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| {{Adams|number = ML081720213}} | | {{Adams |
| | | number = ML081720213 |
| | | issue date = 06/20/2008 |
| | | title = IR 05000272-08-502, 05000311-08-502, 05000354-08-502 on 05/19/2008 - 5/22/2008 for Hope Creek and Salem; Exercise Evaluation; Emergency Action Level and Emergency Plan Changes; Emergency Preparedness Performance Indicators |
| | | author name = Trapp J |
| | | author affiliation = NRC/RGN-I/DRS/PSB1 |
| | | addressee name = Levis W |
| | | addressee affiliation = PSEG Nuclear, LLC |
| | | docket = 05000272, 05000311, 05000354 |
| | | license number = DPR-070, DPR-075, NPF-057 |
| | | contact person = |
| | | document report number = IR-08-502 |
| | | document type = Inspection Report, Letter |
| | | page count = 11 |
| | }} |
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| {{IR-Nav| site = 05000272 | year = 2008 | report number = 502 }} | | {{IR-Nav| site = 05000272 | year = 2008 | report number = 502 }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:une 20, 2008 |
| [[Issue date::June 20, 2008]]
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| Mr. William Levis President and Chief Nuclear Officer PSEG Nuclear LLC 80 Park Plaza, T4B Newark, NJ 07102
| | ==SUBJECT:== |
| | SALEM AND HOPE CREEK GENERATING STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS. |
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| SUBJECT: SALEM AND HOPE CREEK GENERATING STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS. 05000272/2008502, 05000311/2008502, AND 05000354/2008502
| | 05000272/2008502, 05000311/2008502, AND 05000354/2008502 |
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| ==Dear Mr. Levis:== | | ==Dear Mr. Levis:== |
| On May 22, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the 2008 evaluated emergency preparedness exercise at your Salem and Hope Creek Generating Stations. The enclosed inspection report documents the inspection results, which were discussed on May 22, 2008, with Mr. Carl Fricker, Vice President of Operations Support, and other members of your staff. | | On May 22, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the 2008 evaluated emergency preparedness exercise at your Salem and Hope Creek Generating Stations. The enclosed inspection report documents the inspection results, which were discussed on May 22, 2008, with Mr. Carl Fricker, Vice President of Operations Support, and other members of your staff. |
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| The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. | | 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. |
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| Based on the results of this inspection, no findings of significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the 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).
| | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| Sincerely,/RA/ James A. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-272, 50-311, 50-354 License Nos. DPR-70, DPR-75, NPF-57
| | Based on the results of this inspection, no findings of significance were identified. |
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| ===Enclosure:===
| | In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs 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). |
| NRC Inspection Reports 05000272/2008502, 05000311/2008502, and 05000354/2008502 Mr. William Levis President and Chief Nuclear Officer PSEG Nuclear LLC 80 Park Plaza, T4B Newark, NJ 07102
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| SUBJECT: SALEM AND HOPE CREEK GENERATING STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS. 05000272/2008502, 05000311/2008502, and 05000354/2008502 Dear M | | Sincerely, |
| | /RA/ |
| | James A. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-272, 50-311, 50-354 License Nos. DPR-70, DPR-75, NPF-57 Enclosure: NRC Inspection Reports 05000272/2008502, 05000311/2008502, and 05000354/2008502 |
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| | Mr. William Levis President and Chief Nuclear Officer PSEG Nuclear LLC 80 Park Plaza, T4B Newark, NJ 07102 SUBJECT: SALEM AND HOPE CREEK GENERATING STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS. |
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| | 05000272/2008502, 05000311/2008502, and 05000354/2008502 Dear M |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 05000272/2008502, 05000311/2008502, 05000354/2008502; 05/19/2008 - 05/22/2008; Hope Creek and Salem Generating Stations; Exercise Evaluation; Emergency Action Level and Emergency Plan Changes; Emergency Preparedness Performance Indicators. | | IR 05000272/2008502, 05000311/2008502, 05000354/2008502; 05/19/2008 - 05/22/2008; |
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| This was an announced inspection conducted by three region-based inspectors and one senior resident inspector. No findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006. | | Hope Creek and Salem Generating Stations; Exercise Evaluation; Emergency Action Level and Emergency Plan Changes; Emergency Preparedness Performance Indicators. |
