ML112220165
| ML112220165 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/10/2011 |
| From: | Laurie Kauffman Decommissioning Branch I |
| To: | Dominion Nuclear Connecticut |
| References | |
| IR-11-007 | |
| Download: ML112220165 (10) | |
See also: IR 05000245/2011007
Text
Inspection No.
Docket No.
License No.
Licensee:
Location:
Inspection Dates:
Inspector:
Approved By:
u.s. NUCLEAR REGULATORY COMMISSION
REGION I
INSPECTION REPORT
05000245
Dominion Nuclear Connecticut, Inc.
Millstone Power Station, Unit 1
Rope Ferry Road, Waterford, CT 06385
July 11 - 13, 2011
Laurie A. Kauffman
Health Physicist
Decommissioning Branch
Division of Nuclear Materials Safety
Judith A. Joustra, Chief
Decommissioning Branch
Division of Nuclear Materials Safety
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EXECUTIVE SUMMARY
Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 1
NRC Inspection Report No. 05000245/2011007
A routine announced safety inspection was conducted from July 11-13, 2011, at the Millstone
Power Station Unit 1 (U1) by a region-based 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 inspector reviewed
the licensee's programs associated with U1, including the Spent Fuel Pool Island (SFPI), while
in SAFSTOR status. There are no ongoing decommissioning activities being conducted at
Millstone U1. Within the scope of this inspection, no safety concerns or violations were
identified. The conclusions from each inspection area are presented below.
Organization and Management Controls Program
The roles and responsibilities for the operation, maintenance, and control of U1 SAFSTOR
program, required in Technical Specifications (TS) and the Defueled Safety Analysis Report
(DSAR), were adequate to support U1 activities.
Design Changes and Modifications Program
The design change program was adequate to ensure systems and components, important for
maintaining the safe storage of spent fuel, were operable and reliable. The licensee
implemented the plant modification packages in accordance with the regulations in 10 CFR
50.59 and the requirements of the TS and the DSAR.
Corrective Action Program
The licensee's corrective action program (CAP) for identifying, resolving, and preventing
conditions that could degrade safety or the quality of decommissioning activities was adequate.
The threshold for identifying concerns and the priority for addressing condition reports (CRs) and
implementing corrective actions were adequate and based upon safety significance.
Spent Fuel Pool Safety Program
The licensee effectively implemented the SFPI program to ensure that systems and components
important for maintaining the safe storage of spent fuel were operable and reliable.
Maintenance and Surveillance Program
The licensee implemented a preventive maintenance and surveillance program to ensure
systems and components important to maintaining the safe storage of spent fuel were operable
and reliable. Established controls and measures to plan, schedule, and perform work activities
were adequate.
Occupational Radiation Exposure Program
The licensee radiation protection controls were adequate to limit exposures of workers to
external sources of radiation. Posting and labeling of radioactive materials and radiation areas
met regulatory requirements. Radiological controls and dose estimates associated with U1
tasks were effective to achieve dose goals.
Radiological Effluent Control and Radioactive Environmental Monitoring Programs
The licensee maintained adequate radioactive effluent control and radiological environmental
monitoring programs in accordance with regulatory requirements.
Solid Radioactive Waste Management and Transportation Programs
The licensee effectively implemented the radioactive waste management and transportation
programs.
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REPORT DETAILS
1.0
Background
The Millstone site is located in the town of Waterford, Connecticut. Millstone U1 was a single-
cycle, boiling water reactor with a thermal output of 2011 megawatts and a net electrical output
of 652.1 megawatts. The plant went into commercial operation on December 28, 1970 and
permanently ceased operations on July 17, 1998. Subsequently, the fuel was permanently
removed from the reactor vessel and stored in the spent fuel pool.
2.0
Organization and Management Controls Program
a.
Inspection Scope (Inspection Procedure (IP) 36801)
The inspector discussed the roles and responsibilities for the operation, maintenance,
and control of the SAFSTOR program, required in TS 5.1 through 5.4 and described in
the DSAR. The inspector also evaluated the reduction in force (RIF) to determine the
effect on the staff's overall ability to implement the SAFSTOR program.
b.
Observations and Findings
The inspector verified that TS 5.1 through 5.4 were implemented, and that the DSAR and
associated procedures were consistent with the TS requirements. During the previous
inspection, the licensee underwent a RIF between March 1, 2010 and June 1, 2010.
