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=Text=
=Text=
{{#Wiki_filter:ust 4, 2014
{{#Wiki_filter:August 4, 2014


==SUBJECT:==
==SUBJECT:==
ENTERGY NUCLEAR OPERATIONS, INC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1-NRC INSPECTION REPORT NO. 05000003/2014010
ENTERGY NUCLEAR OPERATIONS, INC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1-NRC INSPECTION REPORT NO.
 
05000003/2014010


==Dear Mr. Ventosa:==
==Dear Mr. Ventosa:==
On June 23-25, 2014 and July 14-16, 2014, 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 Commission's 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 D. Mayer, Director Special Projects, Unit 1, and other members of your staff on July 23, 2014, and are described in the enclosed inspection report. No findings of safety significance were identified.
On June 23-25, 2014 and July 14-16, 2014, 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 Commission's 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.


Current NRC regulations and guidance are included on the NRC's website at select Nuclear Materials; Med, lnd, & Academic Uses; then Regulations, Guidance and Communications.
The results of the inspection were discussed with D. Mayer, Director Special Projects, Unit 1, and other members of your staff on July 23, 2014, and are described in the enclosed inspection report.


The current Enforcement Policy is included on the NRC's website at w_V1£yv.nrQ".9..Q..'{;
No findings of safety significance were identified.
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 8:00a.m. to 5:30p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required.


Please contact Laurie Kauffman (610) 337-5323 if you have any questions regarding this matter.
Current NRC regulations and guidance are included on the NRC's website at w~lt{,.Q.rc.gov; select Nuclear Materials; Med, lnd, & Academic Uses; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at w_V1£yv.nrQ".9..Q..'{; 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 8:00a.m. to 5:30p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Laurie Kauffman (610) 337-5323 if you have any questions regarding this matter.


Sincerely,
Sincerely,
/" (; 4------Patricia A Silva, Acting Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure:
/" (;  
Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ
~~~- 4-- -- --
Patricia A Silva, Acting Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ


=SUMMARY=
=EXECUTIVE SUMMARY=
Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating
Entergy Nuclear Operations, Inc.


Station Unit 1 NRC Inspection Report No. 05000003/2014010 A routine announced safety inspection was conducted on June 23-25, 2014 and July 14 -16, 2014. The inspection included a review of operations, management oversight, maintenance, corrective action program (CAP) implementation, fire protection, and plant support activities while in safe storage (SAFSTOR)status. The inspection consisted of observations by the inspector, interviews with Entergy personnel, a review of procedures and records, and plant downs. The inspection also included a review of final activities associated with the partial dismantlement of the IP-1 vent stack. The NRC's program for overseeing the safe operation of a shutdown 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.
Indian Point Nuclear Generating Station Unit 1 NRC Inspection Report No. 05000003/2014010 A routine announced safety inspection was conducted on June 23-25, 2014 and July 14 - 16, 2014. The inspection included a review of operations, management oversight, maintenance, corrective action program (CAP) implementation, fire protection, and plant support activities while in safe storage (SAFSTOR) status. The inspection consisted of observations by the inspector, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The inspection also included a review of final activities associated with the partial dismantlement of the IP-1 vent stack. The NRC's program for overseeing the safe operation of a shutdown nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561,  
"Decommissioning Power Reactor Inspection Program."


3
Based on the results of this inspection, no findings of safety significance were identified.


=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 197 4, and is being maintained in 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 and the unit continues to operate as a support facility for Indian Point Nuclear Generating Station Unit 2 (IP-2) operations.


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; as well as, a common operating organization.
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 197 4, and is being maintained in 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 and the unit continues to operate as a support facility for Indian Point Nuclear Generating Station Unit 2 (IP-2) operations.


IP-1 also contains radioactive waste processing facilities, which 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 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. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in fMC 2561. 2.0 Safe Storage (SAFSTOR)
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; as well as, a common operating organization. IP-1 also contains radioactive waste processing facilities, which provide waste processing services for both units.
Performance and Status Review


====a. Inspection Scope====
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).
(Inspection Procedures (IPs) 36801, 37801, 40801, 62801, 64704, 71801, 83750, 84750,86750)
A routine announced safety inspection was conducted on June 23 -25, 2014 and July 14 -16, 2014. The inspection consisted of observations by the inspector, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs.


The inspector 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 ,"to assess the adequacy of management oversight of SAFSTOR responsibilities for the IP-1 facility.
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).


Specifically, the inspector reviewed the decommissioning management and staff organization and Entergy's implementation of SAFSTOR activities related to safe storage of radioactive material.
