IR 05000334/1979001
| ML19282C592 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/07/1979 |
| From: | Crocker H, Thonus L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19282C575 | List: |
| References | |
| 50-334-79-01, 50-334-79-1, NUDOCS 7903300369 | |
| Download: ML19282C592 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-334/79-01 Docket No.
50-334 License No.
OPR-66 Priority Category C
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Licensee:
Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Facility Name:
Beaver Valley Power Station, Unit 1 Inspection at:
Shippingport, Pennsylvania Inspection conducted:
January 8-12, 1979 Inspectors:
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L[f //1 L. H. Thonus, Radiation Specialist date signed date signed Approved byt 2-f g
g g/
H. W. Crocker, Acting Chief, Radiation daYe signed Support Section, FFMS Branch Inspection Summary:
Inspection on January 8-12,1979 (Report No. 50-334/79-01)
Areas Inspected: Routine, unannounced inspection by a regional based inspector of Radioactive Waste Systems and Radiation Protection, including effluent control instrumentation, solid radioactive waste, licensee audit, qualifications of personnel, notifications and reports, surveys, licensee action on circulars, licensee action on previous inspection findings, and facility tours.
Upon arrival, at 5:00 p.m. on January 8,1979, areas where work was being conducted were examined to review radiation safety procedures and rm ctices. The inspection involved 32 inspector-hours onsite by one NRC regional t.
1spector.
Results: Of the nine areas inspected one item of noncompli
. was found in each of two areas (Infraction - shipping radioactive material without a license -
paragraph 3; Deficiency - failure to maintain records - paragraph 9).
Region I Form 12 79033003Mj (Rev. April 77)
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DETAILS 1.
Persons Contacted Principal Licensee Employees
- Mr. D. Arnold, Radcon Foreman
- Mr. G. Beatty, QA Engineer
- Mr. J. Hrivnak, Station QA
- Mr. D. Kochman, Radcon Engineer
- Mr. E. Kurtz, Senior QA Engineer Mr. S. Lacey, Shift Supervisor Mr. V. Linnenbom, Radiochemist Mr. A. Lonnet, Associate Radcon Engineer
- Mr. F. Lipchick, Station OA
- Mr. R. Mafrice, Results Coordinator Mr. E. Schnell, Radcon Foreman Mr. D. Schultz, Shift Supervisor Mr. T. Slavik, Maintenance Engineer Mr. J. Vassello, Training Supervisor
- Mr. J. Wenkhous, Reactor Control Chemist
- Mr. J. Werling, Station Superintendent The inspector also interviewed seven other personnel including health physics technicians, clerks and maintenance personnel.
- denotes those present at the exit interview.
2.
Effluent Control Instrumentation Calibration and Functional Tests Appendix B, Environmental Technical Specification (ETS) 2.4.2.6 requires that all liquid effluent radiation monitors be calibrated at least quarterly by means of a source which has been traceable to a National Bureau of Standards source. Additionally ETS 2.4.2.6 requires that each liquid effluent monitor shall have a functional test monthly and an instrument check daily.
ETS 2.4.4.4 requires that all waste gas effluent monitors be calibrated at least quarterly by means of a known radioactive source which has been traceable to a National Bureau of Standards source.
ETS 2.4.4.4 also requires that each gaseous effluent monitor shall have a functional test at least monthly and instrument check at least daily.
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Quarterly calibrations for the third and fourth quarters of 1978, perfonned using the licensee's " Maintenance Surveillance Procedure MSP 43.07 B1," were reviewed for the following liquid and gaseous waste monitors:
RM-LW-104, " Liquid Waste Monitor"
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RM-LW-116, " Contaminated Drains Monitor"
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RM-VS-101A, " Ventilation Vent Particulate Monitor"
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RM-VS-1018, " Ventilation Vent Gas Monitor"
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RM-VS-107A, " Elevated Release Particulate Monitor"
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RM-VS-1078, " Elevated Release Gas Monitor"
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Monthly functional tests for the above monitors, perfomed using the licensee's procedure " Operating Surveillance Test 1.43.1", were reviewed for the months October thru December 1978.
The inspector examined the monitors at their field locations and observed air flow readings, background radiation levels, and physical arrangement of equipment.
Alarm and Trip Setpoints ETS Tables 2.4-2 and 2.4-3 detail, for liquid and gaseous effluents respectively, what points are required to be monitored, alarmed, and contain automatic isolation functions.
Current alann and trip setpoints were examined for RM-VS-107A, RM-VS-107B and RM-LW-104.
No items of noncompliance were identified.
3.
Solid Radioactive Waste Appendix B, Environmental Technical Specification (ETS) 2.4.5.1 requires that measurements shall be made to determine or estimate the total curie quantity and principal radionuclide composition of all radio-active solid waste shipped offsite. Appendix A, Technical Specification (TS) 6.10.1.g requires that records of radioactive shipments be retained at least five years.
The inspector reviewed records of waste shipments made during the period October thru December 1978 for radionuclide composition and curie content.
10 CFR 71.3, " Requirement for License," requires that no licensee subject to the regulations in this part shall (a) deliver any licensed materials to a carrier for transport or (b) transport licensed n.aterial except as authorized in a general license or specific license issued by the Commission, or as exempted in this par CFR 71.12(b) confers a general license for shipment of licensed material providing that certain conditions are met.
