ML112690241
| ML112690241 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/26/2011 |
| From: | Laurie Kauffman Decommissioning Branch I |
| To: | |
| References | |
| FOIA/PA-2016-0148 IR-11-008 | |
| Download: ML112690241 (10) | |
See also: IR 05000003/2011008
Text
Docket No.
License No.
Inspection No.
Licensee:
Facility:
Location:
Inspection Dates:
Inspector:
Approved By:
- -
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
INSPECTION REPORT
05000003
05000003/2011008
Entergy Nuclear Operations, Inc.
Indian Point Energy Center (lPEC) Unit 1
450 Broadway
Buchanan, New York 10511-0249
August 30 - September 1, 2011
Laurie A. Kauffman
Health Physicist
Decommissioning Branch
Division of Nuclear Materials Safety
Judith A. Joustra, Chief
Decommissioning Branch
Division of Nuclear Materials Safety
Document Name: G:\\WordDocs\\Current\\lnsp Report\\RDPR-5.201100S.doc
EXECUTIVE SUMMARY
Indian Point Energy Center Unit 1
NRC Inspection Report No. 05000003/2011008
An announced routine safety inspection was conducted on August 30 - September 1, 2011, at Indian
Point Energy Center (IPEC) Unit 1 (Unit 1) by a Region I inspector. The NRC's program for
overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection
Manual Chapter (IMC) 2561, Decommissioning Power Reactor Inspection Program. The inspection
included a review of the programs associated with Unit 1 while in long-term safe storage (SAFSTOR)
status. There are no ongoing decommissioning activities being conducted at Unit 1. Within the
scope of this inspection, no safety concerns or violations were identified. A brief summary of each
area inspected is described below.
Organization and Management Oversight
The licensee's organization and management oversight was adequate to support Unit 1 activities.
The roles and responsibilities for the Unit 1 activities were consistent with the IPEC Site Management
Manual, Control of Indian Point 1 and the Technical Specifications (TS).
Safety Reviews, Design Changes and Modifications
There were no plant modifications since the previous inspection conducted in June 2010.
Audit and Corrective Action Programs
The licensee maintained an adequate audit program and effectively utilized the established corrective
action program to identify, evaluate, and correct issues and problems. Condition reports were
appropriately prioritized and corrective actions were tracked in accordance with approved
procedures.
Decommissioning Performance and Status Reviews
No dismantlement or decommissioning activities were performed since the previous inspection.
Maintenance and Surveillance
The licensee effectively implemented the preventive maintenance and surveillance program and
associated procedures in accordance with TS and Offsite Dose Calculation Manual (ODCM)
requirements.
Occupational Radiation Exposure
The licensee provided adequate controls to limit exposures of workers to external sources of
radiation. Posting and labeling of radioactive materials and radiation areas were in compliance with
regulatory requirements. Radiological controls and dose estimates associated with Unit 1 activities
were effective to achieve dose goals. Implementation and oversight of the SAFSTOR program was
effective for the safe storage of radioactive material.
Effluent, Environmental Monitoring and Radioactive Waste and Transportation
The licensee effectively implemented and maintained the radioactive effluent controls program, the
groundwater monitoring program related to Unit 1, the radiological monitoring program, and the
radioactive waste management and transportation programs.
11
- -------------------------
REPORT DETAILS
1.0
Background
Unit 1 is a pressurized water reactor that has been permanently shut down since
October 31, 1974, and is being maintained in long-term storage (SAFSTOR). Units 1
and 2 are physically contiguous and share systems and facilities as well as a common
operating organization. The Technical Specifications (TS) for Unit 1 recognize this
commonality as well as the intended use of the Unit 1 facilities to support Indian Point
Unit 2. The systems associated with Unit 1 are divided into three classifications:
a) systems required per the Unit 1 TS that support the SAFSTOR condition of the unit;
b) systems required to support the operating units (e.g. Liquid Waste Processing); and
c) systems that are not required to support the TS, SAFSTOR condition, or the operating
units.
2.0
Organization and Management Oversight
a.
Inspection Scope (Inspection Procedure (IP) 36801)
The inspector reviewed procedure IP-SMM-OC-905, IPEC Site Management Manual,
Control of Indian Point 1, Revision 6 (IPEC-SMM), issued February 4, 2010, regarding
the roles and responsibilities for the operation, maintenance and control of Unit 1. The
inspector discussed organization, management and/or staffing changes as outlined in
TS, Sections 3.1 and 3.2, and in IPEC-SMM, Section 5.0. The inspector also interviewed
the personnel in the Employee Concerns Program (ECP).
b.
