IR 05000213/1989014
| ML20248G726 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/21/1989 |
| From: | Bores R, Joseph Furia NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20248G715 | List: |
| References | |
| 50-213-89-14, NUDOCS 8910100350 | |
| Download: ML20248G726 (8) | |
Text
{{#Wiki_filter:.,.. + . .,. - . . e . h L NUCLEAR REGULATORY COMMISSION
REGION I
L Report Nos.
50-213/89-14 Docket Nos.
50-213 License Nos. DPR-61 Priority Category C Licensee: Connecticut Yankee Atomic Power Company P. O. Box 270 Hartford, connecticut 06101 Facility Name: Haddam Neck Plant Inspection At: Haddam Neck Site Inspection Conduct d: Sep_tember 11-15, 1989 ' 74U Inspectors- _ date J.~ turi'a, Radiation Specialist, LRPS P~#/~ @ Approved by: ~ R. BorM, Chief, Effluent Radiation date Protection Section, FRSSB Inspection Summary: Inspection on September 11-15, 1989 (Inspection Report No.
50-213/89-14) Areas Inspected: Routine unannounced inspection of the solid radioactive waste systems, transportation, liquid and gaseous effluents programs including: Management controls, audits, quality assurance, and implementation of the above programs.
Results: Within the areas inspected, no violations or deviations were noted.
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I l< . , . l l l DETAILS 1.0 Personnel Contacted 1.1 Licensee Personnel
- D. Miller, Jr., Station Superintendent
- R. Haight A.Donzello,adioactiveMaterialsHandling&C)pervisor R
Su Instrumentation & Control (I Technician J. LaPlatney, I&C Supervisor
- M. Quinn, Chemistry Supervisor P. Heffernan, Assistant Chemistry Supervisor H. Clow, Health Physics Supervisor D. Ray Operations Supervisor
- E. DeBarba, Station Services Supervisor
- J. Beauchamp, Quality Services Supervisor J. Delawrence, Engineering K. Dingle, Auxiliary Operator
- W. Nevelos, Radiation Protection Supervisor J. McHugh, Radiological Assessment Engineer J. Duroski, Radiological Assessment Engineer P. Burke, Instructor, Radioactive Materials Technicians 1.2 NRC Personnel
- T. Shedlosky, Senior Resident Inspector A. Asars, Resident Inspector
- Denotes those present at the exit meeting on September 15, 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 ship licensed radioactive materials for transport and disposal, and .The licensee's ability to measure liquid and gaseous radioactive effluents during normal and emergency operations.
3.0 Transportation and Solid Radwaste In accordance with plant procedures, preparation, packaging and transportation of wastes is the responsibility of the Radwaste Section of the Health Physics Department. Wastes include spent resins from the primary and secondary systems which are processed by plant ion exchangers; waste water clean up resins utilized in the Chem Nuclear Systems, Inc. (CNSI) mobile demineralization system; and Dry Active Waste (DAW).
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3.1 Quality Assurance / Quality Control The Quality Assurance / Quality Control program at Haddam Neck involves Northeast Utilities Cuality Services audits of in-plant and principle venc or activities, and. surveillance and. inspections conducted by the onsite Northeast Utilities Quality Services. Division (QSD). Audit 1989 was an evaluation of the A60265, dated June 22, kaging and Transportation Program.
licensee's Radwaste Pac There were no findings identified in this audit requiring h ' corrective actions or resolution. Audit A03367, dated Marc 11, 1988 was conducted to evaluate CNSI, who rovides demineralization services, waste liners, ship ing casks and transportation services. The two findings id ntified in this audit were promptly resolved.
QSD conducts periodic surveillance of radwaste activities, and in addition has mandatory radioactive material shipment inspections.
Five surveillance reports encompassing resin procedural compliance, and filter . transfer, trash sorting,d by the inspector.
replacement were reviewe Surveillance and inspections are conducted in accordance with the following procedures.
QSDI-PS-CY-2.01, Rev 1, "CYPOS Radioactive Material Shipment Inspection" QSDI-PS-CY-2.04,llance Activities 9.1"Rev 1, " Performance of Connecticut Yankee Quality Survei These surveillance were found to be adequate and any findings requiring action were promptly resolved. The inspector had no further questions in this area.
