IR 05000263/1977017
| ML20024G533 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/11/1977 |
| From: | Fisher W, Miller D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G529 | List: |
| References | |
| 50-263-77-17, NUDOCS 9102120618 | |
| Download: ML20024G533 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-263/77-17 Docket No. 50-263 License No. DPR-22 Licensee:
Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name: Monticello Nuclear Generating Plant
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Inspection at: Monticello Site, Monticello, MN Inspection conducted:
September 27-29, 1977 Inspectors:
D. E. Miller d/'fM-
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W. L. Fisher Mn
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Approved by:
W. L. Fisher, Chief
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Fuel Facility Projects and Radiation Support Section Inspection Summary Inspection on September 27-29, 1977 (Report No. 50-263/77-17)
Areas Inspected:
Routine, unannounced inspection of operational radiation protection program during refueling and major maintenance, including:
qualifications; training; planning and preparation; exposure control; posting, labeling, and control; surveys; previous items of noncompliance; and previous commitments. The inspection involved 38 inspector-hours on site by two NRC inspectors.
Results:
No items of noncompliance or deviations were identified.
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9102120618 771012 PDR ADOC'A 05000263 o
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DETAILS 1.
Persons Contacted
- L.
Eliason, Plant Manager
- M. Clarity, Plant EngineerinC and Radiation Protection Superintendent
- F. Fey, Radiation Protection Engineer L. Nolan, Engineer R. Jacobson, Chemist J. Windschill, Health Physicist P. Yurezyk, Radiation Protection Coordinator
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J. Peterson, Chemistry Coordinator G. Fbthiasen, Radiation Protection Specialist i
The inspectors also contacted three other radiation protection specialists during the course of the inspection.
- denotes those prssent at the exit inte rview.
2.
General This inspection, which began with visual observation of work in progress on the refueling floor at 12:30 p.m. on September 27, 1977, was conducted to examine the radiation protection aspects of the current refueling and major maintenance outage, previous (
items of noncompliance, and previous commitments made by the licensee.
No significant abnormalities were noted during the visual observa-tions.
3.
Or31 ization John Windschill, a recent masters degree graduate in ra iological d
health, has been hired as a " Health Physicist." The remainder of the radiation protection complement is as previously reported (50-263/7i-10).
The licensee has contracted about twenty additional radiation protection technicians for the duration of the refueling and maintenance outage.
4.
Licensee Action on Previous Inspection Findings (Closed)
Inf raction (50-263/ 77-10. - Calibration of portable
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dose rate survey instruments at a frequency other than specified (
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by procedure. The inspector reviewed the licensee's response dated July 29, 1977. The corrective actions appear to be adequate.
(Closed) Infraction (50-263/77-05): Reactor Building noble gas effluent monitor not being adequately calibrated quarterly. The inspector reviewed the licensee's response dated May 24, 1977.
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The licensee has replaced the G-M tube noble gas effluent monitor wash a beta scintilation monitor which has a bertor detection i
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sensitivity and can readily be calibrated using plant gases or gas standards. The inspector reviewed the calibration and functional i
test procedures which were revised by the licetsee. The corrective actions appear.to be adequate.
This matter is considered resolved.
5.
Training In compliance with a previous commitment, (50-263/76-07) the licensee has developed a new videotaped orientation training presentation. The inspectors reviewed this presentation, which is shown in about forty minutes. The presentation appears to contain information required by 10 CFR 19.12.
6.
Surveys Records of direct radiation, surface contamination, and airborne contamination surveys conducted during the refueling outage were reviewed. The inspectors discussed with the-licensee his methods I
of identification and control of airborne contamination areas.
No.significant problems were identified.
7.
Bioassays and In Vivo Counting The licensee intends to have an onsite whole body counting system in operation before the refueling and maintenance outage is com-pleted. The bioassay program remains as previously reported (50-263/77-10).
8.
ALARA The licensee appears to be effectively controlling both external and internal exposure. The effectiveness of this ALARA effort is reflected in a 1971-76 average dose rate of 0.073 millirems per megawatt-hour (net electrical) produced, less than half the 1976 average for all BWR's.
Efforts in this regard include:
a.
Hydro-lasing the reactor vessel walls and installing a shielded work platform to reduce exposures during the current feedwater Sparger repair.
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LHydro-lasing and scrubbing the torus before starting instal-lation of relief valve spargers.
Review by the Radiation Protection Supervisor of Radiation c.
Work Permits for work in airborne and high radiation areas to ensure that all practical precautions are taken.
d.
Use of three portable. 4000 cfm HEPA and charcoal filtered air movers to provide local ventilation for work having high contamination potential, e.
,Rse of a computer to maintain daily updated personal exposure racerds, thus providing timely information on which to judge the effectiveness of radiation controls.
Each day this com-puter lists, by employer and TLD number, all monitored per-sons, showing their dose for the week, quarter, and year, and sitowing their remaining authorized quarterly dose.
In addition, the computer prints a list of persons whose dose is witi'.in 100 mrems of their authorized dose. These lists are itsed extensively in work planning. Also, the licensee has contrf.cted with the TLD supplier to have a contract empicyte,and necessary equipment, onsite to process the TLD badges as required to determine unusual or unexpected exposures and to process badges at certain dose estimate bench marks.
I 9.
Respiratory Pretection
' The licensee has not implemented 10 CFR 20.103(c) but expects to do so by December 29, 1977. !!eanwhile, the licensee's res-piratory protection program is following the requirements of Technical Specification 6.5.B and applicable portions of 10 CFR 20.103.
10.
RWp's A review of 40 recent Radiation Work Permits indicated adequate planning and authorization of radiation work.
For work resulting in significant radiation exposure, the dose received by each worker is recorded on the file copy of the RWP, thus allowing after-the-fact evaluation of the effectiveness of exposure controls used during the work.
11.
Airborne Tritium Periodic analyses of reactor coolant, condensate, and other water
samples have shown that the tritium concentration in these (
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liquids is relatively steady at about 4E-2,pC1/ml.
Reactor build-
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ing vent samples during 1977 have shown airborne tritium concen-trations typically on the order of IE-8,pci/ml and occasionally several times that value, well below the HPC of SE-6 pci/ml. Thus, it appears that the concentration of tritium in these liquids, resulting f rom reclamation of liquid vastes, has not caused and will not cause significant in-plant exposure to tritium.
12.
Radiation Pro:ection Procedures Radiation protection procedures, Operations Manual, Volume E,
" Radiation Saf ety," Senerally are appropriately written, maintained, and followed.
Individual procedures have been revised periodically, the most recent revision having occurred in September 1977. Minor revisions are needed in Chapter E.1.2, " Radiation Safety Standards,"
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and Chapter E.1.9, "Of f-site Shipments of Radioactive Materials,"
j in order to ensure coupatibility with applicable regulations.
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addition, the section. of Chapter E.1.5, " Personnel Control and Monitoring," concerning respiratory protection vill need revision by December 29, 1977 in order to ensure compliance with the
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revision of 10 CTR 20.103, which becomes completely effective on that date.
13. Exit Interview The inspectors met with licensee representatives (denoted in
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Paragraph 1) at the conclusion of the inspection on September 29, i
1977.
The following matters were discussed:
The purpose and scope of the inspection and the findings.
a.
b.
Previous items of noncompliance.
(Paragraph 4)
The apparent need for revision of certain radiation protection c.
procedures. The licensee stated that the matter would be reviewed.
(Paragraph 12)
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