial Fire Protection Inspection Report 05000269/2022010 and 05000270/2022010 and 05000287/2022010 IR 05000269/20224032022-05-0404 May 2022 Security Baseline Target Set Inspection Report 05000269/2022403 and 05000270/2022403 and 05000287/2022403 IR 05000269/20220012022-05-0404 May 2022 Integrated Inspection Report 05000269/2022001, 05000270/2022001 and 05000287/2022001 IR 05000269/20224042022-04-27027 April 2022 Security Baseline Inspection Report 05000269/2022404 and 05000270/2022404 and 05000287/2022404 IR 05000269/20223012022-03-0707 March 2022 Notification of Licensed Operator Initial Examination 05000269/2022301, 05000270/2022301 and 05000287/2022301 IR 05000269/20210062022-03-0202 March 2022 Annual Assessment Letter for Oconee Nuclear Station, Units 1, 2, and 3 (Report 05000269/2021006, 05000270/2021006, and 05000287/2021006) IR 05000269/20220122022-02-24024 February 2022 Safety Conscious Work Environment Issue of Concern Followup Report 05000269/2022012 and 05000270/2022012 and 05000287/2022012 IR 05000269/20224022022-02-16016 February 2022 Security Baseline Inspection Report 05000269/2022402 and 05000270/2022402 and 05000287/2022402 IR 05000269/20210042022-02-14014 February 2022 Integrated Inspection Report 05000269/2021004 and 05000270/2021004 and 05000287/2021004 and Apparent Violation IR 05000269/20210032021-10-28028 October 2021 Integrated Inspection Report 05000269/2021003 and 05000270/2021003 and 05000287/2021003 IR 05000269/20210102021-09-17017 September 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000269/2021010 and 05000270/2021010 and 05000287/2021010 IR 07200004/20210012021-08-26026 August 2021 Operation of an Independent Spent Fuel Storage Installation Report 07200004/2021001 IR 05000269/20210052021-08-26026 August 2021 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2, and 3 (NRC Inspection Report 05000269/2021005, 05000270/2021005, and 05000287/2021005) IR 05000269/20210022021-08-0404 August 2021 Integrated Inspection Report 05000269/2021002 and 05000270/2021002 and 05000287/2021002 IR 05000269/20213012021-07-0606 July 2021 NRC Operator License Examination Report 05000269/2021301, 05000270/2021301, and 05000287/2021301 IR 05000269/20210112021-06-0202 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000269/2021011 and 05000270/2021011 and 05000287/2021011 IR 05000269/20210012021-04-23023 April 2021 Integrated Inspection Report 05000269/2021001 and 05000270/2021001 and 05000287/2021001 IR 05000269/20214012021-04-22022 April 2021 Security Baseline Inspection Report 05000269/2021401, 05000270/2021401 and 05000287/2021401 (U) IR 05000269/20200062021-03-0303 March 2021 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2, & 3 NRC Inspection Report 05000269/2020006, 05000270/2020006, & 05000287/2020006 IR 05000269/20200042021-02-22022 February 2021 Reissue- Oconee Nuclear Station Integrated Inspection Report 05000269/2020004, 05000270/2020004, 05000287/2020004 ML21036A0012021-02-0404 February 2021 Integrated Inspection Report 05000269/2020004 and 05000270/2020004 and 05000287/2020004 IR 05000269/20200102021-01-22022 January 2021 NRC Design Bases Assurance Inspection (Team) Report 05000269/2020010 and 05000270/2020010 and 05000287/2020010 and Notice of Violation IR 05000269/20204012020-11-13013 November 2020 Security Baseline Inspection Report 05000269/2020401 and 05000270/2020401 and 05000287/2020401 IR 05000269/20200032020-11-0404 November 2020 Integrated Inspection Report 05000269/2020003, 05000270/2020003, 05000287/2020003, and 07200004/2020002 IR 05000269/20204202020-10-15015 October 2020 Security Inspection Report 05000269/2020420, 05000270/2020420 and 05000287/2020420 IR 05000269/20200052020-08-17017 August 2020 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2, and 3 (NRC Inspection Report 05000269/2020005, 05000270/2020005, and 05000287/2020005) IR 05000269/20200022020-08-11011 August 2020 Integrated Inspection Report 05000269/2020002 and 05000270/2020002 and 05000287/2020002 ML20192A3212020-07-13013 July 2020 Review of the Fall 2019 Steam Generator Tube Inspection Report 2024-08-08
[Table view] Category:Letter
MONTHYEARIR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test 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 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 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 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application 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 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program 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 ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections 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 2024-08-08
[Table view] |
Inspection Report - Oconee - 2011016 |
---|
|
|
|
Text
UNITED STATES une 23, 2011
SUBJECT:
OCONEE NUCLEAR STATION - NRC INSPECTION REPORT 05000269/2011016, 05000270/2011016 AND 05000287/2011016
Dear Mr. Gillespie:
On May 19, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of your Oconee Nuclear Station Units 1, 2 and 3. The enclosed inspection report documents the inspection results which were discussed on May 23, 2011, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations, and with the conditions of your license. The inspectors reviewed selected procedures and records.
The report documents one NRC-identified finding of very low safety significance (Green). This finding was determined to involve a violation of NRC requirements. However, because of the very low safety significance and because it is entered into your corrective action program, the NRC is treating the violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the NRCs Enforcement Policy. If you contest the NCV, you should provide a response within 30 days of the date of this inspection report with the basis for your denial to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region 2; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 2055-0001; and the NRC Resident Inspector at Oconee Nuclear Station. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report with the basis for your disagreement, to the Regional Administrator, Region 2, and the NRC Resident Inspector at Oconee Nuclear Station.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the
DPC 2 NRC Public Document Room of from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos.: 50-269, 50-270, 50-287 License Nos: DPR-38, DPR-47, DPR-55
Enclosure:
Inspection Report 05000269/2011016, 05000270/2011016 and 05000287/2011016
REGION II==
Docket Nos: 05000269, 05000270, and 05000287 License Nos: DPR-38, DPR-47, DPR-55 Report Nos: 05000269/2011016, 05000270/2011016, and 05000287/2011016 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Units 1, 2, and 3 Location: Seneca, SC 29672 Dates: March 15, 2011, through May 19, 2011 Inspectors: R. Hamilton, Sr. Health Physicist (Section 2RS6)
Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000269/2011016, 05000270/2011016 and 05000287/2011016; 03/15/2011 - 05/19/2011;
Oconee Nuclear Station Units 1, 2, and 3; Radioactive Gaseous and Liquid Effluent Treatment The report covers the inspection and closure of an Unresolved Item. One non-cited violation was identified. The significance of most findings is identified by their color (Green, White,
Yellow, Red) using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP); the cross-cutting aspect was determined using IMC 0310, Components Within the Cross-Cutting Areas. Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process Revision 4, dated December 2006.
Cornerstone: Mitigating Systems
- Green: An NRC-identified Non-Cited Violation (NCV) of Technical Specification 5.4.1.d, for failure to follow procedures NSD 513, Primary to Secondary Leak Monitoring Program, and OP/0/A/1106/031, Primary to Secondary Leak Rate Monitoring and Instrumentation, which required compensatory actions and compensatory sampling during certain times when RIA-40 (Condenser Off-Gas Radiation Monitor) was out of service. This violation was entered into the licensees corrective action program under PIP O-10-06151.
The failure to recognize that the condenser off-gas radiation monitors were inoperable was a performance deficiency. This performance deficiency is more than minor because it was associated with the equipment performance attribute of the Mitigating Systems Cornerstone, and adversely affected the cornerstone objective in that the capability to detect, quantify, and respond to primary to secondary leakage was degraded. The inspectors evaluated the significance of this finding using inspection Manual Chapter 0609.04, Phase 1-Initial Screening and Characterization of Findings, and determined this finding was of very low safety significance (Green) because the finding did not result in a loss of safety function.
This finding had a cross-cutting aspect in the area of Problem Identification and Resolution under the Corrective Action Program component because the licensee failed to recognize that 1, 2 RIA-40 were inoperable, and to take appropriate corrective actions to address the issue in a comprehensive manner commensurate with its safety significance and complexity
[P.1 (d)] (Section 2RS6).
REPORT DETAILS
RADIATION SAFETY
Cornerstone: Mitigating Systems
2RS6 Radioactive Gaseous and Liquid Effluent Treatment
(Closed) Unresolved Item (URI) 05000269, 270 and 287/2010004-2 Potential Inoperability of Condenser Off-Gas Radiation Monitors
a. Inspection Scope
As documented in NRC IR 2010004, the inspectors identified a potential inoperability of 1 and 2 RIA-40, Condenser Off-Gas Radiation Monitors, in that the flow indicator sight glass downstream and physically above each of the monitors detector chambers contained water. The inspectors opened an Unresolved Item for this issue pending the licensees evaluation of the basis for operability of these detectors, and the ability of the monitors to adequately respond to a primary to secondary leaks. This inspection was conducted to evaluate the results of the licensees evaluation and other pertinent licensee documentation.
b. Findings
Introduction:
An NRC-identified Green NCV of Technical Specification 5.4.1.d, was identified for the failure to follow procedures NSD 513, Primary to Secondary Leak Monitoring Program, and OP/0/A/1106/031, Primary to Secondary Leak Rate Monitoring and Instrumentation, which required compensatory actions and compensatory sampling during certain times when RIA-40 (Condenser Off-Gas Radiation Monitor) was out of service.
Description:
The licensee performed an operability evaluation of 1, 2 RIA-40, and determined both monitors to be inoperable due to water intrusion into the detector chambers. The licensee previously identified the accumulation of water in the monitors shortly after they were installed in the 1990s. At that time, the licensees corrective actions included the installation of moisture separators in the piping upstream of the radiation monitors and periodic draining of the rotameter sight glasses; however, operability of the radiation monitors was not evaluated. The licensee did not recognize the inoperability of the monitors even though the detectors required replacing at a much higher frequency than expected due to water in the detection chamber damaging the Mylar window. The presence of water in the detection chamber was a clear indication that the monitor was inoperable because it shielded the beta radiation detector, reduced the measuring chamber gas volume, and invalidated quantitative measurements.
The condenser off-gas monitors 1 and 2 RIA-40 perform two major functions:
- (1) they are the primary means of detection and quantification of a primary- to- secondary leak; and
- (2) they are effluent gas monitors. The plant was allowed to continue operation with RIA-40 inoperable due to other monitors (Nitrogen-16 monitors RIA-59 and RIA-60)being credited as providing redundancy for primary to secondary leakage detection, and the unit vent noble gas monitor (RIA-45) providing the effluent monitoring redundancy.
Licensee procedures provided for compensatory sampling when the redundant monitors were also inoperable. With RIA-40 being in an inoperable condition, the monitors functions were not consistently met because the required compensatory actions were not performed. OP/0/A/1106/031, Primary to Secondary Leak Rate Monitoring and Instrumentation, step 2.1, required the completion of Attachment 4.8, which evaluated compensatory monitoring requirements. This included immediately and then periodically sampling the condenser off-gas and primary coolant due to not having an operable continuous radiation monitor capable of detecting >30 gallons per day, primary to secondary leakage whenever RIA-40, and RIA-59 or RIA-60 were out of service; and increased surveillance and sampling below 40 percent RTP because RIA-59 and 60 were only operable above 40 percent RTP. The compensatory monitoring evaluation also addressed the concurrent operability of RIA-45, RIA-59 or RIA-60.
Analysis:
The failure to recognize that the condenser off-gas radiation monitors were inoperable due to the presence of water in the monitors detection chamber was a performance deficiency. This performance deficiency was more than minor because it is associated with the Equipment Performance attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective in that the capability to detect, quantify, and respond to primary to secondary leakage was degraded. The significance of the finding was evaluated using inspection Manual Chapter 0609.04, and determined to be of very low safety significance (Green) because there was not a loss of safety function.
The inspectors determined that this performance deficiency had a cross-cutting aspect in the area of Problem Identification and Resolution under the Corrective Action Program component because the licensee failed to recognize that 1 and 2 RIA-40 were inoperable, and to take appropriate corrective actions to address the issue in a comprehensive manner commensurate with its safety significance and complexity
P.1(d).
Enforcement:
Technical Specification 5.4.1.d required, that written procedures shall be established, implemented, and maintained covering various defined activities to include the programs defined in Technical Specification 5.5. Technical Specification 5.5.10.e, established the requirement that the Steam Generator (SG) Program had provisions for monitoring operational primary to secondary leakage. Procedure NSD-513, Primary to Secondary Leakage Monitoring Program, Section 4.1.1, No Available Continuous Radiation Monitor, required compensatory sampling at all times, when a unit is below 40% power and 1 and 2 RIA-40 are inoperable, and at any time when RIA-40, and either RIA-59 or RIA-60 are inoperable. Procedure OP/0/A/1106/031, Primary to Secondary Leak Rate Monitoring and Instrumentation, step 2.1, directs the performance of attachment 4.8 which evaluates compensatory sampling requirements with RIA-40 inoperable.
Contrary to the above, with 1 and 2 RIA-40 in an inoperable condition following their installation in the 1990s, compensatory sampling requirements were not evaluated, and compensatory sampling to meet primary to secondary leak monitoring requirements was not performed. Because this violation was of very low safety significance and was entered into the licensees corrective action program under PIP O-10-06151, this violation is being treated as a non-cited violation in accordance with the NRCs Enforcement Policy: NCV 0500-0269/270/2011016-1 Failure to take required compensatory actions for 1 and 2 RIA-40 condenser off-gas radiation monitor inoperability.
4OA6 Management Meetings (Including Exit Meeting)
Exit Meeting Summary
The inspector presented the inspection results to Mr. Preston Gillespie, and other members of licensee management on May 23, 2011. The licensee acknowledged the findings presented. The inspector stated that there had been no proprietary documents provided by the licensee. The inspector identified that a proprietary EPRI document was reviewed that was not procured from the licensee.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY PERSONNEL
Licensee
P. Gillespie Site VP
T. Ray Engineering Manager
T. Patterson Safety Assurance Manager
D. Robinson RP Manager
K. Alter Regulatory Compliance Manager
E. Lampe RP Supervising Scientist
J. Smith Regulatory Compliance Licensee Admin
NRC
A. Sabisch Sr. Resident Inspector -Oconee Nuclear Station
G. Ottenberg Resident Inspector- Oconee Nuclear Station
LIST OF REPORT ITEMS
Opened and Closed
05000269 and 270/2011016-1 NCV Failure to take required compensatory
actions for 1 and 2 RIA-40 condenser off-
gas radiation monitor inoperability
Closed
05000269, 270, and 287/2010004-2 URI Potential inoperability of condenser off gas
radiation monitors
List of Documents Reviewed
2RS6 Radioactive Gaseous and Liquid Effluent Treatment
(Closed) Unresolved Item (URI) 05000269, 270 and 287/2010004-2 Potential
Inoperability of Condenser Off-Gas Radiation Monitors
Procedures
Nuclear Station Directive 513, Primary-to-Secondary Leak Monitoring Program,
Rev. 5, - Section 513.4.1.1 No Available Continuous Radiation Monitor
OP/0/A/1106/031, Primary to Secondary Leak Rate Monitoring and Instrumentation,
Rev. 105
AP/1/A/1700/031, Primary to Secondary Leakage, Rev. 17
CP/0/B/3002/023, Primary to Secondary Leak Rate Monitoring and Response, Rev. 6
Corrective Action Documents
PIP O-10-06151, The NRC has issued an Unresolved Issue (URI) to ONS due to the
condensation visible in the rotameters for 1RIA-40 and 2RIA40.
Other Documents
Oconee Nuclear Station Consolidated NRC Inspection Report 2010-04, Section 2RS6
Oconee Nuclear Station Selected Licensee Commitments (SLC) 16.11.3, Rev. 12/10/07
NEI 97-06 Steam Generator Program Guidelines, Rev. 2
EPRI PWR Primary-to-Secondary Leak Guidelines, Rev. 3
Oconee Nuclear Station Technical Specification 3.4.13, "RCS Operational Leakage"
Attachment