IR 05000003/2013008

IR 05000003-13-008, on 6/25-27/13, Indian Point

ML13198A555
Person / Time
Site:	Indian Point
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)

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 2 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 3

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.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:

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 5 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.

A-1

=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)

2115111 North Curtain Drain Effluent Line Flow Meter Calibration (WO#52309368-01)

2512012 2012 Annual Radiological

Environmental

Operating

Report, dated May 1 5,2013 lP-RPT-1 1-OOO44, "SAFSTOR 2011 Structural

Inspection" EN-Ll-100, "Process Applicability

Determination;

Engineering

Change 32468/ECN40171

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

Radiological

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

Radiological

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

Dose Totalsfor

2012 and January - June 2013 (RWPs: 2013-1000

through 1005)SEP-FPP-IP-001, 'IPEC Fire Protection

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

lnspection" (monthly:

December 2012 through May 2013)PT-A178, "Fire Hose Stations" (annual: April 2012 and April 2013)2-PT-A062, "Fire Hose Hydrostatic

Test Verification" (annual: July 21,2011 & September

2,2012)2-PT-M112, "Fire Protection

Flow Path and Hose Station Equipment

Verification" (monthly:

April and May 2013)Condition

Reports. lP2-2012-03888;

lP2-2012-03890;

1P2-2012-03986;

lP2-2012-04163;

lP2-2012-Q4752; lP2-2012-04810;

lP2-2012-06344;

tP2-2012-04856;

lP2-2012-04946;

tP2-2012-O7021', lP2-2013-00397;

lP2-2013-0051

9; lP2-2Q13-00807;

lP2-2013-01040;

1P2-2013-01865;

lP2-20 1 3-0 1 687 ; lP2-2Q 1 3-017 1 4; lP2-20 13-0 1 789 ; lP2-20 1 3-02O44;LIST OF ACRONYMS USED CAP Corrective

Action Program EC Engineering

Change ECN Engineering

Change Notice Entergy Entergy Nuclear Operations, Inc.ft feet IMC Inspection

Manual Chapter lP lnspection

Procedure IPEC Indian Point Energy Center lP-1 lndian Point Unit 1 lP-2 lndian Point Unit 2 msl Mean Sea Level NRC Nuclear Regulatory

Commission

ODCM Offsite Dose Calculation

Manual SAFSTOR Safe Storage TS Technical

Specification

UFSAR Updated Final Safety Analysis Report Attachment