IR 05000354/2013001
| ML14062A017 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/04/2014 |
| From: | Glenn Dentel Reactor Projects Branch 3 |
| To: | Joyce T Public Service Enterprise Group |
| DENTEL, GT | |
| References | |
| IR-13-001 IR-13-001 | |
| Download: ML14062A017 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 March 4, 2014 Mr. Thomas President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038 SUBJECT: ANNUAL ASSESSMENT LETTER FOR HOPE CREEK GENERATING STATION (REPORT 05000354/2013001)
Dear Mr. Joyce:
On February 11, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Hope Creek Generating Station. The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from January 1, 2013 through December 31, assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Hope Creek operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Hope Creek during the most recent quarter was within the Licensee Response Column of the s had very low (i.e., green) safety significance, and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct Reactor Oversight Process baseline inspections at your facility. The NRC evaluates cross-cutting areas to determine whether a substantive cross-cutting issue exists and to encourage licensees to take appropriate actions before more significant performance issues emerge. The NRC reviewed the area of safety-conscious work environ-ment (SCWE) due to the potential Chilling Effect Letter (CEL) issued on July 26, 2013, from the NRC to PSEG (ADAMS Accession No. ML13207A078)1. The CEL was issued when we became aware of a jury verdict in U.S. District Court in Camden, New Jersey in favor of a former security supervisor of Wackenhut Corporation (now G4S Security Solutions), the security contractor at the Salem and Hope Creek Nuclear Generating Stations. The jury found that the former security supervisor was terminated by Wackenhut in October 2009 in retaliation for engaging in a protected activity. The NRC requested that PSEG inform the NRC of the actions it has taken and planned to take to ensure Wackenhut actions did not have a chilling effect on the willingness of PSEG employees, and its contractors, to raise safety and regulatory concerns. 1Agencywide Document Access and Management System (ADAMS) accession number for the referenced document. The document is publicly available and retrievable through the ADAMS hyperlink provided at the end of this letter using this number. In a letter dated November 6, 2013 (ADAMS Accession No. ML13311A366), the NRC staff concluded that PSEG was responsive to our July 26 request for information, and that PSEG has taken appropriate action to ensure: (1) employees and contractors are willing to raise concerns; and (2) management will promptly address employee and contractor concerns when identified. The NRC determined that a substantive cross-cutting issue associated with SCWE does not addressing the potential impact on SCWE. The NRC recognizes that PSEG undertook a number of specific actions, as detailed in your August 22 letter (ADAMS Accession No. communicating the jury finding and NRC letter to your entire staff as well as to all contract employees. The most significant of these actions involved communications and case study training sessions for supervisors and above on their responsibility for maintaining an environment where individuals are comfortable speaking up. In addition, the NRC recognized that PSEG previously established a SCWE policy; had communicated that policy to its staff, management and contractors; and had conducted various assessments of its nuclear safety culture and its SCWE in the preceding 15 months. Based on NRC review and your actions taken, the NRC considered this issue to be properly addressed and closed with regard to the assessment process. The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. In addition to baseline inspections, the NRC will perform Temporary Instruction (TI) plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. Additionally, an NRC audit of licensee efforts towards compliance with Order EA-12-Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-nsite component in order for the NRC to evaluate mitigating strategies as described in licensee submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in calendar year (CY) 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. The CY 2013 end-of-cycle assessments were conducted using the IMC 0310 guidance in effect in CY 2013 (dated October 28, 2011). Cross-cutting aspects identified in 2013 using the 2013 terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305. In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390 of the inspection in the NRC Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact me at 610-337-5233 with any questions you have regarding this letter.
