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| {{#Wiki_filter:'g'-\alle.0\receipt\200301 1 Orcv.wpd Allegation Receipt Report Date Received: | | {{#Wiki_filter:'g'-\alle.0\receipt\200301 1Orcv.wpd Allegation Receipt Report Date Received: September 3-4, 2003 Allegation No. RI-2003-A-0110 Received via: (X] Telephone [X] Facsimile [X] E-Mail Employee Receiving Allegation: JohnsonNito Source of information: [X] former contractor A leger Name: DL 'arvn Ph.D Home Address: _ |
| September 3-4, 2003 Allegation No. RI-2003-A-0110 Received via: (X] Telephone | | Cell Phone: . City/State/Zip: |
| [X] Facsimile | | E..Mail Address: *W V. |
| [X] E-Mail Employee Receiving Allegation: | | [Individual currently in South Carolina at Oconee until 915103 when she will move back to her home address in NJ on 9/12/03.] |
| JohnsonNito Source of information: | | Alleger's Employer: PSEG (private contractor) Alleger's Title: Manager, Culture Transformttion Facility: Salem/Hope Creek Docket Nos. 50-272, 311, 354 Was alleger informed of NRC identity protection policy? Yes If H&I was alleged, was alleger informed of DOL rights? Yes (Filing a Civil Suit - has attorney - |
| [X] former contractor A leger Name: DL 'arvn Ph.D Home Address: _Cell Phone: .City/State/Zip: | | not interested in filing wlDOL) |
| E..Mail Address: V.[Individual currently in South Carolina at Oconee until 915103 when she will move back to her home address in NJ on 9/12/03.]Alleger's Employer: | | If a licensee employee or contractor, cid they raise the issue to their management? Yes Does the alleger object to referral of issues to the licensee? No Provide alleger's direct response to this question verbatim on the line below: |
| PSEG (private contractor) | | No objection to NRC requesting a written response from PSEG on this matter as part of the review. (from 914/03 telecon w/SAC) |
| Alleger's Title: Manager, Culture Transformttion Facility: | | Was confidentiality requested? . No Was confidentiality initially granted? No Criteria for determining whether the issue is an allegation: |
| Salem/Hope Creek Docket Nos. 50-272, 311, 354 Was alleger informed of NRC identity protection policy?If H&I was alleged, was alleger informed of DOL rights?Yes Yes (Filing a Civil Suit -has attorney -not interested in filing wlDOL)If a licensee employee or contractor, cid they raise the issue to their management? | | Is it a declaration, statement, or assertion of impropriety or inadequacy? Yes Is ":he impropriety or inadequacy associated with NRC regulated activities? Yes (0 Is t:he validity of the issue unknown? Yes Allegation Summary: .. |
| Yes Does the alleger object to referral of issues to the licensee? | | : 1. Alleger indicated that there are significant problems with the Safety Conscious Work Environment (SCWE) at Salem/Hope Creek. Alleger's position (Manager, Culture Transformation) has afforded]ei ,c access to high level management at PSEG (up to and including the Chairman of the Board). Alleger indicated that the focus of these higher level managers has been production over safety, and that her efforts to raise work environment concerns to them have not been received positively (see specific information in Detailed Description of Allegation below). |
| No Provide alleger's direct response to this question verbatim on the line below: No objection to NRC requesting a written response from PSEG on this matter as part of the review. (from 914/03 telecon w/SAC)Was confidentiality requested? | | : 2. Discrimination - alleger's employment was terminated after rae in s about the work |
| .No Was confidentiality initially granted? No Criteria for determining whether the issue is an allegation: | | ,environment forrais ae,,y issues at Artificial Island to th nd subsequently to the |
| Is it a declaration, statement, or assertion of impropriety or inadequacy? | | .,*_* P%subsequent ECP investigation was conducted, which concluded that the alleger was not discriminated against, but rather that the alleger's position was eliminated. Alleger was employed as contractor for five years. |
| Is ":he impropriety or inadequacy associated with NRC regulated activities? | | 3. |
| Is t:he validity of the issue unknown?Yes Yes Yes (0 Allegation Summary: ..1. Alleger indicated that there are significant problems with the Safety Conscious Work Environment (SCWE) at Salem/Hope Creek. Alleger's position (Manager, Culture Transformation) has afforded]ei ,c access to high level management at PSEG (up to and including the Chairman of the Board). Alleger indicated that the focus of these higher level managers has been production over safety, and that her efforts to raise work environment concerns to them have not been received positively (see specific information in Detailed Description of Allegation below).2. Discrimination | | Functional Area: [X] Power Reactor Dis.zipline for each concern: [1] Other: SCWE [2] Discrimination [3] Wrongdoing WIHWIL,.L Detailed Description of Allegation:* PAC ~E4OF.~PAGE(&) |
