ML20237K106
| ML20237K106 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/24/1987 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 4410-87-L-0126, 4410-87-L-126, IEIN-87-025, IEIN-87-25, NUDOCS 8709040195 | |
| Download: ML20237K106 (5) | |
Text
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GPlj Nuclear Corporation ye Nuclear
- ,ome:r8o i
s Middletown, Pennsylvania 17CS7 0191 717 944 7621 TELEX 84 2386 i
Writer's Direct Dial Nurnber:
(717) 948-8461 1
l 4410-87-L-0126
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Document ID 0213P
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1 August 24, 1987 W. T. Russell - Pagional Administrator Region 1 US Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 I
Dear Mr. Russell:
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Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 i
Docket No. 50-320 i
4 Inspection Report 87-04 Inspection Report 87-D4 dated July 27, 1987, identified two (2) items of non-compliance.
Attacned are the CPU Nuclear responses to those 'tems.
Sincerely, j
1
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)
F. R. Standerfer
.p Director, TMI-2 FRS/C,JD/eml l
Attachment cc: Director, TMI-2 Cleanup Project Directorate - Dr. W. D. Travers i
l 8709040195 B70824 DR ADOCK 0500 0
GPil Nuclear Corporation is a subsidiary of the General Public Utilities Corporation k\\
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s ATTACHMENT 4410-87-L-0126 i
NOTICE OF VIOLATION Technical Specification 6.8.).a states in part: " Written procedures shall...be implemented covering...the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978..."
Specific activities referenced in Regulatory Guide 1.33 include equipment control (e.g., locking and tagging).
1 Procedure 4000-ACM-3020.04, " Switching and Tagging Safety," Revision No. 4-00, paragraph 4.1 states..."Personne; who are to perform tasks on TMI-2 facilities shall be required to first have the equipment taken out-of-service and put in a safe mode."
Contrary to the above, a slurry pump,, DWC-P-108, was inadvertently operated from 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> on May 24, 1987, to 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on May 25, 1987, causing a spill of approximately 200 gallons of contaminated water in the reactor building as a result of personnel failing to take the pump out-of-service and put in a safe mode.
This is a Severity IV violatico (Supplement I).
GPU NUCLEAR RESPONSE As detaileo in Inspection Report 50-320/07-04, personnel failed to correctly take pump DWC-P-108 out-of-service.
Thtt resulted in the inadvertent operation of the pump at a later date, causing a sp 1 of contaminated water in the Reactor Building.
As a result of this event, the following corrective actions have been taken.
Immediate Upon discovery of the event, operation of DWC-P-10B was terminated. The pump was correctly taken out-of-service to prevent further pump operation.
,Long-Term As a long-term corrective action, Shift Supervisors / Shift Foremen are reviewing this event with their 0,nerating crews.
In addition, operating crews are also reviewing NRC Information Notice 87-25, "Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events," to heighten their awareness of the importance of attention to detail. Also, Procedure Change Requests (PCRs) have been submitted for procedures 4000-ADM-3020.34, " Switching and Tagging Safety," and 4000-ADM-3020.06, " Status Tagging," The PCRs provide additional clarification for use of safety and status tags.
The above corrective actions will be completed by September 30, 1987. GoU Nuclear believes that the above actions will preclude a similar event from occurring anc that full compliance has been achie'. J. _ _ _ - - _ _ _ _
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l ATTACHMENT l
4410-87-L-0126
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h0TICE OF VIOLATION Technical Specification, Appendix A, Section 6.11 requires that personnel radiation I
l protection be consistent with the requirements of 10 CFR 20 and the NRC-approved l
Radiation Protection Plan.
Section 8 of the Radiation Protection Plan, 1000-PLN-4010.01, Revision 1, dated May 1, 1966, permits equipment to be released for unrestricted use when the removable beta-gamma contamination is less than 1000 disintegrations per minute per 100 square centimeters of surface area (dpm/100 cm2),
Contrary to the above, on June 7,1987, a wood pallet found in an unrestricted area I
had removable beta-gamma contamination of up to 5000 dpm/100 em2, l
This is a Severity Level IV violation (Supplement IV).
GPU NUCLEAR RESPONSE I
As detailed in Inspection Report 50-320/87-04 and also reported in Licensee Event Report (LER) 87-05, a contaminated wood pallet was discovered in a refuse container in an unrestricted area on June 7, 1987, during a routine survey by Radiological Controls personnel.
The root cause of ils event was a less than adequate strvey prior to the transfer of radioactive material from a controlled area to an unrestricted area. Based on 1
the following information, GPU Nuclear has determined that this event occurred during the period of June 5 through June 7, 1987.
o The subject refuse container is surveyed on a daily basis, o
On June 5, 1987, the refuse container was empty.
o On June 6,1987, the daily survey of the refuse container was performed but the contaminated pallet was not identified.
It is possible that the pallet l
was present on this date but that the survey did not detect it, o
On June 7, 1987, the contaminated pallet was discovered during the daily l
survey.
However, the contamination source, the pallet's origin of location, and the method i
of transport from a controlled area to an unrestricted area cannot be detccmined.
l As a result of this event the following corrective actions were taken.
l Immediate Upon the discovery of this event, the remaining material in the refuse container was surveyed and no additional contaminated material w8s fPand. The contaminated pallet was relocated to a radiological control)eet area and surveyed. An Incident / Event Report was issued and a critique of this event was ccnducted on June 8, 1987. The pallet was disposed of as radiological waste.
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-ATTACHMENT 4410-87-L-0126 Long-Term As a result of previous similar events, GPU Nuclear took positive actions to strengthen the controls for transfer of radioactive materials. For example, procedural requirements for the transfer of radioactive material had been improved, additional radiological postings were erected, and General Employee Training was revised.
However, this event highlights the need for additional i
corrective actions.
Accordingly, as a. result of this event, the following I
additional actions are being taken:
o A survey of areas outside Radiological Controlled Areas and adjacent to craft shops and laydown areas was performed.
This survey was in addition to the regular annual surveys and the special surveys conducted for identification of contaminated lead prior to its sale as scrap.
The survey idontified several items in excess of the current TMI-2 release limits. However, af ter investigating, it was determined that the items had been released prior to the current release limits in accordance with q
the then current less restrictive release limits.
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Radioactive Material Storage Areas have been identified and are being consolidated.
A list of radioactive material storage areas has been generated and a priority has been assigned to the areas to determine the order in which areas should be closed.
This will be an ongoing activity for the remainder of the cleanup project.
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o Vehicle surveys are being conducted after transfer of radioactive materials from the vehicle, o
Radiological Controls is evaluating a proposed practice of surveying all material prior to release from a Radiological Controlled Area. For most hand carried items from the Auxiliary and Fuel Handling Buildings, the I
survey would be accomplished at the Health Physics lab area. For larger l
items and other locations, the survey would be accomplished at the. job j{
site by the Radiological Controls Technician covering the work.
This evaluation is expected to be completed by September 30, 1987.
j CPU Nuclear believes that thse actions will preclude a similar event from occurring and that full compliance has been achieved, i
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