Sincerely,
/RA/ Glenn T. Dentel, Chief Projects Branch 3 Division of Reactor Projects Docket No.: 50-354 License No.: NPF-57 Enclosure: Inspection Plan cc w/encl: Distribution via ListServ
ML14062A017 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP NAME mmt MDraxton/ GTD for via email GDentel/ GTD DATE 02/26/14 02/27/14 Page 1 of 2 02/27/2014 13:52:20 Report 22 Unit NumberPlanned Dates Start EndInspection ActivityTitle No. of Staff on Site Hope CreekInspection / Activity Plan 01/01/2014-06/30/2015 MODS-PERMANENT PLANT MODIFICATIONS 4 1 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T 02/10/2014 02/14/2014 1 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T 02/24/2014 02/28/201471124-REMP 1 1 IP Radiological Environmental Monitoring Program71124.07 05/19/2014 05/23/2014EP EXER-EP EXERCISE INSPECTION 2 1 IP Exercise Evaluation - Hostile Action (HA) Event7111407 05/19/2014 05/23/2014TI-182-DEGRAD UNDERGROUND PIPING - PHASE 2 1 1 IP Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping 2515/182 06/02/2014 06/06/20147111107T-TRIENNIAL HEAT SINK 1 1 IP Heat Sink Performance7111107T 06/23/2014 06/27/2014 INSP-RADIATION PROTECTION 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 07/21/2014 07/25/2014 1 IP Occupational ALARA Planning and Controls71124.02 07/21/2014 07/25/2014 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 07/21/2014 07/25/2014 1 IP Occupational Dose Assessment71124.04 07/21/2014 07/25/2014 1 IP Radiation Monitoring Instrumentation71124.05 07/21/2014 07/25/20147111111B-HOPE CREEK REQUAL INSP WITH P/F RESULTS 2 1 IP Licensed Operator Requalification Program7111111B 10/06/2014 10/10/2014 INSP-RADIATION PROTECTION 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.0108/11/2014 08/15/2014 1 IP Occupational ALARA Planning and Controls71124.0208/11/2014 08/15/2014 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.0308/11/2014 08/15/2014 1 IP Occupational Dose Assessment71124.0408/11/2014 08/15/2014 1 IP Radiation Monitoring Instrumentation71124.0508/11/2014 08/15/2014 2/16EXM-HOPE CREEK INITIAL EXAM 4 1 FY15-HOPE CREEK INITIAL OPERATOR LICENSING EXAM U01904 01/26/2015 01/30/2015 1 FY15-HOPE CREEK INITIAL OPERATOR LICENSING EXAM U01904 02/23/2015 02/27/201571124-RADIATION PROTECTION 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 12/01/2014 12/05/2014 1 IP Occupational ALARA Planning and Controls71124.02 12/01/2014 12/05/2014 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 12/01/2014 12/05/2014 1 IP Occupational Dose Assessment71124.04 12/01/2014 12/05/2014 1 IP Radiation Monitoring Instrumentation71124.05 12/01/2014 12/05/2014 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
Page 2 of 2 02/27/2014 13:52:20 Report 22 Unit NumberPlanned Dates Start EndInspection ActivityTitle No. of Staff on Site Hope CreekInspection / Activity Plan 01/01/2014-06/30/201571124-RADIATION PROTECTION 1 1 IPOccupational Exposure Control Effectiveness71151-OR01 12/01/2014 12/05/2014 PI&R-PI&R - BIENNIAL 1 1 IP Problem Identification and Resolution71152B 01/26/2015 01/30/2015 1 IP Problem Identification and Resolution71152B 02/02/2015 02/06/201571124-RAD CONTROLS 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 03/30/2015 04/04/2015 1 IP Occupational ALARA Planning and Controls71124.02 03/30/2015 04/04/2015 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 03/30/2015 04/04/2015 1 IP Occupational Dose Assessment71124.04 03/30/2015 04/04/2015 1 IP Radiation Monitoring Instrumentation71124.05 03/30/2015 04/04/20157111108G-INSERVICE INSPECTION 1 1 IP Inservice Inspection Activities - BWR7111108G 04/20/2015 04/24/201571124-RAD CONTROLS 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 04/20/2015 04/24/2015 1 IP Occupational ALARA Planning and Controls71124.02 04/20/2015 04/24/2015 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 04/20/2015 04/24/2015 1 IP Occupational Dose Assessment71124.04 04/20/2015 04/24/2015 1 IP Radiation Monitoring Instrumentation71124.05 04/20/2015 04/24/201571124-EFFLUENTS 1 1 IP Radiation Monitoring Instrumentation71124.0505/11/2015 05/15/2015 1 IP Radioactive Gaseous and Liquid Effluent Treatment71124.0605/11/2015 05/15/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.