IR 05000184/1981001
| ML20037D406 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 06/23/1981 |
| From: | Crocker H, Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20037D404 | List: |
| References | |
| 50-184-81-01, 50-184-81-1, NUDOCS 8107100199 | |
| Download: ML20037D406 (4) | |
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a U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-184/81-01 Occket Nc.
50-184 License No.
TR-5 Priority Category E
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Licensee:
U. S. Department of Commerce National Bureau of Standards Washington D.C.
20234 Facility Name:
NBS Reactor
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Inspection At:
Gaithersburg, Maryland Inspection Conducted:
April 22-23, 1981
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Inspectors:
d, /Mt M/bE3M/
gRoth,~FuelFacilityInspector
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date date Approved by:
6/2EM/
A IL W. CrockeMbief, Fuel Facility
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Projects Section'
Inspection Summary:
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Insoection on April 22-23, 1981 (Report No. 50-184/81-01)
Areas Inspected:
Routine unannounced inspection by a region-based inspector of
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licensee action on previously identified enforcement items; review of operations;
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and, followup on regional of the bulletins.
The in'spection involved 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> onsite by one region based inspector and was initiated on the day shift.
Results:
No items of noncompliance were identified.
Region i Form 12 (Rev. A,*ril 1977)
8107100199 810624 PDR ADOCK 05000184 G
PDR J
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DETAILS 1.
Persons Contacted
- R. S. Carter, Chief, Reactor Radiation Division
- T. M. Raby, Deputy Chief, Reactor Radiation Division / Chief, Reactor Operations J. F. Torrence, Deputy Chief, Reactor Operations J. Arras, Reactor Supervisory Health Physicist
- P. Cassidy, Reactor, Health Physicist
- Denotes those present at the exit interview.
2.
Licensee Action on Previously Identified Enforcement Items (Closed) Inspector Follow Item (184/78-04-06) Review electrical penetration sealant.
The inspector examined a licensee memo dated September 20, 1978 which specified the materials used to reseal the cable and conduit floor per.etrations located in the rear of the reactor control room.
The materials were selected for their proven fire resistant qualities and ease of application into unusual configurations.
The inspector examined the sealed floor penetrations and there appeared to be no inadequacies.
Licensee action has been completed on this item.
(Closed) Inspector Follow Item (184/78-05-01) Ensure that the Hazards Evaluation Committee (HEC) reviewed pen and ink changes to operational procedures. The inspector determined that the pen and ink changes made to procedures during the time period March 1976 through November 1978 were reviewed and approved by the facility Hazards Evaluation Committee between December 1978 and April,1979. According to licensee representa-
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tives no additional minor changes have been made to procedures which had not been reviewed and approved by the HEC since April 1979.
Licensee actions have been completed on this item.
(0 pen) Inspector Follow Item (184/79-01-01) Coordination of offsite l
actions / action levels with the Maryland Divison of Radiation Control.
The inspector determine that the licensee had rewritten the facility emergency plan to reflect the requirements of 10 CFR 50 Appendix E, Regulatory Guide 2.6 and ANSI standard 15-16.
This emergency plan is due to be submitted to NRC-NRR by November 3, 1981.
The licensee is currently implementing the facility emergency plan previously cpproved by NRC-NRR.
The new plan will be implemented upon approval by NRC-NRR. Action levels in the new plan have been reduced to below 10 CFR Part 100 levels and are based on a maximum exposure level of 5 rem. According to licensee represent-atives, the licensee has established liaison with the Montogmery County Maryland Civil Defense unit.
This unit will then inform and coordinate with the appropriate state agencies.
The licensee has also established contact with the Maryland Division of Radiation Control although no l
formal contact agreement has been established.
If required by NRC-NRR, j
direct contact with the State of Maryland will be incorporated into the new plan.
Licensee actions will not been completed on this item until i
the new emergency plan has been submitted to and accepted by NRC-NRR and then implemented by the licensee.
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(Closed) Inspector Follow Item (184/78-04-03) Licensee control of algae and correction of spent fuel storage pool protective coating deterioration.
The inspector examined the spent fuel storage pool and noted that the walls were covered with a thin coating of yellow / green algae from the top down about halfway.