Appendix A to 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.


The inspector discussed any design changes or modifications since the Enclosure 4 previous inspection.
The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in fMC 2561.


The inspector also conducted a tour to assess the material condition of the IP-1 facility.
2.0 Safe Storage (SAFSTOR) Performance and Status Review


The tour included the nuclear service building, chemical systems building, fuel handling building, IP-1 main stack, building roofs, and containment dome. Entergy had conducted and completed activities to dismantle a portion of the IP-1 vent stack and containment annulus exhaust duct from June 2012 through October 2013. During the previous inspection, the inspector reviewed the activities that occurred between June 2012 and February 2013. During this inspection, the inspector reviewed the final activities that occurred between February and October 2013. The inspector evaluated management control and oversight of the dismantlement activities and reviewed the engineering change document, "IP-1 Vent Stack Height Modification," related engineering change notices, work orders, radiation work permits, and disposal of the stack debris. The inspector reviewed activities and documentation associated with the following SAFSTOR programs:
====a. Inspection Scope====
occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspector reviewed radiological survey reports, fire extinguisher and fire hose inspection reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, and the annual effluent release report, which included a summary of the radioactive waste management and transportation programs.
(Inspection Procedures (IPs) 36801, 37801, 40801, 62801, 64704, 71801, 83750, 84750,86750)
A routine announced safety inspection was conducted on June 23 - 25, 2014 and July 14 - 16, 2014. The inspection consisted of observations by the inspector, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs.


The inspector also reviewed the quality assurance audit reports for fire protection, chemistry, and radiation protection, and selected CAP condition reports associated with IP-1 to determine if issues were being properly identified, evaluated, and prioritized.
The inspector 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,"to assess the adequacy of management oversight of SAFSTOR responsibilities for the IP-1 facility. Specifically, the inspector reviewed the decommissioning management and staff organization and Entergy's implementation of SAFSTOR activities related to safe storage of radioactive material. The inspector discussed any design changes or modifications since the previous inspection. The inspector also conducted a tour to assess the material condition of the IP-1 facility. The tour included the nuclear service building, chemical systems building, fuel handling building, IP-1 main stack, building roofs, and containment dome.


====b. Observations and Findings====
Entergy had conducted and completed activities to dismantle a portion of the IP-1 vent stack and containment annulus exhaust duct from June 2012 through October 2013. During the previous inspection, the inspector reviewed the activities that occurred between June 2012 and February 2013. During this inspection, the inspector reviewed the final activities that occurred between February and October 2013. The inspector evaluated management control and oversight of the dismantlement activities and reviewed the engineering change document, "IP-1 Vent Stack Height Modification," related engineering change notices, work orders, radiation work permits, and disposal of the stack debris.
The inspector noted that Entergy made significant personnel changes within IP-1 related to the SAFSTOR activities.


The inspector discussed the Change Management Plan with the Special Projects Director and determined that the IP-1 Superintendent retired, Entergy eliminated several contractor positions, and delegated the roles and responsibilities to maintain IP-1 to representatives of specific site departmental disciplines.
The inspector reviewed activities and documentation associated with the following SAFSTOR programs: occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspector reviewed radiological survey reports, fire extinguisher and fire hose inspection reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, and the annual effluent release report, which included a summary of the radioactive waste management and transportation programs.


The inspector also noted that the Change Management Plan is in its early stages and identified that details regarding specific roles and responsibilities need clarification.
The inspector also reviewed the quality assurance audit reports for fire protection, chemistry, and radiation protection, and selected CAP condition reports associated with IP-1 to determine if issues were being properly identified, evaluated, and prioritized.


The inspector will evaluate the effectiveness of the Change Management Plan during the next NRC inspection.
====b. Observations and Findings====
 
The inspector noted that Entergy made significant personnel changes within IP-1 related to the SAFSTOR activities. The inspector discussed the Change Management Plan with the Special Projects Director and determined that the IP-1 Superintendent retired, Entergy eliminated several contractor positions, and delegated the roles and responsibilities to maintain IP-1 to representatives of specific site departmental disciplines. The inspector also noted that the Change Management Plan is in its early stages and identified that details regarding specific roles and responsibilities need clarification. The inspector will evaluate the effectiveness of the Change Management Plan during the next NRC inspection.
The inspector confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures.


The inspector noted that the staff installed two new pumps at the sphere foundation sump. However, during the site tour, the inspector identified several items that require attention and improvement.
