IR 05000341/1991006
| ML20029B561 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/04/1991 |
| From: | Januska A, Paul R, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20029B559 | List: |
| References | |
| 50-341-91-06, 50-341-91-6, NUDOCS 9103130005 | |
| Download: ML20029B561 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION 111
- Report No. 50-341/91006(0RSS)
License No. NPF-43 Docket ;1c. 50-341 L.icensee: The Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166-Facility Name:
Fermi 2 Inspection At:
Fermi Site, Newport, Michigan Inspection Conducted:
bruary 7-15, 1991
T.
c Inspectors:
R.
A'. Paul
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Date
. am ho A. G. Januska
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Db Approved Py:
M. C. Schumacher, Chief k/
Radiological Controls Date '
and Chemistry Section Inspection Summary
- Inspection on February 7-lb 1991 (Report No. 50-341/91006(DRSS))
XFeas Inspected:
Routine unannounced inspection of the licensee's liquid and gaseous radwaste program, and the radiation protectior, program:
inclu_ ding organization and management controls (IP 83750); training and qualifications (IP 83750,84750); audits and appraisals (IP_83750, 84750); effluent reports (IP 84750); effluent control instrumentation (IP 84750); primary coolant radiochemistry (IP 84750); external and internal exposure controls (IP 83750); radiological controls (IP 83750); plant tours, and license actions on previous inspection findings (92701).
Results: The organizational structure, management controls, staffing levels, j-aifd management support for the radiation protection, and liquid and gaseous
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radwaste programs appeared good. The licensee continues to have stro.ng ALARA, audit problem identification, contamination and radiological control programs.
Station dose and personal contamination events were low for 1990.
Problems were identified concerning the reporting of T/S effluent information, and HRA door controls.
9103130005 910305
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PDR ADOCK 0S000341
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DETAILS 1.
Persons Contacted-R. Andersen, Radiation Protection Manager
- S.lCatola, Vice President, Nuclear Engineering and Services
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R.-Baum, Supervisor, Radiological Engineering
- D. Delis, Acting Supervisor, Quality Program Asn. ance
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i R. DeLong, General Supervisor, Radiation Protection
- D. Gipson, Assistant Vice President and Manager Nuclear Production
- L. Goodman, Director, Nuclear Licensing
- J. Heins, Radiological Assessor
- A. Inks,-- Quality Assurance Specialist
- W. Lipton, Senior Engineer
- G. MacAuam, Radiation Protection Supervisor
- R. McKeon, Plant Manager
- W. Miller, Director, Nuclear Quality Assurance
- J. Pendergast, Compliance Engineer
- P. Rashad, Senior Nuclear Engineer
- H. Tate, Radiation Engineer-
- T. VanderMey, Radiation Engineer
- S. Staseck,LNRC Resident Inspector The inspectors also contacted other licensee employees.
- Denotes'those present at the onsite exit meeting on-February 15, 1991.
2.
General This inspection was conducted to review the licensee's liquid and gaseous radwaste and radiation protection programs.
The inspectors
-. toured _the __ licensee's facility to observe posting, labeling and access control.
No significant problems were identified.
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LicenseActiononPreviousInspectionFindings(IP92701}
.(0 pen) Open Item (341/89029-01): Evaluation to determine-the need for-
-imposition of more stringent. controls during the Crud Induced Localized
. Corrosion (CILC)-fuel rod inspection evolution.
This matter is still under review.
Licensee representatives stated that additional controls would be imposed if-the job is performed.
1(0 pen)OpenItem(341/89014-01): Contamination control program for.
valve leak-off. The-licensee will-implement planned improvements during the forthcoming' outage.
(Closed).Open Item (3_41/89014-02):
Replacement of the reactor building first floor overhead equipment drain line to reduce radiation fields.
Approval-for the line replacement has been given and is currently scheduled sometime af ter the plant's second refueling outage (RF02) in
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1991.
Shielding and other measures taken to reduce radiation fields in the reactor building from the line have reduced the priority for replacing the line during RF02.