3.2 Transportation As part of this inspection, the inspector reviewed the records of the 10 radioactive material shipments listed below.
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?.. , - ~ . '4 . -Shipment # Activity (C1) M W-88-10
88 2.026 DAW W-88-11 '8
5.094 DAW , W-88-12
88 14.889 Filters
W-88-13
88 204.556 Resin W-89-01
89 7.112 Resin W-89-02
89 29.790 Filters W-89-03
89 2.724 Resin W-89-04
89 2.967 DAW W-89-05
89 463.025 Resin W-89-06 .8
1.384 DAW 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.
3.3 Radwaste-In accordance 'with plant procedures, liquids were processed through the plant ion exchangers or the CNSI mobile demineralization system with the spent resins sluiced to a High Integrity Container in the spent resin storage pit where they were dewatered. Spent filters were stored on site in a shielded HIC.. DAW was sorted into compactable and non-compactable material with compactables shredded and compacted'on site and non-compactables bulk-loaded in a SeaVan for-shipment to Quadrex. Clean trash was sent to the Unconditional Release Facility for monitoring on both a table monitor and bag monitor prior to release.
Laundry was sent to Interstate Nuclear Services for cleaning.
Waste streams within the plant clearly reflect the problems.
experienced with fuel failure.
Spent resin shipments were predominantly sent to the disposal site as Class C Waste due to the high levels of alpha emitting transuranic present.
Scaling factors for plant wastes were evaluated on a once per fuel cycle basis by Impell Corporation for all waste streams, in accordance with plant procedures.
In addition, all resin tanks were sampled prior to loading, and the primary gamma emitters identified, quantified, and their j ratios tracked to ensure stability of the isotopic content ' of the waste stream. This meets the sampling criteria set forth in the NRC Branch Technical Position for Waste Classification.
The inspector had no further questions in this area.
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, i j 3.4 Training j Training in the areas of transportation and radwaste was presented to Quality Assurance personnel, radwaste , technicians and the Supervisor of Radioactive Material l Handling.
The training program was conducted in accordance with Procedure NTM 3.146, Rev 0, " Connecticut Yankee ! Radioactive Material Workers Training Program Implementing j Procedure".
Initial training of new workers was conducted
in accordance with CY-TT-RHIT, Rev 0, " Connecticut Yankee Radioactive Material Workers Initial Training", and consisted of classroom and on the job training programs.
Continuing training, presented on an annual basis was conducted in accordance with CY-TT-RHCT, Rev 0, " Connecticut , Yankee-Radioactive Material Workers Continuing Training".
' These excellent training programs were found to meet the requirements of NRC IE Bulletin 79-19.
3.5 Interim Radwaste Storage The licensee currently has available its Waste Disposal
Facility for the storage of upwards of five years of ' Hadddam Neck Plant generated DAW, based upon current and projected waste generation rates.
High Integrity Containers and waste disposal liners are currently stored in the spent resin storage area and in concrete storage culverts.
Licensee personnel stated that current onsite storage capacity would be increased from its current three years by I the purchase of additional culverts, if needed.
The
inspector had no further questions in this area.
J 4.0 Effluents The radioactive effluents program was conducted principally by the
Chemistry Department which provided analysis of liquid and i gaseous samples, prepared release permits, prepared dose i calculations, and prepared the semiannual effluent release reports.
The corporate Radiological Assessment Division provided refined dose calculations from airborne releases based upon real time meteorological data.
Instrumentation and Control performed electronic and source calibration of the Radiation i Monitoring System (RMS).
Operations controlled the releases and Engineering conducted testing of the air cleaning systems.
4.1 Liguid and Gaseous Releases The Chemistry Department performed the analyses of liquid ) and gaseous samples prior to release, performed dose calculations, and signed off on release permits which were ' c then sent to the Operations Department for the actual releases.
As part of this inspection, 92 gaseous, 202 I - --
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liquid, and 26 airborne particulate. discharge permits for 1989 were examined and found to properly control the effluent releases,dustry standards.with radioisotopic analyses conducted in accordance with in Dose calculations for gaseous releases are revised monthly by the Radiological Assessment Division based upon the release data contained in the permits in conjunction with.the real-time meteorological data At.the time of the inspection, the licensee was experiencing problems with the venting of the reactor vessel head in conjunction with the refueling activities taking place.
