IR 05000280/1979016
| ML18116A181 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/15/1979 |
| From: | Ewald S, Ewald S, Hosey C, Jenkins G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18116A180 | List: |
| References | |
| 50-280-79-16, 50-281-79-24, NUDOCS 7907230724 | |
| Download: ML18116A181 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos. 50-280/79-16 and 50-281/79-24 Licensee:
Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name:
Surry Power Station License Nos. DPR-32 and DPR-37 near Williamsburg, Virginia Accompanying Personnel:
Approved SUMMARY Inspection on March 27-30, 197 Areas Inspected Chief, FFMS Branch
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Date Signed r/1-;/77 Date Signed This routine unannounced inspection involved 60 inspector-hours on site in the areas of solid radioactive waste, reactor coolant pipe decontamination, radiation protection aspects of the steam generator replacement project, and previously identified item Results Of the 4 areas inspected, no apparent items of noncompliance or deviations were identified.
DETAILS Persons Contacted.
Licensee Employees
- W. L. Stewart, Station Manager
- J. L. Wilson, Superintendent Operations
- J. A. Peebles, Superintendent Technical Services
- R. M. Smith, Health Physics Supervisor
- P. P. Nottingham, IV, SGRP Assistant Supervisor Health Physics
- D. L. Burke Exit Interview The inspection scope and findings were summarized on March 30, 1979 with those persons indicated in Paragraph 1 abov Licensee Action on Previous Inspection Findings Closed (280/78-27-01; 281/78-27-01) Unresolved ite Determination of activity in packaged solid wast An inspector reviewed the licensee's revised procedure for determining curies/package for solid radioactive wast The inspector concluded the new conversion factors are conserva-tive when compared with inspector derived number The Solid Waste is discussed further in paragraph Open (280/79-27-02; 281/79-27-02) Unresolved ite Man-Rem dose commit-ments from resin system Discussions with licensee representatives revealed resin liners for use in the liquid waste treatment system are still being filled inside the Decon Buildin Health Physics represen-tatives stated that, as of April 1, 1979, the resin liners would be filled in a nonrestricted are Closed (281/79-22-16) Unresolved Ite Locked High Radiation Areas in Containmen An interpretation of regulatory requirements by the NRC concluded it is acceptable for the licensee to exercise positive access controls at the containment entrance hatc The inspector had no further question Open (280/79-09-03; 281/79-10-03) Noncomplainc Failure to label contaminated waste drum On March 28, 1979, the inspector observed the
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-2-following items of radioactive material which were not labeled in accordance with 10 CFR 20.203(f):
(1) five filters temporarily stored on the radioactive waste storage pa The highest radiation level on contact with each filter was approximately 1.6 R/h (2) A section of reactor coolant system piping temporarily stored outside Unit 2 equipment hatc The highest radiation level on contact with the outside of the package was 2.5 mr/h These are additional examples of failure to label radio-active containers reported as noncompliance with 10 CFR 20.203(f) in IE Report Nos. 50-280/79-9 and 50-281/79-10 of March 28, 197 It should be noted that the licensee had not formally responded to the item of noncompliance prior to the inspector identifying the additional examples of noncomplianc.
