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Category:Inspection Report Correspondence
MONTHYEARIR 05000387/20164062016-09-14014 September 2016 Problem Identification and Resolution Security Inspection Report 05000387/2016406 and 05000388/2016406 (Cover Letter Only) PLA-7332, Response to Preliminary White Finding in NRC Inspection Report 05000387/2015503 and 05000388/20155032015-05-15015 May 2015 Response to Preliminary White Finding in NRC Inspection Report 05000387/2015503 and 05000388/2015503 ML0914702622009-05-27027 May 2009 IR 05000387-09-201, and IR 05000388-09-201, on 02/10/2009, for Susquehanna, Units 1 & 2, Physical Security Baseline Force on Force Inspection and Preliminary Greater than Green Finding IR 05000387/20074022007-11-19019 November 2007 IR 05000387-07-402, and IR 05000388-07-402, on 10/15/2007 - 10/19/2007, Susquehanna Steam Electric Station, Physical Protection ML0634604702006-12-11011 December 2006 NRC Office of Investigations Cases 1-2005-034, 1-2006-029, 1-2006-033 and 1-2006-037 IR 05000387/20040052005-01-28028 January 2005 IR 05000387-04-005, 05000388-04-005; 10/01/2004 - 12/31/2004; Susquehanna Steam Electric Station, Units 1 and 2; Equipment Alignments, Operability Evaluations, Access Control to Radiologically Significant Areas, and Radioactive Material Pro IR 05000387/20020042002-07-11011 July 2002 IR 05000387-02-004, IR 05000388-02-004, on 05/12-06/29/2002, PPL Susquehanna, LLC, Susquehanna Steam Electric Station, Units 1&2. Routine Integrated Report IR 05000387/20020032002-06-0505 June 2002 IR 05000387/2002-003, IR 05000388/2002-003; on 03/31-05/11/2002; PPL Susquehanna, LLC; Susquehanna Steam Electric Station; Units 1&2. Event Follow-up and Temporary Modifications. Non-cited Violations Identified IR 05000387/20010122002-02-28028 February 2002 IR 05000387/2001-012, IR 05000388/2001-012, on 12/01-02/09-2002; PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Units 1 & 2. Permanent Plant Modifications. Non-cited Violation Noted 2016-09-14
[Table view] Category:Letter
MONTHYEARIR 05000387/20250902025-01-27027 January 2025 EA-24-111 Susquehanna Final Significance Determination of White Finding with Assessment Follow-up and Notice of Violation; Inspection Report 05000387/2025090 and 05000388/2025090 ML25016A1992025-01-16016 January 2025 Supplement to Report for Missed Annual Inventory Required by 40 CFR 266, Subpart N and Request to Reclaim Conditional Exemption PLE-0026677 ML25013A0462025-01-13013 January 2025 Emergency Plan, Revision 68, PLA-8152 IR 05000387/20244012025-01-0606 January 2025 Security Baseline Inspection Report 05000387/2024401 and 05000388/2024401 (Cover Letter Only) PLA-8150, Independent Spent Fuel Storage - Installation Decommissioning Funding Plan Updated PLA-81502024-12-10010 December 2024 Independent Spent Fuel Storage - Installation Decommissioning Funding Plan Updated PLA-8150 IR 05000387/20244022024-12-0505 December 2024 Cyber Security Inspection Report 05000387/2024402 and 05000388/2024402 (Cover Letter Only) PLA-8153, Response to Preliminary White Finding and Apparent Violation Documented in NRC Inspection Report 2024012, EA-24-111 PLA-81532024-12-0404 December 2024 Response to Preliminary White Finding and Apparent Violation Documented in NRC Inspection Report 2024012, EA-24-111 PLA-8153 IR 05000387/20240122024-11-25025 November 2024 Follow-Up to Inspection Procedure 71111.12 Inspection Report 05000387/2024012 and 05000388/2024012 and Preliminary White Finding and Apparent Violation IR 05000387/20244202024-11-20020 November 2024 Security Baseline Inspection Report 05000387/2024420 and 05000388/2024420 Cover Letter IR 05000387/20245012024-11-13013 November 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2024501 and 05000388/2024501 IR 05000387/20240102024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000387/2024010 and 05000388/2024010 IR 05000387/20240032024-11-12012 November 2024 Integrated Inspection Report 05000387/2024003 and 05000388/2024003 PLA-8135, Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-81352024-11-0101 November 2024 Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135 ML24289A1252024-10-22022 October 2024 – Authorized Alternative to Requirements of the ASME OM Code PLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 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 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8098, Annual Financial Report (PLA-8098)2024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance 2025-01-06
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December 11, 2006 Mr. Britt T. McKinney Senior Vice-President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard - NUCSB3 Berwick, PA 18603-0467
Subject:
NRC Office of Investigations Cases 1-2005-034, 1-2006-029, 1-2006-033 and 1-2006-037
Dear Mr. McKinney:
On August 31, 2005, the Region I Field Office, NRC Office of Investigations (OI), initiated an investigation (Case No. 1-2005-034) to determine whether a Susquehanna Maintenance Department foreman knowingly directed untrained/unqualified workers to perform dry fuel storage (DFS) tasks associated with vacuum drying operations and transfer trailer movements during the July/August 2005 DFS campaign. OI also investigated whether the same foreman:
(1) knowingly directed and or pressured workers to sign off training equivalency determination records indicating that they had completed training when they had not; (2) fraudulently signed three specific training equivalency determinations records for a number of workers; (3) knowingly directed untrained/unqualified workers to stow/unstow the mast; (4) fraudulently signed off as having completed upgrade training for the Unit 2 overhead crane when he/she had not; and (5) deliberately operated the overhead crane in two directions at the same time and in a non-critical mode during the 2004 DFS campaign. Lastly, OI investigated whether Susquehanna employees deliberately provided incomplete and inaccurate information to an NRC inspector during an inspection of DFS activities.