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| | This was an announced inspection conducted by three region-based inspectors and one senior resident inspector. No findings of significance were identified. 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. |
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| ===Cornerstone: Emergency Preparedness=== | | ===Cornerstone: Emergency Preparedness=== |
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| ===A. NRC-Identified and Self-Revealing Findings=== | | ===NRC-Identified and Self-Revealing Findings=== |
| No findings of significance were identified. B. Licensee-Identified Findings None. | | |
| | No findings of significance were identified. |
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| | B. Licensee-Identified Findings None. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
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| ===Cornerstone:=== | | ===Cornerstone: Emergency Preparedness (EP)=== |
| Emergency Preparedness (EP)1EP1 Exercise Evaluation (71114.01 - 1 Sample) | | |
| | 1EP1 Exercise Evaluation (71114.01 - 1 Sample) |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| Prior to the May 20, 2008, emergency preparedness exercise, the NRC inspectors conducted an in-office review of the exercise objectives and scenario, which PSEG had submitted to the NRC, to determine if the exercise would test major elements of the PSEG Nuclear LLC Emergency Plan as required by 10 CFR 50.47(b)(14). This overall exercise inspection activity represented the completion of one sample on a biennial cycle. The exercise evaluation consisted of the following review and assessment: | | Prior to the May 20, 2008, emergency preparedness exercise, the NRC inspectors conducted an in-office review of the exercise objectives and scenario, which PSEG had submitted to the NRC, to determine if the exercise would test major elements of the PSEG Nuclear LLC Emergency Plan as required by 10 CFR 50.47(b)(14). This overall exercise inspection activity represented the completion of one sample on a biennial cycle. |
| * The adequacy of PSEG's performance in the biennial full-participation exercise regarding the implementation of the risk-significant planning standards (RSPS) described in 10 CFR 50.47(b)(4), (5), (9), and (10), which are: emergency classification; offsite notification; radiological assessment; and, protective action recommendations, respectively. | | |
| * The overall adequacy of PSEG's emergency response facilities with regard to NUREG-0696, "Functional Criteria for Emergency Response Facilities," and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility (EOF). | | The exercise evaluation consisted of the following review and assessment: |
| * A review of other performance areas, such as: the emergency response organization's (ERO's) recognition of abnormal plant conditions; command and control; intra- and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies; staffing and procedure adequacy; and, the overall implementation of the emergency plan and its implementing procedures. | | * The adequacy of PSEGs performance in the biennial full-participation exercise regarding the implementation of the risk-significant planning standards (RSPS)described in 10 CFR 50.47(b)(4), (5), (9), and (10), which are: emergency classification; offsite notification; radiological assessment; and, protective action recommendations, respectively. |
| * A review of past performance issues from the last NRC exercise inspection report and PSEG's EP drill reports, to determine the effectiveness of licensee corrective actions as demonstrated during the May 20 exercise and to ensure compliance with 10 CFR 50.47(b)(14). | | * The overall adequacy of PSEGs emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility (EOF). |
| * The licensee's post-exercise critiques, to evaluate PSEG's self-assessment of its ERO performance during the April 2 exercise and to ensure compliance with 10 CFR 50, Appendix E, Section IV.F.2.g. The inspectors reviewed the documents listed in the attachment to this report. | | * A review of other performance areas, such as: the emergency response organizations (EROs) recognition of abnormal plant conditions; command and control; intra- and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies; staffing and procedure adequacy; and, the overall implementation of the emergency plan and its implementing procedures. |
| | * A review of past performance issues from the last NRC exercise inspection report and PSEGs EP drill reports, to determine the effectiveness of licensee corrective actions as demonstrated during the May 20 exercise and to ensure compliance with 10 CFR 50.47(b)(14). |
| | * The licensees post-exercise critiques, to evaluate PSEGs self-assessment of its ERO performance during the April 2 exercise and to ensure compliance with 10 CFR 50, Appendix E, Section IV.F.2.g. |
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| | The inspectors reviewed the documents listed in the attachment to this report. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. 1EP4 Emergency Action Level (EAL) and Emergency Plan Changes (71114.04 - 1 Sample) | | No findings of significance were identified. |
