IR 05000309/1993006
| ML20035E872 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 04/06/1993 |
| From: | Joseph Furia, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20035E871 | List: |
| References | |
| 50-309-93-06, 50-309-93-6, NUDOCS 9304200002 | |
| Download: ML20035E872 (7) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-309/93-06 Docket No.
50-309 License No.
DPR-36 l
I Licensee:
Maine Yankee Atomic Power Company 83 Edison Drive Aueusta. Maine 04336 i
Facility Name:
Maine Yankee Nuclear Generating Station
'
Inspection At:
Wiscasset. Maine Inspection Conducted:
March 29 - April 2.1993 (
Inspector:
N~p.
'/~F F3 J. Fupla, SeilioTTladiation Specialist, date Facilities Radiation Protection Section (FRPS),
Facilities Radiological Safety and Safeguards Branch (FRSSB), Division of Radiation Safety and Safeguar RSS)
f
~b h-L- /3 Approved by:
W c'~ o c s c-W. Pasciak, Chief, FRPS, FRSSB, DRSS date Areas Inspected: Announced inspection of the radiation protection program including:
management organization, ALARA, radiation control during normal operations, implementation of the new 10 CFR Part 20, and respiratory protection.
Results: The licensee's early implementation of the new Title 10, Code of Federal Regulations (CFR) Part 20 on April 1,1993 is a notable accomplishment. Strong performance in dosimetry was also obsened.
9304200002 930409 PDR ADOCK 05000309 G
.
. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ - _ _ _
_
_ _ _ _ _
_ _ _ _ _ _ _ _ _
_______
.
.
DETAILS 1. Personnel Contacted 1.1 Licensee Personnel R. Adams, Radiological Engineer
- R. Blackmore, Plant Manager
- D. Caristo, Radiological Programs Section Head G. Collins, Respiratory Protection Specialist M. Finn, Dosimetry Administrator
- E. Heath, Radiological Controls Section Head D. Hickey, Radiation Protection Supervisor
- S. LeClerc, Quality Programs Section Head
- G. Leitch, Vice President - Operations
- S. Nichols, Technical Support Manager
- G. Pillsbury, Radiation Protecticn Manager M. Readinger, Radiation Protection Supervisor
- B. Salter, Radiation Control Technician D. Sellers, Training Department T. Shippee, ALARA Coordinator
- J. Weast, Licensing Engineer 1.2 NRC Personnel
- W. Olsen, Resident Inspector 1.3 Other Personnel
- P. Dostie, State of Maine Nuclear Safety Inspector Denotes those present at the exit interview on April 2,1993.
I 2. Previously Identified Items (Closed) Unresolved (50-309/92-10-01) Update FSAR to reflect use of demineralizer system in lieu of waste evaporator. The licensee made the necessary changes to the FSAR, Rev 10, in paragraphs 9.3.2.2 and 9.3.3.1. This item is closed.
3. Radiation Protection The Radiation Protection Program continued to be implemented effectivly by the Radiation Protection Manager and his staff. The position of Radwaste Coordinator continued to be filled on an acting basis by the Radiological Engineer. A new Radwaste Coordinator had been hired at the time of this inspection, but had not yet arrived on site.
- - _ _ - _ _ -
-
_
--
.
.
On April 1,1993 the licensee implemented the new 10 CFR 20, nine months earlier than it was required to do. This event coincided with the quarterly dosimetry changeout, and was accompanied by numerous procedural changes. These changes were reviewed by the inspector, in the procedures listed in the sections below. A full review of the licensee's implementation will be conducted during the next inspection in this area. In addition, the licensee anticipated completing its Radiation Protection Improvement Program, with the implementation of a new instrumentation program, by the end of April 1993.
3.1 ALARA For 1992 the licensee established a goal of not more than 475 Person-Rem.
The total site dose for 1992 was 464.271 Person-Rem, showing a continuing trend towards lower site doses. For 1993, an ALARA goal of 425 Person-Rem had been established. This included 39.4 Person-Rem for normal operations and 385.6 Person-Rem for the summer refueling outage, scheduled for 52 days.
In order for the licensee to meet its 1993 ALARA goal, significant improvement in ALARA performance during the licensee's refueling outage will be needed. As described in earlier inspection reports, the licensee established an Outage Planning and Implementation Team (OPIT) that included representatives from all major departments, whose task was to schedule the refueling outage. This program has significantly improved the timeliness of ALARA planning, such that, at the time of this inspection, most radiologically significantjobs were more than 50% staged by ALARA. To aid in outage ALARA preparations, the licensee had recently hired two contractor ALARA engineers to augment the permanent ALARA staff (the ALARA Coordinator and two technicians). In addition, the licensee planned on adding six contractor ALARA technicians to its staffin May 1993. These technicians and engineers would be utilized to supervise the installation of shielding packages, conduct in-field surveillances, and perform post-job reviews.
