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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 STATESNUCLEAR REGULATORY COMMISSION REGION I21OO RENAISSANCE BOULEVARD, SUITE 1OOKING OF PRUSSIA.
{{#Wiki_filter:July 17, 2013


PENNSYLVANIA 19406-2713 July 17, 2013Docket No. 05000003John VentosaSite Vice President Entergy Nuclear Operations, Inc,Indian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 1051 1-0249License No. DPR-S
==SUBJECT:==
ENTERGY NUCLEAR OPERATIONS, lNC., INDIAN POINT NUCLEAR GENERATING STATION UNIT 1 - NRC INSPECTION REPORT NO.


SUBJECT:
05000003/201 3008
ENTERGY NUCLEAR OPERATIONS, lNC., INDIAN POINT NUCLEARGENERATING 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 rulesand regulations, and the conditions of your license.
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.


The inspection consisted of observations bythe inspector, interviews with personnel, and a review of procedures and records.
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


The results ofthe inspection were discussed with Chris English, Superintendent, Unit 1, and other members ofyour staff on June 27 ,2Q13, and are described in the enclosed inspection report. No findings ofsafety significance were identified.
Sincerely,
 
{/^sfu 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; selectNuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance andGommunications.
 
The current Enforcement Policy is included on the NRC's website atwww.nrc.qov; select About NRC, Organizations
& Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under'Related Information')..
You mayalso 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 (exceptFederal holidays). Please contact Laurie Kauffman (610-337-5323)
if you have any questions regarding this matter
 
Sincerely,{/^sfuMarc S. Ferdas, ChiefDecommissioning BranchDivision of Nuclear Materials Safety


===Enclosure:===
===Enclosure:===
Inspection Report No. 05000003/201 3008cc w/encl: Distribution via ListServ Please contact Laurie Kauffman (610-337-5323)
Inspection Report No. 05000003/201 3008
if you have any questions regarding this matter.


Sincerely,Original Slgned By Marc S. FerdasMarc S. Ferdas, ChiefDecommissioning BranchDivision of Nuclear Materials Safety
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


===Enclosure:===
=EXECUTIVE SUMMARY=
Inspection Report No. 05000003/201 3008cc Wencl: Distribution via ListServDistribution Wencl: (via E-mail)W. Dean, RA (RIORAMAIL RESOURCE)
Entergy Nuclear Operations, Inc.
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, DRPT. Setzer. DRPS. Mccarver, DRPL. McKown, DRPS. Stewart, DRP, SRIK. Dunham, DRP, RlA. Patel, DRP, RlD. Hochmuth, DRP, AAJ. Clifford, DNMSD. Collins, DNMSM. Ferdas, DNMSL. Kauffman, DNMSB. Watson, FSMES. Giebel, FSMEV. Campbell, Rl OEDORidsNrrPM I ndian Point ResourceRidsNrrDorlLpll
-1 ResourceROPReports Resources DOC U M ENT NAM E: G :\WordDocs\Current\l nsp Letter\LDP R-5. 20 1 3008.docM1131984555 SUNSI Review Complete:
LKauffman After dectaring this document'An official Agency Record" it will be released totheof this document.


indicate in the box: "C' ='E" = Coov W attach/encl
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."
'N"OFFICEDNMS/RI I NDNMS/RINAMELKauffman/lk MFerdas/msf DATEo7t 16 I 201317 l 201307lFICIAL RECORD COPY Inspection No.Docket No.License No.Licensee:
Facility:
Address:Inspection Dates:Inspector:
Approved By:1U.S. NUCLEAR REGULATORY COMMISSION REGION IINSPECTION REPORT05000003/201 300805000003DPR-5Entergy Nuclear Operations Inc. (Entergy)
lndian Point Nuclear Generating Station Unit 1 (lP-1)450 BroadwayBuchanan, NY 1051 1-0249June 25 -27.2013Laurie A. KauffmanHealth Physicist Decommissioning BranchDivision of Nuclear Materials SafetyMarc S. Ferdas, ChiefDecommissioning BranchDivision of Nuclear Materials Safety 2EXECUTIVE
 