| | 1EP4 Emergency Action Level (EAL) and Emergency Plan Changes (71114.04 - 1 Sample) |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors reviewed data for the Salem and Hope Creek EP PIs, which are: (1) Drill and Exercise Performance (DEP); (2) Emergency Response Organization (ERO) Drill Participation; and, (3) Alert and Notification System (ANS) Reliability. The last EP inspection at Salem and Hope Creek was conducted in the first quarter of 2007, so the inspectors reviewed supporting documentation from EP drills and tests from the first, second, third, and fourth calendar quarters of 2007, and the first quarter of 2008, to verify the accuracy of the reported PI data. The review of these PIs was conducted in accordance with NRC Inspection Procedure 71151, using the acceptance criteria documented in NEI 99-02, "Regulatory Assessment Performance Indicator Guidelines," Revision 5. This inspection activity represented the completion of three samples on an annual cycle. | | The inspectors reviewed data for the Salem and Hope Creek EP PIs, which are: |
| | : (1) Drill and Exercise Performance (DEP); |
| | : (2) Emergency Response Organization (ERO) Drill Participation; and, |
| | : (3) Alert and Notification System (ANS) Reliability. The last EP inspection at Salem and Hope Creek was conducted in the first quarter of 2007, so the inspectors reviewed supporting documentation from EP drills and tests from the first, second, third, and fourth calendar quarters of 2007, and the first quarter of 2008, to verify the accuracy of the reported PI data. The review of these PIs was conducted in accordance with NRC Inspection Procedure 71151, using the acceptance criteria documented in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines, Revision 5. |
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| | This inspection activity represented the completion of three samples on an annual cycle. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. | | No findings of significance were identified. |
| | {{a|4OA6}} |
| | ==4OA6 Meetings, Including Exit== |
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| {{a|4OA6}}
| | On May 22, 2008, the inspectors presented the results of this inspection to Mr. C. |
| ==4OA6 Meetings, Including Exit==
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| On May 22, 2008, the inspectors presented the results of this inspection to Mr. C. Fricker, the PSEG Vice President of Operations Support, and other members of the PSEG staff. No proprietary information was provided to the inspectors during this inspection. | | Fricker, the PSEG Vice President of Operations Support, and other members of the PSEG staff. No proprietary information was provided to the inspectors during this inspection. |
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| ATTACHMENT | | ATTACHMENT |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| ===Licensee Personnel=== | | ===Licensee Personnel=== |
| : [[contact::C. Neely]], PSEG Regulatory Affairs Director | | : [[contact::C. Neely]], PSEG Regulatory Affairs Director |
| : [[contact::D. Burgin]], PSEG Emergency Preparedness Manager | | : [[contact::D. Burgin]], PSEG Emergency Preparedness Manager |
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| ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== |
| None | | |
| | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ==Section 1EP1: Exercise Evaluation==
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| : PSEG Nuclear LLC Emergency Plan (Revision 59) PSEG Nuclear Emergency Plan Implementing Procedures PSEG Nuclear May 20, 2008, Hope Creek Emergency Exercise Scenario Package PSEG Nuclear Emergency Preparedness Drill Reports, January 2007 - March 2008
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| ===Condition Reports===
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| written for the May 20, 2008, exercise:
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| : 20370774,
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| : 20370851,
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| : 20370957,
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| : 20370961,
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| : 20370977,
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| : 20370993,
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| : 20370998,
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| : 20371005,
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| : 20371010,
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| : 20371013,
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| : 20371056,
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| : 20371106,
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| : 20371126,
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| : 20371204,
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| : 20371550,
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| : 20371595,
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| : 20371628,
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| : 20371631,