Observations and Findings
Procedure IP-SMM-OC-905 defines roles and assigns responsibility for the operation,
maintenance and control of Unit 1. There were no organizational structure changes
made by the licensee since the previous inspection. The inspector verified that
procedure IP-SMM-OC-905 and associated implementing procedures were consistent
with the TS. Implementation of the TS and the IPEC-SMM was adequate. ECP
personnel provided the inspector with details regarding the licensee commitment to
maintain a high level of awareness to safety.
c.
Conclusions
The licensee's organization and management oversight was adequate to support Unit 1
activities. The roles and responsibilities for the Unit 1 activities were consistent with the
IPEC-SMM and the TS. No safety concerns or violations were identified.
3.0
Safety Reviews, Design Changes, and Modifications
a.
Inspection Scope (lP 37801)
Procedure IP-SMM-OC-905, Rev. 6, provides guidance for modifying or working on
Unit 1 structures, systems and components (SSCs) that have been "retired in place" and
1
that remain in place to support the operation of Unit 2. The inspector discussed
Engineering Change (EC) reports to determine if the licensee conducted safety reviews
and engineering design change screening in accordance with the requirements of
b.
Observations and Findings
There were no plant modifications since the previous inspection conducted in June 2010.
c.
Conclusions
No safety concerns or violations were identified.
4.0
Audit and Corrective Action Program
a.
Inspection Scope OP 40801)
The inspector reviewed the quality assurance (QA) audit report QA-12/18-2011-IP-1,
OperationsiTechnical Specifications, dated June 6-27,2011 related to Unit 1 SAFSTOR
activities. The inspector also reviewed selected condition reports (CRs) and any
associated corrective actions to evaluate the licensee's ability to assess, identify, resolve,
and prevent issues that could impact safety or the quality of SAFSTOR activities.
b.
Observations and Findings
The purpose of the audit was to evaluate the effectiveness of Operations, compliance
with TS requirements and to evaluate selected elements of the Master Audit Plan for
Operations and TS. The audit contained 10 scope elements including: Test Control;
Inspection, Test and Operating Status; Limiting Conditions for Operations; Conduct of
Operations; Operator Knowledge and Performance; Work Coordination and Control;
Corrective Action; Self Assessment and Benchmarking; Instruction, Drawings and
Procedures; and Leadership and Management. The audit was adequate and identified
strengths and weaknesses related to the Unit 1 activities.
The priority for addressing CRs and implementation of corrective actions were
appropriate based upon safety significance. Corrective actions were implemented to
address identified issues, and were being tracked to closure using the licensee's
corrective action program. The licensee did not identify any adverse trends or safety
concerns.
c.
Conclusions
The licensee maintained an adequate audit program and effectively utilized the
established corrective action program to identify, evaluate, and correct issues and
problems. CRs were appropriately prioritized and corrective actions were tracked in
accordance with approved procedures. No safety concerns or violations were identified.
2
5.0
Decommissioning Performance and Status Reviews
a.
Inspection Scope (IP 71801)
The inspector reviewed the licensee's current decommissioning status with respect to the
Decommissioning Plan for Indian Point Unit 1, approved by the NRC in an Order dated
January 31, 1996.
b.
Observations and Findings
Unit 1 is currently in the SAFSTOR condition. The licensee informed the inspector that
they plan to actively decommission Unit 1 in parallel with the decommissioning of Unit 2
after that unit has been permanently shutdown.
c.
Conclusions
No dismantlement or decommissioning activities were performed since the previous
inspection, conducted in June 2010. No safety concerns or violations were identified.
6.0
Maintenance and Surveillance
a.
Inspection Scope (lP 62801)
The inspector evaluated the maintenance program, required by TS, Section 5.0 and
described in the IPEC SSM, Section 6.0. The inspector reviewed the surveillance
requirements for the Unit 1 radioactive effluent monitoring instrumentation, required by
TS, Section 5.2 and the ODCM. The inspector examined the shift logs and the
maintenance and calibration records for the liquid discharge monitor (R-54) and the stack
vent noble gas monitor (R-60) for the period July 2010 through August 2011. The
inspector conducted a plant tour, including the nuclear service building (NSB), the
chemical systems building (CSB), the fuel handling building (FHB), the containment
building, and containment sphere [Le. vapor containment (VC)]. The inspector also
discussed the biennial SAFSTOR engineering and structural assessment inspection with
the licensee.
b.