During this inspection, the inspector discussed the challenges encountered with the staff
and noted the SAFSTOR activities, including the safe operation of the Spent Fuel Pool
(SFP) and its associated equipment were maintained. The inspector noted that the U1
staff continued to obtain assistance from Millstone plant personnel to complete
surveillance procedures and tasks required by U1 TS and procedures. No adverse
trends or safety concerns were identified.
c.
Conclusions
The roles and responsibilities for the operation, maintenance, and control of U1
SAFSTOR program, required in TS and the DSAR, were adequate to support U1
activities. No safety concerns or violations were identified.
3.0
Design Changes and Modifications Program
a.
Inspection Scope (IP 37801)
The inspector reviewed the procedures describing the design change program and the
documentation for two U1 plant modifications related to the Main Exhaust Fan HVE-1A
Motor and the Waste Water Processing System. The inspector reviewed the design
change packages against the regulations in 10 CFR 50.59 and the requirements of the
TS and the DSAR to determine if the licensee ensured that systems and components
important for maintaining the safe storage of spent fuel were operable and reliable.
Specifically, the inspector reviewed the submitted design change packages to verify if the
licensee had appropriately determined whether the design changes required: a 10 CFR
50.59 safety evaluation; license or TS amendment; and/or a DSAR update.
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b.
Observations and Findings
The inspector reviewed the plant modification packages and verified they included a
Design Change Request and a Design Change Notice (DCN). The DCN process was
used to describe the systems or components to be changed, propose solutions, and to*
justify changes. The DCN was used to determine whether a 10 CFR 50.59 safety
evaluation, a license or TS amendment, and/or a DSAR update were required for both
design changes. In particular, the licensee determined that only the Waste Water
Processing System required a DSAR update. The licensee drafted changes to the
DSAR Section 4, as applicable, to allow the release of the reactor building sump water
through the Emergency Service Water discharge piping and through the discharge canal.
The draft changes are under review by the licensing department. No adverse trends or
safety concerns were identified.
c.
Conclusions
The design change program was adequate to ensure systems and components,
important for maintaining the safe storage of spent fuel, were operable and reliable. The
licensee implemented the plant modification packages in accordance with the regulations
in 10 CFR 50.59 and the requirements of the TS and the DSAR. No safety concerns or
violations were identified.
4.0
Corrective Action Program
a.
Inspection Scope liP 40801)
The inspector reviewed the corrective action program (CAP) for identifying, resolving,
and preventing conditions that could degrade safety or the quality of decommissioning
activities. The inspector reviewed the procedures describing the CAP and reviewed
several selected CRs.
b.
Observations and Findings
The license initiated CRs in accordance with the site CAP to identify and resolve
conditions that may impact SAFSTOR activities. The inspector reviewed two self-
identified concerns that were documented in CRs. The concerns were related to a
ventilation fan and a SFP Gate Leakage Alarm. The license investigated and corrected
both concerns.
The inspector reviewed a CR that the licensee issued during a special NRC inspection
pursuant to Temporary Instruction (TI2515/183) relating to the March 2011 Fukushima
Daiichi Nuclear Station fuel damage event. [For details of the T12515/183 inspection,
refer to ADAMS Accession Number ML 111320660.] As a result of the T12515/183
inspection, the inspector identified an enhancement associated with the position of the
U1 SFP crane. Specifically, the crane was over the center of the pool rather than at one
end. During this inspection, the inspector observed the U1 crane operator reposition the
SFP crane to one end of the SFP. No adverse trends or safety concerns were identified.
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c.
Conclusions
The licensee's CAP for identifying, resolving, and preventing conditions that could
degrade safety or the quality of decommissioning activities was adequate. The threshold
for identifying concerns and the priority for addressing CRs and implementing corrective
actions were adequate and based upon safety significance. No safety concerns or
violations were identified.
5.0
Spent Fuel Pool Safety Program
a.
Inspection Scope (lP 60801)
The inspector evaluated the licensee's program for ensuring the safe storage of spent
fuel in the SFP. The inspector reviewed and compared the DSAR, TS, and Technical
Requirements Manual (TRM) with associated procedures to ascertain that they were
consistent with the SFPI requirements.
The inspector performed a tour of the reactor building to evaluate the general condition
of the building, systems, and components including: SFP cooling and ventilation system;
decay heat removal (DHR) pumps and motors; emergency diesel generator (EDG); the
east corner room; and the torus room. The inspector performed a tour of the radioactive
waste facility to evaluate the general material condition of the facility and equipment
including the facility sump. The inspector discussed with the licensee the spent fuel rack
test that was performed in June 2011.
b.
Observations and Findings
The inspector toured the facility and verified that systems and components important to
the safe storage of spent fuel were operable and adequately maintained. The inspector
observed several leak detection stations and noted no obvious SFP leakage. The
inspector noted that the SFP temperature and water level, the SFP cooling rates, and the
DHR system flow rates were monitored in accordance with the TS, TRM, and established
procedures. The inspector determined that plant personnel conducted the routine
system operational checks at the required frequencies. No adverse trends or safety
concerns were identified.
One area not evaluated by the inspector was the spent fuel rack test (also called the
Boron-10 (B-1 0) Areal Density Gauge for Evaluating Racks (BADGER) test) in June
2011. The results of the BADGER test were not available at the time of this inspection.
The inspector will review the final test results during a subsequent inspection.
c.
Conclusions
The licensee effectively implemented the SFPI program to ensure that systems and
components important for maintaining the safe storage of spent fuel were operable and
reliable. No safety concerns or violations were identified.
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6.0
Maintenance and Surveillance Program
a.
Inspection Scope OP 62801)
The inspector reviewed the licensee's preventive maintenance and surveillance program
including the planned and completed maintenance and surveillance activities of systems
and components important for maintaining the safe storage of spent fuel. The inspector
reviewed selected maintenance and surveillance test results for the SFP cooling pumps
and motors; the DHR pumps, fans, and motors; the ventilation fans and motors; and the
EDG to verify that work was being performed within the established frequencies and that
the equipment was being properly maintained. The inspector also reviewed the annual
reactor building bridge and hoist inspection, and the refuel platform load switch
calibration procedures.
b.
Observations and Findings
The maintenance and surveillance test results for the SFP cooling pumps and motors;
the DHR pumps, fans, and motors; the ventilation fans and motors; the EDG; the reactor
building bridge and hoist; and the refuel platform load switch were thorough, performed
within the established frequencies, and met the acceptance criteria defined in the
associated procedures. The inspector determined that the systems and components
were operable and available for service.
c.
Conclusions
The licensee implemented a preventive maintenance and surveillance program to ensure
systems and components important to maintaining the safe storage of spent fuel were
operable and reliable. Established controls and measures to plan, schedule, and
perform work activities were adequate. No safety concerns or violations were identified.
7.0
Occupational Radiation Exposure Program
a.
Inspection Scope (IP 83750)
The inspector reviewed implementation of the occupational exposure control program
associated with SAFSTOR and SFPI activities. The inspection consisted of interviews
with responsible individuals, reviews of documents and postings; and observations of a
radiation protection technician conduct routine surveys in the reactor building.
b.
Observations and Findings
The inspector conducted a plant tour and determined that radiological postings were
readily visible, well maintained, and reflected radiological conditions. The survey maps
and related information maintained at the U1 access point were current. The high
radiation areas and the TS locked high radiation areas were properly posted and locked
as required.
The inspector reviewed the 2010 and 2011 year-to-date exposure reports, the 2011 as
low as reasonably achievable (ALARA) evaluation for the SFP BADGER test, and the
associated radiation work permits. The dose totals for 2010 and 2011 year-to-date dose
reports were 0.142 mrem and 0.154 mrem, respectively. The largest contribution of the
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2011 dose was due to the SFP BADGER testing and SFPI instrument calibrations. The
inspector noted that the associated radiation work permits were commensurate with the
radiological significance of the task and included the appropriate exposure control
measures for the safe implementation of the activity. The inspector determined the
licensee provided adequate exposure controls to limit the exposure of workers to external
sources of radiation and used established methods to track and trend radiation dose.
c.
Conclusions
The licensee radiation protection controls were adequate to limit exposures of workers to
external sources of radiation. Posting and labeling of radioactive materials and radiation
areas met regulatory requirements. Radiological controls and dose estimates associated
with U1 tasks were effective to achieve dose goals. No safety concerns or violations
were identified.
8.0
Radiological Effluent Control and Radioactive Environmental Monitoring Programs
a.
Insp.ection Scope (IP 84750)
The inspector reviewed the radioactive effluent control and the radiological
environmental monitoring programs associated with SAFSTOR and SFPI activities.
b.
