IR 05000003/1998019
| ML20204K023 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/09/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20204K000 | List: |
| References | |
| 50-003-98-19, 50-3-98-19, NUDOCS 9903300212 | |
| Download: ML20204K023 (13) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
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Docket No.:
50-003 License No.:
DPR-5 Report No.:
50-003/98-019 Licensee:
Consolidated Edison Company of New York, Inc.
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Location:
Indian Point Power Station Unit 1 Buchanan, New York
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Date:
November 30,1998 - February 22,1999
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inspector:
Anthony Dimitriadis, Health Physicist Approved by:
Ronald R. Bellamy, Chief Decommissioning and Laboratory Branch Division of Nuclear Materials Safety
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9903300212 990309 PDR ADOCK 05000003
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EXECUTIVE SUMMARY
Indian Point Station Unit 1
NRC Inspection Report 50-003/98-019 This routine decommissioning inspection included a review of facility management and control, decommissioning support activities, radiological safety, self-assessment and auditing, personnel radiation protection, surveillance and contamination control, transportation and radioactive waste management, and the fuel pool cleanup project.
Site History Indian Point Station Unit 1 began operating in 1962 under a provisional operatin J license until October 31,1974, when the plant ceased operations. The reactor was subsequently defueled in January 1976, and the fuel was stored in the facility's Fuel Handling Building, now commonly referred to as the Chemical Systems Building (CSB). The facility was placed in a SAFSTOR condition, which allows for a substantial reduction in radiation levels and further development of protective As Low As is Reasonably Achievable (Al. ARA) techniques which will support lower overall personnel exposure at the time of actual decommissioning activities.
Facility Management and Control The organizational structure and staffing levels of the facility were capable of conducting the decommissioning and surveillance activities currently in place. The Health Physics (HP) group conducted the surveillance activities, which were ultimately reported to the Plant Manager.
DicEJminalg.[1lna Suonort Activities The licensee does not plan to decommission Unit i until the 2013 time frame. Some
' decommissioning work was done from 1974 through 1978 during shutdown and storage of fuel.
Current emphasis was on assuring that the site was free from structural deficiencies and that no abnormal conditions exist. The licensee had adequately characterized the boundaries of the affected areas.
Radiological Safety Radioloaical Safety Staffina
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The organizational structure and staffing lesals of the facility were effective in conducting the surveillance and survey activities currently in place. Licensee management was expending adequate resources on planning and execution of surveillance activities.
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Self-Ase%sment. Audits and Corrective Actions
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The licensee had a Nuclear Power Quality Assurance Group (NQA Audits &
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Surveillance), which is responsible for auditing various aspects of radiation protection of l the Indian Point Station.
Personnel Radiation Protection.
- The licensee provided good radiological controls for access to Unit 1 and work in the restricted and unrestricted a eas. The radiation work permit (RWP) program was being effectively implemented in accordance with plant procedures.
Postina. Labelina. Surveillance and Contamination Control
- The licensee provided appropriate posting and labeling throughout the site in a manner that clearly informed all occupants of the hazards. Licensee surveillance surveys of
, restricted and unrestricted areas were performed in a well planned and organized manner. The inspection verified that the licensee used properly calibrated radiation detection instrumentation.
Radioactive Waste Manaaement
- This inspection confirmed that the licensee properly stored and appropriately surveyed all rad;oactive waste from this Unit. Approximately 5,780 ft of radioactive waste associated with Unit 1 was shipped in 1998. All radioactive waste was shipped to the Low Level Waste Disposal fac.ility in Bamwell, South Carolina.
Sionificant Licensee initiatives Based on a review of work accomplished by the licensee, the inspector concluded that the spent fuel pool clean-up project was effective in ensuring safe spent fuel storage.
Within the scope of this inspection, no safety items or violations of NRC requirements were identified.
