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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSIA. PENNSYLVANIA 19406-2713 July 17, 2013 Docket No. 05000003 John Ventosa Site Vice President Entergy Nuclear Operations, Inc, Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 1051 1-0249 License No. DPR-S SUBJECT: ENTERGY NUCLEAR OPERATIONS, lNC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1 - NRC INSPECTION REPORT NO.05000003/201 3008
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION uly 17, 2013
 
==SUBJECT:==
ENTERGY NUCLEAR OPERATIONS, lNC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1 - NRC INSPECTION REPORT NO.
 
05000003/201 3008


==Dear Mr. Ventosa:==
==Dear Mr. Ventosa:==
On June 25 -27,2A13, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the lndian 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 Chris English, Superintendent, Unit 1, and other members of your staff on June 27 ,2Q13, and are described in the enclosed inspection report. No findings of safety significance were identified.
On June 25 -27,2A13, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the lndian 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 Chris English, Superintendent, Unit 1, and other members of your staff on June 27 ,2Q13, 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 www.nrc.qov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Gommunications.
Current NRC regulations and guidance are included on the NRC's website at www.nrc.qov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Gommunications. The current Enforcement Policy is included on the NRC's website at www.nrc.qov; 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). Please contact Laurie Kauffman (610-337-5323) if you have any questions regarding this matter
  {/^sfu


The current Enforcement Policy is included on the NRC's website at www.nrc.qov; select About NRC, Organizations
Sincerely, Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety
& 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). Please contact Laurie Kauffman (610-337-5323)
===Enclosure:===
if you have any questions regarding this matter
Inspection Report No. 05000003/201 3008


Sincerely,
REGION I==
{/^sfu Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety  
INSPECTION REPORT Inspection No. 05000003/201 3008 Docket No. 05000003 License No. DPR-5 Licensee: Entergy Nuclear Operations Inc. (Entergy)
Facility: lndian Point Nuclear Generating Station Unit 1 (lP-1)
Address:  450 Broadway Buchanan, NY 1051 1-0249 Inspection Dates: June 25 -27.2013 Inspector: Laurie A. Kauffman Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Approved By: Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety


===Enclosure:===
=EXECUTIVE SUMMARY=
Inspection Report No. 05000003/201 3008
Entergy Nuclear Operations, Inc.
 
Indian Point Nuclear Generating Station Unit 1 NRC lnspection Report No. 05000003/2013008 A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1. The inspection included a review of operations, management oversight, maintenance, corrective action program 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, and a review of procedures and records. The inspection also included a review of activities associated with the partial dismantlement of the lP-1 vent stack. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in lnspection Manual Chapter (lMC) 2561, "Decommissioning Power Reactor Inspection Program."
 
Based on the results of this inspection, no findings of safety significance were identified.
 
=REPORT DETAILS=


REGION I INSPECTION REPORT 05000003/201 3008 05000003 DPR-5 Entergy Nuclear Operations Inc. (Entergy)lndian Point Nuclear Generating Station Unit 1 (lP-1)450 Broadway Buchanan, NY 1051 1-0249 June 25 -27.2013 Laurie A. Kauffman Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety 2 EXECUTIVE
1.0  Background lP-1 is a pressurized water reactor that was granted a 4O-year Operating License in 1962, and was permanently shut down in 1974, 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 (lP-2) operations.


=SUMMARY=
lP-1 and lP-2 are physically contiguous and share systems and facilities as well as a common operating organization. lP-1 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).
Entergy Nuclear Operations, Inc.Indian Point Nuclear Generating


Station Unit 1 NRC lnspection Report No. 05000003/2013008 A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1. The inspection included a review of operations, management oversight, maintenance, corrective action program 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, and a review of procedures and records. The inspection also included a review of activities associated with the partial dismantlement of the lP-1 vent stack. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in lnspection Manual Chapter (lMC) 2561, "Decommissioning Power Reactor Inspection Program." Based on the results of this inspection, no findings of safety significance were identified.
Services provided by lP-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).


1.0 3
Appendix A to Provisional Operating License No. DPR-S recognizes this commonality as well as the intended use of the lP-1 facilities to support lP-2 until retirement of that unit, and contains specific references to Appendix A of the lP-2 Facility Operating License No. DPR-26.