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| : 20371642,
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| : 20371652,
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| : 20371781,
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| : 20371800,
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| : 20371805,
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| : 20372044, 20380978
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| ==Section 1EP4: Emergency Action Level and Emergency Plan Changes Procedure==
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| : NC.EP-AP.ZZ-1003, 10CFR50.54(q) Effectiveness Review Guide (Rev. 3)
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| ===Procedure===
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| : LS-AA-104, Exelon 50.59 Review Process (Rev. 5) Procedure
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| : LS-AA-104-1007, 50.59 Resource Manual - Emergency Plan Guidance for Salem and Hop Creek Stations (Rev. 0) Emergency Preparedness EAL Vulnerability Upgrade Project (March 2006- December 2007) 10
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| : CFR 50.54(q) Reviews, Performed January 2007 - April 2008
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| ==Section 4OA1: Performance Indicator Verification Procedure==
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| : EP-AA-125, Emergency Preparedness Self Evaluation Process (Rev. 0) Procedure
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| : EP-AA-125-1001, EP Performance Indicator Guidance (Rev. 0) Procedure
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| : EP-AA-125-1002, ERO Performance - Performance Indicator Guidance (Rev. 0) Procedure
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| : EP-AA-125-1003, ERO Readiness - Performance Indicator Guidance (Rev. 0) Procedure
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| : EP-AA-125-1004, Emergency Response Facilities & Equipment - Performance Indicator Guidance (Rev. 0) ERO Drill Participation PI data, January 2007 - March 2008 Public Notification System PI data, January 2007 - March 2008 DEP PI data, January 2007 - March 2008
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| ==LIST OF ACRONYMS==
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| : [[ANS]] [[Alert Notification System]]
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| : [[DEP]] [[Drill and Exercise Performance]]
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| : [[EAL]] [[Emergency Action Level]]
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| : [[EOF]] [[Emergency Operations Facility]]
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| : [[EP]] [[Emergency Preparedness]]
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| : [[ERO]] [[Emergency Response Organization]]
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| : [[NEI]] [[Nuclear Energy Institute]]
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| : [[NRC]] [[Nuclear Regulatory Commission OSC Operations Support Center]]
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| : [[PI]] [[Performance Indicator]]
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| : [[PSEG]] [[Public Service Electric and Gas]]
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| : [[RSPS]] [[Risk Significant Planning Standard]]
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| : [[TSC]] [[Technical Support Center]]
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| }} | | }} |
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Category:Inspection Report
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[Table view] Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek 2024-02-05
[Table view] |
Text
une 20, 2008
SUBJECT:
SALEM AND HOPE CREEK GENERATING STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS.
05000272/2008502, 05000311/2008502, AND 05000354/2008502
Dear Mr. Levis:
On May 22, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the 2008 evaluated emergency preparedness exercise at your Salem and Hope Creek Generating Stations. The enclosed inspection report documents the inspection results, which were discussed on May 22, 2008, with Mr. Carl Fricker, Vice President of Operations Support, 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, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs 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).
Sincerely,
/RA/
James A. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-272, 50-311, 50-354 License Nos. DPR-70, DPR-75, NPF-57 Enclosure: NRC Inspection Reports 05000272/2008502, 05000311/2008502, and 05000354/2008502
Mr. William Levis President and Chief Nuclear Officer PSEG Nuclear LLC 80 Park Plaza, T4B Newark, NJ 07102 SUBJECT: SALEM AND HOPE CREEK GENERATING STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS.
05000272/2008502, 05000311/2008502, and 05000354/2008502 Dear M
SUMMARY OF FINDINGS
IR 05000272/2008502, 05000311/2008502, 05000354/2008502; 05/19/2008 - 05/22/2008;
Hope Creek and Salem Generating Stations; Exercise Evaluation; Emergency Action Level and Emergency Plan Changes; Emergency Preparedness Performance Indicators.
This was an announced inspection conducted by three region-based inspectors and one senior resident inspector. No findings of significance were identified. 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: Emergency Preparedness
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
B. Licensee-Identified Findings None.
ii
REPORT DETAILS
REACTOR SAFETY
1EP1 Exercise Evaluation (71114.01 - 1 Sample)
a. Inspection Scope
Prior to the May 20, 2008, emergency preparedness exercise, the NRC inspectors conducted an in-office review of the exercise objectives and scenario, which PSEG had submitted to the NRC, to determine if the exercise would test major elements of the PSEG Nuclear LLC Emergency Plan as required by 10 CFR 50.47(b)(14). This overall exercise inspection activity represented the completion of one sample on a biennial cycle.
The exercise evaluation consisted of the following review and assessment:
- The adequacy of PSEGs performance in the biennial full-participation exercise regarding the implementation of the risk-significant planning standards (RSPS)described in 10 CFR 50.47(b)(4), (5), (9), and (10), which are: emergency classification; offsite notification; radiological assessment; and, protective action recommendations, respectively.
- The overall adequacy of PSEGs emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility (EOF).
- A review of other performance areas, such as: the emergency response organizations (EROs) recognition of abnormal plant conditions; command and control; intra- and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies; staffing and procedure adequacy; and, the overall implementation of the emergency plan and its implementing procedures.
- A review of past performance issues from the last NRC exercise inspection report and PSEGs EP drill reports, to determine the effectiveness of licensee corrective actions as demonstrated during the May 20 exercise and to ensure compliance with 10 CFR 50.47(b)(14).
- The licensees post-exercise critiques, to evaluate PSEGs self-assessment of its ERO performance during the April 2 exercise and to ensure compliance with 10 CFR 50, Appendix E, Section IV.F.2.g.
The inspectors reviewed the documents listed in the attachment to this report.
b. Findings
No findings of significance were identified.
1EP4 Emergency Action Level (EAL) and Emergency Plan Changes (71114.04 - 1 Sample)
a. Inspection Scope
Since the last NRC inspection of this program area, Revision 59 of the PSEG Nuclear LLC Emergency Plan was implemented by PSEG. PSEG had determined that in accordance with 10 CFR 50.54(q), the changes resulted in no decrease in effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR 50. The inspectors reviewed all EAL changes made since January 2007, and conducted a sampling review of other Emergency Plan changes, including changes to lower-tier emergency plan implementing procedures, to evaluate for any potential decreases in effectiveness of the Emergency Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
4OA1 Performance Indicator (PI) Verification (71151 - 3 Samples)
a. Inspection Scope
The inspectors reviewed data for the Salem and Hope Creek EP PIs, which are:
- (1) Drill and Exercise Performance (DEP);
- (2) Emergency Response Organization (ERO) Drill Participation; and,
- (3) Alert and Notification System (ANS) Reliability. The last EP inspection at Salem and Hope Creek was conducted in the first quarter of 2007, so the inspectors reviewed supporting documentation from EP drills and tests from the first, second, third, and fourth calendar quarters of 2007, and the first quarter of 2008, to verify the accuracy of the reported PI data. The review of these PIs was conducted in accordance with NRC Inspection Procedure 71151, using the acceptance criteria documented in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines, Revision 5.
This inspection activity represented the completion of three samples on an annual cycle.
b. Findings
No findings of significance were identified.
4OA6 Meetings, Including Exit
On May 22, 2008, the inspectors presented the results of this inspection to Mr. C.
Fricker, the PSEG Vice President of Operations Support, and other members of the PSEG staff. No proprietary information was provided to the inspectors during this inspection.
ATTACHMENT
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- C. Neely, PSEG Regulatory Affairs Director
- D. Burgin, PSEG Emergency Preparedness Manager
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED