IR 05000397/1994003
| ML17290A972 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/04/1994 |
| From: | Brewer R, Reese J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17290A971 | List: |
| References | |
| 50-397-94-03, 50-397-94-3, NUDOCS 9402230071 | |
| Download: ML17290A972 (10) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION REGION V
Report No.:
License:
Licensee:
Facility:
50-397/94-03 NPF-21 Washington Public Power Supply System (WPPSS)
P.O.
Box 968 3000 George Mashington Way Richland, MA 99352 Washington Nuclear Project
(WNP-2)
Inspection location:
WNP-2 Site, Benton County, Washington Inspection duration:
January 24-27, 1993 Inspected by:
ewer, at>on pecia est a
e cygne Approved by:
arne
.
Reese, se il ies Radiologi al Protection Branch ate cygne
~Summau:
Areas Ins ected:
Routine, announced inspection of followup items, occupational radiation exposure, internal exposure controls, outage planning and preparation, training and qualifications, and facility inspections.
NRC Inspection Procedures 92701 and 83750 were used.
Results:
The licensee's program for controlling occupational radiation exposure, in the aspects reviewed, appeared adequate in meeting the licensee's safety objectives.
No violations or deviations were identified.
The effort expended by the licensee to make ALARA planning a more important part of the work and outage planning process, over previous performance in this area, was noted to be a strength in the licensee's radiation protection program.
940223007i 940204 PDR ADOCK 05000397
DETAILS Persons Contacted Licensee
- K. Pisarcik, Licensing Assistance
"W. Barley, Manager, Radiation Protection (Contract)
~J. Albers, Corporate Radiological Health Officer, WPPSS D. Kerlee, Technical Specialist, equality Assurance
"M. Nolan, Supervisor, Radioactive Waste
- B. Hugo, Licensing Engineer
- Y. Derrer, Manager, Health Physics/Chemistry/General Employee Training
"T. Love, Manager, Chemistry
- V. Shockley, Manager, Health Physics W. Rigby, Supervisor, Health Physics Planning/ALARA
- S. Telander, Manager, Support Services
~M. Hedges, Corporate Chemist, Chemistry
"M. Flasch, Director, Engineering
- G. Ehlert, Senior Technician, Health Physics
- M. Kinmark, Senior Technician, Health Physics
- R. Patch, Supervisor, Health Physics Operations
- J. Cooke, Technician, Health Physics
"T. Cooke, Senior Technician, Health Physics
~M. Tuel, Senior Health Physicist, Radiation Protection
~B. Friedel, Technician, Health Physics/ALARA
- P. Rannells, Technical Instructor, Training NRC R. Barr, Sr. Resident Inspector D. Proulx, Resident Inspector
- Denotes those individuals who attended the exit meeting on November 5,
1993.
The inspector met and held discussions with additional members of the licensee's staff during the inspection.
~Followu (92701)
Item 50-397 93-26-01 Closed:
This followup item involved Corporate Licensing and Assurance Audit No.92-594 of the licensee's radiation protection program (RP).
The inspector reviewed the findings of the audit and the status of the RP Department's corrective actions.
The inspector had no further concerns regarding this matter.
This item is considered closed.
Occu ational Radiation Ex osure
{83750)
The inspector examined the licensee's radiation protection program for compliance with 10 CFR Parts 19 and 20, Technical Specificat-:.ons, and licensee procedures.
The examination focused on radiation protection activities conducted by the licensee since the previous inspection on June 28 through July 2, 1993, (50-397/93-26).
The following procedures were reviewed during this inspection.
TTH 6. 1.0, "Training Instructor Certification,".Revision 3.
TTH 5.2.2, "Instructional Skills Training Program Description," Revision 6.
TTP 6.1. 1, "Technical training Instructor gualification/Certification," Revision 7.
~
NOS 38, "Radiation Protection Program," Revision 5.
~
PPH 1.11.14,
"Respiratory Protection Program Description,"
Revision 0.
PPH l. 11.20,
"Use of Respiratory Protection Equipment,"
Revision 0.
PPH 11.2.11.3,
"Issuance of Respiratory Protection Equipment," Revision 7.
PPM 11.2.2.11,
"Exposure Evaluations For Haintaining TEDE ALARA," Revision 0.
~
PPH 1. 11.2,
"ALARA Program Description," Revision 7.