=REPORT DETAILS=
The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC 2561.
Background lP-1 is a pressurized water reactor that was granted a 4O-year Operating License in 1962, and was permanently shut down in 1974, 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 (lP-2) operations.


lP-1 and lP-2 are physically contiguous and share systems and facilities as well as a common operating organization.
2.0  Safe Storage (SAFSTOR) Performance and Status Review a. lnspection Scope (lnspection Procedures (lPs) 36801, 37801. 40801. 62801. 64704. 71801.


lP-1 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 lP-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-S recognizes this commonality as well as the intended use of the lP-1 facilities to support lP-2 until retirement of that unit, and contains specific references to Appendix A of the lP-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 IMC 2561.Safe Storage (SAFSTOR)
83750.84750. 86750)
Performance and Status Review lnspection Scope (lnspection Procedures (lPs) 36801, 37801. 40801. 62801. 64704. 71801.83750.84750.
A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1.


86750)A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1.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 lndian Point 1," to assess the adequacy of management oversight of SAFSTOR responsibilities for the lP-1 facility.
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 lndian Point 1," to assess the adequacy of management oversight of SAFSTOR responsibilities for the lP-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 lP-1 facility (nuclear service building, the chemical systems building, fuel handling building, and the lP-1 main stack).


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 also reviewed activities associated with the partial dismantlement of the lP-1 vent stack and containment annulus exhaust duct that occurred between June 2012 and February 2013. Specifically, the inspector reviewed the most recent engineering change notices (ECNs) to the engineering change (EC) document 32468, "lP-1 Vent Stack Height Modification." The inspector reviewed documents used by Entergy during the partial dismantlement of the lP-l stack, including work orders, radiation work permits, and documents associated with the management, control and transportation of the stack debris.


The inspector discussed any design changes or modifications since the previous inspection.
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 radioactive gaseous and liquid effluent release reports, the groundwater monitoring program, the annual REMP report, and the annual effluent report, which included a summary of the radioactive waste management and transportation programs.


The inspector also conducted a tour to assess the material condition of lP-1 facility (nuclear service building, the chemical systems building, fuel handling building, and the lP-1 main stack).The inspector also reviewed activities associated with the partial dismantlement of the lP-1 vent stack and containment annulus exhaust duct that occurred between June 2012 and February 2013. Specifically, the inspector reviewed the most recent engineering change 2.0 a.
The inspector also reviewed corrective action program (CAP) condition reports associated with lP-1 to determine if issues were being properly identified and evaluated, and if corrective actions were appropriately prioritized in the CAP. The inspector also reviewed corrective actions related to condition report CR-lP2-2012-03986, which addressed a Severity Level lV Non Cited Violation that was issued in NRC Inspection Report No. 0500000312012010, dated July 19,2012.


b.4 notices (ECNs) to the engineering change (EC) document 32468, "lP-1 Vent Stack Height Modification." The inspector reviewed documents used by Entergy during the partial dismantlement of the lP-l stack, including work orders, radiation work permits, and documents associated with the management, control and transportation of the stack debris.The inspector reviewed activities and documentation associated with the following SAFSTOR programs:
b. Observations and Findinqs The inspector noted that there were no personnel changes within lP-1 related to the SAFSTOR activities and confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures.
occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspector reviewed radioactive gaseous and liquid effluent release reports, the groundwater monitoring program, the annual REMP report, and the annual effluent report, which included a summary of the radioactive waste management and transportation programs.The inspector also reviewed corrective action program (CAP) condition reports associated with lP-1 to determine if issues were being properly identified and evaluated, and if corrective actions were appropriately prioritized in the CAP. The inspector also reviewed corrective actions related to condition report CR-lP2-2012-03986, which addressed a Severity Level lV Non Cited Violation that was issued in NRC Inspection Report No. 0500000312012010, dated July 19,2012.Observations and Findinqs The inspector noted that there were no personnel changes within lP-1 related to the SAFSTOR activities and confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures.


The inspector evaluated four ECNs to EC32468 related to the lP-1 vent stack partial dismantlement.
The inspector evaluated four ECNs to EC32468 related to the lP-1 vent stack partial dismantlement. The changes included suspending the demolition of the stack and containment annulus exhaust duct at 200 feet
: (ft) above mean sea level (msl) instead of at 170 ft above msl, as originally planned. The changes also included re-evaluation of the associated seismic, wind fragility, and dose assessments for the stack at20O ft above msl.