Observations and Findings
The inspector reviewed the annual radiological environmental operating report and the
annual radioactive effluent release report and determined that the reports were submitted
to the NRC in accordance with TS 5.7.2 and TS 5.7.3, respectively. The calculated
doses were below the regulatory dose criteria of 10 CFR 50, Appendix I. The effluent
and radiological environmental monitoring programs were implemented in accordance
with TS requirements.
During the previous inspection, the inspector identified significant rainwater in-leakage
into the radioactive waste building. The inspector reviewed the renovations to the
building since the last inspection, which included repairing cracks in the walls and
ceilings. The licensee is completing a new waste water processing system to manage
liquid effluent from the waste building. The inspector determined that there had been no
rainwater in-leakage since the previous inspection.
c.
Conclusions
The licensee maintained adequate radioactive effluent control and radiological
environmental monitoring programs in accordance with regulatory requirements. No
safety concerns or violations were identified.
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~-------------
9.0
Solid Radioactive Waste Management and Transportation Programs
a.
Inspection Scope (IP 86750)
The inspector evaluated the radioactive waste management and transportation programs
to determine whether the licensee properly processed, packaged, stored, and shipped
radioactive materials. The inspector reviewed the waste stream analysis for dry active
waste required by 10 CFR 61.
b.
Observations and Findings
The licensee manages an asset recovery program to remove systems andlor
components that are no longer needed for the safe operation of the SFP. The licensee
removed and disposed three U1 feed pump motors (2M-10A, B, & C) and accessories in
March 2010. The motors and accessories were classified as low specific activity (LSA)
material. The radioactive waste shipment records included copies of characterization
reports and waste manifest shipping papers and were complete. The licensee met the
applicable radioactive waste and transportation requirements for the shipments reviewed.
c.
Conclusions
The licensee effectively implemented the radioactive waste management and
transportation programs. No safety concerns or violations were identified.
Exit Meeting Summary
On June 13, 2010, the inspector presented the preliminary inspection results to Jeffrey
Semancik, Millstone Plant Manager, and members of his staff. The inspector confirmed
that proprietary information was not provided or examined during the inspection.
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Licensee
W. Bartron
D. Delcore
PARTIAL LIST OF PERSONS CONTACTED
Licensing Supervisor
J. Drzewianowski
A. Elms
Nuclear Oversight Specialist
Radiation Protection Technician
Organizational Effectiveness Manager
Site Services Manager
S. Heard
E. Palmieri
L. Salyards
J. Semancik
G. Sturgeon
36801
37801
40801
60801
62801
71801
83750
84750
86750
None
Nuclear Maintenance Supervisor
Licensing Engineer
Plant Manager
Operations Nuclear Specialist
INSPECTION PROCEDURES USED
Organization, Management, and Cost Controls at Permanently Shutdown
Reactors (PSRs)
Safety Reviews, Design Changes, and Modification at PSRs
Self Assessment and Corrective Action
Spent Fuel Pool Safety 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
ITEMS OPEN, CLOSED. AND DISCUSSED
LIST OF DOCUMENTS REVIEWED
Millstone U1 Radiation Surveys conducted between April 2010 and July 2011
Millstone U1 Radiation Exposure (ALARA) Reports for 2010, and most current for 2011
Millstone U1 Surveillance Form for Operator Logs and Inspections (U1 rounds)
Work Order 53102390415 associated with the quarterly run
Work Order 53102281885 associated with the annual inspection of the diesel generator
Asset Recovery Information conducted between March 2010 and June 2011
Summary of Millstone U1 Condition Reports between March 2010 and June 2011
CR 368109 "Unit 1 Reactor Building Crane will Not Raise or Lower"
CR 405562, "MP1 Balance of Plant (BOP) Ventilation Exhaust Fan Failure"
CR 422447, "Control of Unit 1 Refuel Platform Position in Spent Fuel Pool Needs Enhancement"
CR 428247, "Unit 1 Spent Fuel Pool Gate Leakage Alarm no Functioning as Designed"
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CFR
CR
DCN
IMC
mrem
NRC
PSRs
TS
U1
LIST OF ACRONYMS USED
Agencywide Documents Access and Management System
Boron-10 (B-1 0) Areal Density Gauge for Evaluating Racks test
corrective action program
Code of Federal Regulations
condition report
Design Change Notice
defueled safety analysis report
inspection manual chapter
millirem
Nuclear Regulatory Commission
Publicly Available Records System
Permanently Shutdown Reactors
spent fuel pool
spent fuel pool island
technical requirements manual
technical specification
Unit 1
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