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05000003 John Ventosa Site Vice President 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 August 4, 2014 Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 1 0511-0249 License No. DPR-5
05000003 John Ventosa Site Vice President 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 August 4, 2014 Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 1 0511-0249 License No. DPR-5


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


==Dear Mr. Ventosa:==
==Dear Mr. Ventosa:==
On June 23-25, 2014 and July 14-16, 2014, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Indian Point Nuclear Generating Station Unit 1. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license.
On June 23-25, 2014 and July 14-16, 2014, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Indian Point Nuclear Generating Station Unit 1. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with D. Mayer, Director Special Projects, Unit 1, and other members of your staff on July 23, 2014, and are described in the enclosed inspection report. No findings of safety significance were identified.
 
The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records.
 
The results of the inspection were discussed with D. Mayer, Director Special Projects, Unit 1, and other members of your staff on July 23, 2014, and are described in the enclosed inspection report. No findings of safety significance were identified.


Current NRC regulations and guidance are included on the NRC's website at select Nuclear Materials; Med, lnd, & Academic Uses; then Regulations, Guidance and Communications.
Current NRC regulations and guidance are included on the NRC's website at select Nuclear Materials; Med, lnd, & Academic Uses; then Regulations, Guidance and Communications.
Line 39: Line 34:
& Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information').
& 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-
You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-
1800. The GPO is open from 8:00a.m.
1800. The GPO is open from 8:00a.m. to 5:30p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required.
 
to 5:30p.m.
 
EST, Monday through Friday (except Federal holidays). No reply to this letter is required.


Please contact Laurie Kauffman (610) 337-5323 if you have any questions regarding this matter.
Please contact Laurie Kauffman (610) 337-5323 if you have any questions regarding this matter.
Line 50: Line 41:


===Enclosure:===
===Enclosure:===
Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ No reply to this letter is required.
Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ
 
Please contact Laurie Kauffman (61 0) 337-5323 if you have any questions regarding this matter.
 
Sincerely,Original signed by Patricia Silva Patricia A Silva, Acting Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety
 
===Enclosure:===
Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ Distribution w/encl: (via E-mail) (R1 ORAMAIL RESOURCE)
(R1 ORAMAIL RESOURCE)
(R1 DRPMAIL RESOURCE)
(R1 DRPMAIL RESOURCE)
W. Dean, RA D. Lew, ORA H. Nieh, DRP M. Scott, DRP J. Trapp, DRS P. Krohn, DRS A. Burritt, DRP T. Setzer, DRP (R1 DRS MAIL RESOURCE)
(R1 DRS MAIL RESOURCE)
L. McKown, DRP J. Petch, DRP S. Stewart, DRP, SRI A. Patel, DRP, Rl G. Newman, DRP, Rl D. Hochmuth, DRP, AA J. Clifford, DNMS D. Collins, DNMS M. Ferdas, DNMS P. Silva, DNMS L. Kauffman, DNMS B. Watson, FSME S. Giebel, FSME A. Bowers, Rl OEDO RidsNrrPMindianPoint Resource RidsNrrDorllpl1-1 Resource ROPReports Resources ty)L 7 DOCUMENT NAME: G:\DNMS\WordDocs\Current\lnsp Letter\LDPR-5.2014010_1P1.docx SUNS I Review Complete:
LKauffman After declaring this document
"An Official Agency Record" it will be released to the P bl' T f h' h b "C' C "E" C u I C. o receive a copy o t 1s document, indicate in t e ox: -opy w/o attach/encl
= opy w/ attach/encl
"N" = No copy OFFICE DNMS/RI IN DNMS/RI I I I NAME LKauffman/lk PSilva/ps DATE 07/29/2014 08/04/2014 OFFICIAL RECORD COPY Inspection No. Docket No. License No. Licensee:
Facility:
Address:
Inspection Dates: Inspector:
Approved By: U.S. NUCLEAR REGULATORY COMMISSION REGION I INSPECTION REPORT 05000003/2014010 05000003 DPR-5 Entergy Nuclear Operations Inc. (Entergy)
Indian Point Nuclear Generating Station Unit 1 (IP-1) 450 Broadway Buchanan, NY 10511-0249 June 23 -25, 2014; July 14-16, 2014; July 23, 2014 (Exit Meeting)
Laurie A. Kauffman Health Physicist Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Patricia A. Silva, Acting Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure 2 EXECUTIVE


