IR 05000309/1981019
| ML20040E621 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/19/1982 |
| From: | Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20040E618 | List: |
| References | |
| 50-309-81-19, IEB-80-10, IEC-80-14, NUDOCS 8202050180 | |
| Download: ML20040E621 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-309/81-19 Docket No. 50-309 License No. DPR-36 Priority
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Category C
Licensee: Maine Yankee Atomic Power Company 1671 Worcester Road Framingham, Massachusetts 01701 Facility Name: Maine Yankee Nuclear Generating Station Inspection at: Wiscassett, Maine Inspection conducted:
uly 27-30, 1981 Inspectors:
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/// 7 N K. E. Plumlee, Radiation Specialist date signed
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Approved by:
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P. J. Kria'pp, 'C6ief, Fay 11ty date signed Radiological Protection Section, Technical Inspection Branch Inspection Summary:
Inspection on July 27-30, 1981 (Report No. 50-309/81-19)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of licensee actions on NRC:IE Bulletin No. 80-10, " Contamination of Nonradio-active Systems and Resulting Potential for Unmonitored, Uncontrolled Release to Environment", and NRC: IE Circular No. 80-14, " Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel," including:
identification of interfaces between nonradioactive and radioactive systems; implementation of the. sampling program for unmonitored potential release paths, evaluations and consideration of interim measures in the event that nonradioactive systems become radioactive, corrective actions, and documentation. This inspection involved a total of 16 inspector-hours onsite by one NRC regional based inspector.
Results: No items of noncompliance were identified.
9202050100 820122 PDR ADOCK 05000309 D
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Details 1.
Persons Contacted
-*G. Cochrane, Radiological Controls Supervisor B. Kimball, Chemist W. Lach, Chemist P. Radsky, Chemist-J. Stevens, Chemistry Manager
- D. Sturniolo, Assistant to the P' ant Manager
- E. Wood, Plant Manager
- Denotes presence at the exit interview July 30, 1981.
2.
Licensee Action on Bulletins and Circulars (Closed) IE Bulletin No. 80-10 (80-BU-10):
Contamination of Nonradioactive Systems and Resultir.g Potential for Unmonitored, Uncontrolled Release to Environment." Review of the licensee's actions is documented in the following paragraphs.
(Closed) IE Circular No. 80-14 (80-CI-14):
" Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel." A May 12, 1981 licensee review, listed in paragraph 3.b, verified there were no existing water system interfaces with the potable (i.e. well) water system. A sign on a sink in the First Aid Room warns against ingestion of water from that point (nonchlorfiated domestic water).
In order to supplement the potable water supply, the licensee was installing a chlorinator and a domestic water system connection to the well water storage tank.
This has been documented and reviewed by the licensee.
(See reference, " Draft Plant Alteration", paragraph 3.b)
3.
Verification of Licensee Documentation a.
Required ActionsBulletin 80-10 required the follosing licensee actions within 45 days of the date of the Bulletin (dated May 6, 1980):
(1)
Identification of systems that are considered nonradioactive, or are described as nonradioactive in the FSAR, but could possibly become radioactive through interfaces with radioactive systems; (2) Establishment of a routine sampling / analysis or monitoring program to promptly identify any contaminating events in the above systems which could lead to an unmonitored or uncontrolled liquid or gaseous release;
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(3) Restriction of the use of any such system that is or becomes contaminated, until the cause has been identified and corrected and the system has been decontaminated; or if system operation is necessary before these actions are completed, prompt evaluation of the safety of operation in accordance with the requirements of 10 CFR 50.59; and, P
(4) Assurance that any such operation is in compliance with 10 CFR 20.201, General Design Criterion 64 of Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, and the facility's technical specifications.
b.
Required Notification and Documentation Bulletin 80-10 required, within an additional 15 days (of the original 45 days), a letter from the licensee notifying the Director of NRC Region I of the completion of the required actions and the availability of documentation for onsite review of the specifics taken to comply with the Bulletin.