Observations and Findings
The inspector verified that the maintenance and surveillance program for selected
systems and components had been conducted in accordance with TS, implementing
procedures, and the ODCM. The inspector determined from a review of maintenance
and calibration records that the preventative maintenance, routine surveillance, and
calibration results were complete and the results were within acceptable limits. The
inspector also determined that the radioactive effluent monitoring instrumentation were
calibrated and that the set points were appropriate.
The biennial SAFSTOR engineering and structural assessment inspection will be
conducted in November 2011. The inspector will review the engineering and structural
assessment report during the next inspection.
3
c.
Conclusions
The licensee effectively implemented the preventive maintenance and surveillance
program and associated procedures in accordance with TS and ODCM requirements.
No safety concerns or violations were identified.
7.0
Occupational Radiation Exposure
a.
Inspection Scope (lP 83750)
The inspector evaluated the licensee's implementation of the occupational radiation
exposure program to determine the licensee's capability to monitor and control radiation
exposure to employees, and to determine the adequacy of the radiation protection
program. The inspector reviewed procedure EN-RO-1 01, Nuclear Management Manual,
Access Control for Radiologically Control/ed Areas, Rev. 6, issued June 23, 2011,
RP-STD-17, Satellite RP Key Issuance and HRA, LHRA, and VHRA Boundary
Verification, Rev. 10, issued May 17, 2010, and EN-RP-108, Radiation Protection
Posting, Rev. 10, issued August 4, 2011. The inspector interviewed responsible
individuals, reviewed radiological survey plans, survey maps of the radiologically
controlled area, and conducted field observations of radiological postings. The inspector
evaluated the radiation work permits (RWP) related to Unit 1, and the dose totals for
2010 and January 2011 through August 2011.
b.
Observations and Findings
The radiologically controlled areas were appropriately posted for radioactive material.
Radiological postings were readily visible, well-maintained, and reflected radiological
conditions. The radiological survey maps and related information maintained at the
Unit 1 access point were current. High radiation areas and technical specification locked
high radiation areas were properly posted and locked as required. The RWPs were
commensurate with the radiological significance of the tasks and included the
appropriate exposure control measures for the safe implementation of the activities. The
RWP dose totals were below the dose goal totals for 2010 and January 2011 through
August 2011.
c.
Conclusions
The licensee provided adequate controls to limit exposures of workers to external
sources of radiation. Posting of radioactive materials and radiation areas were in
compliance with regulatory requirements. Radiological controls and dose estimates
associated with Unit 1 activities were effective to achieve dose goals. Implementation
and oversight of the SAFSTOR program were effective for the safe storage of radioactive
material. No safety concerns or violations were identified.
4
8.0
Effluent and Environmental Monitoring Programs
a.
Inspection Scope (lP 84750)
The inspector evaluated the radioactive effluent control and the site radiological
environmental monitoring programs. The evaluation included a review of the annual
radioactive effluent release report for 2010, the annual radiological environmental
operating report for 2010, and the associated analytical results for each program. The
inspection also included a review of the Unit 1 TS and the ODCM. The inspector
reviewed the associated radioactive liquid release permits, the analytical sample results,
and the projected doses to the public associated with the groundwater in-leakage into the
North Curtain Drain (NCD) and Sphere Foundation Drain (SFD) sumps. The inspector
also reviewed the gaseous effluent results, the projected doses to the public associated
with the stack vent, and the radiological environmental monitoring program, including the
analytical results associated with samples of shoreline sediment, fish, and water from
January 2011 through August 2011.
b.
Observations and Findings
The annual effluent and environmental monitoring reports demonstrated that the
calculated doses were well below regulatory dose criteria of 10 CFR 50, Appendix I. The
radioactive liquid effluent release permits were completed in accordance with the ODCM.
From a review of the analytical data, the inspector verified that the projected doses to the
public from the liquid and gaseous effluent from Unit 1 were below TS limits and were
performed in accordance with the ODCM and the Code of Federal Regulations
(10 CFR 50.36a) for maintaining doses to the public from radioactive effluents as low as
is reasonably achievable. The inspector verified that the licensee collected and analyzed
the stack vent samples, NCD and SFD sump samples, and the liquid discharge monitor
samples within the required frequencies and that the sample collection was conducted in
accordance with applicable procedures.
