IR 05000029/1989012
| ML20248D872 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/01/1989 |
| From: | Bores R, Joseph Furia NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20248D870 | List: |
| References | |
| 50-029-89-12, 50-29-89-12, IEB-79-19, NUDOCS 8908110157 | |
| Download: ML20248D872 (8) | |
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l NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-029/89-12 Docket No.50-029 License No.
DPR-3 Priority Category _C Licensee:
Yankee Atomic Electric Company 1671 Worcester Road Framinghau, Massachusetts 01701 Facility Name: Yankee Nuclear Power Station Inspection At:
Rowe, Massachusetts Inspection Conduc ed:
July 10-14, 1989 f[//f7 Inspectors:
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Feria,4 Radiation Specialist, ERPS date nla/
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_R.'Bor9p, Ch~ief, Effluents Radiation date Protection Section, FRSSB Inspection Summary:
Inspection on July 10-14, 1989 (Inspection Report No. 50-029/89-12)
Areas Inspected:
Routine, unannounced inspection of the solid radioactive waste systems, transportation, and liquid and gaseous effluents programs including:
Management controls; audits;
-quality assurance; and implementation of the-above programs.
Resulto:
Within the areas inspected, no violations or deviations were noted.
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DETAILS
. 1.0 Personnel Contacted 1.1 Licensee Personnel N. St. Laurent, Plant Superintendent
- M. Hedges, Chemistry Manager J. Gedutis, Senior Chemist L.
Bozek, Quality Assurance Supervisor
- M. Vandale, Radiation Protection Engineer, Radwaste
- G.
Babineau, Radiation Protection Manager J. Kay, Technical _ Support Department Manager
- D. O'Donnell, Senior Instructor, Training Department M. Schuster, Quality Assurance-M.
Thisell, Senior Chemist P. Hollenbeck, Radiation Protection Engineer
- T. Henderson, Assistant Plant Superintendent
- D. Calsyn, Yankee Nuclear Services Department, Quality Assurance 1.2 NRC Personnel
- J. Macdonald,. Senior Resident Inspector M. Markley, Resident Inspector
- Denotes those present at the exit meeting on July 14, 1989.
2.0 Purpose.
The purpose of this routine inspection was to review the licensee's program in the following areas:
.The licensee's ability to properly prepare, package and i
ship licensed radioactive materie1c for transport and disposal.
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.The licensee's ability to measure liquid and gaseous
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radioactive effluents during normal and emergency operations.
i 3.0 Previously Identified Items (Closed) Inspector Follow-Up Item (50-029/85-05-01): Review l
analytical improvements.
The licensee has issued procedures for Post Accident Sampling (OP-9450), has procured new chromatograph and multi-channel analyzer systems and has determined the range, sensitivity and accuracy of the PASS analyses.
This item is closed.
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i (Closed) Unresolved Item (50-029/85-05-02): Deficient sampling capability.
The licensee has modified plant sampling systems to allow for the sampling and analysis of post accident samples at l
the high pressure safety injection system when system pressure falls below 300 psig.
This item is closed.
i (Closed) Inspector Follow-Up Item (50-029/85-05-03):
Review hardware improvements to effluent monitoring system.
The licensee has procured a higher pressure gaseous sampling container, and has added a sampling point at the hydrogen analyzer.
This item is closed.
[ Closed) Inspector Follow-Up Item (50-029/85-05-05):
Review naprovements to effluent monitoring system.
Licensee installed a new vent stack monitoring system in 1986 per EDCR Number 84-326.
This new system corrects all mechanical deficiencies previously identified.
This item is closed.
4.0 Transportation and Solid Radwaste In accordance with plant procedures, packaging and transportation of solid radwaste is the responsibility of the Radwaste Engineer who reports to the Radiation Protection Manager.
Staffing of the Radwaste Section has remained stable and the staffing level is adequate for the volume of wastes being processed.
At the present time the licensee processes evaporator bottoms by solidification, compacts Dry Active Wastes (DAW) khere applicable, and utilizes a vendor for the cleaning of plant laundry.
4.1 Quality Assurance / Quality Control The licensee's Quality Assurance Department is tasked with performing regular periodic audits of both the plant radwaste program and vendors performing 10 CFR 71 Quality Assurance. activities in accordance with the plant Quality Assurance Program.
Audit Report Number Y-88-09, dated November 4, 1988, was the moJt recent audit of the plant radwaste program.
No findings or deficiencies were noted in the audit report.
Audit Report Number 87-060, dated June 5, 1987, was the most recent audit of Chem Nuclear Systems, Inc., which at the present time is the only vendor performing 10 CFR 71 activities.
The licensee identified one finding which was addressed prior to the close of the audit, and was so noted in the final audit eport.
Plant Quality Services performs Quality Control Inspections and Surveillance of radwaste activities in accordance with the plant Quality Assurance Program.