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REPORT DETAILS
Summary of Plant Activities The Indin Point Unit 1 facility is presently in a SAFSTOR condition and final decommissioning will not occur until 2013 rhen the indian Point Unit 2 plant is tentatively scheduled for shutdown
- and decommissioning. Tiie Unit i reactor was defueled and all fuel is stored in the spent fuel pool (SFP). The facility has been shut down for over 25 years. Licensee management was expending adequate resources on the fuel pool clean-up project, execution of surveillance and survey activities, posting and labeling, and ALARA practices.
l. Fellity Management and Control 1.1 General The Indian Point 1 facility is presently in a SAFSTOR condition and final decommissioning will not occur until the 2013 time frame when the indian Point Unit 2 facility is tentatively scheduled for shutdown and decommissioning. The reactor was defueled and the fuel is stored in the SFP. The only radioactivity associated with the facility is contamination that resulted from operation of the reactor. The bulk of the contamination is sealed in the reactor vessel, the primary loop piping, steam generators, circulation pumps and the reactor cleanup system.
The inspector reviewed ongoing and planned future plant activities and discussed these activities with licensee representatives in order to assess overall facility management and j
control. Specific events and findings are detailed in the sections below, i
1.2 Oraanization. Manaaement and Cost Controls a.
Inspection Scooe (36801)
The inspector reviewed the licensee's systems for overall management and control of the limited decommissioning activities underway at Indian Point Unit 1. The licensee's
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organization structure and staffing were reviewed and evaluated to verify that the licensee had the controls and organization to effectively implement licensed requirements.
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Observations and Findinas The organizational structure of the Indian Point Unit 1 station was headed by the Plant Manager, who is ultimately responsible for Unit 1, supported by a dedicated Project Manager. Although the licensee had less staff dedica;ad to Unit 1 functions than it did during the operational phase, the inspector evaluated the organization to determine if reductions in program areas since shutdown and SAFSTOR were appropriate to protect the public health and safety. For example, the inspector observed that the licensee typically has approximately 8 to 10 people performing various duties in the Chemical Systems Building (CSB) involving Unit 1 activities.
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The only radioactivity associated with the facility was contamination that resulted from i
operation of the reactor. Because the majority of the contamination is sealed in the l
reactor vessel, steam Generators and in the spent fuel located in the SFP, the radiological issues in Unit i have been significantly reduced. Discussions with the Project Manager
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for Unit 1 and various HP staff members indicated that the staff was very knowledgeable i
in their subject areas. The Manager of Nuclear Safety and Licensing for Unit 1 had i
extensive historical work experience with the Indian Point Unit 1 facility.
c. Conclusions
The licensee's organization was effectively structured for planning and managing the j
activities that contribute to the overall decommissioning of the facility. Two main fire j
booster pumps were available for providing water for fighting a fire in Unit 1. The presence of the staff member with Unit 1 institutional knowledge provided important l
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background information, which will be useful in supporting a safe and effective decommissioning of the facility. No safety concems were noted.
1.3 Decommissionina Performance and Status Review a.
Insoection Scope (71801)
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l The inspector toured the facility and evaluated plant housekeeping and the fire protection system.
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Observations and Findinas
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All areas were generally clean and well maintained for a facility that has Men shut down for 25 years. The areas were adequately posted and controlled. No combustible materials were observed. Indian Point Unit 1 was monitored by a fire detection system consisting of a network of fire / smoke detectors, which are hard-wired throughout Unit 1 and designed to alarin in the Unit 2 control room. The overall fire protection was under the Indian Point Unit 2 program. The program included fire extinguisher inspections and i
hydrant testing.
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External hydrants, which are part of the Indian Point Unit 1 general service water system, were capable of providing water for fighting fires through the standpipe systems available i
throughout the facility. The fire fighting equipment and stations were properly maintained and ready for use. Fire hose reels stationed throughout the facility were frequently tested and used to ensure that they were in proper operating condition. Consolidated Edison had an Indian Point fire brigade, made up of nuclear plant operators, trained in fire fighting, and led by the support facility supervisor. These individuals were ready to respond to the Unit 1 facility in the event of a fire. Backup fire protection was available j
from the Verplank Fire Company, a local Volur.teer Fire Company.
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c. Conclusions
The licensee's housekeeping and fire protection programs were well developed and established to meet the existing hazards at Indian Point Unit 1.
11. Decommissionina Support Activities 2.1 Maintenance and Surveillance
a. Inspection Scope
(62801)
The inspector conducted a plant walk-through inspection to assess the general material condition of the structures, systems and components in the plant.