~
PPH 11.2.2.5,
"ALARA Bob Planning And Reviews," Revision 0.
The procedures reviewed and the work practices observed appeared to be consistent with 10 CFR 19
& 20 and Technical Specification requirements.
~Chan ea (2)
The licensee had implemented the requirements of the revised
CFR Part 20 since the previous inspection.
As a result, numerous licensee RP program implementing procedures had been revised, superseded, or rescinded.
Since the previous inspection of this area, two licensee personnel-changes had taken place at the supervisory/managerial level.
(a)
An individual who had been serving an extended term with the Institute for Nuclear Power Operations (INPO)
had returned to assume the position of Hanger, Health Physics/Chemistry/General Employee Training (GET).
(b)
An individual who had been working in the training department, and who previously held progressively responsible positions in the RP organizations of
various nuclear power plants, assumed the position of Supervisor, Health Physics Planning/ALARA.
The inspector noted that the qualifications of both individuals appeared to be adequate for their positions.
Internal Ex osure Control The licensee's respiratory protection program was examined for compliance with 10 CFR 20, Subpart H requirements, and consistency with the recommendations of Regulatory Guide (RG) 8.15,
"Acceptable Programs for Respiratory Protection,"
"Manual of Respiratory Protection Against Airborne Radioactive Materials,"
and American National Standards Institute (ANSI)
Z88.2, "Practices for Respiratory Protection."
The examination included a review of the training program provided to users of respiratory protection equipment, the medical examination requirements and respirator fit testing program for respiratory equipment users, applicable respiratory protection program implementing procedures, and an inspection of the respirator issuance and storage facility at the 467 foot elevation of the Radwaste Building and various emergency use respirator storage locations.
(I)
The licensee's respiratory protection training consisted of a classroom presentation which included discussions regarding the types of respiratory hazards at the plant, requirements for qualification to wear respiratory protection equipment (RPE) at WNP-2, the use of engineering controls versus RPE, selection of respirators, protection factors of various types of RPE, and emergency actions in the event of respirator malfunction or other occurrence while wearing a respirator.
The training also included a
laboratory on the proper donning and doffing techniques for full-face air purifying respirators, and positive and negative pressure testing of respirators prior to use.
At the conclusion of the training presentation, a multiple choice exam was administered which required a minimum of seventy percent to pass.
Persons passing the examination were then given a quantitative fit test.
The inspector noted the classroom presentation regarding Annual Limit~ on Intake, Derived Air Concentrations, Total Effective Dose Equivalent ALARA concepts, and the rationale for taking workers out of respirators where historically respirators had been worn, to be adequately presented.
The inspector noted the training provided to users of respiratory protection equipment to contain sufficient information necessary for proper respirator usag (2)
The inspector noted that the licensee verified the medical qualifications of those persons attempting to get respirator qualified by obtaining a current copy of a doctor'
respiratory medical certification for each individual. The inspector also verified that the licensee's respiratory protection program implementing procedures and quantitative fit testing practices satisfied the recommendations of NUREG 0041 and NRC RG 8.15.
(3)
The inspector observed emergency use self contained breathing apparatus respirators staged at various locations of the p1ant to have been inspected within the time period required by procedure PPM 1.11. 14.
The inspector noted that the storage and maintenance practices for respiratory protection equipment satisfied the recommendations of NUREG 0041 and NRC RG 8.15.
The inspector noted the licensee's respiratory protection program, in the aspects reviewed, to be consistent with regulatory requirements, licensee procedures, and the guidance documents
'referenced above.
The inspector had no concerns in this area.
I Plannin and Pre aration Activities associated with the planning and preparations for the upcoming refueling outage (R9), scheduled to start on May 1, 1994, were examined.
The examination included a review of applicable procedures and documents, an inspection of the licensee's facilities, and discussions with members of the licensee's staff.
The inspector's examination disclosed the following:
~
The outage was scheduled to last approximately 60 days.
~
Estimated outage exposure of 650 person-rem had been established.
~
Outage staffing and training needs had been established.
~
The work planning process was in progress with approximately 35 to 50 percent of the work planning in various stages of completion,
~
The licensee was uti'jizing past job history files in outage planning.
~
The licensee was placing increased emphasis on ALARA during the planning of the R9 refueling outage.
The inspector noted the increased level of ALARA involvement to be improved over past performance in this area.