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


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


3
3
Line 89: Line 55:
IP-1 and IP-2 are physically contiguous and share systems, such as the integrated liquid waste system and the air handling system; facilities, such as the chemistry and health physics laboratories; as well as, a common operating organization.
IP-1 and IP-2 are physically contiguous and share systems, such as the integrated liquid waste system and the air handling system; facilities, such as the chemistry and health physics laboratories; as well as, a common operating organization.


IP-1 also contains radioactive waste processing facilities, which provide waste processing services for both units. Radiological effluent limits are met on an overall site basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite Dose Calculation Manual (ODCM). Services provided by IP-2 include maintenance, corrective action program implementation, plant support activities while in SAFSTOR status, and implementation of the SAFSTOR activities required in the Updated Final Safety Analysis Report (UFSAR),
IP-1 also contains radioactive waste processing facilities, which provide waste processing services for both units. Radiological effluent limits are met on an overall site basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite Dose Calculation Manual (ODCM). Services provided by IP-2 include maintenance, corrective action program implementation, plant support activities while in SAFSTOR status, and implementation of the SAFSTOR activities required in the Updated Final Safety Analysis Report (UFSAR), and Technical Specifications (TS). Appendix A to Provisional Operating License No. DPR-5 recognizes this commonality, as well as the intended use of the IP-1 facility to support IP-2 until the retirement of that unit, and contains specific references to Appendix A of the IP-2 Facility Operating License No. DPR-26. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in fMC 2561. 2.0 Safe Storage (SAFSTOR)
and Technical Specifications (TS). Appendix A to Provisional Operating License No. DPR-5 recognizes this commonality, as well as the intended use of the IP-1 facility to support IP-2 until the retirement of that unit, and contains specific references to Appendix A of the IP-2 Facility Operating License No. DPR-26. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in fMC 2561. 2.0 Safe Storage (SAFSTOR)
Performance and Status Review
Performance and Status Review


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The inspector also conducted a tour to assess the material condition of the IP-1 facility.
The inspector also conducted a tour to assess the material condition of the IP-1 facility.


The tour included the nuclear service building, chemical systems building, fuel handling building, IP-1 main stack, building roofs, and containment dome. Entergy had conducted and completed activities to dismantle a portion of the IP-1 vent stack and containment annulus exhaust duct from June 2012 through October 2013. During the previous inspection, the inspector reviewed the activities that occurred between June 2012 and February 2013. During this inspection, the inspector reviewed the final activities that occurred between February and October 2013. The inspector evaluated management control and oversight of the dismantlement activities and reviewed the engineering change document, "IP-1 Vent Stack Height Modification,"
The tour included the nuclear service building, chemical systems building, fuel handling building, IP-1 main stack, building roofs, and containment dome. Entergy had conducted and completed activities to dismantle a portion of the IP-1 vent stack and containment annulus exhaust duct from June 2012 through October 2013. During the previous inspection, the inspector reviewed the activities that occurred between June 2012 and February 2013. During this inspection, the inspector reviewed the final activities that occurred between February and October 2013. The inspector evaluated management control and oversight of the dismantlement activities and reviewed the engineering change document, "IP-1 Vent Stack Height Modification," related engineering change notices, work orders, radiation work permits, and disposal of the stack debris. The inspector reviewed activities and documentation associated with the following SAFSTOR programs:
related engineering change notices, work orders, radiation work permits, and disposal of the stack debris. The inspector reviewed activities and documentation associated with the following SAFSTOR programs:
occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspector reviewed radiological survey reports, fire extinguisher and fire hose inspection reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, and the annual effluent release report, which included a summary of the radioactive waste management and transportation programs.
occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspector reviewed radiological survey reports, fire extinguisher and fire hose inspection reports, radioactive gaseous and liquid effluent release permits, the groundwater monitoring program report, the annual REMP report, and the annual effluent release report, which included a summary of the radioactive waste management and transportation programs.