As part of its improved ALARA program, the licensee continued to evaluate various dose reduction and source reduction techniques. Included in source reduction were evaluations of high boration shutdowns followed by peroxide-injection, which was utilized during the last refueling outage, a cobalt reduction program, and a hot spot reduction program. The cobalt program was examiAg alternative materials to be utilized in the plant, while the hot spot program was evaluating the dose savings versus dose costs for eliminating various hot spots in plant piping and valves.
As part of this inspection, the following licensee procedures were reviewed:
_
_ _ _ _ _ _.
__
_ _ _ _
__________ __________ _ -_____ - ___ _.
.
.
9-309-5, Rev 2, "ALARA Job Reviews" 9-309-6, Rev 2, " Hot Spot Reduction Program" 9-309-9, Rev 2, " Rad Controls Technician Guidance for Performing ALARA Reviews" These procedures were determined to accurately reflect the licensee's ALARA program. They were revisions of earlier procedures, with the changes made to reflect the new 10 CFR Part 20.
3.2 Work Control The licensee continued to maintain an effective radiation protection program during normal operations. Tours of the restricted area, including the Primary Auxiliary Building, Fuel Building and Low Level Waste and Equipment Temporary Storage Building (LLWETSB), indicated the presence of appropriate administrative controls and appropriate radiological housekeeping.
No discrepancies involving calibration of radiological instrumentation or inappropriate radiological work practices were identified.
As pan of this inspection, the following licensee procedures were reviewed:
9-301-2, Rev 0, " Radiation Protection Reports" 9-301-3, Rev 5, " Response to Unexpected radiological Conditions" 9-301-6, Rev 3, " Radiological Incident Report" i
9-301-7, Rev 4, " Radiation Protection Outage Planning and Implementation" l
l 9-301-8, Rev 5, " Radiation Protection Performance Assessment Program" l
l 9-301-10, Rev 6, " Radiation Protection Shift Technician Responsibilities" l
9-301-14, Rev 6, " Radiation Protection Section Management Notifications" l
9-302-1, Rev 3, " Radiation Work Permit Preparation, Review and Approval" 9-302-3, Rev 3, " Posting of Radiation and Radioactive Material Areas" 9-302-4, Rev 3, "High Radiation Area / Key Controls" 9-302-5, Rev 2, " Radiological Control of Hot Particle Areas" 9-302-6, Rev 1, " Radiological Control of Diving Activities" 9-302-7, Rev 1, " Radiological Control of Radiography Operations" 9-302-8, Rev 2, " Radiological Control of Steam generator Entries" 9-302-10, Rev 2, " Radiological Control of Radioactive Filter /Demin Changeout" 9-303-2, Rev 3, " Routine Radiological Surveys" 9-303-3, Rev 3, " Steam Generator Surveys" 9-303-4, Rev 1, " Survey Frequencies" 9-303-5, Rev 3, " Personnel Contamination Monitoring" 9-303-7, Rev 3, " Underwater Surveys" 9-303-9, Rev 2, "Radionuclide Profile Analysis" 9-303-11, Rev 2, " Unconditional Release Surveys"
_ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _
--___
.
.
..
.
.
.
.
9-303-13, Rev 2, " Survey Documentation and Review" 9-305-2, Rev 2, " Protective Clothing" 9-305-4, Rev 2, " Contaminated Area Set-bp" 9-310-1, Rev 3, " Receipt and Handling of New Reactor Fuel" 9-310-2, Rev 3, " Receipt and Handling of Radioactive Sources" 9-310-3, Rev 3, " Receipt and Handling of Radioactive Material" 9-310-4, Rev 3, " Disposal of Radioactive Sources" These procedures were determined to accurately reflect the licensee's radiation control program. They were revisions of earlier procedurts, with the changes made to reflect the new 10 CFR Part 20.
3.3 Respiratory Protection The inspector reviewed the license's program for respiratory protection,
including air sampling and the use of High Efficiency Particulate Air (HEPA)
systems as part of this inspection. As part of the new 10 CFR Part 20 implementation, the licensee has amended its procedures for the use of respirators, so as to maintain the Total Effective Dose Equivalent (TEDE)
ALARA. Licensee analysis of respirator usage during the 1992 refueling
outage indicated an excessive reliance of this protective device, such that over 2000 uses of respirators in areas with less than 0.25 times the Maximum Permissible Concentration (MPC). The licensee expected to sigt,ificantly reduce this utilization, and as part of its engineering controls would increase its utilization of HEPA ventilation systems at the job sites. At the time of this inspection, the licensee was establishing a program of repair and maintenance for these systems, which will be reviewed during a future inspection in this area.