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Observations and Finding!
Because Indian Point 1 is in SAFSTOR, the licensee's surveillance activities were conducted at a reduced frequency or when work was required in the areas. When no work was performed in'the ALARA Locked areas, procedures required that surveit!ance activities be performed at intervals not exceeding 24 months. In most cases, the surveillance activities were performed more frequently than those prescribed in the licensee's procedures. Surveillance was primarily focused on radiation protection issues and are discussed in Section 3.4.
c. Conclusions
The inspector determined that the licensee had an effective maintenecce and surveillance program.
lil. Radioloalcal Safety 3.1 Radioloaical Safety Staffina
a. Inspection Scope
(83750)
The inspector reviewed the liansee's system for ov?rall management and control of the limited decommissioning activities underway. The licensee's organization and staffing were reviewed and discussed to verify that licensing commitments were being met.
b.
Observations and Findinos The Project Manager of Unit 1 had overall responsibilities for Unit 1 activities. This individual reported to the Outage Planning Manager, who reped.ed to the Manager for Work Control who,in turn, reported directly to the Plant Manager. The ultimate responsibility for Unit 1 rests with the Plant Manager who reports to the Vice President of Nuclear Power at the site. The Health Physics program is managed by the Health Physics group. Direct work cr mge was provided by the Indian Point HP staff.
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Individuals had an average of 15 years of experience in health physics and decommission;ng. The HP staff was provided on-site health physics re-training annually.
3.2 Self-Assessment. Auditino and Corrective Actions
a. Inspection Scope
(40801)
The licensee's ability to identify, resolve and prevent issues that may degrade safety or quality were examined. included in this review were self-assessments, audits, and corrective actions. The inspector reviewed the rd alts of two audits conducted in 1997 and 1993. These audits examined programs for controlling effluents and assuring that practices and records were in conformance with the Indian Point Radiation Protection Program and applicable portions of the Unit 1 Technical Specifications.
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Observatiens and Findinos Technical Specifications require the Nuc! ear Facilities Safety Committee (NFSC) to independently audit activities occurring in Units 1 & 2. While the audit program was designed to focus on Indian Point Unit 2, toe audit program incluoed activities performed for Unit 1. The audits were sufficient in depth and scope to identify programmatic problems and had addressed major, non-radiological aspects of the facility as well as radiological concerns.
The inspector reviewed Con Edison's self-assessment and reviewed the audits to verify that the program was adequate to allow the licensee to self-identify developing problems i
and implement timely corrective actions. The inspection consisted of interviews with selected plant personnel, reviews of audits, and independent verification of related plant activities.
Interviews with plant personnel revealed that quality assurance reviews and audits of Unit 1 operations had been performed on a regular basis. The inspector reviewed a sampling of recent quality assurance reports. These included:
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Audit Report 97-03-B Radiological Effluent Audit Report 98-03-C Radiation Protection Program The audits examined:
- (a) adminiMrative procedures for controllhg effluents and;
- (b) evaluated radiation protection practices within Unit 1 restricted areas. The audit reports clearly outline findings and observations requesting a response (ORRs), which require a response within 30 days. The inspector discussed the audit findings with the Unit 1 Project Manager and the corrective actions taken to address those findings.
c. Conclusions
The licensee's self-assessment (audit) program for Indian Point Unit 1 was critical, effective, and contributed to improvements in licensee performance.
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3.3
' Personnel Radiation Protection a.
Jnspection Scope (83750)
The inspector reviewed and discussed the station radiation protection program and exposure of workers.
b.
_ Observations and Findinas The inspector selected several radiation work permits (RWPs) involving typical Unit 1 activities and reviewed them to evaluate if the RWPs effectively communicate radiological conditions and job controls to radiation workers. All RWPs were reviewed by the station ALARA committee to determine if the controls specified for the scope of work were adequate. The ALARA committee also typically reviews all exposures received under each permit. All dosimetry was controlled and processed through the Consolidated Edison Company of New York, Inc. The dosimetry program included both thermoluminescent dosimetars (TLDs) and direct-reading dosimeters (DRDs).