| -alleger's employment was terminated after rae in s about the work ,environment forrais ae,,y issues at Artificial Island to th nd subsequently to theP% subsequent ECP investigation was conducted, which concluded that the alleger was not discriminated against, but rather that the alleger's position was eliminated. | | Safety Conscious Work Environment Issue: . 20 j, 0 4 5 '°"- |
| Alleger was employed as contractor for five years.3.Functional Area: [X] Power Reactor Dis.zipline for each concern: [1] Other: SCWE [2] Discrimination | | -ELxamples provided: |
| [3] Wrongdoing Detailed Description of Allegation:* | | : a. 9/02 - Salem equipment operators raised concerns to alleger about |
| PAC Safety Conscious Work Environment Issue: .2 0 j, 0 4 5 '°"--E Lxamples provided: WIHWIL,.L~E4OF.~PAGE(&)
| | |
| : a. 9/02 -Salem equipment operators raised concerns to alleger about | | - " 2 |
| -" 2.keep the plant operat7VM vs. s ndown e plant. Ailegerin cated that the concerTns of the NEOs were dismissed by PSEG management | | . keep the plant operat7VM vs. s ndown e plant. Ailegerin cated that the concerTns of the NEOs were dismissed by PSEG management |
| : b. Alleger indicated that high levels of management consistently pressure licensed operators to make non-conservative decisj ps. Example: alleger td that a member of Hope Creek Operations manageme -directed an operat.not to commerice shutting down the plant in accordance w'i-Wan LCO shutdown action s ate operator did not commence shutdown of the plant until another SRO (would not provide name over the phone) came into the control room and instructed the operator to adhere to the conditions of his license and commence shutdown of the plant and not to be pressured to take the wrong actions.c. Alleger indicated that discussions with several high level managers during the week of 3/17103 indicated that there was considerable pressure from upper level management to return Hope Creek to service following its forced outage. Indicated that this production vs. safety ' LAr.as coming from the highest levels of management. | | : b. Alleger indicated that high levels of management consistently pressure licensed operators to make non-conservative decisj ps. Example: alleger td that a member of Hope Creek Operations manageme -directedan operat.not to commerice shutting down the plant in accordance w'i-Wan LCO shutdown action s ate operator did not commence shutdown of the plant until another SRO (would not provide name over the phone) came into the control room and instructed the operator to adhere to the conditions of his license and commence shutdown of the plant and not to be pressured to take the wrong actions. |
| Alleger indicated that she informed th M R1about these -comments during her 3/20/03 discussion withe him (see below), and he dismissed them.d. The alleger indicated that at her last meeting (March 20, 2003) with th right before his retirement, sist informed him that high levels of management were telling hQrliat "we are dangerous."I iI is reported to have stated have operators that don't know shit from shinola, and they want to hide behind the safety banner because they don't know what they were doing." e. During a 3/20/03 discussion with th alleger was informed that PSEG management; | | : c. Alleger indicated that discussions with several high level managers during the week of 3/17103 indicated that there was considerable pressure from upper level management to return Hope Creek to service following its forced outage. Indicated that this production vs. safety ' LAr.as coming from the highest levels of management. Alleger indicated that she informed th M R1about these - |
| -lacks "defense-in-depth" thinking,-decision making and reaction to human performance events are not based on safety;-we are one step away from the NRC "taking the keys away;" and-Was not surprised at the reactions of above)[NOTE: during telephone conversation with SAC on 9/4/03, alleger indicated that she had taped a number of the conversations she had with managers in late March 2003. Alleger indicated.that her former attorney had informed her that "one-way" taping of conversations was permitted in New-Jersey.] | | comments during her 3/20/03 discussion withe him (see below), and he dismissed them. |
| Other comments:-safety concerns are given lip-service | | : d. The alleger indicated that at her last meeting (March 20, 2003) with th right before his retirement, sist informed him that high levels of management were telling hQrliat "we are dangerous."IiI is reported to have stated *'we have operators that don't know shit from shinola, and they want to hide behind the safety banner because they don't know what they were doing." |
| -high level managers have informed the alleger that "we focus on appeasing employees vs. resolving-their concerns."-managers are pressured to defend their safety choices Alle~ger indicated that she would equate the SCWE at PSEG to that of Millstone (formerly) and Davis-Besse. She indicated that the situation at PSEG is just as bad.Potential H&I AllEger was called to a meeting with the 2/28/03, puirrte to.discuss "her bor~us." However, after discussing her 'work en.ironment c6ncerns with tp-he informed her that: her employment was to be terminated. | | : e. During a 3/20/03 discussion with th alleger was informed that PSEG management; |