High levels of noble gases in the vessel had placed the offsite beta dose of 10 millirad, g the quarterly limit for licensee in a position of exceedin as specified in Technical S) edification 7.1.2.2.a.
As a result, the licensee was in
tie process of pre)aring the 30-day action statement, for submission to the iRC as required by Technical Specifications.
The licensee had projected.in February, 1989, that the entrained inventory of noble gases and iodines in the reactor coolant would be higher than originally anticipated once the primary coolant system was cooled during shutdown for refueling.
The magnitude of this entrained activit, which peaked at 70 microcuries-per milliliter.
(uCi/ml of reactor coolant for xenon-133 and 11 uti/ml for iodine-31, was greater than predicted, however.
Dose projections for the remainder of the year are expected to be such that the annual Technical Specification limit of 20 millirad for beta radiation will not be exceeded.
There were no violations or deviations in this area.
I 4.2 Monitor Calibration Source calibration of the RMS was the responsibility of the ? I & C Department with technical assistance from the Chemistry Department.
Liquid and gaseous effluent monitors were calibrated once using primary calibration sources traceable to the National Institute of Standards and Technology (NIST), and subsequently calibrated utilizing secondary calibration standards, in accordance with olant procedures.
As part of this inspection the calibration records of the following Technical Specification and Non-Technical Specification monitors were reviewed.
l R-11, Reactor Containment Air Particulate R-12, Reactor Containment Gas R-14A, Primary Vent Stack Gas j R-148, Wide Range Primary Vent Stack Gas
R-15, Condenser Air Ejector l
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R-16A & B, Steam Generator Liquid Sample R-17, Component Cooling Water Systems Liquid R-18, Radioactive Waste Systems Liquid Effluent R-19, Spent Fuel Pit Cooling System Liquid Effluent R-20, Reactor Coolant System Gross Activity R-22, Test Tank Effluent It was noted by the inspector that Monitor R-22 was reported in the January - June 1989 Radiological Effluents Report as being declared out of service for greater than 30 days on June 16, 1989.
Discussions with plant personnel indicated that the problem with this monitor was increased background following each test tank release, and as a result the licensee was unable to meet the daily source check requirement for this monitor.
The licensee has considered a modification to permit backflushing of this system following each release. The region-based inspectors and resident inspector staff will follow this item until completion of repairs to this system (Inspector Follow-Up Item 50-213/89-14-01).
In addition, the following calibration procedures were examined by the inspector.
SUR 5.2-69, Rev 11, " Calibration and Functional Test of the Stack Wide Range Noble Gas Monitor" SUR 5.2-81, Rev 3, " Calibration of the Radiation Monitoring System" These procedures were found to be adequate and the inspector had no further questions in this area.
4.3 Air Cleaning _ Systems j l Testing of the air cleaning systems was the responsibility I of the Engineering Department.
The licensee utilized Nuclear Containment Systems, Inc. to perform air flow, HEPA filter and,harcoal adsorber testing.
As part of this inspection, the documentation for the testing conducted in 1989 was examined.
Testing was conducted on the two , ' . Technical Specification systems, Spent Fuel Building Exhaust i l and Containment Air Recirculation and also on the Primary Auxiliary Building and Emergency Operations Facility I l l E
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Tests were conducted.in accordance with N510-1975 and the following procedures.
ENG 1.7-74, Rev 1, " EOF Filtration System" ENG'1.7-79, Rev 1, "In Place Testing of Spent Fuel Building Exhaust HEPA and HECA Filters" ENG 1.7-80, Rev 0 "In Place Testing of1PAB Ventilation HEPA and HECA Filters" .SUR 5.7-4 Rev 8, "In Place Testing of Containment. Air Recirculation HEPA and HECA Filters" These procedures were found to be adequate and the inspector had no further questions in this area.
-4.4 Audits The' Northeast Utilities Assessment Services conducted biennial audits of the: effluents program in accordance with plant Technical Specifications.
Audit A25030, dated December 1, 1988 was the most recent audit conducted in this-area and was reviewed by the inspector.
There were no findings contained within the audit report which required licensee followup or resolution.
The inspector had no further questions in this area.
5.0 Exit Interview The. inspector met the licensee representatives (denoted in Section 1) at the conclusion of the inspection on September 15, 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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