The licensee planned to establish three ALARA contacts for work conducted in the drywell, the refueling floor, and the balance of plant, for the purpose of aiding in the coordination and dose minimization of work activities in those areas.
The ALARA Supervisor will be serving in the capacity of Drywell Manager with at least four
0'
Drywell Coordinators reporting to the Drywell Manager.
The Drywell Manager will report directly to the Outage Manager and will have the authority to stop work in the,drywell should a
situation warrant stoppage due to radiological or work
'oordination conditions which could adversely affect worker exposures.
The inspector noted that the licensee was considering the installation of permanent shielding around the recirculation pumps the drywell during the R9 refueling outage.
The recirculation pumps are at the same elevation as the personnel entry hatch in'o the drywell.
During drywell entries, workers must walk past the recirculation pumps, and thus receive unnecessary dose while in transit to their work location.
The licensee intends to minimize workers'oses while in transit in the drywell by the installation of permanent shielding around the recirculation pumps.
The primary evolutions scheduled during this outage were identified as follows:
Mechanical Stress Improvement Process (MSIP) on reactor vessel nozzles and jet pumps.
Routine inspection and preventative maintenance of nuclear steam supply system..
In-service inspection.
Replace 30 control rod drives.
~
Replace 18 control blades and 8 low power range monitor strings.
The inspector concluded that the licensee's ALARA program, and the planning and preparation for the R9 refueling outage was consistent with applicable licensee procedures, the recommendations of RG 8.8, "Information Relevant to Ensuring That Occupational Exposures at Nuclear Power Stations Mill Be As Low As Reasonably Achievable,"
and RG 8. 10, "Operating Philosophy for Maintaining Occupational Exposures As Low As Reasonable Achievable."
Trainin and ualifications The inspector examined the licensee's training and qualification program for contract Health Physics Technicians (HPTs)
and GET Instructors.
The examination consisted of reviews of applicable procedures and documents, discussions with members of the licensee's staff, and observations of activities in progress.
1.
The inspector examined the licensee's training and qualification program for contract HPTs scheduled to come on site for the R9 refueling outage.
Specifically, the inspector examined the licensee's training for incorporation of the revised
CFR Part 20 (Part 20) requirements.
The
2.
inspector reviewed the lesson plans, examinations, and on-the-job training task lists and held discussions with members of the training department staff.
The lesson plans appeared to include the necessary information from the revised Part 20, and the training program appeared to provide the training necessary for a contract HPT to implement the licensee's RP program.
The inspector also examined the training and qualification program for GET Instructors.
The inspector's examination included the observation of a GET radiation worker retraining class in progress and review of the qualification requirements for GET Instructors.
The inspector noted the GET radiation worker retraining class to be well structured, well presented, and contain the type of information to enable radiation workers to work safely in the plant.
The inspector noted the licensee's GET Instructor qualification program to be adequate.
The licensee's GET Instructor qualification program appeared to allow GET Instructors to maintain a level of competence in the applicable subject matter'to enable them to adequately present radiation protection material to radiation workers.
The licensee's contract HPT and GET Instructor training and qualification programs, in the aspects reviewed, appeared adequate to meet the licensee's safety objectives.
No concerns were identified.
Facilit Ins ections During facility inspections, the inspector observed that adequate personnel survey instruments were conveniently located near exits from surface contamination areas (SCAs).
All instruments'bserved in use were functional, within their calibration period and had been daily performance tested.
The inspector performed independent dose rate measurements of areas inside the radiological controlled area (RCA) using an ion chamber type detector (Eberline Hodel R0-2, NRC serial No. 022906)
due for calibration July 3, 1994.
All areas observed were adequately posted and were conducive to alerting workers to the radiological conditions present.
The inspector noted.that radioactive materials, radiation, and high radiation areas were posted in accordance with the requirements of 10 CFR 20.1902.
The inspector noted plant housekeeping to be well maintaine The licensee's program for controlling occupational exposure, in the aspects reviewed, appeared adequate in accomplishing the licensee's safety objectives.
No violations or deviations were identified.
Exit Interview The inspector met with members of licensee management at the conclusion of the inspection on January 27, 1994.
The scope and findings of the inspection were summarized.
The licensee acknowledged the inspector's observations.
The licensee did not identify as proprietary, any of the information provided to the inspectors during the inspection.