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The inspector will evaluate the effectiveness of the Change Management Plan during the next NRC inspection.
The inspector will evaluate the effectiveness of the Change Management Plan during the next NRC inspection.


The inspector confirmed that the staff effectively implemented the SAFSTOR program.
The inspector confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures.
 
The inspector verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures.


The inspector noted that the staff installed two new pumps at the sphere foundation sump. However, during the site tour, the inspector identified several items that require attention and improvement.
The inspector noted that the staff installed two new pumps at the sphere foundation sump. However, during the site tour, the inspector identified several items that require attention and improvement.
Line 136: Line 98:
However, the inspector observed that Entergy has not been effective in correcting certain challenges regarding document retrieval, such as, radiological survey records for IP-1 containment.
However, the inspector observed that Entergy has not been effective in correcting certain challenges regarding document retrieval, such as, radiological survey records for IP-1 containment.


The inspector noted that Entergy initiated a condition report and evaluators from the quality assurance department plan to address the concern during the next quality assurance audit. Generally, Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure.
The inspector noted that Entergy initiated a condition report and evaluators from the quality assurance department plan to address the concern during the next quality assurance audit. Generally, Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure. The inspector will review the quality assurance audit results during the next NRC inspection.
 
The inspector will review the quality assurance audit results during the next NRC inspection.