=SUMMARY=
Entergy Nuclear Operations,
 
Inc.Indian Point Nuclear Generating Station Unit 1NRC lnspection Report No. 05000003/2013008 A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1. Theinspection included a review of operations, management oversight, maintenance, corrective actionprogram implementation, fire protection, and plant support activities while in safe storage(SAFSTOR)status. The inspection consisted of observations by the inspector, interviews withEntergy personnel, and a review of procedures and records.
 
The inspection also included a reviewof activities associated with the partial dismantlement of the lP-1 vent stack. The NRC's program foroverseeing 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.
Based on the results of this inspection, no findings of safety significance were identified.


1.03
1.0


=REPORT DETAILS=
=REPORT DETAILS=
Background lP-1 is a pressurized water reactor that was granted a 4O-year Operating License in 1962, andwas permanently shut down in 1974, and is being maintained in SAFSTOR status. Pursuantto 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, datedJanuary 31, 1996, the reactor remains in a defueled status and the unit continues to operateas 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 commonoperating organization.
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 contains radioactive waste processing facilities, which providewaste processing services for both units. Radiological effluent limits are met on an overallsite basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite DoseCalculation Manual (ODCM).Services provided by lP-2 include maintenance, corrective action program implementation, plant support activities while in SAFSTOR status, and implementation of the SAFSTORactivities required in the Updated Final Safety Analysis Report (UFSAR),
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).
and Technical Specifications (TS).Appendix A to Provisional Operating License No. DPR-S recognizes this commonality as wellas the intended use of the lP-1 facilities to support lP-2 until retirement of that unit, andcontains 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 reactoris described in IMC 2561.Safe Storage (SAFSTOR)
Performance and Status Reviewlnspection 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, andprocedure IP-SMM-U1-001,'IPEC Site Management Manual, Control of lndian Point 1," toassess the adequacy of management oversight of SAFSTOR responsibilities for the lP-1facility.
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).


Specifically, the inspector reviewed the decommissioning management and stafforganization and Entergy's implementation of SAFSTOR activities related to safe storage ofradioactive material.
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 inspector discussed any design changes or modifications since theprevious inspection.
The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC 2561.


The inspector also conducted a tour to assess the material condition oflP-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-1vent stack and containment annulus exhaust duct that occurred between June 2012 andFebruary 2013. Specifically, the inspector reviewed the most recent engineering change2.0a.
Safe Storage (SAFSTOR) Performance and Status Review lnspection Scope (lnspection Procedures (lPs) 36801, 37801. 40801. 62801. 64704. 71801.


b.4notices (ECNs) to the engineering change (EC) document 32468, "lP-1 Vent Stack HeightModification."
83750.84750. 86750)
A routine announced safety inspection was conducted on June 25 through 27,2013, at lP-1.


The inspector reviewed documents used by Entergy during the partialdismantlement of the lP-l stack, including work orders, radiation work permits, anddocuments associated with the management, control and transportation of the stack debris.The inspector reviewed activities and documentation associated with the following SAFSTORprograms:
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).
occupational exposure, fire protection, radioactive effluent control, and siteradiological environmental monitoring program (REMP). The inspector reviewed radioactive gaseous and liquid effluent release reports, the groundwater monitoring program, the annualREMP 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 lVNon Cited Violation that was issued in NRC Inspection Report No. 0500000312012010, datedJuly 19,2012.Observations and FindinqsThe inspector noted that there were no personnel changes within lP-1 related to theSAFSTOR activities and confirmed that the staff effectively implemented the SAFSTORprogram.
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 verified that the maintenance and surveillance program for systemsand components had been conducted in accordance with the TS requirements andestablished procedures.
b.


