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{{#Wiki_filter:une 30, 2015 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION une 30, 2015 | ||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 27: | Line 27: | ||
==Dear Mr. Coyle:== | ==Dear Mr. Coyle:== | ||
On June 1 - 4, 2015, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Indian Point Nuclear Generating Station Unit 1. The inspection examined activities conducted under your license as they relate to safety and compliance with the | On June 1 - 4, 2015, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Indian Point Nuclear Generating Station Unit 1. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Don Mayer, Director Special Projects, Unit 1, and other members of your staff on June 4, 2015, at the conclusion of the inspection and are described in the enclosed report. No findings of safety significance were identified. | ||
Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov | Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Mark Roberts (610) 337-5094 if you have any questions regarding this matter. | ||
; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). | |||
You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Mark Roberts (610) 337-5094 if you have any questions regarding this matter. | |||
Sincerely, | Sincerely, | ||
/RA/ | /RA/ | ||
Marc S. Ferdas, Chief Decommissioning and Technical | Marc S. Ferdas, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 05000003/2015009 cc w/encl: Distribution via ListServ | ||
Support Branch Division of Nuclear Materials Safety | |||
Enclosure: Inspection Report No. 05000003/2015009 | |||
cc w/encl: Distribution via ListServ | |||
=EXECUTIVE SUMMARY= | =EXECUTIVE SUMMARY= | ||
Entergy Nuclear Operations, Inc. | Entergy Nuclear Operations, Inc. | ||
NRC Inspection Report No. 05000003/2015009 | Indian Point Nuclear Generating Station Unit 1 NRC Inspection Report No. 05000003/2015009 A routine announced safety inspection was conducted on June 1 - 4, 2015 at IP-1. The inspectors reviewed IP-1s activities related to the safe storage of radioactive material, including site operations, engineering, maintenance, plant support activities, management oversight, and corrective action program (CAP) implementation. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. There are currently no ongoing decommissioning activities being conducted at IP-1. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." Based on the results of this inspection, no findings of safety significance were identified. | ||
A routine announced safety inspection was conducted on June 1 - 4, 2015 at IP-1. The inspectors reviewed IP- | |||
=REPORT DETAILS= | =REPORT DETAILS= | ||
1.0 Background IP-1 is a pressurized water reactor that was granted a 40-year Operating License in 1962, and was permanently shut down in 1974. The facility is being maintained in safe storage (SAFSTOR) status. Pursuant to the June 19, 1980 | 1.0 Background IP-1 is a pressurized water reactor that was granted a 40-year Operating License in 1962, and was permanently shut down in 1974. The facility is being maintained in safe storage (SAFSTOR) status. Pursuant to the June 19, 1980 Commission Order Revoking Authority to Operate Facility and the Decommissioning Plan for Indian Point Unit No. 1, approved by the NRC in an Order, dated January 31, 1996, the reactor remains in a defueled status. | ||
There are ongoing activities in the IP-1 space that are support services for Indian Point Nuclear Generating Station Unit 2 (IP-2) and Unit 3 (IP-3). | There are ongoing activities in the IP-1 space that are support services for Indian Point Nuclear Generating Station Unit 2 (IP-2) and Unit 3 (IP-3). | ||
| Line 64: | Line 54: | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(Inspection Procedures (IPs) 36801, 37801, 40801, 62801, 64704, 71801, 83750, 84750) | (Inspection Procedures (IPs) 36801, 37801, 40801, 62801, 64704, 71801, 83750, 84750) | ||
A routine announced safety inspection was conducted on June 1 - 4, 2015 at IP-1. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC | A routine announced safety inspection was conducted on June 1 - 4, 2015 at IP-1. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC 2561. | ||
The inspectors reviewed the SAFSTOR program as outlined in the UFSAR, TS, ODCM, and procedure IP-SMM-U1-001, IPEC Site Management Manual, Control of Indian Point 1. The inspectors reviewed SAFSTOR activities, including site operations, engineering, maintenance, plant support activities, management oversight, and the CAP. The inspectors assessed the material condition of the IP-1 facilities during plant tours of the containment annulus, chemical systems building, and fuel handling building. The inspectors also discussed any design changes or modifications since the previous inspection. | |||
The inspectors reviewed activities, components, and documentation associated with the following SAFSTOR programs: occupational exposure, fire protection, radioactive effluent control, site radiological environmental monitoring program (REMP), and decommissioning organization and staffing. The inspectors reviewed radiological survey reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, the annual effluent release report, which included a summary of the radioactive waste management and transportation programs, and a work order for replacing a component of the north curtain drain system. | |||
The inspectors reviewed activities, components, and documentation associated with the following SAFSTOR programs: | |||
The inspectors reviewed quality assurance (QA) audit and CAP documents associated with IP-1 to determine if issues were being appropriately identified, assessed and reviewed and that corrective actions were being appropriately implemented. | The inspectors reviewed quality assurance (QA) audit and CAP documents associated with IP-1 to determine if issues were being appropriately identified, assessed and reviewed and that corrective actions were being appropriately implemented. | ||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
The inspectors performed a follow-up review of the changes to the IP-1 SAFSTOR organization that were initiated in early 2014 and initially reviewed during the previous NRC SAFSTOR inspection of IP-1 [NRC Inspection Report No. 05000003/2014010 (ADAMS Accession Number ML14217A037)]. The inspectors discussed functional roles and staff duties with the Director, IP-1 and other staff impacted by the organizational changes. The inspectors noted that organizational changes appeared to be integrated with assigned staff duties and procedural actions, and that the Director, IP-1 had a sufficient budget to fund actions essential to maintaining IP- | The inspectors performed a follow-up review of the changes to the IP-1 SAFSTOR organization that were initiated in early 2014 and initially reviewed during the previous NRC SAFSTOR inspection of IP-1 [NRC Inspection Report No. 05000003/2014010 (ADAMS Accession Number ML14217A037)]. The inspectors discussed functional roles and staff duties with the Director, IP-1 and other staff impacted by the organizational changes. The inspectors noted that organizational changes appeared to be integrated with assigned staff duties and procedural actions, and that the Director, IP-1 had a sufficient budget to fund actions essential to maintaining IP-1s SAFSTOR condition. The inspectors also followed-up on the structural engineering inspection that Entergy had scheduled for late 2014 and was also discussed in the previous NRC SAFSTOR inspection of IP-1. Based on discussions with engineering staff, the inspectors noted that the field work from the engineering inspection was only recently completed and the written report was not yet available. | ||
The inspectors confirmed that the staff effectively implemented the SAFSTOR program. | |||
The inspectors verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures. The annual radiological effluent and REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix I. | |||
The inspectors noted that Entergy installed and effectively tested a replacement of the carbon absorption vessel for one of the trains of the north curtain drain system. The installation and testing appeared to be completed in accordance with the scope of the work order and associated procedures. The inspectors noted that the carbon absorption vessel from the north curtain drain system was shipped offsite as radioactive waste and the residual carbon was awaiting shipment until the waste container was full. | The inspectors noted that Entergy installed and effectively tested a replacement of the carbon absorption vessel for one of the trains of the north curtain drain system. The installation and testing appeared to be completed in accordance with the scope of the work order and associated procedures. The inspectors noted that the carbon absorption vessel from the north curtain drain system was shipped offsite as radioactive waste and the residual carbon was awaiting shipment until the waste container was full. | ||
| Line 93: | Line 81: | ||
=====Exit Meeting Summary===== | =====Exit Meeting Summary===== | ||
On June 4, 2015, the inspectors presented the inspection results to Don Mayer, Director, IP-1, and other members of | On June 4, 2015, the inspectors presented the inspection results to Don Mayer, Director, IP-1, and other members of Entergys organization. The inspector confirmed that proprietary information was not removed from the site. | ||
=SUPPLEMENTARY INFORMATION= | =SUPPLEMENTARY INFORMATION= | ||
PARTIAL LIST OF PERSONS CONTACTED | PARTIAL LIST OF PERSONS CONTACTED | ||
Licensee | Licensee | ||
: [[contact::R. Beesley]], Radiation Protection (RP) Technician | : [[contact::R. Beesley]], Radiation Protection (RP) Technician | ||
: [[contact::G. Dahl]], Nuclear Safety/Licensing Specialist IV, Regulatory Assurance* | : [[contact::G. Dahl]], Nuclear Safety/Licensing Specialist IV, Regulatory Assurance* | ||
: [[contact::J. Doroski]], Senior Health Physics/Chemistry Specialist | : [[contact::J. Doroski]], Senior Health Physics/Chemistry Specialist | ||
: [[contact::R. Drake]], Supervisor, Design Engineering - Civil | : [[contact::R. Drake]], Supervisor, Design Engineering - Civil | ||
: [[contact::C. English]], Consultant | : [[contact::C. English]], Consultant | ||
: [[contact::R. Fuchek]], Online Work Control Superintendent | : [[contact::R. Fuchek]], Online Work Control Superintendent | ||
: [[contact::R. Mages]], Senior Specialist, ALARA | : [[contact::R. Mages]], Senior Specialist, ALARA | ||
: [[contact::D. Mayer]], Director, IP-1* | : [[contact::D. Mayer]], Director, IP-1* | ||
: [[contact::J. Michetti]], System Engineer, Radiation Monitoring System | : [[contact::J. Michetti]], System Engineer, Radiation Monitoring System | ||
: [[contact::M. Mirzai]], Nuclear Safety/Licensing Specialist IV, Regulatory Assurance | : [[contact::M. Mirzai]], Nuclear Safety/Licensing Specialist IV, Regulatory Assurance | ||
: [[contact::W. | : [[contact::W. OBrien]], RP Supervisor | ||
: [[contact::J. Ruch]], Engineer III, Design Engineering - Civil | : [[contact::J. Ruch]], Engineer III, Design Engineering - Civil | ||
: [[contact::R. Threlkeld]], Quality Assurance (QA) Auditor | : [[contact::R. Threlkeld]], Quality Assurance (QA) Auditor | ||
: [[contact::R. Walpole]], Manager, Regulatory Assurance* | : [[contact::R. Walpole]], Manager, Regulatory Assurance* | ||
: [[contact::C. Wilson]], Systems Engineer, Fire Protection | : [[contact::C. Wilson]], Systems Engineer, Fire Protection | ||
NRC | NRC | ||
: [[contact::A. Bolger]], Resident Inspector, Division of Reactor Projects, Region I* | : [[contact::A. Bolger]], Resident Inspector, Division of Reactor Projects, Region I* | ||
: [[contact::K. Conway]], Project Manager, NMSS* | : [[contact::K. Conway]], Project Manager, NMSS* | ||
: [[contact::G. Newman]], Resident Inspector, Division of Reactor Projects, Region I* | : [[contact::G. Newman]], Resident Inspector, Division of Reactor Projects, Region I* | ||
* Denotes individuals present during final exit meeting held on June 4, 2015 | * Denotes individuals present during final exit meeting held on June 4, 2015 | ||
ITEMS OPEN, CLOSED, AND DISCUSSED | ITEMS OPEN, CLOSED, AND DISCUSSED | ||
None | None | ||
LIST OF DOCUMENTS REVIEWED | |||
IP-1 TS (Appendix A to Provisional Operating License No. DPR-5) | IP-1 TS (Appendix A to Provisional Operating License No. DPR-5) | ||
Indian Point Unit 1 Final Safety Analysis Report | Indian Point Unit 1 Final Safety Analysis Report | ||
IP-SMM-U1-001, | IP-SMM-U1-001, IPEC Site Management Manual, Control of Indian Point 1, Rev. 3 | ||
Indian Point Offsite Dose Calculation Manual (ODCM) | Indian Point Offsite Dose Calculation Manual (ODCM) | ||
IP-RPT-11-00044, | IP-RPT-11-00044, SAFSTOR 2011 Structural Inspection | ||
IP-RPT-15-00019, | IP-RPT-14-00020, Maintenance Rule Structural Monitoring Inspection Report for the Unit 1 | ||
Nuclear Services Building | Turbine Building | ||
EN-LI-100, Process Applicability Determination, Rev. 16 EN-LI-102, Corrective Action Program, Rev. 24 EN-PL-155, Policy, Rev. 5 (Completed Attachments to procedure describing IP-1 organization | IP-RPT-15-00019, Maintenance Rule Structural Monitoring Inspection Report for the Unit 1 | ||
Nuclear Services Building | |||
EN-LI-100, Process Applicability Determination, Rev. 16 | |||
EN-LI-102, Corrective Action Program, Rev. 24 | |||
EN-PL-155, Policy, Rev. 5 (Completed Attachments to procedure describing IP-1 organization | |||
change) | change) | ||
EN-QV-109, Audit Process, Rev. 28 | EN-QV-109, Audit Process, Rev. 28 | ||
EN-QV-129, Vulnerability Review Process, Rev. 8 QA-2/6-2013-IP-01, | EN-QV-129, Vulnerability Review Process, Rev. 8 | ||
QA-14/15-2013-IP-01, | QA-2/6-2013-IP-01, Quality Assurance Audit Report (Chemistry, Effluent & Environmental), | ||
October 15, 2013 | |||
QA-12/18-2013-IP-01, Quality Assurance Audit Report (Operations & Technical Specifications) | |||
QA-9-2014-IP-1, Quality Assurance Audit Report (Fire Protection) | |||
QA-14/15-2013-IP-01, Quality Assurance Audit Report (Radiation Protection & Radwaste) | |||
Audit Plan for QA-2/6-2013-IP-01, Combined Chemistry, Effluent Monitoring Audit, October 15, | |||
2013 | |||
Audit Plan for QA-12/18-2013-IP-01, Operations & Technical Specifications Audit, June 5, 2013 | |||
Audit Plan for QA-9-2014-IP-1, Fire Protection Audit, January 2, 2014 | Audit Plan for QA-9-2014-IP-1, Fire Protection Audit, January 2, 2014 | ||
Audit Plan for QA-14/15-2013-IP-01, Radiation Protection & Radwaste, Audit, September 16, 2013 | Audit Plan for QA-14/15-2013-IP-01, Radiation Protection & Radwaste, Audit, September 16, 2013 | ||
EN-RP-101, Rev. 11, | EN-RP-101, Rev. 11, Access Control for Radiologically Controlled Areas | ||
EN-RP-108, Rev. 15, Radiation Protection Posting | |||
0-RP-ADM-109, Rev. 8, Radiation Protection Periodic Task Scheduling | |||
2014 Annual Radioactive Effluent Release Report | 2014 Annual Radioactive Effluent Release Report | ||
2014 Annual Radiological Environmental Operating Report | 2014 Annual Radiological Environmental Operating Report | ||
Liquid Release Permits and Dose Reports, July 2014 - May 2015 | Liquid Release Permits and Dose Reports, July 2014 - May 2015 | ||
Radiation Work Permit 20151000, Rev. 0, Unit 1 Support - All Groups SEP-FPP-IP-001, Rev. 4, | Radiation Work Permit 20151000, Rev. 0, Unit 1 Support - All Groups | ||
SEP-FPP-IP-001, Rev. 4, IPEC Fire Protection Program Plan | |||
Work Order for Replacement of North Curtain Drain Train A Carbon Absorption Vessel, LW-1271 | |||
(WO-IPC-00379018, High Delta P, LW-1271 Leak), 5-8-2015 | (WO-IPC-00379018, High Delta P, LW-1271 Leak), 5-8-2015 | ||
Radiological Survey Reports - Containment (all elevations) and IP-1 steam generators Radiological Survey - IPEC-1503-0682, VI-004 U1 33 ft VC Annulus, 3-26-2015 Radiological Survey - IPEC-1505-0069, VI-004 U1 33 ft VC Annulus, 5-18-2015 Condition Reports: | Radiological Survey Reports - Containment (all elevations) and IP-1 steam generators | ||
2443 | Radiological Survey - IPEC-1503-0682, VI-004 U1 33 ft VC Annulus, 3-26-2015 | ||
Radiological Survey - IPEC-1505-0069, VI-004 U1 33 ft VC Annulus, 5-18-2015 | |||
Condition Reports: CR-IP2-2014-05249; CR-IP2-2014-05287; CR-IP2-2015-01378; CR-IP2-2014- | |||
2443 | |||
LIST OF ACRONYMS USED | LIST OF ACRONYMS USED | ||
CAP | CAP Corrective Action Program | ||
CR Condition Report | |||
Entergy Entergy Nuclear Operations, Inc. | Entergy Entergy Nuclear Operations, Inc. | ||
IMC | IMC Inspection Manual Chapter | ||
IP | IP Inspection Procedure | ||
NRC | IP-1 Indian Point Unit 1 | ||
ODCM | IP-2 Indian Point Unit 2 | ||
QA | NRC Nuclear Regulatory Commission | ||
TS | ODCM Offsite Dose Calculation Manual | ||
UFSAR Updated Final Safety Analysis Report | QA Quality Assurance | ||
REMP Radiological Environmental Monitoring Program | |||
SAFSTOR Safe Storage | |||
TS Technical Specification | |||
UFSAR Updated Final Safety Analysis Report | |||
Attachment | |||
}} | }} | ||
Revision as of 09:32, 31 October 2019
| ML15182A283 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 06/30/2015 |
| From: | Marc Ferdas Division of Nuclear Materials Safety I |
| To: | Coyle L Entergy Nuclear Operations |
| References | |
| FOIA/PA-2016-0148 IR 2015009 | |
| Download: ML15182A283 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION une 30, 2015
SUBJECT:
ENTERGY NUCLEAR OPERATIONS, INC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1 - NRC INSPECTION REPORT NO.
05000003/2015009
Dear Mr. Coyle:
On June 1 - 4, 2015, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Indian Point Nuclear Generating Station Unit 1. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Don Mayer, Director Special Projects, Unit 1, and other members of your staff on June 4, 2015, at the conclusion of the inspection and are described in the enclosed report. No findings of safety significance were identified.
Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Mark Roberts (610) 337-5094 if you have any questions regarding this matter.
Sincerely,
/RA/
Marc S. Ferdas, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 05000003/2015009 cc w/encl: Distribution via ListServ
EXECUTIVE SUMMARY
Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Station Unit 1 NRC Inspection Report No. 05000003/2015009 A routine announced safety inspection was conducted on June 1 - 4, 2015 at IP-1. The inspectors reviewed IP-1s activities related to the safe storage of radioactive material, including site operations, engineering, maintenance, plant support activities, management oversight, and corrective action program (CAP) implementation. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. There are currently no ongoing decommissioning activities being conducted at IP-1. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." Based on the results of this inspection, no findings of safety significance were identified.
REPORT DETAILS
1.0 Background IP-1 is a pressurized water reactor that was granted a 40-year Operating License in 1962, and was permanently shut down in 1974. The facility is being maintained in safe storage (SAFSTOR) status. Pursuant to the June 19, 1980 Commission Order Revoking Authority to Operate Facility and the Decommissioning Plan for Indian Point Unit No. 1, approved by the NRC in an Order, dated January 31, 1996, the reactor remains in a defueled status.
There are ongoing activities in the IP-1 space that are support services for Indian Point Nuclear Generating Station Unit 2 (IP-2) and Unit 3 (IP-3).
IP-1 and IP-2 are physically contiguous and share systems, such as the integrated liquid waste system and the air handling system facilities, such as the chemistry and health physics laboratories. IP-1 also contains radioactive waste processing facilities that provide waste processing services for both units. Radiological effluent limits are met on an overall site basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite Dose Calculation Manual (ODCM).
Services provided by IP-2 include maintenance, corrective action program implementation, plant support activities while in SAFSTOR status, and implementation of the SAFSTOR activities required in the Updated Final Safety Analysis Report (UFSAR), and Technical Specifications (TS). Appendix A to the IP-1 Provisional Operating License No. DPR-5 recognizes this commonality, as well as the intended use of the IP-1 facility to support IP-2 until the retirement of that unit, and contains specific references to Appendix A of the IP-2 Facility Operating License No. DPR-26.