TLDs were issued and processed quarterly. The licensee's TLD program was inspected in 1996 by the National Voluntary Laboratory Accreditation Program (NVLAP) and was re-accredited through June,1999. A review of the dosimetry results for Health Physics
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technicians performing the surveillance activities for the previous 12 months revealed that the doses received were minimal. Direct observations and discussions revealed that personnel dosimeters were used effectively arsd in accordance with requirements. There j
was good job planning, work practices, and attention to the ALARA program. There were no reports or evidence of internal exposures due to intakes of radioactive material during
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surveillance operations for the past 12 months.
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c. Conclusions
Based on the inforrnation gained during the inspection, the inspector concluded that the radiological safety program was effective in implementing the requirements for the licensee's SAFSTOR program and the limited decommissioning projects being undertaken. The RWP program was being effectively implemented in accordance with plant procedures. The inspector had no concerns with the Indian Point i radiological safety program.
3.4 Surveillance Surveys and Contamination Control
a. Inspection Scope
(83750)
The inspector reviewed selected direct radiation and contamination survey results for the
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past twelve months.
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Observations and Findinas The licensee had established a survey schedule for all accessible areas of Unit 1 on a
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six-month to two-year frequency based on the locations of serviceable equipment and operator surveillance requirements. Facility surveillance and surveys had been at least j
weekly, well under the minimum requirement of 24 months as required by the Technical
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Specifications. A review of select records from the past 12 months indicated that J
recorded area exposure raMa were typically 2 - 5 milliroentgens per hour (mR/hr) with a j
maximum exposure rate of 70 mR/hr. The licensee roped off and posted the area. The
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exposure rate surveys were performed with calibrated Eberline Ionization chambers (Model RO-2), and contamination wipes were analyzed with an Eberline beta counter (Model BC-4).
l Contamination levois were less than 1,000 disintegrations per minute (dpm) per 100 cm" j
of beta / gamma activity in the clean area walkways. Contaminated rooms / areas were
appropriately posted and the drained fuel handling pools were covered and locked with
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HP-controlled locks. All personnel leaving the Unit 1 facility are required to check
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themselves at the exit point of the restricted area for radioactive contamination using hand i
held survey instruments and whole body contamination monitors.
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c. Conclusions
i The inspector observed individuals checking themselves for contamination at the exit
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point of the restricted area. No problems or safety concerns were noted.
3.5 Transoortation and Radioactive Waste a.
Insoection Scope (86750)
A review of the radioactive waste program was performed for Unit 1 activities. The inspector toured the facility to determine how the licensee packages, stores and ships i
radioactive waste, and if the waste was shipped in accordance with applicable l
regulations.
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Observations and Findinas The inspector observed radioactive waste in the CSB in the areas around the fuel
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handling pools. The licensee stored radioactive waste cargo containers and shipping casks in the CSB until the containers were ready for shipment. Licensee staff were observed mopping floors, removing trash, and processing liquid waste. Walkways and aisles were generally clear and free of debris, and informational postings and boundaries
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were clear and well delineateo. The inspector was informed of radiological hazards I
before entry into the restricted areas. HP technicians were observed performing surveys j
of the areas surrounding the NUKEM liquid waste processing station.
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In 1998, five shipments of radioactive waste containing approximately 2,512 curies of
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activity were shipped from Unit 1. The inspector examined the radioactive waste
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processing system and reviewed a selected number of the shipping manifests. The
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majority of the waste was comprised of irradiated hardware and metal components.
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Conc lusions Radioactive waste storage was well organized and waste was segregated into logical groupings. Shipping documentation was very good and showed that the shipments had been made in compliance with NRC and Department of Transportation (DOT) regulations.
All of the radioactive waste was shipped for disposal to the Low-Level Radioactive Waste Dlsposal facility located in Barnwell, South Carolina. There were no safety concerns identifiexf.
IV. Slanificant Licensee initi_atives 4.1 Fuel Pool Cleanuo Proiect a.
Inspection Scooe A review was petformed of the Fuel Pool Cleanup Project in the CSB. Information was gathered through piant tours and discussions with cognizant personnel.
