IR 05000244/1985007
| ML17254A372 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/03/1985 |
| From: | Dragoun T, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17254A371 | List: |
| References | |
| 50-244-85-07, 50-244-85-7, NUDOCS 8505200323 | |
| Download: ML17254A372 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-244/85-07 Docket No.
50-244 License No.
DPR-18 Pri ority Category C
Licensee:
Rochester Gas and Electri~cCor 49 East Avenue Rochester New York 14649 Facility Name:
R.
E. Ginna Nuclear Power Plant Inspection At:
Ontario New York Inspection Conducted:
March 25-29 1985 Inspectors:
T. Dra oun Radiati ecialist date Approved by:
M. Shanbaky, ief PWR Radiation Protection Section da e
Ins ection Summar 50-244/85-07 Inspection on March 25-29, 1985 (Inspection Report R
safety program including:
status of previously identified items, respiratory protection, control of high radiation areas, radiation work practices, qualification of contractor HP technicians, calibration of survey instruments.
The inspection involved
hours on site by one region based inspector.
Results:
No violations were identified.
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Details 1.0 Persons Contacted During the course of this routine inspection the following personnel were contacted or interviewed:
1. 1 Licensee Personnel
- R.
W. Kober, Vice President, Electric and Steam Production
"B. A. Snow, Plant Superintendent
- Nuclear
- D. Fi lkins, Manager Health Physics and Chemistry
- W. P.
Goodman, HP Foreman J.
R. Supina, Dosimetry Supervisor F. J
~ Mis, Health Physicist S. Sagaties, Health Physicist
~S.
B. Warren, Health Physicist K. Triou, Training Department A. Plummer, Plant Nurse Other licensee and contractor employees were also contacted or interviewed during this inspections
- Attended the Exit Interview on March 29, 1985.
2.0
~Per ose The purpose of this routine inspection was to review the licensee's radiation protection program with respect to the following elements:
~
Status of Previously Identified Items
~
Respiratory Protection
~
Control of High Radiation Areas
~
Radiation Work Practices
~
gualification and Training of Contractor HP Technicians
~
Maintenance and Calibration of Survey Instruments 3.0 Status of Previousl Identified Items 3. 1 (Closed)
Violation (84-02-01)
and Violation (84-12-02)
Failure to properly survey airborne activity.
The licensee has developed a
new procedure (HP14.0)
that clearly describes the use of the various air sampling devices that are available in the station.
Licensee action as described in letters dated May 24, 1984; July 27, 1984; and August 3,
1984 is complete and satisfactor.2 (Closed) Violation (84-02-02)
Failure to obtain supervisor approval for a Special Work Permit.
The licensee revised procedure HP4.3 to clearly delineate the function and responsibility of the job supervisor in issuing Special Work Permits.
Licensee action as described in a letter dated May 24, 1984 is complete and satisfactory.
3. 3 (Cl osed)
Fol 1 ow-up Item (85-01-02)
Insure receivers of radi oacti ve materials shipments are licensed and activity is within license limits.
The licensee has revised procedure RD10.0 and included a check-off list that verifies materials license information.
3.4 (Closed)
Fol low-up Item (85-01-03)
Establ i sh timetables for surveys of incoming radioactive material and burial site receipt verification for radwaste shipments.
The date and time of receipt of material is now logged per instructions in the
"HP Tech Duty Book".
Procedure RD10.6 has been modified by Permanent Change Notice 85T289 to initiate an investigation if radwaste receipt verification is not obtained within
days of shipment.
3.5 (Closed)
Follow-up Item (85-01-05).
Provide QC oversight of non-radwaste shipments.
Procedure RD10.0 has been revised to include gC concurrence for all non-radwaste shipments.
3.6 (Closed)
Follow-up Item (85-01-05)
Include transporters address and phone number on radwaste shipment manifests.
The computer software used to generate the manifests has been,reprogrammed with this information.
4.0 Res irator Protection Pro ram The licensee's respiratory protection program was reviewed against criteria contained in:
CFR 20. 103
"Exposure of individuals to concentrations of radioactive materials in air in restricted areas" Reg.
Guide 8.9
"Acceptable Concepts, Models, Equations and Assumptions for a Bioassay Program" Reg.
Guide 8. 15
"Acceptable Program for Respiratory Protection" I
E Notice 84-24,
"Physical gualification of Individuals to Use Respiratory Protection Devices" ANSI N343,
"Internal Dosimetry for Mixed Fission and Activation Products" Licensee Procedures A-1.6.3, HP-12.2, HP-12.3, HP-12.4, HP-12.5, HP-12.6, HP-2.5, HP-2.5. 1, HP-2.5.2, HP-2.5.3, HP-2.2, HP-2. 1, HP-2.2. 1, HP-2. The licensees performance relative to these criteria was determined by a
review of the following areas:
Medical screening and training of respirator users.
Maintenance and repair of respiratory protection equipment Issuance and use of respirators Assessment of internal exposures and whole body counting Record keeping Within the scope of this review no violations were observed.
However, the following improvement items were noted:
RG&E personnel receive a
medical evaluation on site by a
specially trained nurse prior to participation in the respirator program, This evaluation consists of a
medical history questionnaire, blood pressure and spirometry tests.
Only personnel with some contraindication for respirator use are referred to the company physician for evaluation.
The remainder are certified by the nurse.
Regulation
CFR 20. 103(c)(2)
states that a "determination by a physician... that the individual user is physically able to use the respiratory protective equipment" is required.
The acceptability of determinations made by a
nurse is unresolved pending review of this item (85-07-01)
The licensee maintains a
Helgeson whole body counter to detect and evaluate uptakes of radioactive material by workers.
The licensee advised that the computer program used to analyze the WBC data was recently updated to provide information on the location of deposits in addition to radioisotope and quantity.
The current operating procedures for the WBC do not clearly provide the technician with the steps necessary to obtain this information.
The licensee advised that the applicable procedures would be clarified.
This matter will be reviewed in a subsequent inspection.
(85-07-02)
The inspector noted that the licensee made extensive use of multiple channel Continuous Air Monitors (CAM) in Containment and the Auxiliary Building work areas.
These CAMs monitored airborne iodine and noble gases in addition to particulate activity.
The continuous monitoring is supplemented by grab samples.
5.
Control of Hi h Radiation Areas The licensees control of high radiation areas was reviewed against criteria contained in:
CFR 20.201,
"Surveys"
CFR 20.202,
"Personnel monitoring"
CFR 20.203,
"Caution signs, labels, signals and controls" Technical Specification 6. 13 - High Radiation Area Procedure A-l.1, "Locked Radiation Areas" Procedure A-l,, "Radiation Control Manual" The licensees performance relative to these criteria was determined by a
review of the following areas:
HP control of high radiation area entries via Special Work Permits.
Use of postings, barricades and locks.
Control of keys recordkeeping Within the scope of this review no violations were identified.
6.
Radiation Work Practices The licensees radiation work practices were reviewed against criteria contained in:
Radiation Control Manual A-1 Administrative Procedure A-1.6. 1 Procedure HP-4.3, "Health Physics Work Permit Use" Procedure A-3, "Containment Vessel Access Requirements" The licensees performance relative to these criteria was determined by a
review of the following areas:
Control of radioactive tools and material Radiation surveys Exposure control Surveillance of work by HP Technicians Use of respirators and protective clothing ALARA Program Evaluation Response to alarms and warnings
Within the scope of this review no violations were identified.
However, the inspector noted that personnel did not evacuate the Containment Vessel during a High Flux at Shutdown Alarm.
Discussions with various personnel indicate that this alarm had sounded sporadically during the outage due to electrical maintenance.
HP technicians had been warned about these false alarms during an orientation briefing.
Many personnel had become desensitized to the siren alarm in Containment.
A high ambient noise level in Containment was created by operation of coolant pumps and ventilation systems.
The public address system was unintelligible in many locations while the alarms were clearly recognizable.
The licensee stated that the alarms in Containment would be reviewed to ensure that only valid alarms would be sounded and that emergency action by personnel would be required.
This matter will be reviewed by the resident inspector.
(85-07-03).
7.
Trainin and uglification of Contractor HP Technicians The training and qualifications of the contractor HP Technicians was reviewed against criteria contained in:
Technical Specification 6.3 Station Staff gualifications ANSI N18. 1-1971,
"Selection and Training of Nuclear Power Plant Personnel" Regulatory Guide 1.8,
"Personnel Selection and Training" Contractor HP Technicians were supplied by NUMANCO and consist of technicians permanently assigned at Ginna supplemented by several temporary technicians to assist with the outage.
The training and qualification resumes of the temporary technicians were reviewed.
Within the scope of this review, no violations were observed.
8.
Maintenance and Calibration of Surve Instruments The maintenance and calibration of survey instruments was reviewed against criteria contained in:
CFR 20.201 Surveys
CFR 20.202 Personnel monitoring Reg Guide 8.6 Standard Test Procedure for Geiger Muller Counters ANSI N323 Radiation Protection Instrumentation Test and Calibration.
.The licensee maintains and calibrates all beta-gamma survey meters on site.
Included in this program are friskers, portal monitors, lapel air samples and low volume air samples.
A collimated millicurie Cs" 'ource
is used for low ranges while an Eberline 1000B calibrator is used for high ranges.
Cloth silhouettes of hands and feet with uniformly distributed fixed contamination of known quantity are used for frisker response checks.
Recordkeeping is adequate.
Within the scope of this review no violations were identified.
9.
Exit Interview The inspector met with the licensee personnel denoted in Section 1.0 on March 29, 1985, to discuss the scope and findings of this inspection.
At no time during this inspection was written material provided to the licensee by the inspector.