IR 05000317/1981029
| ML20052D207 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/15/1982 |
| From: | Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052D205 | List: |
| References | |
| 50-317-82-29, 50-318-81-27, IEB-80-10, NUDOCS 8205060362 | |
| Download: ML20052D207 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION I
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50-317/81-29 Report No. 50-318/81-27 50-317 Docket No. 50-318 0P7.-53 Category'
C License No. DP't-60 Priority _
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Licensee:
Baltimore Gas & Electric _ Company
P.O. Box 1475
Baltia_ ore, Maryland ~21203 s
Facility Name:
[alv)rtCliffsNuclearPowerPlant, Units 1&2 l
Inspection at:
8.usby, Maryknd
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Inspection conducted: August 17 to 21, 1981 Inspector:
M/ / V/b--
'K!E.'Pluinlee, Radiation Specialist
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Approved by:
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P.J.Knapp, Chief,Tacility
date 7,igned Radiological Protection Section
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Technical Inspection Branch ' /,
Inspection Summary:
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Combined Inspection on August 17 to 21, 1981 (Combined Report Nos. 50-317/81-29 and 50-318/81-27)
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Areas Inspected:
Routine, unannounced safety inspe'ction by a regicn based inspector, of licensee actions on NRC:IE Bulletin No. 80-10, " Contamination of Nonradio-active Systems and Resulting Potentici for Unmonitored, Uncontrolled Release to Environment," including:
identification of interfaces between nonradioactive and radioactive systems, evaluations and consideration of interim measures in
.i the event that nonradioactive systems become radioactive, corrective actions,
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implementation of the sampling program for unmonitored potential release paths, E
and documentation. The inspection involved 10 inspector-hours
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onsite by one NRC region based inspector.
Results: No items of noncompliance were identified.
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?O F205060362 820421
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DETAILS 1.
Persons Contacted A. Barth, Quality Assurance (QA) Engineer
- D. Bowman, Engineer, Radiation Safety P. Crinigan, Engineer, Radiation Chemistry
- G. Brobst, General Supervisor, Chemistry
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- R. Heibel, Supervisor, Technical Support
- A. Hetrick, Engineer, Radiation Safety
- J. Lenhart, Jr., Supervisor, Radiation Safety
- N. Millis, General Supervisor, Radiation Safety
- E. Reimer, Plant Health Physicist
- L. Russell, Plant Superintendent
- L. Smialek, Senior Engineer, Radiation Safety J. Speciale, Supervisor of Chemistry
- T. Sydnor, General Superintendent, Operations OA P. Wright, Training Specialist
- Denotes those present at the exit interview conducted on August 21, 1981.
2.
Verification of Licensee Documentation a.
Required Actions
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Bulletin 80-10 required the following licensee actions,within 45 days of the date of the Bulletin (May 6,1980):
(1)
Identification of systems that are considered nonradioactive, or are described as nonradioactive in the Final Safety Analysis Report (FSAR), but could possibly become radioactive through interfaces with radioactive systems; (2) Establish 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; (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 iccordance with the requirements of 10 CFR 50.59; i
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(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 day time frame, a licensee letter notifying the Administrator of the NRC Region I Office of the completion of the required actions and the availability of documentation for onsite review of the specifics taken to comply with the Bulletin requirements.
The licensee letter to Region I, dated June 16, 1980, stated that the above actions were completed.
In order to verify the completion of the above actions, the inspector reviewed the following documents and drawings:
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Technical Specifications Semi-Annual Effluent Release Reports for the periods July 1 to December 31, 1980, and January 1 to June 30, 1981 Memorandum, "10 CFR 50.59 Safety Evaluations," dated June 19, 1980, L. B. Russell to R. F. Ash Procedure RCP-1-219, " Plant Unmonitored Effluent Activity Surveillance Program," dated July 16, 1980
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Chemistry Log Sheets (Various sampling)
Worksheets showing the monitor and sample points, flow paths, and interfaces for:
Auxiliary Boiler System Condensate Collection System Demineralized Water System Nitrogen System Service Water System Drawings for the above systems i
FSAR descriptions of the above systems FSAR Table 11.9.1-2 Process and Effluent Radiation Monitors FSAR Table 11.10.2-1 Radiation Monitors on Plant Effluent Streams The above information identified the interfaces between the nonradioactive and radioactive systems.
There is one slightly l
concaminated system, the component cooling water system (concen-tration about 1E-6 uCi/ml). The licensee representative stated that
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the present water contamination is the result of material that plated-out during a previous interface leak, rather than an existing leak that could be corrected. The system has been flushed out to
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remove as much contamination as feasible by this technique.
The licensee has reviewed the safety of continued operation of this system and 'found it to.be acceptable.