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-(Closed)L0penitem(341/90018-01):
Results of a study (evaluation)
to' determine shielding 3f fectiveness of-safety eye glasses for beta radiation.
The evaluation was reviewed by the inspectors who agreed with the licensee's-conclusion that safety glasses are sufficient for use to meet NRC Form 5 criteria shielding requirements for the eye,
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(Closed) Violation ~(341/90018-06):
Failure to perform an evaluation of a shipment of radioactive waste, which included neutron producing material, to ensure compliance with 10 CFR 20.101 requirements. The inspectors verified the licensee's corrective actions to prevent recurrence were implemented as described in a letter to the NRC dated December 28, 1990.
(Closed) Violation (341/90018-07): A package of radioactive waste was
transferred to a waste bariel site which exceeded 49 CFR 173.441(b)(1)
limits. The inspectors verified the licensee's corrective actions to prevent recurrence were implemented as described in a letter to the NRC dated December 28, 1990.
4._
Changes (IP183750, 84750)
The overall administration of the liquid and gaseous radwaste programs continue to be the. responsibility of.the RPM who reports directly to the Station Manager.
Direct implementation of these progiams is the responsibility of the Supervisor-Radiation Effluents, who is supported by several staff members responsible for the process and effluent
- monitoring systems, effluent reports and tracking of off site doses.
The overall responsibility for the process monitoring and effluent systems is shared with radiation protection.
Calibration and related surveillances for effluent monitoring and control instruments are the responsibility of the radiological effluent department.
- Since the previous irispectior, (Inspection Report No. 90021), a
- professional health physicist (Certified) has terminated employment.
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This is the second professional health physicist (HP) the staff has lost in 1990. At the time of the inspection one of these HP positions
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had'been filled with an experienced HP and the licensee is in the process of finding ancther. Although the loss of these HPs has had an effect on the experience level of the professional staff for this specific plant, the staff is still comprised of a sufficient number
- of11Ps, and remains generally stable with good support from upper management, and communications and support from other department heads.
.No violations or deviations were identified.
5.
T*aining and Qualifications (IP 83750)
The inspectors reviewed the licensee's methods of selecting contract
- radiation protection technicians (RPTs) ~for the Spring 1991 refueling-outage and'their radiation protection contractor qualification program.
Licensee representatives review * sumes of contractor RPTs to determine if the station's selection criteria are met and selectively verify the accuracy of the resume.
The licensee cualification course is
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approximately 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and instructs the RPTs in site-specific radiological procedures, equipment and techniques which requirements.
Several written examinations are given which the RPTs are required to pass. The content.of-the qualification program appeared good.
No violations or deviations were identified.
6.
HighRadiationArea('HRA) Controls (IP83750)
Although-the licensee's overall program for controlling HRAs is
generally good, there.were several Deviation Event Reports (DERs)
written in 1990 identifying violations of Technical Specification and Non-Technical Specification HRA controls.
A ncn-cited violation was issued (Inspection Report 341/90013) for failure to control a Technical Specification HRA door. Since then, the licensee had written a DER for failure to control a Non-Technical Specification door.
In reviewing this mutter the inspectors noted that the licensee's-investigation, followup, and proposed corrective measures to prevent recurrence of HRA control pr'oblems appear to be adequate; however, completion of these measures was delayed by. difficulty in obtaining
. appropriate door locks. This matter has been discussed with the licensee and will be reviewed further during a future inspection.
(0penitem 341/91006-01)
No violations or deviations were identified.
.7.
Internal Exposure Control (IP_83750)
. Selected aspects of-the licensee's respiratory program were reviewed.
Workers' authorization information, proof of required training, and
. expiration date-are required. Provisions are made during the issuance and return cycle for MPC accountability and'it appeared that sufficient
'3 attention is given to respirator inspection, storage, and-maintenance.
Inspector observations of workers wearing respirators in the field indicated adherence to the radiation protection technician's instructions and procedural requirements.
However, on three occasions during piant-tours used respirators were observed lying on the' floor inside the Step-OffPad(SOP)insteadofdesignatedcontainers.