The changes included suspending the demolition of the stack and containment annulus exhaust duct at 200 feet
The inspector determined that the decision to suspend the dismantlement activities at 200 ft above msl did not significantly alter the conclusions of the originat EG and that Entergy's overall dismantlement goals had been met. The inspector determined through interviews and a review of condition reports that there were no accidental drop events during this project.
: (ft) above mean sea level (msl) instead of at 170 ft above msl, as originally planned. The changes also included re-evaluation of the associated seismic, wind fragility, and dose assessments for the stack at20O ft above msl.The inspector determined that the decision to suspend the dismantlement activities at 200 ft above msl did not significantly alter the conclusions of the originat EG and that Entergy's overall dismantlement goals had been met. The inspector determined through interviews and a review of condition reports that there were no accidental drop events during this project.The inspector noted that the partial demolition of the stack and containment annulus exhaust duct was completed and Entergy was in the process of completing some final activities associated with the project (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) at the time of the inspection.


The annual radiological effluent and REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix l. The inspector noted that Entergy shipped one container of debris from the stack dismantlement project for offsite disposal, as low specific activity radioactive material.
The inspector noted that the partial demolition of the stack and containment annulus exhaust duct was completed and Entergy was in the process of completing some final activities associated with the project (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) at the time of the inspection.


The inspector determined that the radioactive waste shipping papers were complete and accurate.
The annual radiological effluent and REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix l. The inspector noted that Entergy shipped one container of debris from the stack dismantlement project for offsite disposal, as low specific activity radioactive material. The inspector determined that the radioactive waste shipping papers were complete and accurate.


3.0 5 The inspector determined that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance.
The inspector determined that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance. Corrective actions were implemented to address identified issues and were being tracked to closure using the CAP.


Corrective actions were implemented to address identified issues and were being tracked to closure using the CAP.Conclusions Based on the results of this inspection, no findings of safety significance were identified.
Conclusions Based on the results of this inspection, no findings of safety significance were identified.


Exit Meeting Summary On June 27,2013, the inspector presented the inspection results to Chris English, Superintendent, lP-1, and other members of Entergy's organization.
3.0


The inspector confirmed that proprietary information was not provided or examined during the inspection.
=====Exit Meeting Summary=====
On June 27,2013, the inspector presented the inspection results to Chris English, Superintendent, lP-1, and other members of Entergy's organization. The inspector confirmed that proprietary information was not provided or examined during the inspection.


A-1
=SUPPLEMENTARY INFORMATION=


=SUPPLEMENTARY
PARTIAL LIST OF PERSONS CONTACTED
INFORMATION=
Licensee
: [[contact::G. Dahl]], Licensing Engineer
M, Donegan, Certified Health Physicist Consultant, lP-1
: [[contact::J. Doroski]], Health Physics and Chemistry Specialist
: [[contact::C. English]], Superintendent, lP-1
: [[contact::M. Readinger]], Radiation Protection Supervisor
: [[contact::R. Rodino]], Superintendent, Radiation Protection
: [[contact::W. Scholtens]], Radioactive Waste Engineer
ITEMS OPEN. CLOSED. AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED
Indian Point Unit 1 Final Safety Analysis Report
lP-1 TS (Appendix A to Provisional Operating License No. DPR-S)
lP-2 TS (Appendix A of the Indian Point Unit 2 Facility Operating License No. DPR-26)
lndian Point Offsite Dose Calculation Manual (ODCM)
0-CY-1 840,'ODCM lmpact Reviews"
lP-SMM-U1-001, 'IPEC Site Management Manual, Gontrol of Indian Point 1"
O-RP-ADM-1 09, "Radiation Protection Periodic Task Scheduling"
EN-RP-101, Access Control for Radiologically Controlled Areas"
EN-RP-1 08, Radiation Protection Posting"
EN-RP-203, "Dose Assessment"
RP-STD-17, "satellite RP Key lssuance and HRA, LHRA, and VHRA Boundary Verifications"
IPEC-CHM-13-001, Radioactivity Releases From IPEC - December 2012. Memorandum dated
January 9,2013
2012 Annual Radioactive Effluent Release Report, dated May 1 ,2013
Liquid Release and Dose Summary Reports, January 2012- May 2013
Gaseous Release and Dose Summary Reports, January 2012 - May 2013
TST-2-PC-EM32-2Y TS PRM R-60 GAL (WO#52309310-01) April 19, 2013
TST-2-PC- 2Y 23-62-2Y CAL R-62 (WO#5230 9287 -O 1) Au g ust 24, 201 1
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 (WO#52309615-01) 12115111
North Curtain Drain Effluent Line Flow Meter Calibration (WO#52309368-01) 912512012
2012 Annual Radiological Environmental Operating Report, dated May 1 5,2013
lP-RPT-1 1-OOO44, "SAFSTOR 2011 Structural Inspection"
EN-Ll-100, "Process Applicability Determination; Engineering Change 32468/ECN40171
EC No.: 324681 ECN 37267; ECN 40171; ECN 42663; ECN 44305; ECN 45312