The inspector confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures. The inspector noted that the staff installed two new pumps at the sphere foundation sump. However, during the site tour, the inspector identified several items that require attention and improvement. The items are: general housekeeping, including potential combustible material and storage of ladders; radiological postings and controls; and initial signs of spalling of the containment dome. The inspector noted that Entergy has a structural engineering inspection scheduled for September 2014 that includes the exterior dome. The inspector will evaluate the results of the engineering inspection during the next NRC inspection.


The items are: general housekeeping, including potential combustible material and storage of ladders; radiological postings and controls; and initial signs of spalling of the containment dome. The inspector noted that Entergy has a structural engineering inspection scheduled for September 2014 that includes the exterior dome. The inspector will evaluate the results of the engineering inspection during the next NRC inspection.
The inspector evaluated the final activities associated with the IP-1 vent stack partial dismantlement and containment annulus exhaust duct. The final activities were: welding a new grating cover at the top of the stack, removing debris from the hopper, and painting the stack and containment annulus exhaust duct. The inspector noted that Entergy safely completed the partial dismantlement of the stack and containment annulus exhaust duct in accordance with the related engineering documents and established procedures.


5 The inspector evaluated the final activities associated with the IP-1 vent stack partial dismantlement and containment annulus exhaust duct. The final activities were: welding a new grating cover at the top of the stack, removing debris from the hopper, and painting the stack and containment annulus exhaust duct. The inspector noted that Entergy safely completed the partial dismantlement of the stack and containment annulus exhaust duct in accordance with the related engineering documents 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 inspector noted that radioactive waste was not shipped for offsite disposal since the last inspection.


The annual radiological effluent and REMP reports demonstrated that all calculated doses . were below regulatory dose criteria of 10 CFR 50, Appendix I. The inspector noted that radioactive waste was not shipped for offsite disposal since the last inspection.
The inspector determined that Entergy effectively entered concerns into the CAP to prioritize and evaluate them commensurate with their safety significance. However, the inspector observed that Entergy has not been effective in correcting certain challenges regarding document retrieval, such as, radiological survey records for IP-1 containment.


The inspector determined that Entergy effectively entered concerns into the CAP to prioritize and evaluate them commensurate with their safety significance.
The inspector noted that Entergy initiated a condition report and evaluators from the quality assurance department plan to address the concern during the next quality assurance audit.


However, the inspector observed that Entergy has not been effective in correcting certain challenges regarding document retrieval, such as, radiological survey records for IP-1 containment.
Generally, Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure. The inspector will review the quality assurance audit results during the next NRC inspection.
 
The inspector noted that Entergy initiated a condition report and evaluators from the quality assurance department plan to address the concern during the next quality assurance audit. Generally, Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure. The inspector will review the quality assurance audit results during the next NRC inspection.


====c. Conclusions====
====c. Conclusions====
Based on the results of this inspection, no findings of safety significance were identified.
Based on the results of this inspection, no findings of safety significance were identified.
3.0


3.0 Exit Meeting Summary On July 23, 2014, the inspector presented the inspection results to D. Mayer, Director of Special Projects and other members of Entergy's organization.
===Exit Meeting Summary===
On July 23, 2014, the inspector presented the inspection results to D. Mayer, Director of Special Projects and other members of Entergy's organization. The inspector confirmed that proprietary information was not provided or examined during the inspection.


The inspector confirmed that proprietary information was not provided or examined during the inspection.