====c. Conclusions====
====c. Conclusions====
Line 154: Line 114:
PARTIAL LIST OF PERSONS CONTACTED
PARTIAL LIST OF PERSONS CONTACTED
Licensee  
Licensee  
: [[contact::S. Baer]], Supervisor,
: [[contact::S. Baer]], Supervisor, Rad Operations, Radiation
Rad Operations,
Radiation
Protection  
Protection  
: [[contact::P. Bode]], Senior HP/Chemistry
: [[contact::P. Bode]], Senior HP/Chemistry
Specialist,
Specialist, Radiation
Radiation
Protection  
Protection  
*#
*#
Line 167: Line 124:
IV, Regulatory
IV, Regulatory
Assurance  
Assurance  
: [[contact::J. Doroski]],
: [[contact::J. Doroski]], Senior HP/Chemistry
Senior HP/Chemistry
Specialist, Chemistry  
Specialist,
: [[contact::R. Drake]], Supervisor, Design Engineering  
Chemistry  
: [[contact::R. Drake]], Supervisor,
Design Engineering  
-Civil  
-Civil  
: [[contact::K. Elliott]],
: [[contact::K. Elliott]], Senior Staff Engineer, Systems & Components
Senior Staff Engineer,
Systems & Components
Engineering  
Engineering  
: [[contact::D. Gray]], Supervisor,
: [[contact::D. Gray]], Supervisor, Chemistry  
Chemistry  
: [[contact::L. Hedges]], U2 Control Room Supervisor  
: [[contact::L. Hedges]], U2 Control Room Supervisor  
*#
*#
: [[contact::D. Mayer]], Director,
: [[contact::D. Mayer]], Director, IP-1  
IP-1  
: [[contact::J. Michetti]], Senior Lead Engineer, Systems & Components
: [[contact::J. Michetti]],
Senior Lead Engineer,
Systems & Components
Engineering  
Engineering  
: [[contact::J. Ruch]], Engineer
: [[contact::J. Ruch]], Engineer Ill, Design Engineering -Civil  
Ill, Design Engineering  
: [[contact::W. Scholtens]], Senior HP/Chemistry
-Civil  
Specialist, Radiation
: [[contact::W. Scholtens]],
Senior HP/Chemistry
Specialist,
Radiation
Protection  
Protection  
: [[contact::C. Smyers]], Manager,
: [[contact::C. Smyers]], Manager, Chemistry  
Chemistry  
: [[contact::S. Stevens]], Superintendent, Rad Operations, Radiation
: [[contact::S. Stevens]],
Superintendent,
Rad Operations,
Radiation
Protection  
Protection  
*#  
*#  
: [[contact::R. Walpole]],
: [[contact::R. Walpole]], Manager, Regulatory
Manager,
Regulatory
Assurance
Assurance
State *  
State *  
: [[contact::B. Frymire]],
: [[contact::B. Frymire]], Power Systems Operations
Power Systems Operations
Specialist, Department
Specialist,
Department
of Public Service *  
of Public Service *  
: [[contact::A. Burritt]],
: [[contact::A. Burritt]], Branch Chief, Branch 2, Division of Reactor Projects *  
Branch Chief, Branch 2, Division
: [[contact::S. Stewart]], Senior Resident Inspector, Division of Reactor Projects  
of Reactor Projects  
: [[contact::A. Patel]], Resident Inspector, Division of Reactor Projects * Denotes individuals
*  
present during pre-exit briefing held on June 25, 2014 # Denotes individuals
: [[contact::S. Stewart]],
Senior Resident
Inspector,
Division
of Reactor Projects  
: [[contact::A. Patel]], Resident
Inspector,
Division
of Reactor Projects  
* Denotes individuals
present during pre-exit
briefing
held on June 25, 2014 # Denotes individuals
present during final exit meeting held on July 23, 2014 ITEMS OPEN, CLOSED, AND DISCUSSED
present during final exit meeting held on July 23, 2014 ITEMS OPEN, CLOSED, AND DISCUSSED
None Attachment
None Attachment
LIST OF DOCUMENTS
LIST OF DOCUMENTS
REVIEWED
REVIEWED Indian Point Unit 1 Final Safety Analysis Report IP-1 TS (Appendix
Indian Point Unit 1 Final Safety Analysis
Report IP-1 TS (Appendix
A to Provisional
A to Provisional
Operating
Operating
License No. DPR-5) IP-2 TS (Appendix
License No. DPR-5) IP-2 TS (Appendix
A of the Indian Point Unit 2 Facility
A of the Indian Point Unit 2 Facility Operating
Operating
License No. DPR-26) Indian Point Offsite Dose Calculation
License No. DPR-26) Indian Point Offsite Dose Calculation
Manual (ODCM) IP-SMM-U1-001,  
Manual (ODCM) IP-SMM-U1-001, "IPEC Site Management
"IPEC Site Management
Manual, Control of Indian Point 1" QA-12/18-2013-IP-01, "Quality Assurance
Manual, Control of Indian Point 1" QA-12/18-2013-IP-01,  
"Quality