In addition, an evaluation was made of the likely consequences of any potential contamination event in the auxiliary boiler system, the demineralized. water system, the service water system and the plant heating water system (Reference Combined Inspection Report Nos. 50-317/80-22 and 50-318/80-18).
Based on the above documentation, and on interviews with plant personnel, the licensee has complied with Bulletin No. 80-10 requirements.
3.
Summary of the Monitoring and Sampling Program
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a.
Water Systems The plant draws water from the Chesapeake Bay) through the plant intake and returns it to the discharge canal.
Discharge monitors are provided for systems that interface with radioactive systems, with the exception that certain drain system tanks are sampled and evaluated before each release, rather than monitored.
Three plant wells provide fresh water for domestic use, fire protection, and feedwater to the demineralized water system.
The licensee's program for monitoring and sampling the nonradioactive water systems is summarized in Table.
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Table I Nonradioactive Water Systems Summary Monitored Sampling Sample Analysis System or Sampled Frequency (uCi/ml)
Circulating Water System Sampled Monthly
<5E-8*
Service Water System Both Weekly
<5E-8*
Monitor Tank System Sampled Each Release
~7E-8**
Sewage System Final Effluent Sampled Monthly
<5E-8*
Steam Generator Blowdown Both 3X Daily
<5E-8*
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Component Cooling System Both Weekly
~1E-6***
Demineralized Water System Sampled Weekly
<5E-8*
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Auxiliary Boiler / Nuclear Steam Supply System Sampled Weekly
<5E-8*
Plant Heating Water System Sampled Weekly
<5E-8*
Storm Drain System Neither Fire Protection System Neither Waste Neutralizing Tank Sampled Monthly
<5E-8*
Yard Oil Interceptor Sampled Monthly
<5E-8*
Diesel Generating Room Waste Oil Collector Sampled-Monthly
<5E-8*
Nominal Lower Limit of detection, as sampled.
Variable - the value shown was the maximum reported during April through
June, 1981.
Variable generally below 1E-6.
Occasionally a larger value is
reported, up to 1E-5.
The licensee representative stated the above analyses were typical of routine plant operating conditions.
Review of the radiation monitor indications and trip settings, identified no changes from the present FSAR description.
No unacceptable conditions were identified.
b.
Ventilation Systems The Unit 1 and Unit 2 main plant vents, are monitored separately and also sampled periodically. Certain area ventilation systems, as depicted in Table II, are also monitore.
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j Table II Ventilation System Summary Monitor Sample Sensitivity Analyses *
System Monitored or Sampled (uC1/ml)
(uC1/ml)
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Unit main vent Both Noble gas **
<3E-6
<4E-7 ***
Both Particulates
<4E-10
<lE-13 ***
~1E-13
~4E-12 ***
Containment atmosphere Both Noble gas **
<3E-6 (3tl)E-3 Both Particulates
<3E-6 (413)E-7 (Grab Sample)
~1E-13 (9 1)E-9 Auxiliary Building area ventilation:
Access Control Monitored Gaseous **
<3E-6 (411)E-10
ECCS Pump Room Monitored Gaseous **
<3E-6 (3tl)E-10 Fuel Handling Monitored Gaseous **
<3E-6
~1E-10 Condenser Vacuum Pump Discharge Monitored **** Gaseous **
<1E-6
~1E-5
- Unit 1 and Unit 2 samples fall in the range shown.
- The monitor uses a Geiger-Mueller type detector.
- Post-filter sample.
- Monitor sample lines being rerouted (monitor temporarily out of service)
A licensee representative stated that the above analyses were typical of routine plant operating conditions.
The licensee has recently installed a computerized system to record the plant vent releases, and to calculate the exposures downwind.
The range of the main plant vent monitor for each unit is to be extended as part of TMI Lessons Learned follow-up.
Two previous reviews of effluent monitoring were documented in combined NRC Region I Reports 50-317/80-09 and 50-318/80-07, and 50-317/80-22 and 50-318/80-18.
Review of the above systems did not iaentify any errors in trip settings or calibrations.
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No unacceptable conditions were identified.
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c.
Compressed Air Systems (Nitrogen System)
The compressed air systems extend throughout the facility. The air compressors are located in the Turbine Building. The service air and instrument air systems are designed for mutual backup use in the event of a compressor failure.
The service air system may be used for the breathing air supply.
The air supply headers are sampled-and analyzed before use when supplying respirators.
Check valves have been installed in the nitrogen supply system header to prevent backflow of contaminated gas, or water.
No undocumented changes from the system design were identified.
No unacceptable conditions were identified.
4.
Exit Interview The inspector met with licensee's representatives, as denoted in paragraph 1, at the conclusion of the inspection to discuss inspection findings.
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