The inspector evaluated four ECNs to EC32468 related to the lP-1 vent stack partialdismantlement.
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 changes included suspending the demolition of the stack andcontainment annulus exhaust duct at 200 feet (ft) above mean sea level (msl) instead of at170 ft above msl, as originally planned.
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 changes also included re-evaluation of theassociated 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 ftabove 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 anda 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 exhaustduct 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, removingdebris from the hopper, and painting the stack and containment annulus exhaust duct) at thetime of the inspection.
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.


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


3.05The inspector determined that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance.
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.


Corrective actions were implemented toaddress 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.
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.


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


A-1
Conclusions Based on the results of this inspection, no findings of safety significance were identified.


=SUPPLEMENTARY
===Exit Meeting Summary===
INFORMATION=
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
PARTIAL LIST OF PERSONS CONTACTED
Licensee
Licensee
: [[contact::G. Dahl]], Licensing
: [[contact::G. Dahl]], Licensing Engineer
EngineerM, Donegan,
M, Donegan, Certified Health Physicist Consultant, lP-1
Certified
: [[contact::J. Doroski]], Health Physics and Chemistry Specialist
Health Physicist
: [[contact::C. English]], Superintendent, lP-1
Consultant,
: [[contact::M. Readinger]], Radiation Protection Supervisor
lP-1
: [[contact::R. Rodino]], Superintendent, Radiation Protection
: [[contact::J. Doroski]],
: [[contact::W. Scholtens]], Radioactive Waste Engineer
Health Physics and Chemistry
ITEMS OPEN. CLOSED. AND DISCUSSED
Specialist
None
: [[contact::C. English]],
LIST OF DOCUMENTS REVIEWED
Superintendent,
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
lP-1
: [[contact::M. Readinger]],
lndian Point Unit 1
Radiation
lP-2
Protection
lndian Point Unit 2
Supervisor
msl
: [[contact::R. Rodino]], Superintendent,
Mean Sea Level
Radiation
NRC
Protection
Nuclear Regulatory Commission
: [[contact::W. Scholtens]],
ODCM
Radioactive
Offsite Dose Calculation Manual
Waste EngineerITEMS OPEN. CLOSED. AND DISCUSSED
SAFSTOR Safe Storage
NoneLIST OF DOCUMENTS
TS
REVIEWEDIndian Point Unit 1 Final Safety Analysis
Technical Specification
ReportlP-1 TS (Appendix
UFSAR Updated Final Safety Analysis Report
A to Provisional
Attachment
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
datedJanuary 9,20132012 Annual Radioactive
Effluent
Release Report, dated May 1 ,2013Liquid Release and Dose Summary Reports,
January 2012- May 2013Gaseous Release and Dose Summary Reports,
January 2012 - May 2013TST-2-PC-EM32-2Y
TS PRM R-60 GAL (WO#52309310-01)
April 19, 2013TST-2-PC-
2Y 23-62-2Y
CAL R-62 (WO#5230
287 -O 1) Au g ust 24, 201 12-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)
2115111North Curtain Drain Effluent
Line Flow Meter Calibration
(WO#52309368-01)
2512012
2012 Annual Radiological
Environmental
Operating
Report, dated May 1 5,2013lP-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 45312Attachment
A-2Radiological
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:
Apriland 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
USEDCAP Corrective
Action ProgramEC Engineering
ChangeECN Engineering
Change NoticeEntergy Entergy Nuclear Operations,
Inc.ft feetIMC Inspection
Manual ChapterlP lnspection
Procedure
IPEC Indian Point Energy CenterlP-1 lndian Point Unit 1lP-2 lndian Point Unit 2msl Mean Sea LevelNRC Nuclear Regulatory
Commission
ODCM Offsite Dose Calculation
ManualSAFSTOR Safe StorageTS Technical
Specification
UFSAR Updated Final Safety Analysis
ReportAttachment
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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
Download: ML13198A555 (10)
v • d • e


Text

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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