This matter was discussed with the General Supervisor Radiation Protection. - Overall, the general scope of the licensee's respiratory-program appears-satisfactory.
No violations or deviations were identified.
8.
Control _of Radioactive Materials and Contaminination _(IP 83750)
The licensee's general contamination control program is described in Inspection Report No. 341/88009. Since then, the primary RCA control-point has been-upgraded to provide better health physics control over
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entry and exit from the RCA.- The licensee still provides sufficient facilities to perform equipment and personnel decontamination and for work on contaminated material and equipment. Several of these facilities lwere visited during this inspection, and one of which that had work in progress appeared to provide adequate contamination control measures as designed.
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The licensee's program for identifying, evaluating dose, and reporting personal contamination and hot particle events appears to be accomplished in-accordance with procedural requirements.
The methodology to assess skin dose from hot particles and skin contamination had been previously reviewed by the inspectors and found appropriate; no significant changes have been made. There were about 53 personal hot particle and skin contamination events in 1990, most involved low level radioactivity.
Tours ai 'he station indicated housekeeping was adequate and the plant generali; clean.
However, it was noted that a significant number of tools with fixed contamination (identified by purple color) were lying about the reactor buildig both inside and outside of SOPS. Although this practice is allowed inside the RCA, the inspectors expressed concern that if significant numbers of tools are spread around the RCA, worker attitude problems concerning proper tool use and return policies could develop and lead to tool control problems the licensee has-experienced in the past, which in one case led to a violation of regulatory requirements. This matter was discussed with licensee management.
No violations or deviations were identified.
PrimarL oolant Radiochemistry f lP 84750]
9.
C Technical. Specification (T/S) 3.4.8 requires that the specific activity of the primary coolant not exceed 0.2 microcuries per gram of dose equivalent 1-131-(del-131) except under certain limiting conditions of operation. The inspectors selectively reviewed the licensee's primary coolant radiochemistry results for 1990 to determine compliance with the T/S requirement for the del-131 concentration. The review,.and discussion with licensee personnel indicated that the del-131 concentrations for the-primary system were much lower than the applicable T/5 limit during the review period and also that no other T/S required chemical analyses had been missed.
No violations or deviations were identified.
10.
Liquid Radioactive Wastes (lP 84750)
The inspectors reviewed the licensee's liquid radioactive waste (radwaste)
ef fluent -program including:
procedures for calibration, discharge batch releases and the Semiannual Radiological Effluent Release Reports for the second half of 1989 and the first half of 1990. The program is the same as described in Inspection Report 50-341/89023(DRSS).
All radioactive-liquid effluents 'are evaluated by analyses of-samples and
. batch eleased, diluted and discharged into Lake Erie.
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The licensee reported 39 lake discharge batch releases in the second half of 1989 and-12 in the first half of 1990.
A total of 13f; millicuries and 219 millicuries respectively excluding tritium, gases and alpha were reported for batch releases. The licensee is striving to become a zero release plant by the use of water effective management.
The inspectors examined selected batch release packages which include analytical results and maximum potential dose to nembers of the public.
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The packages were completed in accordance with the appropriate procedure.
The inspectors verified the personnel dose recorded in two release packages for two nuclides using the Offsite Dose Calculational Manual (0DCM) methodology.
No problems were r.oted in this area.
No changes in the ODCM or the Process Control Program were reported and no abnormal releases occurred during these periods.
No violations ur deviations were identified.
11. Gaseous Radioactive Wastes (IP 84750)
The inspectors reviewed selected portions of the licensee's gaseous radwaste program including instrument calibration, release cuantifica-tion, and Semiannual Radioactive Effluent Release Reports for the last half of 1989 and the first half of 1990.
The prcgram is the same as described in Inspection Report 50-341/89023(DRSS). Airborne effluent samples are collected from each of the seven plant monitors.
Venting or purging of the primary containment atmosphere are quantified as batch releases.
