IR 05000312/1982024
| ML20055A224 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/25/1982 |
| From: | Book H, North H, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20055A222 | List: |
| References | |
| 50-312-82-24, NUDOCS 8207150588 | |
| Download: ML20055A224 (5) | |
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U. S. NUCLEAR FIGUL\\ TORY C0!!41SSION
REGION V
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Report No.
50-312/82-24 Docket No.
50-312 1.icense No.
DPR-54 Safeguards croup Licensee:
Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Facility Name:
Rancho Seco Nuclear Generating Station.
Inspection at:
Clay Station, California Inspection conducted:
June 16-17, 1982 Inspectors:
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H. '5.'Horth, KaolaLlon 3peclat1st
/ ate Signed D
Date Signed Date Signed Approved by:
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fm F. A. Wensla' ski, Chief, Reactor Radiation Sately Date S'igned
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H. E. Book, Chief, Radiological Safety Branch Date Signed
Summary:
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Inspection on June 16-17, 1982 (Report No. 50-312/82-24)
Areas Inspected:
Organization and staffing, personnel monitoring, radiation protection and job coverage, containment tour, and surveys associated with auxiliary feedwater header repair work on steam generators.
The inspection involved 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> onsite by one inspector.
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Results:
In the 6 areas inspected, no items of noncompliance or deviations were identified.
RV Form 219 (2)
8207150588 820625 PDR ADOCK 05000312 G
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DETAILS i
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Persons Contacted
- R. Columbo, Technical Assistant, Nuclear Operations
- R. Miller, Chemistry-Radiation Supervisor (CRS)
- G. Coward, Maintenance Supervisor B. Cowart, Senior Radiation Protection Technician (SRPT), Nuclear Support Services Inc. (NSS)
- S. Crunk, Assistant Nuclear Engineer D.Gardiner,SeniorChemistry-RadiationAssistant(SCRA)
- W. Jurkovich, Site Resident Engineer, Generation Engineering
- F. Kellie, Assistant Chemistry-Radiation Supervisor (ACRS)
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- J. Reese, Health Physicist
- S. Rutter, QA Engineer
- D. Whitney, Engineering and Q.C. Supervisor l
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W. Wilson, SCRA
- Denotes attendance at the exit interview on June 17, 1982.
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2.
Inspection Scope Radiation protection as related to major modifications of the Once l
Through Steam Generator (OTSG) auxiliary feedwater header was examined.
l Additional tasks in progress in containment including conduit and
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cable tray installation, OTSG eddy current testing and welding of supports for the reactor coolant pump oil drain system were observed during the inspection.
I No items of noncompliance or deviations were identified.
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3.
Organization and Staffing Inspection Report No. 50-312/82-10 (March 22-26, 1982) included a review of staffing. Reductions in staffing include the loss of one Chemistry-Radiation Assistant (CRA) and one Craf t Helper. Additions to the staff include two CRAs. Four additional CRA's have been employed and will be reporting shortly, bringing the CRA staff to a total of 19. The licensee stated that all newly hired CRAs are ANSI-3.1 qualified.
CRA qualifications will be examined during a subsequent inspection (82-24-01). Selection of additional reaft Helpers to raise the complement
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to eight or nine, is in progress. The licensee is currently interviewing candidates for the position of nuclear chemist.
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In support of the current work in progress the staff of contract RPT has been raised from six to twenty-three including four junior technicians.
Senior technicians require 6000 hours0.0694 days <br />1.667 hours <br />0.00992 weeks <br />0.00228 months <br /> of experience and previous employment as a senior at Rancho Seco or another power plant. A passing grade on an examination is required for technicians who upgrade to senior status at Rancho Seco. Qualifications of contract technicians were examined by the SCRA-Radiation Protection.
No items of noncompliance or deviations were identified.
4.
Personnel Monitoring The licensee is using Landauer film badges and finger rings for measuring exposures for the record. Early in the work on the steam generators a failure of the onsite TLD reader presented problems in personnel whole body and extremity job monitoring which the licensee overcame by using pocket ionization chambers and film badges. At the time of the inspection, job monitoring was based on inhouse TLDs. A daily summary of individual whole body exposures by work group is provided for guidance to the supervisory staff.
