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| issue date = 07/17/2013
| issue date = 07/17/2013
| title = IR 05000003-13-008, on 6/25-27/13, Indian Point
| title = IR 05000003-13-008, on 6/25-27/13, Indian Point
| author name = Ferdas M S
| author name = Ferdas M
| author affiliation = NRC/RGN-I/DNMS/DB
| author affiliation = NRC/RGN-I/DNMS/DB
| addressee name = Ventosa J A
| addressee name = Ventosa J
| addressee affiliation = Entergy Nuclear Operations, Inc
| addressee affiliation = Entergy Nuclear Operations, Inc
| docket = 05000003
| docket = 05000003
Line 19: Line 19:


=Text=
=Text=
{{#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
{{#Wiki_filter:July 17, 2013


SUBJECT: ENTERGY NUCLEAR OPERATIONS, lNC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1 - NRC INSPECTION REPORT NO.05000003/201 3008
==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. 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
 
Sincerely,
{/^sfu Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety
 
===Enclosure:===
Inspection Report No. 05000003/201 3008
 
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


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.
=EXECUTIVE SUMMARY=
Entergy Nuclear Operations, Inc.


The current Enforcement Policy is included on the NRC's website at www.nrc.qov; select About NRC, Organizations
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."
& 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)
Based on the results of this inspection, no findings of safety significance were identified.
if you have any questions regarding this matter


Sincerely,
1.0
{/^sfu Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety Enclosure:
 
Inspection Report No. 05000003/201 3008 cc w/encl: Distribution via ListServ Please contact Laurie Kauffman (610-337-5323)
=REPORT DETAILS=
if you have any questions regarding this matter.


Sincerely, Original Slgned By Marc S. Ferdas Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety Enclosure:
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.
Inspection Report No. 05000003/201 3008 cc Wencl: Distribution via ListServ Distribution Wencl: (via E-mail)W. Dean, RA (RIORAMAIL RESOURCE)D. Lew, DRA (RIORAMAIL RESOURCE)D. Roberts, DRP (RIDRPMAlL RESOURGE)A. Burritt, DRP (RIDRPMAIL RESOURCE)R. Lorson, DRS (RIDRSMAlL RESOURCE)J. Rogge, DRS (RIDRSMAIL RESOURCE)S. Rutenkroger, DRP T. Setzer. DRP S. Mccarver, DRP L. McKown, DRP S. Stewart, DRP, SRI K. Dunham, DRP, Rl A. Patel, DRP, Rl D. Hochmuth, DRP, AA J. Clifford, DNMS D. Collins, DNMS M. Ferdas, DNMS L. Kauffman, DNMS B. Watson, FSME S. Giebel, FSME V. Campbell, Rl OEDO RidsNrrPM I ndian Point Resource RidsNrrDorlLpll
-1 Resource ROPReports Resources DOC U M ENT NAM E: G :\WordDocs\Current\l nsp Letter\LDP R-5. 20 1 3008.doc M1131984555 SUNSI Review Complete:
LKauffman After dectaring this document'An official Agency Record" it will be released to the of this document.


indicate in the box: "C' ='E" = Coov W attach/encl
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).
'N" OFFICE DNMS/RI I N DNMS/RI NAME LKauffman/lk MFerdas/msf DATE o7t 16 I 2013 17 l 2013 07l FICIAL RECORD COPY Inspection No.Docket No.License No.Licensee: Facility: Address: Inspection Dates: Inspector:
Approved By: 1 U.S. NUCLEAR REGULATORY COMMISSION 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


=SUMMARY=
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).
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.
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.


1.0 3
The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC 2561.


=REPORT DETAILS=
Safe Storage (SAFSTOR) Performance and Status Review lnspection Scope (lnspection Procedures (lPs) 36801, 37801. 40801. 62801. 64704. 71801.
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.
83750.84750. 86750)
A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1.


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)
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).
Performance and Status Review 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.
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.


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


The inspector discussed any design changes or modifications since the previous inspection.
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 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 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.


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:
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.
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.
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 changes included suspending the demolition of the stack and containment annulus exhaust duct at 200 feet
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.
: (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 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 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 determined that the radioactive waste shipping papers were complete and accurate.
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.


3.0 5 The inspector determined that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance.
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.


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 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.


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


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
REVIEWED Indian Point Unit 1 Final Safety Analysis Report lP-1 TS (Appendix
Corrective Action Program
A to Provisional
EC
Operating
Engineering Change
License No. DPR-S)lP-2 TS (Appendix
ECN
A of the Indian Point Unit 2 Facility Operating
Engineering Change Notice
License No. DPR-26)lndian Point Offsite Dose Calculation
Entergy Entergy Nuclear Operations, Inc.
Manual (ODCM)0-CY-1 840,'ODCM
ft
lmpact Reviews" lP-SMM-U1-001, 'IPEC Site Management
feet
Manual, Gontrol of Indian Point 1" O-RP-ADM-1
IMC
09, "Radiation
Inspection Manual Chapter
Protection
lP
Periodic Task Scheduling" EN-RP-101, Access Control for Radiologically
lnspection Procedure
Controlled
IPEC
Areas" EN-RP-1 08, Radiation
Indian Point Energy Center
Protection
lP-1
Posting" EN-RP-203, "Dose Assessment" RP-STD-17, "satellite
lndian Point Unit 1
RP Key lssuance and HRA, LHRA, and VHRA Boundary Verifications" IPEC-CHM-13-001, Radioactivity
lP-2
Releases From IPEC - December 2012. Memorandum
lndian Point Unit 2
dated January 9,2013 2012 Annual Radioactive
msl
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
Mean Sea Level
TS PRM R-60 GAL (WO#52309310-01)
NRC
April 19, 2013 TST-2-PC-
Nuclear Regulatory Commission
2Y 23-62-2Y CAL R-62 (WO#5230 9287 -O 1) Au g ust 24, 201 1 2-SOP-12-03-01
ODCM
and 2-SOP-12-03-02
Offsite Dose Calculation Manual
for Radiation
SAFSTOR Safe Storage
Monitor (R-60) Operation Sphere Foundation
TS
Sump Pump Discharge
Technical Specification
Flow Meter Calibration (WO#52309615-01)
UFSAR Updated Final Safety Analysis Report
2115111 North Curtain Drain Effluent Line Flow Meter Calibration (WO#52309368-01)
Attachment
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
}}
}}

Latest revision as of 06:44, 11 January 2025

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
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July 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

Sincerely,

{/^sfu Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety

Enclosure:

Inspection Report No. 05000003/201 3008

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

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.

1.0

REPORT DETAILS

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.

Safe Storage (SAFSTOR) Performance and Status Review 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 2.0 a.

b.

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.

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.

3.0 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.

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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