Plant radwaste procedures require notification of Plant Quality Services
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whenever solidified drums are being processed, when DAY.
boxes are being closed and when a radwaste shipment is to take place.
Plant Quality Services performs an inspection of all of these activities with 100 % coverage, and then issues a Quality Control Inspection report to document these activities.
Inspection Reports for seven waste shipments were reviewed by the inspector and found to be comprehensive in scope, with no negative findings in the reports.
Additionally, Plant Quality Services performs random surveillance of selected radwaste activities, the results of which were also reviewed by the inspector and found to be adequate.
This program provides excellent coverage of radwaste activities and the inspector had no further questions in this area.
4.2 Transportation As part of this inspection, the inspector reviewed the recor[1 of the eight radioactive material shipments listed below.
Shipment #
Date Activity (mci)
Volume (cu ft)
88-36 11/21/88 40800 120.3 88-53 12/14/88 1.6 62.6 89-06 1/12/89 1.99 13.5 89-12 3/8/89 572.0 1111.0 89-18 3/29/89 1010.0 300.0 89-21 5/3/89 3.193 294.0 89-26 5/31/89 0.027 0.935 89-28 6/28/89 416.0 401.0 These shipments included solidified drums, compacted and uncompacted DAW, dewatered resin, contaminated laundry and chemistry samples.
All records were found to be complete, and to accurately classify the material in accordance with 10 CFR 71 and 49 CFR Parts 100-179.
4.3 Raduaste At the present time the plant, in accordance with the Final Safety Analysis Report and plant procedures processas liquids through an evaporator system, with khe evaporator bottoms solidified by operations personnel in 55-gallon drums using Portland cement.
Spent filters are currently stored on site until a sufficient number are present when they will then be solidified in preparation for disposal.
Spent resin at the current time is generated at a very low l,
rate, with one High Integrity Container (HIC) generated
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approximately inspection, y once every three years.the following procedures were review As part of this
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OP-2175, Rev 8, " Changing Purification System Filter
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Capsules' Cartridges" OP-2380, Rev 18, " Operation of the Waste Disposal Evaporator System" OP-2381, Rev 21, " Batch Record for Concentrating and Drumming Evaporator Bottoms" OP-8301, Rev 10, " Radioactive Material Shipment" OP-8302, Rev 0, " Final Preparation, Inspection and Loading i
of Radwaste Containers for Transport and Dispos,al"
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OP-8303 Rev 4, Shipment"
" Preparation of Spent Ion Exchange Resin for OP-8310, Rev 0, " Preparation and Inspection of Dry, Drummed Evaporator Bottoms"
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OP-8320, Rev 2, " Operation of the CGR Radwaste Compactor" OP-8321, Rev 1, Preparation and Inspection of DAW Boxes" These procedures were found to be comprehensive in scope and to adequately reflect existing radwaste processing.
Scaling factors for plant wastes are currently evaluated on a once per fuel cycle basis for eva compacted DAW and uncompacted DAW, porator bottoms, in accordance with plant procedures.
This is adequate since packages of these wastes have historically been Class A Waste and the fuel cycle is currently 18 months.
4.4 Trainino plant procedure AP-0527, Training of radwaste workers is conducted in acc Rev O,
"Radwaste/Decon Technician program co/ Worker Training Program".
nsists of classroom and on-the-job aThe initial training which are typically completed within one year.ctivities training Continuing Assurance, personnel,which is also provided to management and Quality is conducted on an annual basis.
records of the four plant staff members working in the The o
Radwaste Section were reviewed by the inspector and found to be complete.
At the time of this inspection, a contractor was at the plant conducting annual radwaste worker training, g
the content of which was evaluated and found to meet the criteria set forth in NRC IE Bulletin 79-19.
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b approximately once every three years.
As part of this inspection, the following procedures were reviewed.
OP-2175, Rev 8,
" Changing Purification System Filter Capsules' Cartridges" OP-2380, Rev 18, " Operation of the Waste Disposal Evaporator System" OP-2381, Rev 21, " Batch Record for Concentrating and Drumming Evaporator Bottoms" OP-8301, Rev 10, " Radioactive Material Shipment" OP-8302, Rev 0,
" Final Preparation, Inspection, and Loading of Radwaste Containers for Transport and Disposal" OP-8303, Rev 4, " Preparation of Spent Ion Exchange Resin for Shipment" OP-8310, Rev 0, " Preparation and Inspection of Dry, Drummed Evaporator Bottoms" OP-8320, Rev 2,
" Operation of the CGR Radwaste Compactor" OP-8321, Rev 1,
" Preparation and Inspection of DAW Boxes" These procedures were found to be comprehensive in scope and to adequately reflect existing radwaste processing.
Scaling factors for plant wastes are currently evaluated on a once per fuel cycle basis for evaporator bottoms compacted DAW and uncompacted DAW, in accordance w1th plant procedures.
