IR 05000317/1985035
| ML20140B709 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/17/1986 |
| From: | Clemons P, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20140B698 | List: |
| References | |
| 50-317-85-35, 50-318-85-35, NUDOCS 8601270098 | |
| Download: ML20140B709 (4) | |
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O-U.S. NUCLEAR REGULATORY COMMISSION
REGION I
50-317/85-35 Report No.
50-318/85-35 50-317 Docket No.
50-318 OPR-53 License No. DPR-69 Priority Category C
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Licensee: Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection At: Lusby, Maryland Inspection Conducted: December 16-19, 1985 Inspectors:
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j2N P. Clemons, Radiation Specialist d te/
Approved by: M k. hlb
% )h l9R6 M. Shanbaky, Chief 4;9 dWte PWR Radiation Safety Section Inspection Summary:
Inspection _on December 16-19, 1985 (Combined Report Nos. 50-317/85-35 and 50-3T8785-35)
Areas Inspected: Routine, unannounced inspection of the~ radiation protection activities including:
training, source inventory and leak tests, instrument maintenance and calibration, posting and labeling and outage exposures. This inspection involved 29 inspector hours on site by one regionally-based inspector.
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Results: No violations were identified.
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O DETAILS 1.0 Persons Contacted 1.1 Licensee Personnel P. Crinigan, General Supervisor - Chemistry J. Carlson, Assistant General Supervisor - Radiation Control P. Rizzo, Supervisor - Materials Processing L. Smialek, Senior Plant Health Physicist W. Putnam, Senior Quality Assurance Auditor W. Cartwright, Engineer - Plant Chemistry B. Watson, Plant Health Physicist S. Cowne, Licensing Engineer 1.2 NRC Personnel T. Foley, Senior Resident Inspector Other licensee employees were contacted and interviewed during the inspection.
2.0 Purpose The purpose of this routine inspection was to review the licensee's radiation protection activities with respect to the following elements:
Review of training of licensee personnel;
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Review of source inventory and leak tests;
Review of instrument maintenance and calibration;
Review of posting and labeling; and
Review on outage exposures.
- 3.0 Training The licensee's training program for Radiological Controls Technicians was, reviewed against criteria contained in Technical Specification 6.4,
" Training"andProcedureNo.CCI-617,"RadiationSafetySectionTrainingj and Qualification".
The licensee's performance relative to these criteria was determined by interviewing the Technical Training Supervisor, and the Supervisor of Radiological Controls-Operations, and by reviewing appropriate documents.
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The licensee's training program for Radiological Control Technicians
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j appears to be adequate.
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Within the scope of this review, no violations were identified.
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4.
Posting and Labeling i
j The licensee's program for area posting and control was reviewed against
the criteria in 10 CFR 20.203, " Caution signs, labels, signals and j
controls".
l The licensee's performance relative to these criteria was determined from a tour of the Controlled Areas and from discussions with the staff I
members.
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i Throughout all of the areas inspected, posting and labeling were more
j than adequate.
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Within the scope of this review, no violations were identified.
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Source Inventory and Leak Test
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Radioactive source inventory and leak tests were reviewed against the
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criteria contained in Technical Specification 3/4.7.9, " Sealed Source a
Contamination". The licensee's performance relative to these criteria
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i was determined by interviewing Radiological Controls Personnel and by i
reviewing appropriate records.
Within the scope of this review, no violations were identified.
6.
Instrument Maintenance and Calibration I
l The licensee's program for the calibration and maintenance of portable
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I instruments was reviewed against criteria contained in:
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10 CFR 20.201, " Surveys";
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Reg Guide 8.6, " Standard Test Procedure for Geiger - Muller
Counters";
i ANSI-N323, " Radiation Protection Instrumentation Test and
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j Calibration"; and j
)t Licensee Operation and Calibration Procedures.
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The licensee's performance relative to these criteria was determined by
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discussions with Instrument and Control personnel, a Radiological
i Controls Supervisor and by reviewing appropriate records.
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Within the scope of this review, no violations were identified.
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Outage Exposure - ALARA During the pre planning activities for this most recent outage, the licensee's ALARA personnel predicted a projected exposure of 250 man-rem'.
The total exposure for the outage was 202 man-rem.
It should be noted that the licensee actually completed the outage with 197 man-rem, but upon resuming power, the licensee experienced a problem with a seal on a Reactor Coolant Pump, and the additional exposure was received making the necessary repairs.
The licensee's ALARA program is very effective, and must be recognized and commended.
8.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on December 19, 1985.
The inspector summarized the purpose and scope of the inspection, and the inspection
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findings. At no time during this inspection was written material provided
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to the licensee by the inspector, i
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