PARTIAL LIST OF PERSONS CONTACTED Licensee
Radiological Surveys - Containment (allelevations) (June 2012; November 2012; April2013)
: [[contact::G. Dahl]], Licensing
Radiological Surveys - lP-1 steam generators (June 2012; November 2012; April2013)
Engineer M, Donegan, Certified
Dose Totalsfor 2012 and January - June 2013 (RWPs: 2013-1000 through 1005)
Health Physicist
SEP-FPP-IP-001, 'IPEC Fire Protection Program Plan"
Consultant, lP-1
O-PT-M004, "Fire Extinguisher lnspection" (monthly: December 2012 through May 2013)
: [[contact::J. Doroski]], Health Physics and Chemistry
PT-A178, "Fire Hose Stations" (annual: April 2012 and April 2013)
Specialist
2-PT-A062, "Fire Hose Hydrostatic Test Verification" (annual: July 21,2011 & September 2,2012)
: [[contact::C. English]], Superintendent, lP-1
2-PT-M112, "Fire Protection Flow Path and Hose Station Equipment Verification" (monthly: April
: [[contact::M. Readinger]], Radiation
and May 2013)
Protection
Condition Reports. lP2-2012-03888; lP2-2012-03890; 1P2-2012-03986; lP2-2012-04163; lP2-2012-
Supervisor
Q4752; lP2-2012-04810; lP2-2012-06344; tP2-2012-04856; lP2-2012-04946; tP2-2012-O7021',
: [[contact::R. Rodino]], Superintendent, Radiation
lP2-2013-00397; lP2-2013-0051 9; lP2-2Q13-00807; lP2-2013-01040; 1P2-2013-01865; lP2-
Protection
1 3-0 1 687 ; lP2-2Q 1 3-017 1 4; lP2-20 13-0 1 789 ; lP2-20 1 3-02O44;
: [[contact::W. Scholtens]], Radioactive
LIST OF ACRONYMS USED
Waste Engineer ITEMS OPEN. CLOSED. AND DISCUSSED None LIST OF DOCUMENTS
CAP               Corrective Action Program
REVIEWED Indian Point Unit 1 Final Safety Analysis Report lP-1 TS (Appendix
EC               Engineering Change
A to Provisional
ECN               Engineering Change Notice
Operating
Entergy Entergy Nuclear Operations, Inc.
License No. DPR-S)lP-2 TS (Appendix
ft               feet
A of the Indian Point Unit 2 Facility Operating
IMC               Inspection Manual Chapter
License No. DPR-26)lndian Point Offsite Dose Calculation
lP               lnspection Procedure
Manual (ODCM)0-CY-1 840,'ODCM
IPEC             Indian Point Energy Center
lmpact Reviews" lP-SMM-U1-001, 'IPEC Site Management
lP-1             lndian Point Unit   1
Manual, Gontrol of Indian Point 1" O-RP-ADM-1
lP-2             lndian Point Unit 2
09, "Radiation
msl               Mean Sea Level
Protection
NRC               Nuclear Regulatory Commission
Periodic Task Scheduling" EN-RP-101, Access Control for Radiologically
ODCM Offsite Dose Calculation Manual
Controlled
SAFSTOR Safe Storage
Areas" EN-RP-1 08, Radiation
TS               Technical Specification