2.0 Safe Storage (SAFSTOR) Performance and Status Review
a. Inspection Scope
(Inspection Procedures (IPs) 36801, 37801, 40801, 62801, 64704, 71801, 83750, 84750)
A routine announced safety inspection was conducted on June 1 - 4, 2015 at IP-1. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC 2561.
The inspectors reviewed the SAFSTOR program as outlined in the UFSAR, TS, ODCM, and procedure IP-SMM-U1-001, IPEC Site Management Manual, Control of Indian Point 1. The inspectors reviewed SAFSTOR activities, including site operations, engineering, maintenance, plant support activities, management oversight, and the CAP. The inspectors assessed the material condition of the IP-1 facilities during plant tours of the containment annulus, chemical systems building, and fuel handling building. The inspectors also discussed any design changes or modifications since the previous inspection.
The inspectors reviewed activities, components, and documentation associated with the following SAFSTOR programs: occupational exposure, fire protection, radioactive effluent control, site radiological environmental monitoring program (REMP), and decommissioning organization and staffing. The inspectors reviewed radiological survey reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, the annual effluent release report, which included a summary of the radioactive waste management and transportation programs, and a work order for replacing a component of the north curtain drain system.
The inspectors reviewed quality assurance (QA) audit and CAP documents associated with IP-1 to determine if issues were being appropriately identified, assessed and reviewed and that corrective actions were being appropriately implemented.
b. Observations and Findings
The inspectors performed a follow-up review of the changes to the IP-1 SAFSTOR organization that were initiated in early 2014 and initially reviewed during the previous NRC SAFSTOR inspection of IP-1 [NRC Inspection Report No. 05000003/2014010 (ADAMS Accession Number ML14217A037)]. The inspectors discussed functional roles and staff duties with the Director, IP-1 and other staff impacted by the organizational changes. The inspectors noted that organizational changes appeared to be integrated with assigned staff duties and procedural actions, and that the Director, IP-1 had a sufficient budget to fund actions essential to maintaining IP-1s SAFSTOR condition. The inspectors also followed-up on the structural engineering inspection that Entergy had scheduled for late 2014 and was also discussed in the previous NRC SAFSTOR inspection of IP-1. Based on discussions with engineering staff, the inspectors noted that the field work from the engineering inspection was only recently completed and the written report was not yet available.
The inspectors confirmed that the staff effectively implemented the SAFSTOR program.
The inspectors verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures. The annual radiological effluent and REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix I.
The inspectors noted that Entergy installed and effectively tested a replacement of the carbon absorption vessel for one of the trains of the north curtain drain system. The installation and testing appeared to be completed in accordance with the scope of the work order and associated procedures. The inspectors noted that the carbon absorption vessel from the north curtain drain system was shipped offsite as radioactive waste and the residual carbon was awaiting shipment until the waste container was full.
The inspectors determined that Entergy conducted audits in a timely fashion and utilized vulnerability determinations and operating experience to develop audit checklists. Findings or issues identified from audits were entered into the CAP as Condition Reports (CRs).
Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure. CRs appeared to be prioritized and evaluated commensurate with their safety significance.
c. Conclusions
Based on the results of this inspection, no findings of safety significance were identified.
3.0
Exit Meeting Summary
On June 4, 2015, the inspectors presented the inspection results to Don Mayer, Director, IP-1, and other members of Entergys organization. The inspector confirmed that proprietary information was not removed from the site.