The inspector compared the analytical water sample results related to the groundwater
monitoring program, specifically the NCD and SFD analytical sample results from
January 2011 through August 2011 to the results from 2010. The levels of tritium ranged
from 13500 picoCuries per Liter (pCi/L) to 3 pCi/L for the NCD and from 642 pCi/L to
480 pCi/L for the SFD. The licensee informed the inspector that the levels of radioactivity
appear to be trending downward. The inspector's review of this data confirmed the
licensee's conclusion.
The inspector reviewed the analytical results for shoreline sediment, fish, and water from
January 2011 through August 2011 for the radiological environmental monitoring
program and noted that the results indicated that no significant radioactivity was
identified in fish and the environment.
c.
Conclusions
The licensee effectively implemented and maintained the radioactive effluent controls
program, the groundwater monitoring program, and the radiological monitoring program.
No safety concerns or violations were identified.
5
-- ---
-
9.0
Radioactive Waste Management and Transportation of Radioactive Materials
a.
Inspection Scope (IP 86750)
The inspector evaluated and discussed the radioactive waste management and
transportation programs to determine whether the licensee properly processed,
packaged, stored, and shipped radioactive materials. The inspector also conducted a
tour of the Unit 1 FHB.
b.
Observations and Findings
The inspector noted that there were no radioactive waste shipments since the previous
inspection conducted in June 2010.
Additionally, the inspector determined from the Unit 1 FHB tour and discussions with
individuals cognizant of the radioactive waste management and radioactive materials
transportation programs that the Class B waste from the cleanup of the spent fuel pool is
still being maintained in the Unit 1 FHB until an appropriate disposal option is available.
c.
Conclusions
The licensee effectively implemented the radioactive waste management and
transportation programs. No safety concerns or violations were identified.
Exit Meeting Summary
On September 1, 2011, the inspector presented the inspection results to Donald Mayer,
Director, Unit 1, and other members of the licensee's staff. The inspector confirmed that
proprietary information was not provided or examined during the inspection.
6
A-1
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee
C. English, Superintendant, Unit 1
J. Doroski, Health Physics and Chemistry Specialist
W. Henries, Senior Engineer Consultant, Unit 1
F. Inzirillo, Quality Assurance Manager
D. Mayer, Director, Unit 1
J. Michetti, System Engineering Support - RMS
S. Sandike, Senior Chemistry Engineer
W. Scholtens, Radioactive Waste Engineer
D. Smith, Health Physicist, Radiation Protection
G. Dahl, Licensing Engineer
B. Taggart, Employee Concerns Program
R. Tagliamante, Radiation Protection Manager
INSPECTION PROCEDURES USED
36801
Organization, Management, and Cost Controls at Permanently Shutdown
Reactors (PSRs)
37801
40801
62801
71801
83750
84750
86750
Safety Reviews, Design Changes, and Modifications at PSRs
Self Assessment, Auditing, and Corrective Action at PSRs
Maintenance and Surveillance at PSRs
Decommissioning Performance and Status Reviews at PSRs
Occupational Radiation Exposure
Radioactive Waste Treatment, and Effluent and Environmental Monitoring
Solid Radioactive Waste Management and Transportation of Radioactive
Materials
Attachment
A-2
ITEMS OPEN, CLOSED, AND DISCUSSED
Opened, Closed and Discussed - None
CFR
CR
CSB
EC
FHB
IMC
IP
IPEC-SMM
NCD
NRC
NSB
PSRs
SAFSTOR
SFD
TS
Unit 1
Unit2
LIST OF ACRONYMS USED
Agencywide Documents Access and Management Systems
Code of Federal Regulations
condition reports
chemical systems building
Engineering Change
Employee Concerns Program
fuel handling building
Inspection Manual Chapter
Inspection Procedure
Indian Point Energy Center
IPEC Site Management Manual, Control of Indian Point 1
North Curtain Drain
Nuclear Regulatory Commission
nuclear service building
Offsite Dose Calculation Manual
Permanently Shutdown Reactors
quality assurance
radiation monitoring system
radiation work permits
long-term safe storage
Sphere Foundation Drain
structures, systems and components
technical specification
Indian Point Unit 1
Indian Point Unit 2
vapor containment (containment sphere)
Attachment