Protection
UFSAR Updated Final Safety Analysis Report
Posting" EN-RP-203, "Dose Assessment" RP-STD-17, "satellite
Attachment
RP Key lssuance and HRA, LHRA, and VHRA Boundary Verifications" IPEC-CHM-13-001, Radioactivity
Releases From IPEC - December 2012. Memorandum
dated January 9,2013 2012 Annual Radioactive
Effluent Release Report, dated May 1 ,2013 Liquid Release and Dose Summary Reports, January 2012- May 2013 Gaseous Release and Dose Summary Reports, January 2012 - May 2013 TST-2-PC-EM32-2Y
TS PRM R-60 GAL (WO#52309310-01)
April 19, 2013 TST-2-PC-
2Y 23-62-2Y CAL R-62 (WO#5230 9287 -O 1) Au g ust 24, 201 1 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 (WO#52309615-01)
2115111 North Curtain Drain Effluent Line Flow Meter Calibration (WO#52309368-01)
2512012 2012 Annual Radiological
Environmental
Operating
Report, dated May 1 5,2013 lP-RPT-1 1-OOO44, "SAFSTOR 2011 Structural
Inspection" EN-Ll-100, "Process Applicability
Determination;
Engineering
Change 32468/ECN40171
EC No.: 324681 ECN 37267; ECN 40171; ECN 42663; ECN 44305; ECN 45312 Attachment
Radiological
Surveys - Containment (allelevations) (June 2012; November 2012; April2013)
Radiological
Surveys - lP-1 steam generators (June 2012; November 2012; April2013)
Dose Totalsfor
2012 and January - June 2013 (RWPs: 2013-1000
through 1005)SEP-FPP-IP-001, 'IPEC Fire Protection
Program Plan" O-PT-M004, "Fire Extinguisher
lnspection" (monthly:
December 2012 through May 2013)PT-A178, "Fire Hose Stations" (annual: April 2012 and April 2013)2-PT-A062, "Fire Hose Hydrostatic
Test Verification" (annual: July 21,2011 & September
2,2012)2-PT-M112, "Fire Protection
Flow Path and Hose Station Equipment
Verification" (monthly:
April and May 2013)Condition
Reports. lP2-2012-03888;
lP2-2012-03890;
1P2-2012-03986;
lP2-2012-04163;
lP2-2012-Q4752; lP2-2012-04810;
lP2-2012-06344;
tP2-2012-04856;
lP2-2012-04946;
tP2-2012-O7021', lP2-2013-00397;
lP2-2013-0051
9; lP2-2Q13-00807;
lP2-2013-01040;
1P2-2013-01865;
lP2-20 1 3-0 1 687 ; lP2-2Q 1 3-017 1 4; lP2-20 13-0 1 789 ; lP2-20 1 3-02O44;LIST OF ACRONYMS USED CAP Corrective
Action Program EC Engineering
Change ECN Engineering
Change Notice Entergy Entergy Nuclear Operations, Inc.ft feet IMC Inspection
Manual Chapter lP lnspection
Procedure IPEC Indian Point Energy Center lP-1 lndian Point Unit 1 lP-2 lndian Point Unit 2 msl Mean Sea Level NRC Nuclear Regulatory
Commission
ODCM Offsite Dose Calculation
Manual SAFSTOR Safe Storage TS Technical
Specification
UFSAR Updated Final Safety Analysis Report Attachment
}}
}}

