IR 05000354/2005001
| ML050610334 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/02/2005 |
| From: | Collins S Region 1 Administrator |
| To: | Levis W Public Service Enterprise Group |
| Cobey, Eugene W. RI/DRP/PB3 610-337-5171 | |
| References | |
| IR-05-001 | |
| Download: ML050610334 (7) | |
Text
March 2, 2005
SUBJECT:
ANNUAL ASSESSMENT LETTER - HOPE CREEK NUCLEAR GENERATING STATION (REPORT 05000354/2005001)
Dear Mr. Levis:
On February 7, 2005, the NRC staff completed its end-of-cycle plant performance assessment of the Hope Creek Nuclear Generating Station. The end-of-cycle review for Hope Creek involved the participation of the reactor technical divisions in evaluating performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2004. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility so that you will have an opportunity to prepare for these inspections and to inform us of any planned inspections that may conflict with your plant activities.
This performance review and enclosed inspection plan do not include physical protection information. A separate end-of-cycle performance review letter, designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390, will include the physical protection review and resultant inspection plan.
Overall, Hope Creek operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, was within the Regulatory Response Column of the NRCs Action Matrix, based on two inspection findings being classified as having low to moderate safety significance (White) and all PIs indicating performance at a level requiring no additional NRC oversight (Green).
In the first quarter of 2004, the NRC staff identified a White inspection finding in the Mitigating Systems Cornerstone involving inadequate maintenance on a service water traveling screen that had resulted in its failure and unavailability of the associated service water pump train. The staff subsequently completed a supplemental inspection in response to this inspection finding and concluded that your corrective actions appeared appropriate.
In the fourth quarter of 2004, the NRC staff identified a White inspection finding in the Initiating Events Cornerstone involving inadequate evaluation and corrective action for a degraded level control valve for a moisture separator drain tank which resulted in a pipe failure in a moisture separator drain line in October 2004. As a result of this finding, we plan to conduct a
Mr. William Levis supplemental inspection in accordance with Inspection Procedure 95001. This supplemental inspection procedure is conducted to provide assurance that the causes and contributing causes of risk significant performance issues are understood, the extent of condition is identified, and the corrective actions are sufficient to prevent recurrence. Please inform Mr. Eugene Cobey of my staff of your schedule for completing any evaluations of the issues that led to this White inspection finding. We will use this information to schedule our supplemental inspection at an appropriate time mutually convenient to both parties.
The NRCs last four assessment letters [dated March 3, 2003, August 27, 2003, March 3, 2004, and August 30, 2004; ADAMS Refs. ML030620772, ML032390424, ML040630856, and ML042440233] documented a substantive cross-cutting issue in the area of problem identification and resolution (PI&R). During this assessment period, there were 13 inspection findings that were attributable, at least in part, to weaknesses in problem identification, problem evaluation and effectiveness of corrective actions. A few examples included PSEG personnel not identifying a degraded condition with a service water pump which ultimately led to the unavailability of the pump and an unplanned power transient; inadequacies in the evaluation and corrective action for a degraded level control valve for a moisture separator drain tank which resulted in the aforementioned pipe failure in the moisture separator drain line; and inadequate corrective action for a degraded service water strainer which resulted in the unavailability of a service water pump train. Based on these findings, the staff continues the substantive cross-cutting issue in the area of PI&R.
In addition, as discussed in the mid-cycle assessment letter dated August 30, 2004 [ADAMS Ref. ML042440233], the staff documented a substantive cross-cutting issue in the area of safety conscious work environment (SCWE) based on the results of the NRCs review of the work environment. The NRC conducted several management meetings with PSEG throughout the year to further monitor and evaluate the state of the work environment at the station. While we recognize that PSEG has taken significant steps to evaluate the stations work environment and initiated actions to begin addressing deep-seated causes, it is too early to effectively assess whether or not the work environment at the station is significantly improving. As a result, the staff determined that the SCWE cross-cutting issue will continue, and the NRC will continue to monitor your progress.
The NRC plans to conduct Reactor Oversight Process baseline inspections at Hope Creek, and these inspections will include a focus on PSEGs implementation of the vibration monitoring program for the B reactor recirculation pump. Further, in order to provide an appropriate level of NRC oversight for Hope Creek, in view of the substantive cross-cutting issue in SCWE and the longstanding cross-cutting issue in PI&R, the NRCs Executive Director for Operations (EDO) approved a deviation from the NRCs Action Matrix on August 23, 2004 [ADAMS Ref.