In addition, a list of RWP's and cumulative exposures to date is also prepared. These sumaries are available at the morning meeting. Special monitoring, head, extremity etc., records are maintained as written records. The highest extremity exposures have been associated with removing debris from thi secondary side of the OTSG following hole drilling. Approximately 15 rem to the hands was accumulated in this activity. The total extremity exposure was approximately 34 rem for all work during this outage to date.
One person rem whole body was accumulated during the cleanout activities.
The maximum individual extremity exposure was 4.995 rem. To aid in dose distribution, nonradiation worker SMUD volunteers carried out the cleanup activities.
Additional tasks, drilling holes in
"A" and "B" 0TSG's, conduit and cable tray installation in containment and conduit installation in the "D" rings, each contributed approximately 10 person rem to the total whole body exposure. To the date of the inspection, the 1982 site whole body exposure total is approximately 250 person rem.
Selected personnel files were examined. Based on the examination it was found that completed forms NRC-4 and -5 and administrative approvals for increased exposure were included.
No items of noncompliance or deviations were identified.
5.
Radiation Protection and Job Coverage The major portion of the inspection was devoted to observation of work in progress and touring containment. During hole drilling in the "B" 0TSG a sheet of plastic foam (approximately 10" x 15" x 1")
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-3-used as a chip catcher inside the OTSG was dropped. The recovery was made using hand holes 180 apart at the level of the plate separating the steam and feed water annuluses. The recovery was effected promptly with good attention to radiation protection by the assigned technician.
In addition, welding of supports for the reactor coolant pump oil drain system was in progress in the same area. A radiation protection technician was monitoring that specific task. Air samplers were in use and the welder used a respirator. Respirator control included a plastic packaged respirator not opened until required and positive-negative pressure test after donning.
The licensee reported that the initial hole drilling operation on
"B" 0TSG required approximately 2 weeks. The experience gained pe mitted the "A" 0TSG to be drilled in about 3 days. The holes in the OTSG were sources of streaming radiation up to about 400 mrem /hr. The licensee fabricated metal enclosed high density concrete plugs to use on the penetrations which reduced the dose rate to about 5 mrem /hr.
Welder qualification and technique development using mock ups was effective in reducing exposure.
In order to stabilize the existing auxiliary feedwater header, the pins and support plates require tack welding.
In addition, gusset plates were tack welded in place to provide added strength.
Special techniques were developed and practiced on mock ups using MIG welding equipment. Although four days were scheduled for the completion of the work on "B" 0TSG, the work was completed in approximately two days with a resultant reduction in personnel exposures.
During the inspection, eddy current testing was begun with double
step off pad, tent enclosed, HEPA ventilated upper manway access.
A 200 mrem whole body exposure was received for the initial entry.
Personnel monitoring used considered the principal source of radiation which was beneath the worker. A small reduced pressure enclosure constructed of plastic sheeting using a HEPA filtered vacuum cleaner, was in use for stud cleaning.
The containment tour included all levels and both OTSG's.
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It was noted that because of the high level of work in progress some l
areas appeared cluttered, however, there was no excessive accumulation of waste, no abandoned respiratory protective equipment or protective clothing.
i It was noted that appropriate signs were posted, hot spots identified and barriers established. During the tour and work observation confirmatory surveys were performed using a Keithley ion chamber instrument, model 36100, serial number 11108, NRC 009163 due for calibration 12/7/82.
These surveys confirmed that the licensee's postings were correct and in compliance with regulatory requirements.
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No items of noncompliance or deviations were identified.
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Surveys
Records of surveys for the period 6/11-16/82 were examined. The surveys were performed both as routine and as part of special job coverage.
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The surveys included direct radiation, penetrating and nonpenetrating,
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airborne and contamination.
No items of noncompliance or deviations were identified.
7.
Planning and ALARA Due to an inability to contact the appropriate licensee personnel
the planned review in this area was not conducted. These areas will be reviewed during a subsequent inspection (82-24-02).
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No items of noncompliance or deviations were identified.
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8.
Exit Interview i
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The results of.the inspection were discussed with the licensee r:presentatives
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denoted in paragraph 1.
The licensee was informed that no items of noncompliance or deviations had been identified.
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