| Alle er i.£ted that she was initially told that she could stay on board until 4/16/03, but later learned that the fhad directed that her departure be"accelerated" and she left the site on 3/28/03. Afrditional details of alleger's employment terminatioh are provided in the documentation attached to the Allegation Receipt Report. A\LL Regarding the licensee/ECP assertion that the alleger's positibn was eliminated and that she was not discriminated against, the alleger indicated that people were brought in to perform the function she was performing immediately after her departure.}} | | - lacks "defense-in-depth" thinking, |
| | - decision making and reaction to human performance events are not based on safety; |
| | - we are one step away from the NRC "taking the keys away;" and |
| | - Was not surprised at the reactions of *see above) |
| | [NOTE: during telephone conversation with SAC on 9/4/03, alleger indicated that she had taped a number of the conversations she had with managers in late March 2003. Alleger indicated.that her former attorney had informed her that "one-way" taping of conversations was permitted in New-Jersey.] |
| | Other comments: |
| | - safety concerns are given lip-service |
| | - high level managers have informed the alleger that "we focus on appeasing employees vs. resolving |
| | -their concerns." |
| | - managers are pressured to defend their safety choices Alle~ger indicated that she would equate the SCWE at PSEG to that of Millstone (formerly) and Davis-Besse. She indicated that the situation at PSEG is just as bad. |
| | Potential H&I AllEger was called to a meeting with the 2/28/03, puirrte to.discuss "her bor~us." However, after discussing her 'work en.ironment c6ncerns with tp-he informed her that: her employment was to be terminated. Alle er i.£ted that she was initially told that she could stay on board until 4/16/03, but later learned that the fhad directed that her departure be "accelerated" and she left the site on 3/28/03. Afrditional details of alleger's employment terminatioh are provided in the documentation attached to the Allegation Receipt Report. A\LL Regarding the licensee/ECP assertion that the alleger's positibn was eliminated and that she was not discriminated against, the alleger indicated that people were brought in to perform the function she was performing immediately after her departure.}} |
|
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Category:Report
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature ML21179A2352021-06-25025 June 2021 PSEG Salem Generating Station - Incidental Take Report Atlantic Sturgeon 6/24/2021 ML21078A0002021-03-25025 March 2021 Review of the Spring 2020 Steam Generator Tube Inspection Report LR-N21-0004, U.S Additional Protocol for Salem, Unit 12021-01-31031 January 2021 U.S Additional Protocol for Salem, Unit 1 LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report ML20274A0762020-09-25025 September 2020 PSEG to NRC, Biological and Engineering Evaluation of Alternatives in Connection with Reinitation of Endangered Species Act Section 7 Consultation LR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N19-0103, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20192019-11-26026 November 2019 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2019 LR-N19-0010, U.S. Additional Protocol for Salem Unit 1 2018 Report2019-01-31031 January 2019 U.S. Additional Protocol for Salem Unit 1 2018 Report ML19029B0172019-01-29029 January 2019 Containment Building, Salem Nuclear Generating Station, Structural Analysis & Design LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 ML18337A3262018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for April 11, 2018 (1 of 2) ML18337A3252018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for March 28, 2018 ML18337A3242018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for February 6, 2018 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0076, Focused Evaluation of External Flooding2017-06-30030 June 2017 Focused Evaluation of External Flooding LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0051, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2017-02-16016 February 2017 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-30030 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16280A5232016-08-31031 August 2016 Technical Evaluation Report Salem Generating Station Storm Surge Hazard Reevaluation Review ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0026, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2016-02-26026 February 2016 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N15-0218, Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report2015-10-21021 October 2015 Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report LR-N15-0207, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report2015-10-0707 October 2015 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. ML15119A1612015-04-17017 April 2015 Report of Impingement of Atlantic Sturgeon LR-N14-0268, Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days2014-12-24024 December 2014 Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days 2023-09-06