One of these conditions is that the licensee must have a copy of the specific license, certificate of compliance, or other approval authorizing use of the package and all other documents referred to in the license, certificate, or other approval as applicable. A second condition is that the licensee must submit in writing to the Director of Nuclear Material Safety and Safeguards or the Atomic Energy Commission his name and license number, the name and license or certificate number of the person to whom the package approval has been issued, and the package identification number specified in the package approval.
Contrary to 10 CFR 71.3, on October 27, 1978, the licensee delivered licensed material to a carrier for transport and did not have a specific license for such delivery.
In addition, he did not ful-fill the requirements for a general license in that he did not have a copy of the documents called for in the certificate of compliance (several drawings) nor did he provide the required information to the Director of Nuclear Material Safety and Safeguards.
This shipment consisted of a cask of spent resin containing 188 Ci of CoSS Co60 54 and Nb95 The cask was an Atcor model LL-50-100, certificate'
Mn of compliance number 6601; the licensee possessed a copy of the certificate. The inspector determined that this shipment did not qualify for an exemption from 10 CFR 71 requirements. The inspector noted that the above constituted noncompliance with 10 CFR 71.3.
(334/79-01-01)
4.
Licensee Audit The inspector reviewed the following licensee audits which examined the area of radiation protection:
Audit Number Audit Group Dates BV-1-78-1 Quality Assurance February 22-24, 1978 ORC-78-8.0-E Offsite Review Committee September 12-13, 1978 BV-1-78-ll Quality Assurance June 5-8, 1978 BV-1-78-20 Quality Assurance September 18-20, 1978 BV-1-78-23 Quality Assurance November 16-21,1978 The licensee's responses to the audits, corrective actions taken and re-audits were also examined.
No items of noncompliance were identifie.
Qualifications of Personnel Technical Specification (TS) 6.3.1 endorses ANSI N18.1-1971 regarding qualifications of the facility staff.
The inspector reviewed the qualifications of six licensee and eight contractor radiation pro-tection technicians against the above criteria.
No items of noncompliance were identified.
6.
Notifications and Reports The inspector examined the records of the licensee's notifications and reports for compliance with 10 CFR 20.405 and 10 CFR 20.408 and 10 CFR 20.409.
No overexposures, excess levels, or concentrations had occurred which would have required reporting in accordance with 10 CFR 20.405.
The inspector examined termination reports of twenty individuals who had terminated in 1978.
Exposure infonnation on Fonn NRC-5 was compared to that contained on the termination reports for six of the individuals.
No items of noncompliance were identified.
7.
Surveys Appendix 4 " Frequency of Airborne, Radiation and Contamination Surveys" of the Radiological Control Manual details the licensee's scheduled survey program.
The inspector examined monthly radiation and con-tamination surveys taken on the 722 ft. and 735 ft. elevations of the primary auxiliary building during the period October thru December 1978.
10 CFR 20.201 requires that the licensee make or cause to be made such surveys as may be necessary to comply with the regulations in 10 CFR Part 20.
The inspector examined licensee surveys taken in support of the repair of two charging pumps under radiation work permits 5010, 5018, 5020, 5032, and 5035.
Independent measurements were made to verify selected recent licensee surveys.
No items of noncompliance were identified.
8.
Licensee Action on IE Circulars The inspector examined the licensee's preventive and corrective actions taken in response to IE Circulars 76-03 and 78-0 :
Corrective actions to minimize radiation exposures in reactor cavities.
Licensee action including review of plant areas, surveys, access control modifications, and specific training re-garding Circular 76-03 were examined.
Further review of high radiation area control will be followed via item (334/78-22-01).
The inspector had no further questions in this area.
78-03:
Packaging greater than Type A quantities of low specific activity radioactive material for transport.
The licensee changed his radioactive material shipment procedure to flag shipments of greater than Type A quantities of radioactive material. Such ship-ments are then given management attention and handled on a case by case basis.
The licensee has not submitted a quality assurance program for review and does not qualify for a general license to make shipments in accordance with 10 CFR 71.12. This area will be followed via item (334/79-01-01).
The inspector had no further questions at this time.
No items of noncompliance were identified.
9.
Licensee Action on Previous Inspection Findings (Closed) Unresolved item (334/78-15-01): The licensee had determined that no record could be found of the results of the weekly airborne particulate sample, for release point VS 107, for the period March 22-30, 1978.
Technical Specification (TS) 6.10.2.e requires that the licensee maintain records of gaseous and liquid radioactive material released to the environs for the duration of the Facility Operating License.
The inspector identified the above failure to maintain records of VS 107 particulate releases as noncompliance with TS 6.10.2.e.
(334/79-01-02)
The inspector reviewed the licensee's corrective action which had been initiated and completed.
The corrective actions included the institution of a new log to record and track airborne effluent release results.
10.
Facility Tours Upon arrival, at 5:00 p.m. on January 8, 1979, areas where work was being conducted were examined to review radiation safety control practices.
Radiation work permits (RWP) were reviewed for jobs in
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progress and the work sites examined for cumpliance with RWP require-ments.
Several portable radiation survey meters in use were exanined.
An additional tour was made to examine the installation of fixed radiation monitoring equipment.
No items of noncompliance were identified.
11.
Exit Interview The inspector met with licensee management representatives (denoted in paragraph 1) at the conclusion of the inspection on January 12, 1979. The inspector summarized the purpose and scope of the inspec-tion and the findings. Additionally,the inspector noted that the licensee's corrective action had been completed regarding maintaining records of airborne effluents.