A licensee representative stated that no document other than the reply letter dated July 7, 1980 specifically addressed Bulletin 80-10.
The inspector reviewed the following licensee documentation of actions pursuant to, or on the same topics as,Bulletin 80-10.
Licensee reply to Bulletin 80-10, D. Moody, July 7, 1980 Memo, " Review of Maine Yankee Water Supply Systems for Sources of Cross Contamination," P. Radsky, May 12, 1981 Memo, " Additional Sampling Requirements," J. Stevens, July 1, 1980 Maine Yankee FSAR Sections:
9.13 Ventilation Systems 11.2 Station Radiation Monitoring System Draft Plant Alteration, "Well Water System Modification,"
latest revision dated July,1977 Procedure 3.7.1.1, " Liquid Radioactive Waste Cischarges,"
March 19, 1981. (Revision No. 7)
Procedure 3.7.1.2, " Gaseous Radioactive Waste Discharges,"
December 30, 1980 (Revision No. 7)
Procedure 3.7.4.1, " Primary Chemistry... Test Frequencies and... Specifications," April 14, 1981 (Revision No. 7)
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Procedure 3.7.4.2, " Steam Generator Test Frequencies and Specifications," May 5,1981 (Revision No. 7)
Procedure 7.207.1, " Water Treatment Test Frequencies and Specifications," April 28, 1981 Procedure 7.207.2, " Auxiliary Boiler Test Frequencies and Specifications," October 1, 1979 (Revision No. 4)
Chemistry Analysis Reports, April 14, 1981 Marked-up drawings of system interfaces for the systems listed in paragraph 4.
Based on this review the inspector determined that the licensee had complied with Bulletin No. 80-10, 4.
Summary of the Monitori_ng and Sampling Program The inspector reviewed the licensee program while onsite and clarified certain information during a telephone contact with Mr. J. Stevens on August 6, 1981. The licensee program is summarized in Tables I and II.
a.
Liquid Systems Summary A licensee representative presented the following information on the nonradioactive water systems:
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Table I Nonradioactive Water System Summary Monitored or Sample
- Sample Analysis Nonradioactive System Sampled Period (pCi/ml)
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Discharge Canal Sampled Monthly **
< 1 E-10 i
Yard Drain to Discharge Sampled
~ Semiannually < 1 E-7 Canal Yard Drain to Back Cove Sampled
~ Semiannually < 1 E-7
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Service Water System Both Monthly
< 1 E-7 Discharge Header This is a common discharge header for:
Auxiliary Boiler System CondensateSampieg,henused)
Dail
< 1 E-6 blowdown
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Nuclear Steam Supply CondensateSamplefWhhnuled)
< 1 E-6 I
System blowdown Sanitary Sewage System Sampled Monthly
< 1 E-7 Turbine Building Sump Neither
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and Secondary System Leakage Pit Steam Generator Blowdown Both Daily
< 1 E-6 Primary Water Storage Tank Sampled Daily
< 1 E-6 Demineralized Water Storage Sampled Daily
< 1 E-6 Tank Primary Component Cooling **
Both Weekly
< 1 E-6 Secondary Component Both Weekly
< 1 E-6 Cooling **
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Well (Potable) Water (State of Maine samples)
l MONTSWEAG Reservoir None
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.The reservoir supplies the:
Raw Water Storage Pond, None
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Domestic Water,
Makeup Water,
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Fire Protection Water None
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"The lower limit of detection (LLD) for routine gross beta gamma analyses is approximately 1 E-6 pC1/ml; and for routine gamma spectrum analyses
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approximately 1 E-7 pCi/ml for prominent activation products and fission product isotopes such as Co-60, Cs-137, and I-131.
- Environmental sample schedule.
primary component cooling system).
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- Domestic water was used for lavatories and showers. A plant alteration is being implemented to supplement the well (potable) water system, using chlorinated domestic water.
This supplemental system is routinely sampled and analyzed to verify hygienic acceptability as potable water, and periodic sample analyses for radioactivity will be made.
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The Primary Water Storage Tank and the Demineralized Water Storage Tank have outdoor locations.
The former was once contaminated and surveys indicated there is radioactive residue in the tank.
However, analysis of liquid from the tank indicates no activity above the lower limit of detection.
The FSAR listed the following system monitor sensitivities (for Cs-137) in pCi/ml:
Service Water System 1 E-6 Primary Component Cooling Water 1 E-5
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Secondary Component Cooling Water 1 E-5
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Steam Generator Blowdown Monitors (3)
S E-6
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Liquid Waste Disposal System Monitor 5 E-6 Technical Specifications section 3.16.A.2 requires prompt action to reduce the release rate, and submission of a 7-day report to NRC, if the release rate reaches eight times the design objective of five Ci per year in liquid waste (excluding tritium and dissolved gases).
The inspector noted that, for a 20,000 gpm sustained discharge rate (as from the Service Water System), a monitor having 1 E-6 pCi/ml sensitivity would assure early identification of a release rate of about (3 Ci per year.
Technical Specifications section 3.16. A.1 specifies corrective action and submission of a 30-day report to NRC if the release rate reaches twice the design objective.
The above system is sampled to assure this requirement is met. Assuming the concentration is just below the monitor sensitivity, monthly sampling would identify the problem with no more than about a 3 Ci release; weekly sampling a 0.8 Ci release; or daily sampling, a 0.1 Ci release.
No items of noncompliance were identified.
b.
Ventilation and Compressed Air Systems Summary The FSAR in Section 9.13, " Ventilation Systems," states that the Fuel Building, Primary Auxiliary Building, and Service Building ventilation exhaust is discharged past particulate filters and radiation monitors to the primary vent stack or the Service Building exhaust.
The Turbine Building ventilation discharges (non-filtered) through gravity ventilators located on the roof.
The Laboratory Area (Chemistry and HP) hood ventilation systems exhaust through particulate filter..
A licensee representative stated that monitoring and sampling of the ventilation and compressed air systems were maintained as listed in Table II.
Since the Containment Atmosphere contains detectable airborne radioactivity during reactor operation, detectable contamin-ation could be present in the Containment Instrument Air System prefilters and driers, through which this system delivers air within containment. A hose may be used to cross-connect this system to the Service Air supply, which is protected from backflow.
Primary Auxiliary Building, Fuel Building, and (filtering optional)
Containment Spray Pump Area ventilation discharge through charcoal filters as wel _
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l Table II Ventilation and Compressed Air Systems Summary
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Monitored or Monitor (orSample)
l System Sampled Sensitivity pCi/ml
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Primary Vent Stacks *
Both 1 E-9 (I-131)
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1 E-5 (Xe-133)
Service Building Exhaust Both 1 E-10 (I-131)
- Condenser Air Ejector Both 5 E-6 (Kr-85)
Breathing Air (Compressed Sampled (1 E-10)
Air Cylinder Cart)
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Service Air ** & Instrument Neither Air i
Containment Instrument Air
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- Particulate, Halogen and Noble Gas Monitor
- Supplies Fuel Building, Circulating Water Pump House, Primary
Auxiliary Building, Service Building, and Turbine Building.
Part of the Containment equipment is supplied by this system during refueling. Cross-connection to Containment Instrument Air may be provided by a hose.
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- Containment Instrument Air is supplied by two compressors located inside Containment. (Containment atmosphere is routinely monitored and sampled).
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Review of the monitoring and sampling of these systems did not
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identify any changes from the FSAR description and the Technical Specifications Bases, which have been evaluated by NRC.
6.
Exit Interview
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The inspector reviewed the status of the inspection with the licensee
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representatives, denoted in. paragraph 1, at the conclusion of the i
inspection.
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