[Table view] Category:Miscellaneous
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML21179A2352021-06-25025 June 2021 PSEG Salem Generating Station - Incidental Take Report Atlantic Sturgeon 6/24/2021 ML21078A0002021-03-25025 March 2021 Review of the Spring 2020 Steam Generator Tube Inspection Report LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments LR-N19-0010, U.S. Additional Protocol for Salem Unit 1 2018 Report2019-01-31031 January 2019 U.S. Additional Protocol for Salem Unit 1 2018 Report LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N17-0076, Focused Evaluation of External Flooding2017-06-30030 June 2017 Focused Evaluation of External Flooding LR-N17-0051, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2017-02-16016 February 2017 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-30030 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0026, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2016-02-26026 February 2016 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N15-0218, Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report2015-10-21021 October 2015 Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report LR-N15-0207, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report2015-10-0707 October 2015 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report ML15119A1612015-04-17017 April 2015 Report of Impingement of Atlantic Sturgeon LR-N14-0268, Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days2014-12-24024 December 2014 Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 ML14113A2212014-04-30030 April 2014 NRC Staff Review of the Documentation Provided by PSEG Nuclear LLC for the Salem Generating Station Units 1 and 2 Concerning Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station ML14316A4092014-03-31031 March 2014 Well AA-V Installation Report - Table 5 Well Search Summary ML14316A4082014-03-31031 March 2014 Well AA-V Installation Report - Table 4 Mean Hydraulic Grad Study Results ML14316A4072014-03-31031 March 2014 Well AA-V Installation Report - Table 2 Groundwater Sample Analytical Results Vincentown Wells ML14316A4062014-03-31031 March 2014 Well AA-V Installation Report - Table 1 Well Construction Details ML14316A4032014-03-31031 March 2014 Well AA-V Installation Report - Table 3 Well AA-V Extended Purge Salem Chemistry Screening Results ML14316A4022014-03-31031 March 2014 Well AA-V Installation Report - FIG-06 Potable Well Locations in Lower Alloways Creek Elsinboro and Greenwich Townships ML14316A4012014-03-31031 March 2014 Well AA-V Installation Report - FIG-05 Vincentown Formation Mean Hydraulic Fluctuation Study Results Map - August 2013-5 ML14316A4002014-03-31031 March 2014 Well AA-V Installation Report - FIG-02 Regional Cross SECTION-2 ML14316A3982014-03-31031 March 2014 Well AA-V Installation Report - FIG-04 Monitoring Wells Screened within the Vincentown FORMATION-4 ML14316A3972014-03-31031 March 2014 Well AA-V Installation Report - FIG-03 Facility Cross Section Through AA-V-3 ML14316A3792014-03-31031 March 2014 Well AA-V Installation Report - Appendix a - Monitoring Well Certification Form B ML14316A3692014-03-31031 March 2014 Final Well AA-V Installation Report 031214 ML14316A3342014-03-31031 March 2014 Well AA-V Installation Report - Appendix F - Well Search Results ML14316A3332014-03-31031 March 2014 Well AA-V Installation Report - Appendix E - Summary, Charts and Raw Data ML14316A3312014-03-31031 March 2014 Well AA-V Installation Report - Appendix D Specific Capacity Test for Well AA-V ML14316A3292014-03-31031 March 2014 Well AA-V Installation Report - Appendix C - AA-V Construction and Boring Logs ML14316A3282014-03-31031 March 2014 Well AA-V Installation Report - Appendix B - Cb Abandonment Report LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident LR-N13-0259, Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22)2013-11-0404 November 2013 Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22) LR-N13-0083, Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, ...2013-04-26026 April 2013 Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, ... 2023-12-15
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'g'-\alle.0\receipt\200301 1Orcv.wpd Allegation Receipt Report Date Received: September 3-4, 2003 Allegation No. RI-2003-A-0110 Received via: (X] Telephone [X] Facsimile [X] E-Mail Employee Receiving Allegation: JohnsonNito Source of information: [X] former contractor A leger Name: DL 'arvn Ph.D Home Address: _
Cell Phone: . City/State/Zip:
E..Mail Address: *W V.
[Individual currently in South Carolina at Oconee until 915103 when she will move back to her home address in NJ on 9/12/03.]