Radioactive and Contaminated Material Control By review of records, observations, and discussions with licensee representatives, the inspector evaluated the licensee's program for radioactive material control, including handling of radioactive material, intra-site transfers, identification, labeling, storage of material and the disposal of radioactive wast Specific comments concerning the program are contained in the paragraphs belo On the evening of March 28, 1979, the inspector surveyed a loaded trailer containing low specific activity radioactive material that the licensee was preparing for shipment to a licensed burial facilit The inspector found an area approximately 6 inches in diameter on the side of the trailer that read 340 mr/hr on contact with the traile A survey performed by the licensee on March 13, 1979, indicated the highest radiation levels on contact with the trailer was 8 mr/h The inspector brought this apparent discrepancy to the attention of a licensee representativ The licensee represen-tative stated the truck would be resurveyed prior to leaving the sit However, on March 29, 1979, a licensee representative informed the inspector that the truck had not been resurveyed prior to leaving the sit CFR 173.393(j) requires, in part, that the radiation levels on the external surface of a closed vehicle which has been consigned for exclusive use must be less than 200 mr/h At the request of the licensee, the operator of the burial ground surveyed the truck upon arriva The highest radiation level reported was 225 mr/h CFR does not require any notification when radiation limits are exceede The inspector selectively reviewed shipping records for radioactive material shipped out between February 9, 1979 and March 28, 1979 and identified the following discrepancies in the shipping paper CFR 172.200 specifies the information which must be included on the shipping papers for hazardous material. The proper shipping name prescribed for the material was not used op the shipping papers as required by 49 CFR 172.10 *
( * The category of label applied to each package was omitted on shipping papers for several shipment The transport index was omitted on shipping papers for one shipmen The material for one shipment was described as "Radioactive Material - Limited Quantities" and exempted from specification packaging, marking and labeling in accordance with 49 CFR 173.39 However, the shipping papers indicated the highest radiation levels on the package was 0.7 mr/hr which exceeded the maximum allowable dose rate of 0.5 mr/hr for limited quantities of radioactive materia A licensee representative stated that the individuals responsible for preparation and review of shipping papers would be reinstructed in the proper preparation of shipping paper This was identified as an open item (280/79-16-02; 281/79-24-02).
During a tour of the sit~ on March 28, 1979, the inspector observed approximately twelve 55-gallon drums of industrial oil stored on the same outdoor pad as radioactive materia The concrete slab below the drum storage rack was covered with oi A licensee representative stated that smoking was per-mitted in the area surrounding the radioactive material storage are The licensee representative stated that drums of oil would be removed from the are Wrappings on some of the radioactive material in the outside storage area were torn and some of the covers had been partially remove The inspector stated that this situation would increase the potential for rain water to seep into the package and for radioactivity to leak out to the surrounding are A licensee representative stated that the storage of radioactive material would be reviewe The inspector identified this as an open item (280/79-16-03; 281/79-24-03).
Decon Building Drain During a tour of the radiation controlled area on March 28, 1979, an inspector took several contamination smears in the area of the roll up equipment door to the Decon buildin One2smear indicated removable activity of approximately 15,000 dpm/lOOcm.
Health Physics represen-tatives were notified and the area was promptly surveyed, posted, and roped of Further investigation by the inspectors and licensee health physics staff revealed contamination around a yard drain near the roll-up doo A sample of dirt and silt from the drain was analyzed indicating activities of approximately 0.001 µci/cc (comprised of Cobalt 58 and 60, Cesium 134 and 137, and Mangenese 54).
Licensee representatives stated
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-4-the source of the activity might be the subsurface drain system which is sampled on a routine basi The inspectors discussed the yard drain system with licensee representatives and determined the drain in question leads straight to the discharge cana Licensee representatives stated they would investigate this item further to identify the source of the activit The inspector stated this item would be reviewed during future i~spections (280/79-16-01; 281/79-24-01). Reactor Coolant Pipe Decontamination An inspector reviewed portions of the ETA addressing decontamination of removed sections of reactor coolant pip Decontamination involves removal of end shield plugs, removal of slag from the pipe, and decontamination using an electropolishing techniqu The removal of shield plugs and slag are carried out in a tent in Unit 2 containment with a special filtered ventillation syste Workers wear supplied air respirators as a precaution against airborne particulate In addition, air samples are taken during grinding and cutting operation An inspector observed the removal of shield plugs on March 28 involving the cutting and grinding of tack welds holding the shield plugs in plac The inspector observed workers removing slag from a section of pipe on March 2 The slag was being removed using a pneumatic grinding dis When the air sample particulate filter was removed, it was found to be radioactive by gamma analysi The inspector was told the filter had surface radiation levels of about 35 mrem/h In addition, the interior of the tent was found to be contaminated in excess of normal level Reactor coolant pipe decon operations were temporarily suspende Some questions as to the validity of the air sample were raised in that the sampler had been placed on the floor and was subject to contamination and the sampler (high volume) ran in excess of one hou Subsequent air samples indicated no significant airborne activit The worker involved was whole body counted and showed no uptake of radioactive material In addition, the radiation work permit was reissued prohibiting the use of grinding equipment for removal of slag.