Assurance
Audit Report" (Operations  
Audit Report" (Operations  
& Technical
& Technical
Specifications)
Specifications)
QA-9-2014-IP-1,  
QA-9-2014-IP-1, "Quality Assurance
"Quality
Assurance
Audit Report" (Fire Protection)
Audit Report" (Fire Protection)
QA-2/6-2013-IP-01,  
QA-2/6-2013-IP-01, "Quality Assurance
"Quality
Audit Report" (Chemistry, Effluent & Environmental)
Assurance
QA-14/15-2013-IP-01, "Quality Assurance
Audit Report" (Chemistry,
Effluent  
& Environmental)
QA-14/15-2013-IP-01,  
"Quality
Assurance
Audit Report" (Radiation
Audit Report" (Radiation
Protection  
Protection  
Line 270: Line 179:
09, "Radiation
09, "Radiation
Protection
Protection
Periodic
Periodic Task Scheduling" EN-RP-1 01, "Access Control for Radiologically
Task Scheduling"
EN-RP-1 01, "Access Control for Radiologically
Controlled
Controlled
Areas" EN-RP-1 08, "Radiation
Areas" EN-RP-1 08, "Radiation
Protection
Protection
Posting"
Posting" EN-RP-203, "Dose Assessment" RP-STD-17, "Satellite
EN-RP-203,  
RP Key Issuance and HRA, LHRA, and VHRA Boundary Verifications" 2013 Annual Radioactive
"Dose Assessment"
Effluent Release Report 2013 Annual Radiological
RP-STD-17,  
"Satellite
RP Key Issuance
and HRA, LHRA, and VHRA Boundary
Verifications"
2013 Annual Radioactive
Effluent
Release Report 2013 Annual Radiological
Environmental
Environmental
Operating
Operating
Report Liquid and Gaseous Release Permits and Dose Summary Reports,
Report Liquid and Gaseous Release Permits and Dose Summary Reports, January 2014-June 2014 TST-2-PC-EM32-2Y;
January 2014-June 2014 TST-2-PC-EM32-2Y;
TS PAM R-60 CAL; TST-2-PC-2Y23-62-2Y
TS PAM R-60 CAL; TST-2-PC-2Y23-62-2Y
CAL R-62 2-SOP-12-03-01
CAL R-62 2-SOP-12-03-01
Line 299: Line 197:
Sump Pump Discharge
Sump Pump Discharge
Flow Meter Calibration
Flow Meter Calibration
North Curtain Drain Effluent
North Curtain Drain Effluent Line Flow Meter Calibration
Line Flow Meter Calibration
IP-RPT-11-00044, "SAFSTOR 2011 Structural
IP-RPT-11-00044,  
Inspection" Engineering
"SAFSTOR
Change 32468, "IP-1 Vent Stack Height Modification" EN-LI-1 00, "Process Applicability
2011 Structural
Inspection"
Engineering
Change 32468, "IP-1 Vent Stack Height Modification"
EN-LI-1 00, "Process
Applicability
Determination";
Determination";
Engineering
Engineering
Line 316: Line 208:
ECN42663;
ECN42663;
ECN44305;
ECN44305;
ECN45312
ECN45312 Radiological
Radiological
Survey Reports-Containment (all elevations)
Survey Reports-Containment  
(all elevations)
and IP-1 steam generators
and IP-1 steam generators
Dose Totals for 2013 and January-June 2014 SEP-FPP-IP-001,  
Dose Totals for 2013 and January-June 2014 SEP-FPP-IP-001, "IPEC Fire Protection
"IPEC Fire Protection
Program Plan" O-PT-M004, "Fire Extinguisher
Program Plan" O-PT-M004,  
Inspection" PT-A 178, "Fire Hose Stations" 2-PT-A062, "Fire Hose Hydrostatic
"Fire Extinguisher
Test Verification" 2-PT -M112, "Fire Protection
Inspection"
PT-A 178, "Fire Hose Stations"
2-PT-A062,  
"Fire Hose Hydrostatic
Test Verification"
2-PT -M112, "Fire Protection
Flow Path and Hose Station Equipment
Flow Path and Hose Station Equipment
Verification"
Verification" Condition
Condition
Reports: CR-IP2-2013-02268;
Reports:
CR-IP2-2013-02268;
CR-IP2-2013-02299;
CR-IP2-2013-02299;
CR-IP2-2013-02302;
CR-IP2-2013-02302;
Line 351: Line 233:
CR-IP2*2014-03356;
CR-IP2*2014-03356;
CR-IP2-2014-03429; IP2-2014-03932
CR-IP2-2014-03429; IP2-2014-03932
CAP Entergy IMC IP IPEC IP-'1 IP-2 NRC ODCM REMP SAFSTOR TS UFSAR A-3 LIST OF ACRONYMS
CAP Entergy IMC IP IPEC IP-'1 IP-2 NRC ODCM REMP SAFSTOR TS UFSAR A-3 LIST OF ACRONYMS USED Corrective
USED Corrective
Action Program Entergy Nuclear Operations, Inc. Inspection
Action Program Entergy Nuclear Operations,
Inc. Inspection
Manual Chapter Inspection
Manual Chapter Inspection
Procedure
Procedure
Line 365: Line 245:
Program Safe Storage Technical
Program Safe Storage Technical
Specification
Specification
Updated Final Safety Analysis
Updated Final Safety Analysis Report Attachment
Report Attachment
}}
}}