Alleger's Employer: PSEG (private contractor) Alleger's Title: Manager, Culture Transformttion Facility: Salem/Hope Creek Docket Nos. 50-272, 311, 354 Was alleger informed of NRC identity protection policy? Yes If H&I was alleged, was alleger informed of DOL rights? Yes (Filing a Civil Suit - has attorney -
not interested in filing wlDOL)
If a licensee employee or contractor, cid they raise the issue to their management? Yes Does the alleger object to referral of issues to the licensee? No Provide alleger's direct response to this question verbatim on the line below:
No objection to NRC requesting a written response from PSEG on this matter as part of the review. (from 914/03 telecon w/SAC)
Was confidentiality requested? . No Was confidentiality initially granted? No Criteria for determining whether the issue is an allegation:
Is it a declaration, statement, or assertion of impropriety or inadequacy? Yes Is ":he impropriety or inadequacy associated with NRC regulated activities? Yes (0 Is t:he validity of the issue unknown? Yes Allegation Summary: ..
- 1. Alleger indicated that there are significant problems with the Safety Conscious Work Environment (SCWE) at Salem/Hope Creek. Alleger's position (Manager, Culture Transformation) has afforded]ei ,c access to high level management at PSEG (up to and including the Chairman of the Board). Alleger indicated that the focus of these higher level managers has been production over safety, and that her efforts to raise work environment concerns to them have not been received positively (see specific information in Detailed Description of Allegation below).
- 2. Discrimination - alleger's employment was terminated after rae in s about the work
,environment forrais ae,,y issues at Artificial Island to th nd subsequently to the
.,*_* P%subsequent ECP investigation was conducted, which concluded that the alleger was not discriminated against, but rather that the alleger's position was eliminated. Alleger was employed as contractor for five years.
3.
Functional Area: [X] Power Reactor Dis.zipline for each concern: [1] Other: SCWE [2] Discrimination [3] Wrongdoing WIHWIL,.L Detailed Description of Allegation:* PAC ~E4OF.~PAGE(&)
Safety Conscious Work Environment Issue: . 20 j, 0 4 5 '°"-
-ELxamples provided:
- a. 9/02 - Salem equipment operators raised concerns to alleger about
- " 2
. keep the plant operat7VM vs. s ndown e plant. Ailegerin cated that the concerTns of the NEOs were dismissed by PSEG management
- b. Alleger indicated that high levels of management consistently pressure licensed operators to make non-conservative decisj ps. Example: alleger td that a member of Hope Creek Operations manageme -directedan operat.not to commerice shutting down the plant in accordance w'i-Wan LCO shutdown action s ate operator did not commence shutdown of the plant until another SRO (would not provide name over the phone) came into the control room and instructed the operator to adhere to the conditions of his license and commence shutdown of the plant and not to be pressured to take the wrong actions.
- c. Alleger indicated that discussions with several high level managers during the week of 3/17103 indicated that there was considerable pressure from upper level management to return Hope Creek to service following its forced outage. Indicated that this production vs. safety ' LAr.as coming from the highest levels of management. Alleger indicated that she informed th M R1about these -
comments during her 3/20/03 discussion withe him (see below), and he dismissed them.
- d. The alleger indicated that at her last meeting (March 20, 2003) with th right before his retirement, sist informed him that high levels of management were telling hQrliat "we are dangerous."IiI is reported to have stated *'we have operators that don't know shit from shinola, and they want to hide behind the safety banner because they don't know what they were doing."
- e. During a 3/20/03 discussion with th alleger was informed that PSEG management;
- lacks "defense-in-depth" thinking,
- decision making and reaction to human performance events are not based on safety;
- we are one step away from the NRC "taking the keys away;" and
- Was not surprised at the reactions of *see above)
[NOTE: during telephone conversation with SAC on 9/4/03, alleger indicated that she had taped a number of the conversations she had with managers in late March 2003. Alleger indicated.that her former attorney had informed her that "one-way" taping of conversations was permitted in New-Jersey.]
Other comments:
- safety concerns are given lip-service
- high level managers have informed the alleger that "we focus on appeasing employees vs. resolving
-their concerns."
- managers are pressured to defend their safety choices Alle~ger indicated that she would equate the SCWE at PSEG to that of Millstone (formerly) and Davis-Besse. She indicated that the situation at PSEG is just as bad.
Potential H&I AllEger was called to a meeting with the 2/28/03, puirrte to.discuss "her bor~us." However, after discussing her 'work en.ironment c6ncerns with tp-he informed her that: her employment was to be terminated. Alle er i.£ted that she was initially told that she could stay on board until 4/16/03, but later learned that the fhad directed that her departure be "accelerated" and she left the site on 3/28/03. Afrditional details of alleger's employment terminatioh are provided in the documentation attached to the Allegation Receipt Report. A\LL Regarding the licensee/ECP assertion that the alleger's positibn was eliminated and that she was not discriminated against, the alleger indicated that people were brought in to perform the function she was performing immediately after her departure.