SUPPLEMENTARY INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee
- R. Beesley, Radiation Protection (RP) Technician
- G. Dahl, Nuclear Safety/Licensing Specialist IV, Regulatory Assurance*
- J. Doroski, Senior Health Physics/Chemistry Specialist
- R. Drake, Supervisor, Design Engineering - Civil
- C. English, Consultant
- R. Fuchek, Online Work Control Superintendent
- D. Mayer, Director, IP-1*
- J. Michetti, System Engineer, Radiation Monitoring System
- M. Mirzai, Nuclear Safety/Licensing Specialist IV, Regulatory Assurance
- J. Ruch, Engineer III, Design Engineering - Civil
- R. Threlkeld, Quality Assurance (QA) Auditor
- R. Walpole, Manager, Regulatory Assurance*
- C. Wilson, Systems Engineer, Fire Protection
NRC
- A. Bolger, Resident Inspector, Division of Reactor Projects, Region I*
- K. Conway, Project Manager, NMSS*
- G. Newman, Resident Inspector, Division of Reactor Projects, Region I*
- Denotes individuals present during final exit meeting held on June 4, 2015
ITEMS OPEN, CLOSED, AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED
IP-1 TS (Appendix A to Provisional Operating License No. DPR-5)
Indian Point Unit 1 Final Safety Analysis Report
IP-SMM-U1-001, IPEC Site Management Manual, Control of Indian Point 1, Rev. 3
Indian Point Offsite Dose Calculation Manual (ODCM)
IP-RPT-11-00044, SAFSTOR 2011 Structural Inspection
IP-RPT-14-00020, Maintenance Rule Structural Monitoring Inspection Report for the Unit 1
Turbine Building
IP-RPT-15-00019, Maintenance Rule Structural Monitoring Inspection Report for the Unit 1
Nuclear Services Building
EN-LI-100, Process Applicability Determination, Rev. 16
EN-LI-102, Corrective Action Program, Rev. 24
EN-PL-155, Policy, Rev. 5 (Completed Attachments to procedure describing IP-1 organization
change)
EN-QV-109, Audit Process, Rev. 28
EN-QV-129, Vulnerability Review Process, Rev. 8
QA-2/6-2013-IP-01, Quality Assurance Audit Report (Chemistry, Effluent & Environmental),
October 15, 2013
QA-12/18-2013-IP-01, Quality Assurance Audit Report (Operations & Technical Specifications)
QA-9-2014-IP-1, Quality Assurance Audit Report (Fire Protection)
QA-14/15-2013-IP-01, Quality Assurance Audit Report (Radiation Protection & Radwaste)
Audit Plan for QA-2/6-2013-IP-01, Combined Chemistry, Effluent Monitoring Audit, October 15,
2013
Audit Plan for QA-12/18-2013-IP-01, Operations & Technical Specifications Audit, June 5, 2013
Audit Plan for QA-9-2014-IP-1, Fire Protection Audit, January 2, 2014
Audit Plan for QA-14/15-2013-IP-01, Radiation Protection & Radwaste, Audit, September 16, 2013
EN-RP-101, Rev. 11, Access Control for Radiologically Controlled Areas
EN-RP-108, Rev. 15, Radiation Protection Posting
0-RP-ADM-109, Rev. 8, Radiation Protection Periodic Task Scheduling
2014 Annual Radioactive Effluent Release Report
2014 Annual Radiological Environmental Operating Report
Liquid Release Permits and Dose Reports, July 2014 - May 2015
Radiation Work Permit 20151000, Rev. 0, Unit 1 Support - All Groups
SEP-FPP-IP-001, Rev. 4, IPEC Fire Protection Program Plan
Work Order for Replacement of North Curtain Drain Train A Carbon Absorption Vessel, LW-1271
(WO-IPC-00379018, High Delta P, LW-1271 Leak), 5-8-2015
Radiological Survey Reports - Containment (all elevations) and IP-1 steam generators
Radiological Survey - IPEC-1503-0682, VI-004 U1 33 ft VC Annulus, 3-26-2015
Radiological Survey - IPEC-1505-0069, VI-004 U1 33 ft VC Annulus, 5-18-2015
Condition Reports: CR-IP2-2014-05249; CR-IP2-2014-05287; CR-IP2-2015-01378; CR-IP2-2014-
2443
LIST OF ACRONYMS USED
CAP Corrective Action Program
CR Condition Report
Entergy Entergy Nuclear Operations, Inc.
IMC Inspection Manual Chapter
IP Inspection Procedure
IP-1 Indian Point Unit 1
IP-2 Indian Point Unit 2
NRC Nuclear Regulatory Commission
ODCM Offsite Dose Calculation Manual
QA Quality Assurance
REMP Radiological Environmental Monitoring Program
SAFSTOR Safe Storage
TS Technical Specification
UFSAR Updated Final Safety Analysis Report
Attachment