=SUPPLEMENTARY INFORMATION=
 
A-1
 
=SUPPLEMENTARY
INFORMATION=


PARTIAL LIST OF PERSONS CONTACTED
PARTIAL LIST OF PERSONS CONTACTED
Licensee  
Licensee  
: [[contact::S. Baer]], Supervisor, Rad Operations, Radiation
: [[contact::S. Baer]], Supervisor, Rad Operations, Radiation Protection  
Protection  
: [[contact::P. Bode]], Senior HP/Chemistry Specialist, Radiation Protection  
: [[contact::P. Bode]], Senior HP/Chemistry
Specialist, Radiation
Protection  
*#
*#
: [[contact::G. Dahl]], Nuclear Safety/Licensing
: [[contact::G. Dahl]], Nuclear Safety/Licensing Specialist IV, Regulatory Assurance  
Specialist
: [[contact::J. Doroski]], Senior HP/Chemistry Specialist, Chemistry  
IV, Regulatory
: [[contact::R. Drake]], Supervisor, Design Engineering - Civil  
Assurance  
: [[contact::K. Elliott]], Senior Staff Engineer, Systems & Components Engineering  
: [[contact::J. Doroski]], Senior HP/Chemistry
Specialist, Chemistry  
: [[contact::R. Drake]], Supervisor, Design Engineering  
-Civil  
: [[contact::K. Elliott]], Senior Staff Engineer, Systems & Components
Engineering  
: [[contact::D. Gray]], Supervisor, Chemistry  
: [[contact::D. Gray]], Supervisor, Chemistry  
: [[contact::L. Hedges]], U2 Control Room Supervisor  
: [[contact::L. Hedges]], U2 Control Room Supervisor  
*#
*#
: [[contact::D. Mayer]], Director, IP-1  
: [[contact::D. Mayer]], Director, IP-1  
: [[contact::J. Michetti]], Senior Lead Engineer, Systems & Components
: [[contact::J. Michetti]], Senior Lead Engineer, Systems & Components Engineering  
Engineering  
: [[contact::J. Ruch]], Engineer Ill, Design Engineering -Civil  
: [[contact::J. Ruch]], Engineer Ill, Design Engineering -Civil  
: [[contact::W. Scholtens]], Senior HP/Chemistry
: [[contact::W. Scholtens]], Senior HP/Chemistry Specialist, Radiation Protection  
Specialist, Radiation
Protection  
: [[contact::C. Smyers]], Manager, Chemistry  
: [[contact::C. Smyers]], Manager, Chemistry  
: [[contact::S. Stevens]], Superintendent, Rad Operations, Radiation
: [[contact::S. Stevens]], Superintendent, Rad Operations, Radiation Protection  
Protection  
*#  
*#  
: [[contact::R. Walpole]], Manager, Regulatory
: [[contact::R. Walpole]], Manager, Regulatory Assurance
Assurance
State  
State *  
*  
: [[contact::B. Frymire]], Power Systems Operations
: [[contact::B. Frymire]], Power Systems Operations Specialist, Department of Public Service  
Specialist, Department
*  
of Public Service *  
: [[contact::A. Burritt]], Branch Chief, Branch 2, Division of Reactor Projects  
: [[contact::A. Burritt]], Branch Chief, Branch 2, Division of Reactor Projects *  
*  
: [[contact::S. Stewart]], Senior Resident Inspector, Division of Reactor Projects  
: [[contact::S. Stewart]], Senior Resident Inspector, Division of Reactor Projects  
: [[contact::A. Patel]], Resident Inspector, Division of Reactor Projects * Denotes individuals
: [[contact::A. Patel]], Resident Inspector, Division of Reactor Projects  
present during pre-exit briefing held on June 25, 2014 # Denotes individuals
* Denotes individuals present during pre-exit briefing held on June 25, 2014  
present during final exit meeting held on July 23, 2014 ITEMS OPEN, CLOSED, AND DISCUSSED
# Denotes individuals present during final exit meeting held on July 23, 2014
None Attachment
ITEMS OPEN, CLOSED, AND DISCUSSED
LIST OF DOCUMENTS
None  
REVIEWED Indian Point Unit 1 Final Safety Analysis Report IP-1 TS (Appendix
 
A to Provisional
LIST OF DOCUMENTS REVIEWED
Operating
Indian Point Unit 1 Final Safety Analysis Report
License No. DPR-5) IP-2 TS (Appendix
IP-1 TS (Appendix A to Provisional Operating License No. DPR-5)
A of the Indian Point Unit 2 Facility Operating
IP-2 TS (Appendix A of the Indian Point Unit 2 Facility Operating License No. DPR-26)
License No. DPR-26) Indian Point Offsite Dose Calculation
Indian Point Offsite Dose Calculation Manual (ODCM)
Manual (ODCM) IP-SMM-U1-001, "IPEC Site Management
IP-SMM-U1-001, "IPEC Site Management Manual, Control of Indian Point 1"
Manual, Control of Indian Point 1" QA-12/18-2013-IP-01, "Quality Assurance
QA-12/18-2013-IP-01, "Quality Assurance Audit Report" (Operations & Technical Specifications)