As part of this inspection, the following licensee procedures were reviewed:
9-304-1, Rev 4, " Sampling for Airborne Radioactive Materials" 9-304-2, Rev 4, " Analysis and Evaluation of Airborne Radioactive Materials Samples" 9-304-3, Rev 1, " Changing of Containment Radiation Monitoring System Filter Paper" 9-306-1, Rev 4, " Description and Selection of Respiratory Protection Equipment" 9-306-10, Rev 1, " Respiratory Protection Program Quality Assurance" These procedures were determined to accurately reflect the licensee's respiratory protection program. They were revisions of earlier procedures, with the changes made to reflect the new 10 CFR Part 20.
l l
t
_ -
_ -...
_ _ _ _ _ _ _ _ _ _ -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
__
.
,
3.4 Dosimetry The licensee's implementation of the new 10 CFR Part 20 was meant to coincide with its quarterly dosimetry changeout. Starting on the aftemoon of March 31, all thermoluminescent dosimeters (TLDs) for the period January 1 -
March 31 were exchanged with new dosimeters provided by the licensee's vendor laboratory, the Yankee Atomic Laboratory in Massachusetts. Prior to this the license had worked with this laboratory to establish a new computerized data base that would reflect the new 10 CFR Part 20. This operation was conducted in a skilled and professional manner by the licensee's dosimetry staff.
As part of this inspection, the following licensee procedures were reviewed:
9-307-2, Rev 1, " Dose Extensions" 9-307-3, Rev 2, " Exposure Investigations" 9-307-4, Rev 3, " Issue, Use and Termination of Dosimetry" 9-307-5, Rev 4, " Issue of Special Dosimetry" 9-307-7, Rev 2, " Dosimetry Changeout" 9-307-9, Rev 2, " Skin Dose Calculations" 9-307-12, Rev 2, " Dosimetry Records Management" 9-307-13, Rev 2, " Dosimetry Quality Assurance" 9-307-14, Rev 2, " Operation of the Health Physics Information System" 9-307-15, Rev 0, " Operation of the Whole Body Counter" 9-307-16, Rev 0, " Calibration of the Whole Body Counter" 9-307-17, Rev 0, " Operation of the Series 85 Multi-Channel Analyzer" 9-307-18, Rev 0, "In-Vitro Bioassay Sampling and Analysis" 9-307-19, Rev 0, " Evaluation and Investigation of Positive Bioassay Results" These procedures were determined to accurately reflect the licensee's dosimetry program. They were revisions of earlier procedures, with the changes made to reflect the new 10 CFR Part 20.
3.5 Transnortation and Radwaste Since January 1,1993, the State of Maine, and consequently the licensee, has been excluded from access to the Barnwell IAw-Level Waste Management j
Facility. In response to this, the licensee has begun preparations to begin storage of low-level radwaste in its LLWETSB. Dry Active Wastes (DAW)
were anticipated by the licensee to be stored in this facility by the end of April. The licensee also recently installed a new DAW compactor to replace its existing system. Utilizing the old system, the licensee was able to package DAW in B-25 containers.at approximately 25 pounds per cubic foot. Early results with the new system show a 50% increase in waste loading, which will
-
_ _ _ _ _ _ _ _ _ _ _ _ _ _
. _ _ _
.__ __ __ _______________-____________
__
,
.
.
>
significantly reduce the amount of waste that needs to be placed in the LLWETSB.
As part of this inspection, the following licensee procedures were reviewed:
9-313-6, Rev 3, " Shipment of Radioactive Waste for Burial" 9-313-16, Rev 1, " Transfer to and Storage of Radwaste and Material in the Iow Level Waste and Equipment Temporary Storage Building (LLWETSB)"
9-313-17, Rev 1, " Surveillance of the LLWETSB, High-Rad Bunker, and LSA Building" 9-313-19, Rev 1, " Shipment of Radioactive Waste for Offsite Processing" 9-313-24, Rev 1, " Shipment of Contaminated Laundry Via Sole Use Vehicle" These procedures were determined to accurately reflect the licensee's radwaste and transportation program. They were revisions of earlier procedures, with the changes made to reflect the new 10 CFR Part 20.
4. Exit Interview The inspector met with the licensee representatives denoted in Section l' at the conclusion of the inspection on April 2,1993. The inspector summarized the purpose, scope and findings of the inspection.
_ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _