IR 05000219/1981015
| ML20050C838 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/23/1982 |
| From: | Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20050C834 | List: |
| References | |
| 50-219-81-15, IEB-80-10, NUDOCS 8204090397 | |
| Download: ML20050C838 (6) | |
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U.S. NUCLEAR REGULATORY. COMMISSION Region I Report No.
50-219/81-15 Docket No.
50-219 License No.
DPR-16 Priority
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Category C
Licensee:
GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Facility Name: Oyster Creek Nuclear Generating Station Inspection at:
Forked River, New Jersey Inspection conducted: 'A il 30-May 1, 1981 Oi, L4
F Inspectors:
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K.E.PlumleegRadiationSpecialist
'date signed Approved by:
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EMM Mo 3/25[rn
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-P. TR Knapp,' Chief, Faci kf ty Radiological datefsigned Protection Section, T.echnical Inspection Branch Inspection Summary:
Inspection on April 30-May 1, 1981 (Report No. 50-219/81-15)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of licensee actions on NRC:IE Bulletin No. 80-10, " Contamination of Nonradioactive
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Systems and Resulting Potential for Unmonitored, Uncontrolled Release to Environment", including:
the identification of interfaces between nonradicactive and radioactive systems; the sampling program to identify any occurrence of an unmonitored release path; any interim measurements or safety evaluations, necessary to use nonradioactive systems that have become radioactive; and any scheduled corrective actions. This inspection involved 10 inspector-hours onsite by one NRC regional based inspector.
Results: No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
8204090397 820324 PDR ADOCK 0 N3OO219 G
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I DETAILS 1.
Persons Contacted G. Busch, Licensing Engineer J. Carroll, Jr., Director, Station Operations K. Fickeissen, Manager, Plant Engineering S. Fuller, Supervisor, Site QA R. Garner, Programs and Controls Director B. Somers, Group Chemical Supervisor J. Sullivan, Unit Superintendent D. Turner, Manager, Radiation Control 2.
Review of Licensee Action on Bulletin 80-10 a.
Bulletin 80-10 required the following licensee actions within 45 days of the date of the Bulletin:
(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 a subsequent unmonitored or uncontrolled liquid or, gaseous release; (3) Restriction of the use of any_such systems that is or becomes contaminated, until the cause has been identified and corrected
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and the system has been decontaminated; or if the 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, (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 specifi-cations, b.
Required Notification and Documentation Bulletin 80-10 required, within an additional 15 days of the 45 day action date, a licensee letter notifying the Director of the NRC Region I office of the completion of the required actions and the availability of documentation for onsite review of.he specifications taken to comply with the Bulletin.
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I c.
Inspection of Documents The inspector reviewed copies of the following documents maintained i
pursuant to Bulletin 80-10:
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Document Title or Subject of Document Date Due Date
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Notification to Director, NRC Region I 7/1/80*
7/5/80
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S&W** Task No. 018***
6/17/80 6/20/80 l
PD-3.8.020, " Sampling Schedule" 5/8/80 6/20/80 S&W Safety Evaluation Auxiliary Boiler 7/17/80 N/A JCPL Safety Evaluation RBCCW 8/4/80 N/A JCPL Safety Evaluation RWCCW 8/4/80 N/A JCPL Safety Evaluation Auxiliary Boiler 8/4/80 N/A
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Reviews of these documents verified that the licensee had provided the required information.
d.
Summary of Licensee Systems and Actions The above referenced S&W Report, dated 6/17/80, reviewed the following systems and recommended the additional actions, shown
below to comply with the requirements of Bulletin 80-10.
Present Status i
Additional Radiation Sample Action i
Nonradioactive System Monitor Program Required Emergency Service Water Yes No None Service Water Yes No None
- Received by NRC on July 5, 1980.
- "S&W" refers to Stone & Webster Engineering Corporation.
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- Consultant's report on identified systems and interfaces.
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Present Status Additional Radiation Sample Action Nonradioactive System Monitor Program Required Circulating Water No No None Chlorination No No None Vacuum Priming No No None Well & Domestic Water No Yes None Dilution System No No None Fire Protection No No None Makeup Water No Yes None TBCCW No Yes None RBCCW Yes Yes Relocate Monitor Nitrogen Inerting, Purge No No None
& MU Inst. Service & Breathing No No Sample Prog' ram Air Sewage Treatment No No None Auxiliary Boilers No Yes Sample / Monitor Exhaust Oil Transfer & Purification No Yes None Stator Cooling No No None Liquid Poison No No None
. Isolation Condenser Yes Yes None Turbine Oil No.
Yes None Rx Building Ventilation Yes No None Turbine Building Ventilation No No None Machine Shop Ventilation No No Sample and/or Monitor Office Building Ventilation No No None Radwaste Closed Cooling Water No Yes None Screen Wash No No None Feed Pump Rcom Ventilation No No Install Monitor Sump 1-5 No No Sample and/or Monitor The S&W Report indicated that drawings for several systems should be updated to as-built status to assure that flow from one system to another can be properly traced.
These systems are:
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Floor and Equipment drain Sewage treatment Sumps Makeup water demineralizer The report also stated that an administrative procedure should be prepared to control the use of temporary hose and/or piping in the plant.
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The licensee representative stated during the exit interview that monitoring or sampling will be implemented in the sanitary sewer discharge line and in the 30-inch diameter header that presently receives treated sanitary sewage liquid effluent, nonradioactive equipment drainage, and roof and yard drainage.
On or about July 1,1981, the licensee planned to commence discharging raw sanitary sewage into an offsite publicly-owned sanitary sewage and treatment system. At the time of this inspection, the onsite treatment system remained in service.
No existing interface was identified with any radioactive system, however, the possibility of misuse was considered sufficient to justify discharge monitoring or sampling.
The equipment drainage into the 30-inch header was monitored but other in-flow was not monitored.
Specific examples were documented in Report No. 50-219/81-09, Paragraph 9, involving radioactive liquid leakage that was not entirely collected in the radioactive liquid waste system.
These examples demonstrated a potential to leak into the 30-inch header and to the discharge canal.
The in-flow to the 30-inch header was being sampled periodically at a point which did not include the treated sewage effluent, reof, and yard drainage. The review of this system may result in the selection of a new sample point.
The implementation of sampling of the sewage and of the 30-inch header discharge will be followed up on a subsequent inspection.
(219/81-15-01)
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The inspector reviewed the applicable sections of the FSAR and plant
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drawings.
The consultants (S&W) drawing file was not reviewed inasmuch as it was maintained in Cherry Hill, New Jersey.
Within the scope of this inspection, no omissions of required actions were identified.
,i e.
Review of Licensee Sampling Program The licensee reported the following liquid sample analyses obtained during March or April,1981.
System Identified Isotopes (uCi/ml)
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NDA*
Service Water NDA Well & Domestic Water NDA Makeup Water NDA
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- NDA - No detectable reactor activation or fission products.
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System Identified Isotopes (UCi/ml)
Turbine Building Closed Cooling H-3 3.96 E-6 Water (TBCCW)
Cs-137 2.56 E-6
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Co-60 2.40 E-6 Reactor Building Closed Cooling H-3 8.63 E-6 Water (RBCCW)
Xe-133 9.98 E-6 Xe-135 8.08 E-6 Co-60 6.13 E-6
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I-133 4.61 E-6 Cs-137 1.33 E-6 Auxiliary Boilers Cs-137 9.21 E-7
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Isolation Condensers H-3 3.71 E-4
Augmented Offgas Building H-3 1.65 E-6
Closed Cooling Water (A0GCCW)
Co-60 2.05 E-6 l
Mn-54 6.12 E-7
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New Radwaste Building Closed H-3 7.72 E-7 Cooling Water (RWCCW)
Co-60 8.68 E-6 The inspector noted that the sample analysis for RBCCW, but for no other system, exceeded the 10 CFR 20, Appendix B, limit for release to unrestricted areas.
None of the analyses exceeded the values used in the safety evaluations.
Specifically, the evaluations showed the accidental discharge of the water contained in the RBCCW would not exceed the accidental release of' liquid radioactive material evaluated in the Technical. Specifications Bases. The S&W report indicated that the RBCCW monitor sensitivity is adequate to identify increases in RBCCW contamination. Any significant increase in the concentration of radioactive materials in the RBCCW will be reviewed by the licensee.
In addition to the gaseous sampling program described in the table in paragraph 2.d above, air sampling was being conducted throughout the facility during the inspection in order to control working hazards during the outage. The inspector observed that no releases to the environment exceeded the 10 CFR 20, Appendix B, limit for release to unrestricted areas.
The inspector reviewed the indications on the ventilation system
monitors.
No omissions of required sampling were identified. No items of noncompliance were identified.
5.
Exit Interview
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The inspector met with the individuals listed in paragraph 1 at the completion of the inspection on May 1, 1981.
The inspector reviewed the
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irispection findings.
The licensee representative committed to either periodically sample or monitor the sanitary sewer and the 30-inch diameter drain header.
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