Audit Report" (Operations  
QA-9-2014-IP-1, "Quality Assurance Audit Report" (Fire Protection)
& Technical
QA-2/6-2013-IP-01, "Quality Assurance Audit Report" (Chemistry, Effluent & Environmental)
Specifications)
QA-14/15-2013-IP-01, "Quality Assurance Audit Report" (Radiation Protection & Radwaste)
QA-9-2014-IP-1, "Quality Assurance
0-RP-ADM-1 09, "Radiation Protection Periodic Task Scheduling"
Audit Report" (Fire Protection)
EN-RP-1 01, "Access Control for Radiologically Controlled Areas"
QA-2/6-2013-IP-01, "Quality Assurance
EN-RP-1 08, "Radiation Protection Posting"
Audit Report" (Chemistry, Effluent & Environmental)
EN-RP-203, "Dose Assessment"
QA-14/15-2013-IP-01, "Quality Assurance
RP-STD-17, "Satellite RP Key Issuance and HRA, LHRA, and VHRA Boundary Verifications"
Audit Report" (Radiation
2013 Annual Radioactive Effluent Release Report
Protection  
2013 Annual Radiological Environmental Operating Report
& Radwaste)
Liquid and Gaseous Release Permits and Dose Summary Reports, January 2014-June 2014
0-RP-ADM-1
TST-2-PC-EM32-2Y; TS PAM R-60 CAL; TST-2-PC-2Y23-62-2Y CAL R-62
09, "Radiation
2-SOP-12-03-01 and 2-SOP-12-03-02 for Radiation Monitor (R-60) Operation
Protection
Sphere Foundation Sump Pump Discharge Flow Meter Calibration
Periodic Task Scheduling" EN-RP-1 01, "Access Control for Radiologically
Controlled
Areas" EN-RP-1 08, "Radiation
Protection
Posting" EN-RP-203, "Dose Assessment" RP-STD-17, "Satellite
RP Key Issuance and HRA, LHRA, and VHRA Boundary Verifications" 2013 Annual Radioactive
Effluent Release Report 2013 Annual Radiological
Environmental
Operating
Report Liquid and Gaseous Release Permits and Dose Summary Reports, January 2014-June 2014 TST-2-PC-EM32-2Y;
TS PAM R-60 CAL; TST-2-PC-2Y23-62-2Y
CAL R-62 2-SOP-12-03-01
and 2-SOP-12-03-02
for Radiation
Monitor (R-60) Operation
Sphere Foundation
Sump Pump Discharge
Flow Meter Calibration
North Curtain Drain Effluent Line Flow Meter Calibration
North Curtain Drain Effluent Line Flow Meter Calibration
IP-RPT-11-00044, "SAFSTOR 2011 Structural
IP-RPT-11-00044, "SAFSTOR 2011 Structural Inspection"
Inspection" Engineering
Engineering Change 32468, "IP-1 Vent Stack Height Modification"
Change 32468, "IP-1 Vent Stack Height Modification" EN-LI-1 00, "Process Applicability
EN-LI-1 00, "Process Applicability Determination"; Engineering Change 32468/ECN40171
Determination";
EC No. 32468/Engineering Change Notice 37267; ECN40171; ECN42663; ECN44305; ECN45312
Engineering
Radiological Survey Reports-Containment (all elevations) and IP-1 steam generators
Change 32468/ECN40171
Dose Totals for 2013 and January-June 2014
EC No. 32468/Engineering
SEP-FPP-IP-001, "IPEC Fire Protection Program Plan"
Change Notice 37267; ECN40171;
O-PT-M004, "Fire Extinguisher Inspection"
ECN42663;
PT-A 178, "Fire Hose Stations"
ECN44305;
2-PT-A062, "Fire Hose Hydrostatic Test Verification"
ECN45312 Radiological
2-PT -M112, "Fire Protection Flow Path and Hose Station Equipment Verification"
Survey Reports-Containment (all elevations)
Condition Reports: CR-IP2-2013-02268; CR-IP2-2013-02299; CR-IP2-2013-02302; CR-IP2-2013-
and IP-1 steam generators
2370; CR-IP2-2013-02535; CR-IP2-2013-02624; CR-IP2-2013-05188; CR-IP2-2013-05206; CR-
Dose Totals for 2013 and January-June 2014 SEP-FPP-IP-001, "IPEC Fire Protection
IP2-2014-00169; CR-IP2-2014-00210; CR-IP2-2014-00214; CR-IP2-2014-00217; CR-IP2-2014-
Program Plan" O-PT-M004, "Fire Extinguisher
027; CR-IP2-2014-01 030; CR-IP2-2014-00527; CR-IP2*2014-03356; CR-IP2-2014-03429; CR-
Inspection" PT-A 178, "Fire Hose Stations" 2-PT-A062, "Fire Hose Hydrostatic
IP2-2014-03932
Test Verification" 2-PT -M112, "Fire Protection
CAP
Flow Path and Hose Station Equipment
Entergy
Verification" Condition
IMC
Reports: CR-IP2-2013-02268;
IP
CR-IP2-2013-02299;
IPEC
CR-IP2-2013-02302;
IP-'1
CR-IP2-2013-
IP-2
2370; CR-IP2-2013-02535;
NRC
CR-IP2-2013-02624;
ODCM
CR-IP2-2013-05188;
REMP
CR-IP2-2013-05206; IP2-2014-00169;
SAFSTOR
CR-IP2-2014-00210;
TS
CR-IP2-2014-00214;
UFSAR
CR-IP2-2014-00217;
LIST OF ACRONYMS USED
CR-IP2-2014-
Corrective Action Program
027; CR-IP2-2014-01
Entergy Nuclear Operations, Inc.