In addition, the licensee now samples the Offgas Vent Pipe for fission and activation gases and compares the results to those from the reactor building SPlHG and reports the most conservative results.- This is a change which resulted from an observation made in a previous NRC inspection.
It has resulted in more accurate reporting of dose. The licensee revised the Effluent Report for July 1,1988, through December 31, 1988 to reflect this change. The reported site boundary dose increased significantly as a result of these changes but still was below one millirad per year.
No violations or deviations were identified.
12. Calibrations and Functional Tests of Gaseous and Liquid Effl.nt flonitors, AHi RiBiation Monitors, and Porta 5WRonitors TTP M750)
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The inspectors selectively reviewed calibration test records for liquid and gaseous effluent radwaste monitors, area monitors (ARMS) and portable radiation monitors. The calibrations were performed using appropriate procedures with all required verifications and data sheets-completed.
The inspectors noted that the Alnor digital dosimeters used by the licensee were one point calibrated at nominally 750 mr/hr.
The inspectors questioned this practice. The licensee stated that this was in accordance with ANSI N323-1978 (Rcdiation Protection
' instrumentation Test and Calibration) Section 4.2.2.3 and with the manufacturers literature. The licensee further stated that linearity is not routinely verified but was evaluated prior to acceptance, and demonstrateo by testing four units at dose rates of 200, 750 and 5000 mr/hr; the measured dose was within 5% of the delivered dose.
No violations or deviations were identified.
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13.
HEPAfilterandCharcoalAbsorberSystem(IP84750]
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The inspectors selectively reviewed records of in-place-testing of HEPA and charcoal filters, inc'uding laboratory analysis for methyl iodine removal efficiency for charcoal absorbers from January 1990, to date.
Tests appeared to be conducted in accordance with Technical Specification requirements, and showed that the surveillance for the ventilation systems had been timely and met test criteria.
No violations or deviations were identified.
14.
Audits and Apprjisals (IP 83750,84750)
The inspectors reviev.ed audit report 90-0127 conducted April 20 through May 16, 1990, by the licensee pursuant to Section 6 of the technical specifications.
The audit covered Radiological Effluents and Radiological Material Transfer and Disposal Program.
The-audit was very thorough, technically sound and performance. based.- Responses were generally thorough; however, the inspectors noted that no correction had been made in response to an observation concerning solid radwaste shipments made in audit report 89-0145 which dealt with a nonconservative error in the second 6 month period of 1988 effluent report. The total curies of activity in spent resins, filter sludges, evaporator bottoms, etc. was erroneously reported as 4.29E00 while the individual nuclides reported on the same page summed to 4.29E02 and that this was determined
"...not a critical mistake..." by.a member of DECO Licensing. The inspectors discussed this with the licensee who stated that the corrected information will be reported in the next issued semiannual effluent rcport. The data erroneously reported has no related dose projection requirement and the licensee acknowledged the inspectors' comments regarding the regulatory requirement for accurate reporting.
No violations or deviations were identified.
15.
Closed LER 90-013-00:
Inadequate Control During Containment Air Grab Sampling Process. The licensee identified a concern about the method of taking primary containment atmospheric grab samples, in that sampling procedures did not contain appropriate administrative controls and could result in an increased risk of a radioactive release f rom containment durina a loss of Coolant Accident (LOCA). The licensee performed a safety analysis of a Deign Basis Accident (DBA) Loss of Coolant Accident (LOCA) occurring while-a sample of the primary containment atmosphere was being collected and concluded that relying on administrative controls using original sample taps for e manual grab sample was not optimal.
The licensee initiated corrective action tc add new sampling taps to the primary containment radiation monitoring skid, downstream of existing automatic isolation valves. The inspectcrs examined the modified skid to. verify this ccrrective action.
No violations of deviations were identified.
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16. Exit Interview The scope and findings of the inspection were discussed with licensee representatives (Section 1) at the conclusion of the inspection on February 15, 1991.
The licensee stated that a correction to the Semiannual Effluent Report will be made (Section 14).
Licensee representatives did not identify any documents or processes re*ciewed during the inspection as proprietary,
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