IR 05000003/2014010
| ML14217A037 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/04/2014 |
| From: | Patricia Silva NRC/RGN-I/DNMS/NMSB3 |
| To: | Ventosa J Entergy Nuclear Operations |
| References | |
| FOIA/PA-2016-0148 IR14-010 | |
| Download: ML14217A037 (11) | |
Text
ust 4, 2014
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-
2370; CR-IP2-2013-02535;
CR-IP2-2013-05206; IP2-2014-00169;
CR-IP2-2014-
027; CR-IP2-2014-01
030; CR-IP2-2014-00527;
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