030; CR-IP2-2014-00527;
Inspection Manual Chapter
CR-IP2*2014-03356;
Inspection Procedure
CR-IP2-2014-03429; IP2-2014-03932
Indian Point Energy Center
CAP Entergy IMC IP IPEC IP-'1 IP-2 NRC ODCM REMP SAFSTOR TS UFSAR A-3 LIST OF ACRONYMS USED Corrective
Indian Point Unit 1
Action Program Entergy Nuclear Operations, Inc. Inspection
Indian Point Unit 2
Manual Chapter Inspection
Nuclear Regulatory Commission
Procedure
Offsite Dose Calculation Manual
Indian Point Energy Center Indian Point Unit 1 Indian Point Unit 2 Nuclear Regulatory
Radiological Environmental Monitoring Program
Commission
Safe Storage
Offsite Dose Calculation
Technical Specification
Manual Radiological
Updated Final Safety Analysis Report
Environmental
Attachment
Monitoring
Program Safe Storage Technical
Specification
Updated Final Safety Analysis Report Attachment
}}
}}

Latest revision as of 17:32, 10 January 2025

IR 05000003-14-010 on June 23 - 25, 2014; July 14- 16, 2014; July 23, 2014 (Exit Meeting), Indian Point Nuclear Generating Station Unit 1
ML14217A037
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 08/04/2014
From: Patricia Silva
NRC/RGN-I/DNMS/NMSB3
To: Ventosa J
Entergy Nuclear Operations
References
FOIA/PA-2016-0148 IR14-010
Download: ML14217A037 (11)
v • d • e


Text

August 4, 2014

SUBJECT:

ENTERGY NUCLEAR OPERATIONS, INC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1-NRC INSPECTION REPORT NO.

05000003/2014010

Dear Mr. Ventosa:

On June 23-25, 2014 and July 14-16, 2014, 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 Commission's 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 D. Mayer, Director Special Projects, Unit 1, and other members of your staff on July 23, 2014, and are described in the enclosed inspection report.

No findings of safety significance were identified.

Current NRC regulations and guidance are included on the NRC's website at w~lt{,.Q.rc.gov; select Nuclear Materials; Med, lnd, & Academic Uses; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at w_V1£yv.nrQ".9..Q..'{; 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 8:00a.m. to 5:30p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Laurie Kauffman (610) 337-5323 if you have any questions regarding this matter.

Sincerely,

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Patricia A Silva, Acting Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ

EXECUTIVE SUMMARY

Entergy Nuclear Operations, Inc.

Indian Point Nuclear Generating Station Unit 1 NRC Inspection Report No. 05000003/2014010 A routine announced safety inspection was conducted on June 23-25, 2014 and July 14 - 16, 2014. The inspection included a review of operations, management oversight, maintenance, corrective action program (CAP) implementation, fire protection, and plant support activities while in safe storage (SAFSTOR) status. The inspection consisted of observations by the inspector, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The inspection also included a review of final activities associated with the partial dismantlement of the IP-1 vent stack. The NRC's program for overseeing the safe operation of a shutdown 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 197 4, and is being maintained in 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 and the unit continues to operate as a support facility for Indian Point Nuclear Generating Station Unit 2 (IP-2) operations.

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; as well as, a common operating organization. IP-1 also contains radioactive waste processing facilities, which 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 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.

The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in fMC 2561.

2.0 Safe Storage (SAFSTOR) Performance and Status Review

a. Inspection Scope

(Inspection Procedures (IPs) 36801, 37801, 40801, 62801, 64704, 71801, 83750, 84750,86750)

A routine announced safety inspection was conducted on June 23 - 25, 2014 and July 14 - 16, 2014. The inspection consisted of observations by the inspector, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs.