Revision as of 13:04, 9 July 2018

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


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I DocketNo.

05000003 John Ventosa Site Vice President 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 August 4, 2014 Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 1 0511-0249 License No. DPR-5

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

Dear Mr. Ventosa:

On June 23-25, 2014 and July 14-16, 2014, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Indian Point Nuclear Generating Station Unit 1. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with D. Mayer, Director Special Projects, Unit 1, and other members of your staff on July 23, 2014, and are described in the enclosed inspection report. No findings of safety significance were identified.

Current NRC regulations and guidance are included on the NRC's website at select Nuclear Materials; Med, lnd, & Academic Uses; then Regulations, Guidance and Communications.

The current Enforcement Policy is included on the NRC's website at w_V1£yv.nrQ".9..Q..'{;

select About NRC, Organizations

& Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information').

You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-

1800. The GPO is open from 8:00a.m. to 5:30p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required.

Please contact Laurie Kauffman (610) 337-5323 if you have any questions regarding this matter.

Sincerely,/" (; 4------Patricia A Silva, Acting Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety

Enclosure:

Inspection Report No. 05000003/2014010 cc w/encl: Distribution via ListServ

SUMMARY

Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating

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

3

REPORT DETAILS

1.0 Background IP-1 is a pressurized water reactor that was granted a 40-year Operating License in 1962, and was permanently shut down in 197 4, and is being maintained in SAFSTOR status. Pursuant to the June 19, 1980 "Commission Order Revoking Authority to Operate Facility" and the "Decommissioning Plan for Indian Point Unit No. 1 ,"approved by the NRC in an Order, dated January 31, 1996, the reactor remains in a defueled status and the unit continues to operate as a support facility for Indian Point Nuclear Generating Station Unit 2 (IP-2) operations.

IP-1 and IP-2 are physically contiguous and share systems, such as the integrated liquid waste system and the air handling system; facilities, such as the chemistry and health physics laboratories; as well as, a common operating organization.

IP-1 also contains radioactive waste processing facilities, which provide waste processing services for both units. Radiological effluent limits are met on an overall site basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite Dose Calculation Manual (ODCM). Services provided by IP-2 include maintenance, corrective action program implementation, plant support activities while in SAFSTOR status, and implementation of the SAFSTOR activities required in the Updated Final Safety Analysis Report (UFSAR), and Technical Specifications (TS). Appendix A to Provisional Operating License No. DPR-5 recognizes this commonality, as well as the intended use of the IP-1 facility to support IP-2 until the retirement of that unit, and contains specific references to Appendix A of the IP-2 Facility Operating License No. DPR-26. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in fMC 2561. 2.0 Safe Storage (SAFSTOR)

Performance and Status Review

a. Inspection Scope

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

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

The inspector reviewed the SAFSTOR program as outlined in the UFSAR, TS, ODCM, and procedure IP-SMM-U1-001, "IPEC Site Management Manual, Control of Indian Point 1 ,"to assess the adequacy of management oversight of SAFSTOR responsibilities for the IP-1 facility.

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

The inspector discussed any design changes or modifications since the Enclosure 4 previous inspection.

The inspector also conducted a tour to assess the material condition of the IP-1 facility.

The tour included the nuclear service building, chemical systems building, fuel handling building, IP-1 main stack, building roofs, and containment dome. Entergy had conducted and completed activities to dismantle a portion of the IP-1 vent stack and containment annulus exhaust duct from June 2012 through October 2013. During the previous inspection, the inspector reviewed the activities that occurred between June 2012 and February 2013. During this inspection, the inspector reviewed the final activities that occurred between February and October 2013. The inspector evaluated management control and oversight of the dismantlement activities and reviewed the engineering change document, "IP-1 Vent Stack Height Modification," related engineering change notices, work orders, radiation work permits, and disposal of the stack debris. The inspector reviewed activities and documentation associated with the following SAFSTOR programs:

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

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

b. Observations and Findings

The inspector noted that Entergy made significant personnel changes within IP-1 related to the SAFSTOR activities.

The inspector discussed the Change Management Plan with the Special Projects Director and determined that the IP-1 Superintendent retired, Entergy eliminated several contractor positions, and delegated the roles and responsibilities to maintain IP-1 to representatives of specific site departmental disciplines.

The inspector also noted that the Change Management Plan is in its early stages and identified that details regarding specific roles and responsibilities need clarification.

The inspector will evaluate the effectiveness of the Change Management Plan during the next NRC inspection.

The inspector confirmed that the staff effectively implemented the SAFSTOR program. The inspector verified that the staff conducted the maintenance and surveillance program for systems and components in accordance with the TS requirements and established procedures.

The inspector noted that the staff installed two new pumps at the sphere foundation sump. However, during the site tour, the inspector identified several items that require attention and improvement.

The items are: general housekeeping, including potential combustible material and storage of ladders; radiological postings and controls; and initial signs of spalling of the containment dome. The inspector noted that Entergy has a structural engineering inspection scheduled for September 2014 that includes the exterior dome. The inspector will evaluate the results of the engineering inspection during the next NRC inspection.

5 The inspector evaluated the final activities associated with the IP-1 vent stack partial dismantlement and containment annulus exhaust duct. The final activities were: welding a new grating cover at the top of the stack, removing debris from the hopper, and painting the stack and containment annulus exhaust duct. The inspector noted that Entergy safely completed the partial dismantlement of the stack and containment annulus exhaust duct in accordance with the related engineering documents and established procedures.

The annual radiological effluent and REMP reports demonstrated that all calculated doses . were below regulatory dose criteria of 10 CFR 50, Appendix I. The inspector noted that radioactive waste was not shipped for offsite disposal since the last inspection.

The inspector determined that Entergy effectively entered concerns into the CAP to prioritize and evaluate them commensurate with their safety significance.

However, the inspector observed that Entergy has not been effective in correcting certain challenges regarding document retrieval, such as, radiological survey records for IP-1 containment.

The inspector noted that Entergy initiated a condition report and evaluators from the quality assurance department plan to address the concern during the next quality assurance audit. Generally, Entergy effectively addressed identified issues, implemented corrective actions, and tracked them to closure. The inspector will review the quality assurance audit results during the next NRC inspection.

c. Conclusions

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

3.0 Exit Meeting Summary On July 23, 2014, the inspector presented the inspection results to D. Mayer, Director of Special Projects and other members of Entergy's organization.

The inspector confirmed that proprietary information was not provided or examined during the inspection.

A-1

=SUPPLEMENTARY

INFORMATION=

PARTIAL LIST OF PERSONS CONTACTED

Licensee

S. Baer, Supervisor, Rad Operations, Radiation

Protection

P. Bode, Senior HP/Chemistry

Specialist, Radiation

Protection

G. Dahl, Nuclear Safety/Licensing

Specialist

IV, Regulatory

Assurance

J. Doroski, Senior HP/Chemistry

Specialist, Chemistry

R. Drake, Supervisor, Design Engineering

-Civil

K. Elliott, Senior Staff Engineer, Systems & Components

Engineering

D. Gray, Supervisor, Chemistry
L. Hedges, U2 Control Room Supervisor
D. Mayer, Director, IP-1
J. Michetti, Senior Lead Engineer, Systems & Components

Engineering

J. Ruch, Engineer Ill, Design Engineering -Civil
W. Scholtens, Senior HP/Chemistry

Specialist, Radiation

Protection

C. Smyers, Manager, Chemistry
S. Stevens, Superintendent, Rad Operations, Radiation

Protection

R. Walpole, Manager, Regulatory

Assurance

State *

B. Frymire, Power Systems Operations

Specialist, Department

of Public Service *

A. Burritt, Branch Chief, Branch 2, Division of Reactor Projects *
S. Stewart, Senior Resident Inspector, Division of Reactor Projects
A. Patel, Resident Inspector, Division of Reactor Projects * Denotes individuals

present during pre-exit briefing held on June 25, 2014 # Denotes individuals

present during final exit meeting held on July 23, 2014 ITEMS OPEN, CLOSED, AND DISCUSSED