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Observations and findinas The Unit 1 SFP system located in the CSB included six interconnected pools. The system included the failed fuel pool, cask disassembiy pool, cask load pool, water storage pool, and the east and west SFPs. All fuel at Unit 1 had been removed from the reactor and is stored on site in the west spent fuel storage pool. This pool contains 160 spent fuel assemblies that wil! Iemain on site, pending the availability of permanent disposal.
The CSB is served primarily by a perimeter footing drain (North Curtain Drain System) at the 33 foot elevation. The North Curtain Drain System is connected to the licensee's radwaste processing system.
The failed fuel pool, cask disassemb8y pool and the cask load pool had been drained at the time of the inspection. Covers wue lifted from the east SFP and the inspector observed that the equipment baskets had been removed. The Unit 1 Project Manage <
pointed out discoloration on the east SFP walls that may indicate specific areas of leakage in the past. The licensee was conducting ongoing engineering reviews of the east SFP walls. With the aid vf an underwate* camera, sludge in the west pool was vacuumed, mechanically filtered, and the water sent to the liquid waste processing system.
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The water storage pool contained water that was removed and processed through the waste collection and waste distillate tanks. A sample of the sludge from the pool indicated elevated levels of polychlorinated biphenyl (PCBs). The licensee was working to identify the source of the PCBs and a strategy to c*ean up the pool.
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The licensee identified radiological contamination in the sphere foundation drain and the North Curtain Drain that was most likely caused by the SFPs and the water storage pool.
At the time of the inspection, the licensee was working to identify the r clay of the contamination leak to the North Curtain Drain and sphere foundation c:
mid will be addressing this issue in the next fiscal year.
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c. Conclusions
Based on tours, discussions with staff, and a review of work accomplished by the licensee, the inspector concluded that the SFP clean-up project was effective in ensuring safe spent fuel storage.
V. Manaaement Meetinas 5.1 Exit Meetina Summarv The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on December 2,1998 and during a telephone call on February 22,1999. The licensee acknowledged the findings presented. The licensee did j
not identify any of the documents reviewed by the inspector as proprietary.
Anthony Dimitriadis, inspector, and Ronald Bellamy, Chief, Decommissioning and Laboratory Branch attended a public meeting in Buchanao, New York on January 20,
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1999 to inform the public of the NRC inspection activities being undertaken during the SAFSTOR status.
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PARTIAL LIST OF PERSONS CONTACTED N. Cams, Senior Vice President - Nuclear Operations A. Alan Blind, Vice President - Nuclear Power
- Don Moffel, Project Menager, IP Unit 1, Consolidated Edison of New York
- Mike Dampf, Radiation Protection Manager, Consolidated Edison of New York
- Bill Zolotas, Senior Health Physics Technician, Consolidated Edison Jay Colville, Health Physics Technician, Consolidated Edison Jim Peters, Chemistry Supervisor, Louie Meuschal, Radiological Engineer Rich Louie, Licensing Engineer Dave Smith, Radiological Assessor
' Kevin Cullen, Health Physics Technician Cynthia Lord, Analyst, Trust investments, Consolidated Edison of New York
- The asterisk denotes the individuals present at the Exit Meeting conducted on December 2,1998.
INSPECTION PROCEDURES USED IP 36801:
Organization, Management, and Cost Controls IP 40801:
Self-Assessment, Auditing and Corrective Action IP 62801:
Maintenance and Surveillance IP 71801:
Decommissioning Performance and Status Review IP 83750:
Occupational Radiation Exposure IP 86750:
Solid Radioactive Waste Management and Transportation LIST OF
DOCUMENTS REVIEWED
Audit Report 97-03-B, Radiological Effluent
Audit Report 98-03-C, Radiation Protection Program
LIST OF ACRONYMS USED
As Low As is Reasonably Achievable
.CSB
Chemical Systems Building
Department of Transportation
Direct Reading Dosimeters
Hea'th Physics
NFSC
Nuclear Facilities Safety Committee
Nationai Voluntary Laboratory AccrMitation Program
ORRs
Observations Requesting a Response
PCB
Polychlorinated Biphenyl
Radiation Work Permit
Spent Fuel Pool
Thermoluminescent Dosimeters
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