The inspector 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,"to assess the adequacy of management oversight of SAFSTOR responsibilities for the IP-1 facility. Specifically, the inspector reviewed the decommissioning management and staff organization and Entergy's implementation of SAFSTOR activities related to safe storage of radioactive material. The inspector discussed any design changes or modifications since the previous inspection. The inspector also conducted a tour to assess the material condition of the IP-1 facility. The tour included the nuclear service building, chemical systems building, fuel handling building, IP-1 main stack, building roofs, and containment dome.

Entergy had conducted and completed activities to dismantle a portion of the IP-1 vent stack and containment annulus exhaust duct from June 2012 through October 2013. During the previous inspection, the inspector reviewed the activities that occurred between June 2012 and February 2013. During this inspection, the inspector reviewed the final activities that occurred between February and October 2013. The inspector evaluated management control and oversight of the dismantlement activities and reviewed the engineering change document, "IP-1 Vent Stack Height Modification," related engineering change notices, work orders, radiation work permits, and disposal of the stack debris.

The inspector reviewed activities and documentation associated with the following SAFSTOR programs: occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspector reviewed radiological survey reports, fire extinguisher and fire hose inspection reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, and the annual effluent release report, which included a summary of the radioactive waste management and transportation programs.

The inspector also reviewed the quality assurance audit reports for fire protection, chemistry, and radiation protection, and selected CAP condition reports associated with IP-1 to determine if issues were being properly identified, evaluated, and prioritized.

b. Observations and Findings

The inspector noted that Entergy made significant personnel changes within IP-1 related to the SAFSTOR activities. The inspector discussed the Change Management Plan with the Special Projects Director and determined that the IP-1 Superintendent retired, Entergy eliminated several contractor positions, and delegated the roles and responsibilities to maintain IP-1 to representatives of specific site departmental disciplines. The inspector also noted that the Change Management Plan is in its early stages and identified that details regarding specific roles and responsibilities need clarification. The inspector will evaluate the effectiveness of the Change Management Plan during the next NRC inspection.

The inspector confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures. The inspector noted that the staff installed two new pumps at the sphere foundation sump. However, during the site tour, the inspector identified several items that require attention and improvement. The items are: general housekeeping, including potential combustible material and storage of ladders; radiological postings and controls; and initial signs of spalling of the containment dome. The inspector noted that Entergy has a structural engineering inspection scheduled for September 2014 that includes the exterior dome. The inspector will evaluate the results of the engineering inspection during the next NRC inspection.

The inspector evaluated the final activities associated with the IP-1 vent stack partial dismantlement and containment annulus exhaust duct. The final activities were: welding a new grating cover at the top of the stack, removing debris from the hopper, and painting the stack and containment annulus exhaust duct. The inspector noted that Entergy safely completed the partial dismantlement of the stack and containment annulus exhaust duct in accordance with the related engineering documents 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 inspector noted that radioactive waste was not shipped for offsite disposal since the last inspection.

The inspector determined that Entergy effectively entered concerns into the CAP to prioritize and evaluate them commensurate with their safety significance. However, the inspector observed that Entergy has not been effective in correcting certain challenges regarding document retrieval, such as, radiological survey records for IP-1 containment.

The inspector noted that Entergy initiated a condition report and evaluators from the quality assurance department plan to address the concern during the next quality assurance audit.

Generally, Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure. The inspector will review the quality assurance audit results during the next NRC inspection.

c. Conclusions

Based on the results of this inspection, no findings of safety significance were identified.

3.0

Exit Meeting Summary

On July 23, 2014, the inspector presented the inspection results to D. Mayer, Director of Special Projects and other members of Entergy's organization. The inspector confirmed that proprietary information was not provided or examined during the inspection.