None Attachment

LIST OF DOCUMENTS

REVIEWED Indian Point Unit 1 Final Safety Analysis Report IP-1 TS (Appendix

A to Provisional

Operating

License No. DPR-5) IP-2 TS (Appendix

A of the Indian Point Unit 2 Facility Operating

License No. DPR-26) Indian Point Offsite Dose Calculation

Manual (ODCM) IP-SMM-U1-001, "IPEC Site Management

Manual, Control of Indian Point 1" QA-12/18-2013-IP-01, "Quality Assurance

Audit Report" (Operations

& Technical

Specifications)

QA-9-2014-IP-1, "Quality Assurance

Audit Report" (Fire Protection)

QA-2/6-2013-IP-01, "Quality Assurance

Audit Report" (Chemistry, Effluent & Environmental)

QA-14/15-2013-IP-01, "Quality Assurance

Audit Report" (Radiation

Protection

& Radwaste)

0-RP-ADM-1

09, "Radiation

Protection

Periodic Task Scheduling" EN-RP-1 01, "Access Control for Radiologically

Controlled

Areas" EN-RP-1 08, "Radiation

Protection

Posting" EN-RP-203, "Dose Assessment" RP-STD-17, "Satellite

RP Key Issuance and HRA, LHRA, and VHRA Boundary Verifications" 2013 Annual Radioactive

Effluent Release Report 2013 Annual Radiological

Environmental

Operating

Report Liquid and Gaseous Release Permits and Dose Summary Reports, January 2014-June 2014 TST-2-PC-EM32-2Y;

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

CAL R-62 2-SOP-12-03-01

and 2-SOP-12-03-02

for Radiation

Monitor (R-60) Operation

Sphere Foundation

Sump Pump Discharge

Flow Meter Calibration

North Curtain Drain Effluent Line Flow Meter Calibration

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

Inspection" Engineering

Change 32468, "IP-1 Vent Stack Height Modification" EN-LI-1 00, "Process Applicability

Determination";

Engineering

Change 32468/ECN40171

EC No. 32468/Engineering

Change Notice 37267; ECN40171;

ECN42663;

ECN44305;

ECN45312 Radiological

Survey Reports-Containment (all elevations)

and IP-1 steam generators

Dose Totals for 2013 and January-June 2014 SEP-FPP-IP-001, "IPEC Fire Protection

Program Plan" O-PT-M004, "Fire Extinguisher

Inspection" PT-A 178, "Fire Hose Stations" 2-PT-A062, "Fire Hose Hydrostatic

Test Verification" 2-PT -M112, "Fire Protection

Flow Path and Hose Station Equipment

Verification" Condition

Reports: CR-IP2-2013-02268;

CR-IP2-2013-02299;

CR-IP2-2013-02302;

CR-IP2-2013-

2370; CR-IP2-2013-02535;

CR-IP2-2013-02624;

CR-IP2-2013-05188;

CR-IP2-2013-05206; IP2-2014-00169;

CR-IP2-2014-00210;

CR-IP2-2014-00214;

CR-IP2-2014-00217;

CR-IP2-2014-

027; CR-IP2-2014-01

030; CR-IP2-2014-00527;

CR-IP2*2014-03356;

CR-IP2-2014-03429; IP2-2014-03932

CAP Entergy IMC IP IPEC IP-'1 IP-2 NRC ODCM REMP SAFSTOR TS UFSAR A-3 LIST OF ACRONYMS USED Corrective

Action Program Entergy Nuclear Operations, Inc. Inspection

Manual Chapter Inspection

Procedure

Indian Point Energy Center Indian Point Unit 1 Indian Point Unit 2 Nuclear Regulatory

Commission

Offsite Dose Calculation

Manual Radiological

Environmental

Monitoring

Program Safe Storage Technical

Specification

Updated Final Safety Analysis Report Attachment