Revision as of 15:52, 4 November 2019

IR 05000003-13-008, on 6/25-27/13, Indian Point
ML13198A555
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 07/17/2013
From: Marc Ferdas
Decommissioning Branch I
To: Ventosa J
Entergy Nuclear Operations
References
FOIA/PA-2016-0148 IR-13-008
Download: ML13198A555 (10)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION uly 17, 2013

SUBJECT:

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

05000003/201 3008

Dear Mr. Ventosa:

On June 25 -27,2A13, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the lndian 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 Chris English, Superintendent, Unit 1, and other members of your staff on June 27 ,2Q13, 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 www.nrc.qov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Gommunications. The current Enforcement Policy is included on the NRC's website at www.nrc.qov; 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). Please contact Laurie Kauffman (610-337-5323) if you have any questions regarding this matter

{/^sfu

Sincerely, Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety

Enclosure:

Inspection Report No. 05000003/201 3008

REGION I==

INSPECTION REPORT Inspection No. 05000003/201 3008 Docket No. 05000003 License No. DPR-5 Licensee: Entergy Nuclear Operations Inc. (Entergy)

Facility: lndian Point Nuclear Generating Station Unit 1 (lP-1)

Address: 450 Broadway Buchanan, NY 1051 1-0249 Inspection Dates: June 25 -27.2013 Inspector: Laurie A. Kauffman Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Approved By: Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety

EXECUTIVE SUMMARY

Entergy Nuclear Operations, Inc.

Indian Point Nuclear Generating Station Unit 1 NRC lnspection Report No. 05000003/2013008 A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1. The inspection included a review of operations, management oversight, maintenance, corrective action program 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, and a review of procedures and records. The inspection also included a review of activities associated with the partial dismantlement of the lP-1 vent stack. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in lnspection Manual Chapter (lMC) 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 lP-1 is a pressurized water reactor that was granted a 4O-year Operating License in 1962, and was permanently shut down in 1974, 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 (lP-2) operations.

lP-1 and lP-2 are physically contiguous and share systems and facilities as well as a common operating organization. lP-1 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 lP-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-S recognizes this commonality as well as the intended use of the lP-1 facilities to support lP-2 until retirement of that unit, and contains specific references to Appendix A of the lP-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 IMC 2561.

2.0 Safe Storage (SAFSTOR) Performance and Status Review a. lnspection Scope (lnspection Procedures (lPs) 36801, 37801. 40801. 62801. 64704. 71801.

83750.84750. 86750)

A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1.

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 lndian Point 1," to assess the adequacy of management oversight of SAFSTOR responsibilities for the lP-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 lP-1 facility (nuclear service building, the chemical systems building, fuel handling building, and the lP-1 main stack).

The inspector also reviewed activities associated with the partial dismantlement of the lP-1 vent stack and containment annulus exhaust duct that occurred between June 2012 and February 2013. Specifically, the inspector reviewed the most recent engineering change notices (ECNs) to the engineering change (EC) document 32468, "lP-1 Vent Stack Height Modification." The inspector reviewed documents used by Entergy during the partial dismantlement of the lP-l stack, including work orders, radiation work permits, and documents associated with the management, control and transportation 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 radioactive gaseous and liquid effluent release reports, the groundwater monitoring program, the annual REMP report, and the annual effluent report, which included a summary of the radioactive waste management and transportation programs.

The inspector also reviewed corrective action program (CAP) condition reports associated with lP-1 to determine if issues were being properly identified and evaluated, and if corrective actions were appropriately prioritized in the CAP. The inspector also reviewed corrective actions related to condition report CR-lP2-2012-03986, which addressed a Severity Level lV Non Cited Violation that was issued in NRC Inspection Report No. 0500000312012010, dated July 19,2012.

b. Observations and Findinqs The inspector noted that there were no personnel changes within lP-1 related to the SAFSTOR activities and confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures.

The inspector evaluated four ECNs to EC32468 related to the lP-1 vent stack partial dismantlement. The changes included suspending the demolition of the stack and containment annulus exhaust duct at 200 feet

(ft) above mean sea level (msl) instead of at 170 ft above msl, as originally planned. The changes also included re-evaluation of the associated seismic, wind fragility, and dose assessments for the stack at20O ft above msl.

The inspector determined that the decision to suspend the dismantlement activities at 200 ft above msl did not significantly alter the conclusions of the originat EG and that Entergy's overall dismantlement goals had been met. The inspector determined through interviews and a review of condition reports that there were no accidental drop events during this project.

The inspector noted that the partial demolition of the stack and containment annulus exhaust duct was completed and Entergy was in the process of completing some final activities associated with the project (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) at the time of the inspection.

The annual radiological effluent and REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix l. The inspector noted that Entergy shipped one container of debris from the stack dismantlement project for offsite disposal, as low specific activity radioactive material. The inspector determined that the radioactive waste shipping papers were complete and accurate.

The inspector determined that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance. Corrective actions were implemented to address identified issues and were being tracked to closure using the CAP.