ML042290139]. This deviation authorized the staff to provide a greater level of oversight for the Hope Creek station than would typically be called for by the Regulatory Response Column of the Action Matrix including: (1) conduct of periodic management meetings and site visits; (2)
elevation of the level of NRC management involvement in meetings, site visits, and correspondence; (3) establishment of an internal NRC coordination team, involving regional and headquarters experts in reactor oversight, SCWE and related performance attributes, to coordinate NRC review efforts and assist in evaluation of licensee self-assessment efforts; (4)
review of PSEGs detailed improvement plans to identify SCWE and related performance attributes for further NRC inspection; and (5) enhancement of existing baseline inspections by
Mr. William Levis adjusting inspection scope, as necessary, to verify the effectiveness of licensee improvement efforts in these areas. The enhanced regulatory oversight established by the deviation memorandum will be used to monitor your progress in addressing the PI&R and SCWE cross-cutting issues. The NRC plans to continue with this heightened oversight until PSEG has concluded that substantial, sustainable progress has been made; and the NRC has completed a review, the results of which confirm PSEGs assessment results.
The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through September 30, 2006. In addition to the baseline inspection activities specified by the Reactor Oversight Process, the enclosed plan includes augmentation of existing inspections per the deviation memorandum and additional inspections of the employee concerns program and SCWE improvement initiatives. The inspection plan is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last nine months of the inspection plan are tentative and may be revised at the mid-cycle review meeting.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made 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).
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Mr. Eugene Cobey at 610-337-5171 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Samuel J. Collins Regional Administrator Docket Nos. 50-354 License Nos. NPF-57 Enclosure: Hope Creek Inspection/ Activity Plan
Mr. William Levis cc w/encl:
G. Barnes, Site Vice President - Hope Creek M. Brothers, Vice President, Nuclear Assessment M. Gallagher, Vice President, Engineering and Technical Support W. F. Sperry, Director, Finance C. Perino, Director, Regulatory Assurance M. Massaro, Hope Creek Plant Manager R. Kankus, Joint Owner Affairs J. J. Keenan, Esquire M. Wetterhahn, Esquire Consumer Advocate, Office of Consumer Advocate F. Pompper, Chief of Police and Emergency Management Coordinator J. Lipoti, Ph.D., Assistant Director of Radiation Programs, State of New Jersey K. Tosch - Chief, Bureau of Nuclear Engineering, NJ Dept. of Environmental Protection H. Otto, Ph.D., DNREC Division of Water Resources, State of Delaware N. Cohen, Coordinator - Unplug Salem Campaign W. Costanzo, Technical Advisor - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance Institute of Nuclear Power Operations (INPO)
Mr. William Levis Distribution w/encl:
S. Collins, RA J. Wiggins, DRA A. Blough, DRP W. Lanning, DRS B. Holian, DRP J. Lubinski, DRS E. Cobey, DRP S. Barber, DRP M. Gray - DRP, Senior Resident Inspector K. Venuto, DRP, Resident OA S. Lee, RI OEDO R. Laufer, NRR D. Collins, PM, NRR R. Ennis, (Backup) PM, NRR D. Screnci, PAO N. Sheehan, PAO DRS Branch Chiefs, Region I (5)
RidsNrrDipmIipb@nrc.gov Region I Docket Room (with concurrences)
DOCUMENT NAME: S:\\ROP5 End of Cycle Review\\Branch 3\\HC ROP5 Annual Assessment Ltr FINAL.wpd SISP Review Complete: ___EWC______ (Reviewers Initials)
After declaring this document An Official Agency Record it will 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 RI/DRP RI/DRP RI/DRP
NAME SBarber/SB ECobey/EWC ABlough/ARB DATE 02/25/05 02/25/05 03/01/05 OFFICIAL RECORD COPY
Hope Creek Inspection / Activity Plan 03/01/2005 - 09/30/2006 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 1 of 2 03/02/2005 12:25:02 Report 22
71114
- EP PROGRAM INSP & PI VERIFICATION Baseline Inspections 04/03/2005 04/07/2005 Alert and Notification System Testing IP 7111402
Baseline Inspections 04/03/2005 04/07/2005 Emergency Response Organization Augmentation Testing IP 7111403
Baseline Inspections 04/03/2005 04/07/2005 Emergency Action Level and Emergency Plan Changes IP 7111404