The coating did not appear severe.
Licensee represent-atives stated that a thin coating of algae could be tolerated and that an algae control program would be initiated if deemed necessary.
The inspector also noted that tha paint on the north pool wall at the east and we3t ends was peeling away in small areas.
Licensee representatives states that since inspection 50-184/78-04 this situation was being watched carefully.
However, since the water in the pool was high purity, no problems have been identified because of this peeling paint.
The licensee is continuing to observe both these conditions and has stated that corrective actions will be immediately taken if any problems are observed.
(Closed) Infraction (184/79-05-01) Failure to survey in order to comply with 10 CFR 20.203(e)(1) posting requirenents and 10 CFR 20.301 " Waste x
Disposal" resulting in the inadvertent release of 2 millicuries Co-60 to the environs.
The inspector verified that the licensee initiated the conduct of a documented monthly radiation survey of the facility perimeter outside the restricted area fence.
In addition, the licensee conducts a documented monthly radiation survey of the facility shipping / receiving / holding The inspector examined a tickler file card which documented the area.
dates of these radiation surveys for the time period March 1980 through March 1981.
The licensee also checks the reactor secondary coolant for tritium whenever a helium blowdown of the secondary coolant system is performed.
Secondary coolant water samples are taken for analysis by health physics personnel or by reactor operators if health physics personnel are not present or available at the time that helium blowdown is performed.
Corrective actions have been completed on this item of noncompliance.
(Closed) Infraction (184/79-05-02) Failed to maintain procedures adequate to prevent an undetected inadvertent release of 2 millicuries Co-60 to the environs.
The inspector reviewed the following health physics procedures:
HP-2.7 " Contamination Control" dated July 15, 1976 Hp-3.1 " Radiation Surveys" dated July 15, 1976 Hp-3.2 " Smear Sampling and Counting" dated July 15, 1976
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These procedures were determined to cover radioactive material control, posting and surveillance requirements.
The facility radiation surveys discussed above were established to implement the requirements of these procedures.
The inspector verified that the licensee had conducted health physics staff training sessions to assure that these procedures were understood and th.', they would be carefully and implicitly followed.
Corrective actions have been completed on this item of noncompliance.
However, it was noted that the licensee was in the process of revising these and other health physics department procedures to incorporate action levels and to define the type of actions to be taken when and if these action levels are exceeded.
(81-01-01)
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3.
Review of Operations The inspector examined all areas of the facility to observe operations and activities in progress, to become acquainted with the facility and to examine the general state of cleanliness and housekeeping.
No items of noncompliance were identified.
4.
Fellowup on Regional Office Bulletins a.
IE Bulletin 78-07 Tiie inspector determined through discussions with licensee representa-tions and review; of licensee records that IE Bulletin 78-07, dated June 12, 1978, " Protection Afforded by Air-Line Respirators and Supplied-Air Hoods" had been received and reviewed for applicability.
In the licensee's response dated August 4, 1978, it was stated that the facility safety pregram does not include the use of air-line supplied respirators in the demand mode or supplied-air hoods.
Thereiure, no actions in connection with this IE Bulletin were considered necessary.
No items of noncompliance were identified, t.
IE Bulletin 78-08 The inspector determinec< through discussions with licensee representa-tives and review of ficer.see records that IE Bulletin 78-08, dated June 12, 1978, " Radiation Levels from Fuel Element Transfer Tubes" had been received and reviewed for applicability.
In the licensee's reponse dated August 4, 1978,.it was stated that a review of the facility shielding design in the plant areas adjacant to the fuel transfer tube did not identify any potential for radiation streaming from shielded spaces surrounding the fuel transfer tube.
The license has established and continues to maintain positive control of access into potential high radiation r eas where a portion of the fuel tranfer tube is accessible in an unshielded condition.
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These areas are conspicuously posted in accordance with 10 CFR 20.203(c).
No items of noncompliance were identified.
5.
Exit Interview
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The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection at 9:15 a.m. on April 23, 1981.
The inspector summarized the scope and findings of the inspection and stated that no items of noncompliance were identified.
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