ML19289D837
| ML19289D837 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 01/12/1979 |
| From: | Fisher W, Greger L, Peck C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19289D836 | List: |
| References | |
| 79-1308-78-07, 79-1308-78-7, NUDOCS 7903190051 | |
| Download: ML19289D837 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III Report No. 70-1308/78-07 Docket No. 70-1308 License No. SNM-1265 Licensee: General Electric Company 175 Curtner Avenue San Jose, CA 95125 Facility Name: Morris Operation Inspection At: Morris Operation Inspection Conducted: December 4-6 and,ll-12, 1978 g.sl.$..? l+{u-u Inspectors:bD.C. Peck
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,.h?CV P L. R. Greger /)
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Approved By:
W. L. F'isher, Chief
///k/77 Fuel Facility Proj ects and Radiation Support Section Inspection Summarv Inspection on December 4-6 and 11-12, 1978 (Report No. 70-1308/78-07)
Areas Inspected: Routine, unannounced inspection of safety activities, including: organization, facility changes and modifications, internal reviews and audits, safety committees, training, quality assurance main-tenanc<, fuel storage and handling, and surveillance testing; and radiation protection activities, including: surveys, exposure control, posting and labeling, and licensee action on previously identified enforcement items and commitments. The inspection involved 53 inspector-hours on site by two NRC inspectors.
Results: No items of noncompliance or deviations were found in the 13 areas inspected.
790319005l
DETAILS 1.
Persons Contacted (1)(2)E. E. Voiland, Plant Manager (1)(2)K. J. Eger, Senior. Engineer, Licensing and Radiological Saf ety (2)J. P. Kesman, Plant Engineering and Maintenance Manager J. E. McGrath, Plant Safety Supervisor E. S. Serdar, Maintenance Coordinator B. C. Wing, Quality Control Specialist (2)H. R. Strickler, Operations Manager The inspectors also contacted several other cembers of the plant operations and technical staffs.
(1) denotes those present at December 6,1978, exit interview.
(2) denotes those present at December 12, 1978, exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (70-1308/78-04):
Improper posting of a radiation area.
The area has since been properly posted; a thorough review of radiation areas did not disclose any current improper postings.
3.
General The -inspection began at 9:45 a.m. on December 4, 1978. On the first day of the inspection, one of the inspectors made a tour of the control room and auxiliary plant buildings.
The other inspector arrived on December 5, 1978, and both inspectors toured the site, including the fuel storage area and other areas containing radio-active materials.
4.
Organization There have been no significant changes, either in the Merris Operation organization or in the Nuclear Energy Programs Oper-ation at San Jose, of which ibrris Operation is a part.
5.
Fuel Storage and Handling No spent fuel has been received since March, 1978.
There are 1196 fuel assemblies in the basin containing 309.2 metric tons of heavy metal.
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Amendment No. 6 to license SNM-1265 was received, authorizing the receipt and storage cf spent fuel assemblies from the La Cresse Boiling Water Reactor. A new fuel grapple and spacers for use in the storage containers to be used for LACBWR fuel have been fabricated.
No items of noncompliance or deviations were identified.
6.
Facility Changes and Modifications The licensee continues the system of documented review and approval
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of all proposed changes by the Plant Safety Committee.
Detailed safety analyses are required for those changes of safety significance.
All recent changes were reviewed by the inspector.
Principal changes of interest were:
a.
The installation of the system for decontaminating the basin coolers described in Report No. 70-1308/78-05 was completed. Decontamination efforts removed most of the
" red crud" in the tubes, primarily cobalt and cesium.
Some spots of over 100 mR/hr remain, so the area contin-ues as a high radiation fenced area.
The contaminants were transferred to the low activity waste (LAW) vault.
b.
A decontamination system was also devised for contami-nated BWR fuel baskets, used for storage of spent fuel in the IF-300 casks. The system was effective in cleaning two baskets. Personnel exposures during main-tenance and general handling of the baskets may be reduced by use of the system in the future.
c.
The underground steam line from the utility building to the process building developed a leak and was replaced by an overhead pipeline.
7.
Internal Reviews and Audits Audits of various systems and activities are conducted by company representatives from San Jose and by local employees who have no responsibility for the activity being audited. Audits are described in Fuel Recovery Instructions (FRI's) and Morris Operating Instructions (MOI's).
Formal check sheets are used during the audits.
An audit of Operations procedures was conducted in the third quarter rf 1978. Several changes were recommended as a result of the audit.
No items of noncompliance or deviations were identified.
8.
Safety Committ9es The Plant Safety Committee has held regular monthly meetings. Meeting minutes were examined by the inspector.
No items or noncompliance or deviations were identified.
9.
}bintenance The licensee's Special Work Permit (SWP) system was inspected and SWP's completed since the previous inspection in August 1978 were examined. The completed forms contained all necessary information.
The inspector examined the licensee's preventive maintenance system.
Under this system preventive maintenance at regular intervals is performed on safety-related equipment, systems, and instruments.
Card files of the various items are used to record completed main-tenance work and to schedule future maintenance.
No items of noncompliance or deviations were identified.
10.
Surveillance Tests Records of all operability and compliance tests performed on safety-related systems since the last inspection in August 1978 were inspected. Records indicated all tests had been completed on schedule.
No items of noncompliance or deviations were identified.
11.
Training The annual retraining program was in progress at the time of the inspection. Operating technicians, safety technicians, and mainte-nance personnel are required to complete training sessions and accompanying quizzes on operating, utility, instrument, and radia-tion safety systems. Approximately one third of the program for 1978 had been completed.
_4_
According to licensee personnel, the radiological orientation training and retraining programs were modified since the preceding radiation protection inspection in order to better provide the training required by 10 CFR 19.12.
A cursory examination of the licensee's training program did not reveal any discrepancies.
The training program will be reviewed in additicnal detail during a subsequent inspection.
No items of noncompliance or deviations were identified.
12.
Radiological Protection Procedures The licensee had revised the Morris Operation Safety Manual since the preceding radiation protection inspection. The discrep inspection have been adequately resolved.gpcies noted during that No items of noncompliance or deviations were identified.
13.
Instruments and Equipment Remote handling problems encountered with the seven-curie (nominal)
Co-60 instrument calibration source have been resolved. The source, installed in a hot cell in the chemistry laboratory, will be put into service upon completion of procedures for its use.
The licensee continues to use five-micron membrane filters for airborne particulate sampling but now assumes a 90% collection efficiency based upon data contained in ANSI N13.1-1969.
No items of noncompliance or deviations were identified.
14.
External Exposure Control The inspector reviewed the licensee's personal exposure records for the second and third quarters of 1978. In addition to the vendor film badge records, the licensee's thermoluminescent dosimeter and self-reading pencil dosimeter records for the period were selectively reviewed. There were no recorded personal exposures in excess of 1250 mrees per quarter. Monthly personal exposures, averaging slightly over two man-rems during the second and third quarters decreased primarily as a result of a decrease in fuel receipts.
The licensee had completed procedures for calibration and drift checks of self-reading pencil dosimeters but the procedures had not been fully implemented at the time of this inspection.
This item will be reviewed further during a future inspection.
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IE Inspection Report No. 70-1308/78-04, 70-1309/78-01.
The licensee had instituted a revised procedure for determining badging requirements for contractors and visitors since the previcus radiation protection inspection. The licensee now bases the deter-mination of monitoring requirements per 10 CFR 20.202 upon antici-pated exposures. Personal monitoring may also be provided for individuals who do not require monitoring by 10 CFR 20.202.
Termination reports are provided only to those individuals requiring monitoring by 10 CFR 20.202, according to the revised procedure.
No items of noncompliance or deviations were identified.
15.
Internal Exposure Control Results of the most recent whole body counts, conducted during November 1978, had not been received from the vendor. According to licensee personnel, one individual will be recounted to resolve an initial indication of possible exposure to greater than forty NTC-hours, but less than 520 >TC-hours.
The whole body counting results will be reviewed during a future inspection.
The licensee had completed a procedure since the preceding radia-tion protection inspection, specifying evaluative actions to be taken regarding whole body counting and urinalyses results.
The procedure is further implemented in a memorandum from the Licensing and Radiological Safety Engineer. The memorandum defines a codel for correlating the results of whole body counts / bioassays with exposures to airborne concentrations of radioactive materials, in terms of MPC-hours. The inspector disagrees with certain of the techniques described in the memo; in particular, the use of a ten-day effective half-life for elimination of the inhaled insoluble particulates which are swallowed in the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the use of urinary excreta for quantifying internal depositions of insoluble particulates.
This matter was discussed at the exit interview.
Changes to the licensee's respiratory protection program regarding the policy statement and medical screening documentation requirements have resolved discrepagpies identified during the previous radiation protection inspection.i The inspector also reviewed the licensee's actions regarding IE Bulletin 77-07 " Protection Afforded by Airline Respirators and Supplied Air Hoods".
No problems were noted.
No items of noncompliance or deviations were identified.
16.
Posting, Labelin g, and Control While inspecting the licensee's facilities, the inspectors examined radiation caution sign postings, high radiation area access controls,
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2/
Ibid.
radiation work permit usage, and survey postings for conformance to regulatory requirements and the licensee's procedures. No discrep-ancies were identified. High radiation areas existed in the basin demineralizer room and the basin cooler enclosure.
The basin coolers had been cleaned since the previous radiation protection inspection; radiation IcVels were reduced significantly but general radiation Irrels in excess of 100 mR/hr still exist at certain locations.
The documents required to be posted pursuant to 10 CFR 19.11 were posted as required.
No items of noncompliance or deviations were identified.
17.
Survevs The licensee's direct radiation, contamination, and airborne radio-activity survey records for the second and third quarters of 1978 were selectively reviewed.
No discrepancies were identified.
No airborne concentration exceeding one MPC (IE-8pCi/ml) was noted during review of the licensee's survey records.
No items of noncompliance or deviations were identified.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1) at the conclusion of their respective portions of the inspection on December 6 and 12, 1978. The inspectors summarized the scope and findings of the inspection.
In response to certain items discussed by the inspectors, the licensee:
1.
Acknowledged the inspector's comments regarding acceptability of the licensee's method for determining personal monitoring requirements of visitors and contract personnel.
(Paragraph 14) 2.
Stated that implementation of the self-reading pencil dosimeter cali-bration and drift checks would be completed.
(Paragraph 14) 3.
Acknowledged the inspector's disagreement with certain aspects of the licensee's proposed method for evaluating whole body counting and urinalyses results for correlation to airborne exposures to radioactive materials.
(Paragraph 15)
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