Based on its investigation, OI found that there was insufficient evidence to conclude that the maintenance foreman engaged in any deliberate misconduct, or that any Susquehanna employee provided the NRC with incomplete or inaccurate information.
On April 10, April 19, and May 25, 2005, OI initiated three other investigations (Case Nos. 1-2006-029, 1-2006-033, and 1-2006-037) to determine whether three workers were discriminated against for engaging in NRC protected activity, specifically, for raising safety concerns regarding refuel floor activities. Testimonial and documentary evidence showed that the workers were transferred to a different work group based on legitimate business reasons. OI reviewed documents and received testimony indicating that Susquehanna management was concerned with the safety of the plant because of a lack of cooperation and communication amongst refuel floor employees (i.e., the fact that several individuals refused to work for, and interact with, the refueling floor foreman). Also, these changes to the work group were used as an initiative to train other employees to facilitate additional certifications.
CERTIFIED MAIL RETURN RECEIPT REQUESTED
Mr. Britt T. McKinney 2
In addition to questions regarding matters of alleged discrimination, as part Case No. 1-2006-034, OI questioned over twenty individuals (mostly mechanics/welders) regarding the safety conscious work environment (SCWE) at Susquehanna. OI determined that a great majority of the interviewees stated that they are willing to raise nuclear safety issues using the licensees processes. Additionally, a great majority of the individuals said they have written ARs/CRs and will continue to do so, and that management does not discourage them from being written or discourage the formal corrective action program from being used.
Additionally, as you are aware, an inspection team performed a Problem Identification and Resolution (PI&R) Inspection (Report 05000387/2006006 and 05000388/2006006) in February 2006. The inspection team assessed the SCWE at the site, including whether individuals were being discouraged in any way from raising safety concerns to their management or to the NRC through formal or informal processes. Specifically, the team interviewed station personnel to assess whether they were hesitant to raise safety concerns to their management and/or the NRC, due to a fear of retaliation. The team also reviewed Susquehannas Employee Concerns Program (ECP) to determine if employees were aware of the program and had used it to raise concerns. The team reviewed a sample of the ECP files to ensure that issues were entered into the corrective action program.
The inspection team determined that the plant staff were aware of the importance of having a strong SCWE and expressed a willingness to raise safety issues. No one interviewed had experienced retaliation for safety issues raised, or knew of anyone who had failed to raise issues. All persons interviewed had an adequate knowledge of the corrective action program and the ECP. Based on these limited interviews, the team concluded that there was no evidence of an unacceptable SCWE.
While the aforementioned OI investigations did not substantiate that discrimination occurred, and while another OI investigation and NRC inspection did not conclude that there was an unacceptable SCWE at Susquehanna, we feel that PPL should recognize, by way of the number of concerns raised and the feedback provided to OI, that negative perceptions exist among those performing refuel floor activities regarding the advisability of raising safety concerns to PPL management. The NRC is aware that PPL is currently assessing the SCWE at the site and we plan to review the results of your assessment. We believe that it is important that PPL maintain focus in this area to ensure a healthy work environment for all employees at Susquehanna, including those involved in refuel floor activities. In addition, the NRC plans to focus its inspection effort in the SCWE area during our biennial Problem Identification and Resolution Team and during our routine oversight activities at your site.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be 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). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/
adams.html (the Public Electronic Reading Room).
Mr. Britt T. McKinney 3
Please note that final NRC investigation documents, such as the OI reports described above, may be made available to the public under the Freedom of Information Act (FOIA) subject to redaction of information appropriate under the FOIA. Requests under the FOIA should be made in accordance with 10 CFR 9.23, Requests for Records, a copy of which is enclosed for your information.
Should you have any questions regarding this letter, please contact Mr. James Trapp of my staff at (610) 337-5186.
Sincerely,
/RA/
David C. Lew, Director Division of Reactor Projects
Enclosure:
10 CFR 9.23, Request for Records
Mr. Britt T. McKinney 4
Distribution:
C. Carpenter, OE R. Urban, SAC ADAMS (Docket Nos. 50-387 and 50-388)
D. Screnci, PAO Region I Docket Room (w/concurrences)
SUNSI Review Complete: JMT1 (Reviewers Initials)
DOCUMENT NAME: C:\\FileNet\\ML063460470.wpd After declaring this document An Official Agency Record it will/will not be released to the Public.
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE DRP:RPB4 RI:OI RI:RC ORA:SAC DRP:DD NAME JTrapp EWilson KFarrar RUrban DLew DATE 11/22/06 11/22/06 11/24/06 12/4/06 12/8 /06
Mr. Britt T. McKinney 5
OFFICIAL RECORD COPY