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

3.0

Exit Meeting Summary

On June 27,2013, the inspector presented the inspection results to Chris English, Superintendent, lP-1, 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

G. Dahl, Licensing Engineer

M, Donegan, Certified Health Physicist Consultant, lP-1

J. Doroski, Health Physics and Chemistry Specialist
C. English, Superintendent, lP-1
M. Readinger, Radiation Protection Supervisor
R. Rodino, Superintendent, Radiation Protection
W. Scholtens, Radioactive Waste Engineer

ITEMS OPEN. CLOSED. AND DISCUSSED

None

LIST OF DOCUMENTS REVIEWED

Indian Point Unit 1 Final Safety Analysis Report

lP-1 TS (Appendix A to Provisional Operating License No. DPR-S)

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

lndian Point Offsite Dose Calculation Manual (ODCM)

0-CY-1 840,'ODCM lmpact Reviews"

lP-SMM-U1-001, 'IPEC Site Management Manual, Gontrol of Indian Point 1"

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

EN-RP-101, Access Control for Radiologically Controlled Areas"

EN-RP-1 08, Radiation Protection Posting"

EN-RP-203, "Dose Assessment"

RP-STD-17, "satellite RP Key lssuance and HRA, LHRA, and VHRA Boundary Verifications"

IPEC-CHM-13-001, Radioactivity Releases From IPEC - December 2012. Memorandum dated

January 9,2013

2012 Annual Radioactive Effluent Release Report, dated May 1 ,2013

Liquid Release and Dose Summary Reports, January 2012- May 2013

Gaseous Release and Dose Summary Reports, January 2012 - May 2013

TST-2-PC-EM32-2Y TS PRM R-60 GAL (WO#52309310-01) April 19, 2013

TST-2-PC- 2Y 23-62-2Y CAL R-62 (WO#5230 9287 -O 1) Au g ust 24, 201 1

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 (WO#52309615-01) 12115111

North Curtain Drain Effluent Line Flow Meter Calibration (WO#52309368-01) 912512012

2012 Annual Radiological Environmental Operating Report, dated May 1 5,2013

lP-RPT-1 1-OOO44, "SAFSTOR 2011 Structural Inspection"

EN-Ll-100, "Process Applicability Determination; Engineering Change 32468/ECN40171

EC No.: 324681 ECN 37267; ECN 40171; ECN 42663; ECN 44305; ECN 45312

Radiological Surveys - Containment (allelevations) (June 2012; November 2012; April2013)

Radiological Surveys - lP-1 steam generators (June 2012; November 2012; April2013)

Dose Totalsfor 2012 and January - June 2013 (RWPs: 2013-1000 through 1005)

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

O-PT-M004, "Fire Extinguisher lnspection" (monthly: December 2012 through May 2013)

PT-A178, "Fire Hose Stations" (annual: April 2012 and April 2013)

2-PT-A062, "Fire Hose Hydrostatic Test Verification" (annual: July 21,2011 & September 2,2012)

2-PT-M112, "Fire Protection Flow Path and Hose Station Equipment Verification" (monthly: April

and May 2013)

Condition Reports. lP2-2012-03888; lP2-2012-03890; 1P2-2012-03986; lP2-2012-04163; lP2-2012-

Q4752; lP2-2012-04810; lP2-2012-06344; tP2-2012-04856; lP2-2012-04946; tP2-2012-O7021',

lP2-2013-00397; lP2-2013-0051 9; lP2-2Q13-00807; lP2-2013-01040; 1P2-2013-01865; lP2-

1 3-0 1 687 ; lP2-2Q 1 3-017 1 4; lP2-20 13-0 1 789 ; lP2-20 1 3-02O44;

LIST OF ACRONYMS USED

CAP Corrective Action Program

EC Engineering Change

ECN Engineering Change Notice

Entergy Entergy Nuclear Operations, Inc.

ft feet

IMC Inspection Manual Chapter

lP lnspection Procedure

IPEC Indian Point Energy Center

lP-1 lndian Point Unit 1

lP-2 lndian Point Unit 2

msl Mean Sea Level

NRC Nuclear Regulatory Commission

ODCM Offsite Dose Calculation Manual

SAFSTOR Safe Storage

TS Technical Specification

UFSAR Updated Final Safety Analysis Report

Attachment

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