SUPPLEMENTARY INFORMATION

PARTIAL LIST OF PERSONS CONTACTED

Licensee

S. Baer, Supervisor, Rad Operations, Radiation Protection
P. Bode, Senior HP/Chemistry Specialist, Radiation Protection
G. Dahl, Nuclear Safety/Licensing Specialist IV, Regulatory Assurance
J. Doroski, Senior HP/Chemistry Specialist, Chemistry
R. Drake, Supervisor, Design Engineering - Civil
K. Elliott, Senior Staff Engineer, Systems & Components Engineering
D. Gray, Supervisor, Chemistry
L. Hedges, U2 Control Room Supervisor
D. Mayer, Director, IP-1
J. Michetti, Senior Lead Engineer, Systems & Components Engineering
J. Ruch, Engineer Ill, Design Engineering -Civil
W. Scholtens, Senior HP/Chemistry Specialist, Radiation Protection
C. Smyers, Manager, Chemistry
S. Stevens, Superintendent, Rad Operations, Radiation Protection
R. Walpole, Manager, Regulatory Assurance

State

B. Frymire, Power Systems Operations Specialist, Department of Public Service
A. Burritt, Branch Chief, Branch 2, Division of Reactor Projects
S. Stewart, Senior Resident Inspector, Division of Reactor Projects
A. Patel, Resident Inspector, Division of Reactor Projects
  • Denotes individuals present during pre-exit briefing held on June 25, 2014
  1. Denotes individuals present during final exit meeting held on July 23, 2014

ITEMS OPEN, CLOSED, AND DISCUSSED

None

LIST OF DOCUMENTS REVIEWED

Indian Point Unit 1 Final Safety Analysis Report

IP-1 TS (Appendix A to Provisional Operating License No. DPR-5)

IP-2 TS (Appendix A of the Indian Point Unit 2 Facility Operating License No. DPR-26)

Indian Point Offsite Dose Calculation Manual (ODCM)

IP-SMM-U1-001, "IPEC Site Management Manual, Control of Indian Point 1"

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-2/6-2013-IP-01, "Quality Assurance Audit Report" (Chemistry, Effluent & Environmental)

QA-14/15-2013-IP-01, "Quality Assurance Audit Report" (Radiation Protection & Radwaste)

0-RP-ADM-1 09, "Radiation Protection Periodic Task Scheduling"

EN-RP-1 01, "Access Control for Radiologically Controlled Areas"

EN-RP-1 08, "Radiation Protection Posting"

EN-RP-203, "Dose Assessment"

RP-STD-17, "Satellite RP Key Issuance and HRA, LHRA, and VHRA Boundary Verifications"

2013 Annual Radioactive Effluent Release Report

2013 Annual Radiological Environmental Operating Report

Liquid and Gaseous Release Permits and Dose Summary Reports, January 2014-June 2014

TST-2-PC-EM32-2Y; TS PAM R-60 CAL; TST-2-PC-2Y23-62-2Y CAL R-62

2-SOP-12-03-01 and 2-SOP-12-03-02 for Radiation Monitor (R-60) Operation

Sphere Foundation Sump Pump Discharge Flow Meter Calibration

North Curtain Drain Effluent Line Flow Meter Calibration

IP-RPT-11-00044, "SAFSTOR 2011 Structural Inspection"

Engineering Change 32468, "IP-1 Vent Stack Height Modification"

EN-LI-1 00, "Process Applicability Determination"; Engineering Change 32468/ECN40171

EC No. 32468/Engineering Change Notice 37267; ECN40171; ECN42663; ECN44305; ECN45312

Radiological Survey Reports-Containment (all elevations) and IP-1 steam generators

Dose Totals for 2013 and January-June 2014

SEP-FPP-IP-001, "IPEC Fire Protection Program Plan"

O-PT-M004, "Fire Extinguisher Inspection"

PT-A 178, "Fire Hose Stations"

2-PT-A062, "Fire Hose Hydrostatic Test Verification"

2-PT -M112, "Fire Protection Flow Path and Hose Station Equipment Verification"

Condition Reports: CR-IP2-2013-02268; CR-IP2-2013-02299; CR-IP2-2013-02302; CR-IP2-2013-

2370; CR-IP2-2013-02535; CR-IP2-2013-02624; CR-IP2-2013-05188; CR-IP2-2013-05206; CR-

IP2-2014-00169; CR-IP2-2014-00210; CR-IP2-2014-00214; CR-IP2-2014-00217; CR-IP2-2014-

027; CR-IP2-2014-01 030; CR-IP2-2014-00527; CR-IP2*2014-03356; CR-IP2-2014-03429; CR-

IP2-2014-03932

CAP

Entergy

IMC

IP

IPEC

IP-'1

IP-2

NRC

ODCM

REMP

SAFSTOR

TS

UFSAR

LIST OF ACRONYMS USED

Corrective Action Program

Entergy Nuclear Operations, Inc.

Inspection Manual Chapter

Inspection Procedure

Indian Point Energy Center

Indian Point Unit 1

Indian Point Unit 2

Nuclear Regulatory Commission

Offsite Dose Calculation Manual

Radiological Environmental Monitoring Program

Safe Storage

Technical Specification

Updated Final Safety Analysis Report

Attachment

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