Baseline Inspections 04/03/2005 04/07/2005 Correction of Emergency Preparedness Weaknesses and Deficiencies IP 7111405
Baseline Inspections 04/03/2005 04/07/2005 Performance Indicator Verification IP 71151
1 71121
- OCC RAD SAFETY Baseline Inspections 05/09/2005 05/13/2005 Access Control to Radiologically Significant Areas IP 7112101
Baseline Inspections 05/09/2005 05/13/2005 ALARA Planning and Controls IP 7112102
Baseline Inspections 05/09/2005 05/13/2005 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103
2 ECP
- EMPLOYEE CONCERNS PROGRAM Other Routine 05/16/2005 05/20/2005 Resolution Of Employee Concerns IP 40001
4 11/14EXM
- OPERATOR LICENSING INITIAL EXAMS Not Applicable 10/17/2005 10/21/2005 HOPE CREEK INITIAL EXAM (1/06)
U01586
Not Applicable 11/14/2005 11/18/2005 HOPE CREEK INITIAL EXAM (1/06)
U01586
1 7112203
- PUB RAD SAFETY - REMP Baseline Inspections 06/20/2005 06/24/2005 Radiological Environmental Monitoring Program IP 7112203
5 SCWE
- SCWE TEAM INSPECTION Baseline Inspections 06/20/2005 06/24/2005 Identification and Resolution of Problems IP 71152
1 71121
- OCC RAD SAFETY Baseline Inspections 08/15/2005 08/19/2005 Access Control to Radiologically Significant Areas IP 7112101
Baseline Inspections 08/15/2005 08/19/2005 ALARA Planning and Controls IP 7112102
Baseline Inspections 08/15/2005 08/19/2005 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103
1 7112201
- PUB RAD SAFETY - RETS Baseline Inspections 09/26/2005 09/30/2005 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems IP 7112201
4 71152B
- PI&R Baseline Inspections 11/28/2005 12/02/2005 Identification and Resolution of Problems IP 71152B
Baseline Inspections 12/12/2005 12/16/2005 Identification and Resolution of Problems IP 71152B
1 7112202
- PUB RAD SAFETY - RADWASTE Baseline Inspections 12/05/2005 12/16/2005 Radioactive Material Processing and Transportation IP 7112202
Baseline Inspections 12/05/2005 12/16/2005 Performance Indicator Verification IP 71151
1 7111112B
- MAINTENANCE RULE Baseline Inspections 01/09/2006 01/13/2006 Maintenance Effectiveness IP 7111112B
2 7111107B
- HEAT SINK Baseline Inspections 02/27/2006 03/03/2006 Heat Sink Performance IP 7111107B
This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
Hope Creek Inspection / Activity Plan 03/01/2005 - 09/30/2006 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 2 of 2 03/02/2005 12:25:02 Report 22
71114
- EXERCISE & EP PI VERIFICATION Baseline Inspections 03/20/2006 03/24/2006 Exercise Evaluation IP 7111401
Baseline Inspections 03/20/2006 03/24/2006 Performance Indicator Verification IP 71151
1 7111108G
- INSERVICE INSPECTION Baseline Inspections 04/10/2006 04/14/2006 Inservice Inspection Activities - BWR IP 7111108G
1 71121
- OCC RAD SAFETY Baseline Inspections 04/17/2006 04/21/2006 Access Control to Radiologically Significant Areas IP 7112101
Baseline Inspections 04/17/2006 04/21/2006 ALARA Planning and Controls IP 7112102
Baseline Inspections 04/17/2006 04/21/2006 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103
6 SSDI
- SSDI Baseline Inspections 07/10/2006 07/14/2006 Safety System Design and Performance Capability IP 7111121
1 71121
- OCC RAD SAFETY Baseline Inspections 07/17/2006 07/21/2006 Access Control to Radiologically Significant Areas IP 7112101
Baseline Inspections 07/17/2006 07/21/2006 ALARA Planning and Controls IP 7112102
Baseline Inspections 07/17/2006 07/21/2006 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103
6 SSDI
- SSDI Baseline Inspections 07/24/2006 07/28/2006 Safety System Design and Performance Capability IP 7111121
1 7112201
- PUB RAD SAFETY - RETS Baseline Inspections 08/28/2006 09/01/2006 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems IP 7112201
2 7111111B
- LICENSED OPERATOR REQUL PROGRAM Baseline Inspections 08/28/2006 09/01/2006 Licensed Operator Requalification Program IP 7111111B
Baseline Inspections 09/04/2006 09/08/2006 Licensed Operator Requalification Program IP 7111111B
1 71121
- OCC RAD SAFETY Baseline Inspections 09/25/2006 09/29/2006 Access Control to Radiologically Significant Areas IP 7112101
Baseline Inspections 09/25/2006 09/29/2006 ALARA Planning and Controls IP 7112102
Baseline Inspections 09/25/2006 09/29/2006 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103
Baseline Inspections 09/25/2006 09/29/2006 Performance Indicator Verification IP 71151
This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.