This is adequate since packages of these wastes have historically been Class A Waste and the fuel cycle is currently 18 months.
4.4 Training Training of radwaste workers is conducted in accordance with plant procedure AP-0527, Rev 0,
"Radwaste/Decon Technician / Worker Training Program".
The initial training program consists of classroom and on-the-job activities which are typically completed within one year.
Continuing training, which is also provided to management and Quality Assurance personnel, is conducted on an annual basis.
The records of the four plant staff members working in the Radwaste Section were reviewed by the inspector and found to be complete.
At the time of this inspection, a contractor was at the plant conducting annual radwaste worker training, i
the content of which was evaluated and found to meet the criteria set forth in NRC IE Bulletin 79-19.
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5.0 Effluents The radioactive effluents program is divided between Chemistry which provides aralysis of liguid and gaseous samples and tests the air cleaning systems; Radiation Protection which performs isotopic calibration of the process radiation monitors; Instrumentation and Control which performs electronic calibration of the process radiation monitoring system; Operations which conducts the releases; and the corporate office which performF dose calculations on the effluent releases and issues the semiannual effluent release report.
5.1 Liquid and Gaseous Releases The Chemistry Department is responsible for analyzing liquid and gaseous samples prior to release, and initiation of release permits.
As part of this inspection, three gaseous and five liquid release permits for 1989 were examined and found to properly control the effluent releases, with radioisotopic analysis conducted in accordance with industry standards.
This review included examination of control charts and associated data for the two germanium detectors presently in use by the licensee for these analyses.
Copies of the release permits were forwarded to the corporate office for dose calculation and for inclusion into the semiannual effluent release reports.
In addition, the Chemistry Department performed its own dose calculations which were kept on file on a monthly basis, and included parterly and year to date computations.
As part of this inspection, the following procedures pertaining to the release of liquid and gaseous effluents were reviewed.
OP-2379, Rev 14, " Recirculating / Releasing No.
Test Tank" OP-2385, Rev 9, " Operation of the Waste Gas System" OP-2386, Rev 9, " Releasing Radioactive Gases From the Waste Gas Surge Drum to Atmosphere" OP-9246, Rev 11, " Radioactive Liquid Releases" OP-9247, Rev 7, "Sumpling, Measuring, and Reporting Radioactive Airborne Releases" OP-9251, Rev 4, "Use of the Offsite Dose Calculation Manual"
OP-9415, Rev 9,
" Radioactive Gas Sampling" OP-9450, Rev 8, " Post Accident Sampling and Analysis" These procedures were found to be adequate, and the inspector had no further questions in this are _ - _ _ _ _ _ _ _
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5.2 Monitor-Calibration-Source calibration of the process radiation monitors is the res onsibility of the Radiation Protection Department.
Li id-and gaseous effluent monitors were calibrated once us ng primary calibration sources traceable to the National Institute of: Standards and Technology (NIST), and then calibrated at least every 18 months using. secondary-calibration: standards, in accordance with plant procedures.
As part of this inspection the calibration records of the Steam Generator Blowdown Tank monitor-and the Primary Vent Stack Noble Gas monitor were examined and found to be complete and in accordance with Plant Technical Specifications.
In addition, the following calibration procedures were-examined by the inspector.
OP-4801, Rev 17, " Functional Test and Alarm Settings of the Process Radiation Monitoring System" Rev 5, " Calibration of the Primary' Vent Stack OP-4813,itoring System" Mon OP-4814, Rev 3,
" Calibration of the Tech Spec Process Radiation Monitors" OP-4818, Rev 3,
" Calibration of the Liquid Radwaste Effluent and Steam Generator Blowdown Tank Effluent Radiation Monitors" OP-4821,itor"Rev 0,
" Calibration of the Air Ejector Radiation Mon These procedures were found to be adequate and the inspector had no further questions in this area.
'5.3 Air Cleaning Systems Testing of the air cleaning systems is the responsibility of the Chemistry Department.
At the time of this inspection, the licensee utilized a vendor to perform air flow, HEPA filter and charcoal adsorber testing once per fuel cycle.
As part of this inspection, the documentation for the testing conducted on December 6, 1988 was examined.
These records contained plant (OP-9243, Pcv 8, " Nuclear Air i'
Cleanup Systems Filter Testing) and vendor procedures approved for-use at the plant for the testing of the F-10 and'F-11 filter trains of the Plant Ventilation Exhadst Treatment System (PVETS) and the Control Room Emergency Air Cleanup System (CREACS).
These results demonstrated that these two systems met the standards set forth in ANSI N510, 1975 for Nuclear Air Handling Systems.
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,6.0 Exit Interview-The inspector met.the licensee representatives (denoted in Section.1) at the conclusion of the inspection on' July-14,:1989.
The inspectors summarized the purpose, scope, and findings of the
' inspection. ~ At no time during the inspection did the inspector provide any written-information to the licensee.
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