IR 05000317/1982013

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IE Insp Repts 50-317/82-13 & 50-318/82-11 on 820511-14.No Noncompliance Noted.Major Areas Inspected:Radiation Safety Program,Including Action on Previously Identified Items,Unit 1 Refueling Activities & Radwaste & Effluent Sys
ML20028F483
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/12/1983
From: Plumlee K, Shanbaky M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20028F478 List:
References
50-317-82-13, 50-318-82-11, NUDOCS 8302010384
Download: ML20028F483 (4)


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U. S. NUCLEAR-REGULATORY COMMISSION

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- REGION I 50-317/82-13

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Report No. 50-318/82-11'

50-317 Docket No. 50-318 DPR-53 C

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License No. DPR-69 Priority

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Category C

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Licensee: Baltimore Gas & Electric Company P. O. Box 1475_..

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Baltf nore, Maryland 21203

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Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 & 2

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Inspection At: Lusby, Maryland Inspection Conducted: May11-1N,1982

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Inspectors:

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"K4 Plumlee~, Radta'tibrr-Specialist date Approved by:

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///2.[M M. Shanbafy, Chief, Facilities Radiation

' dat'e Protection Section, Radiological Protection Branch Inspection Summary: Combined Inspection, May 11-14,1982 (Report No.

50-317/82-13; 50-318/82-11)'

Areas Inspected:

Routine,lnannouncedsafetyinspection,byoneNRCregion-based inspector of the radiation safety program, including:

action on previ-ously identified items,_Orif t-1. refueling activities, radioactive effluent and waste systems, and transportation. This inspection involved 30 inspector-hours onsite by one NRC region-based inspector.

Results: No violatichs were identified.

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8302010384 830117 PDR ADOCK 05000317-G PDR

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DETAILS 1.

Persons Contacted

  • J. Carlson, Supervisor, Radiation Control
  • A. Hetrick, Engineer, Radiation Safety
  • D. Latham, Principal Engineer-Operational Licensing and Safety
  • N. Millis, General Supervisor, Radiation Safety
  • E. Reimer, Plant Health Physicist
  • L. Smialek, Senior Plant Health Physicist
  • denotes presence at exit interview on May 14, 1982.

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Inspection of..icensee Actions on Previously Identified Items 2.1 Previous Inspection Items (0 pen) Violation (317/80-16-04; 318/80-15-03):

Failure to process liquid effluents in accordance with the 1.25 Curie action level of the Technical Specifications, during the fourth calendar quarter of 1979. The licensee has not reached this action level since 1979.

Instead of the miscallaneous waste evaporator, the licensee plans to keep available a new lineup, through a filter-demineralizer, to process liquid effluents should the action level be reached.

  • Although installed for another use, the filter-demineralizer is available on a priority basis.

This change was not yet included in the Final Safety Analysis Report (FSAR) and in the bases of the Safety Evalua;. ion Report (SER). The licensee demonstration of acceptability will be reviewed in accor-

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dance with 10 CFR 50.59, " Changes, tests and experiments".

(0 pen) Unresoived Item (317/80-16-06; 318/80-15-05):

Installation of post-accident monitors and sampling equipment. The licensee

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expected to declare this equipment operational within a few days following this inspection. The acceptance tests will be reviewed on a routine inspection.

(Closed) Inspection Follow Item (318/81-01-02):

Review of the corrected records of individuals who experienced dosimetry discrep-l ancies. A review of the corrected records of ten individuals, following dosimetry discrepancies, did not identify any violations.

l 2.2 Previous Program Evaluations The inspector determined by interviews of per:,onnel, and by document reviews, that the licensee periodically audited and reviewed the radiation protection program, and implemented the resulting recommen-dations. The inspector also verified that the Health Physics.

Appraisal (HPA) Inspection (Combined Report No. 50-317/80-09; 50-318/80-07), and the Institute of Nuclear Power Operations (INPO)

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recommendations were being implemented on a schedule. These recommenda-tions involved the organization, assignments of responsibilities, management controls, procedures, training and qualification of personnel, ALARA program, neutron survey instrument calibrations, whole body counter calibrations, and the radioactive waste transpor-tation program.

No violations were identified.

2.3 Licensee Investigation The inspector reviewed a draft event report of a spent resin spill on April 13, 1982.

The inspector noted the responsibility for the report was assigned to a radiation safety engineer, the investigation procedure was observed, and the apparent contributing factors were being iden-tified.

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No violations were identified.

3.

Inspection _.of Unit-1 Refueling and Maintenance Activities 3.1 ALARA Program The licensee stated.that, during the outage, ALARA reviews were made of each job and procedure involving significant exposures to person-nel. Daily and weekly follow-up was provided on all outage jobs.

Review of current ALARA records, and observation of ALARA practices on ten jobs, did not identify any violations.

3.2 Radiation Control Procedures (RCPs)

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During facility tours to observe the acceptability of, and adherence

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to, the RCPs, the inspector noticed two shoe-cover change points without stepoff pads or equiva;ent controls. These were in'an area l

near the entranc-to the biolcgical shield, and the containment entrance / exit.

The first required a change of rubbers, but none were stocked there. Discards were neither identified nor surveyed to control their reuse on either side of this change point. The discards on exiting containment were dropped into the supply barrel for those entering, without a survey.

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On May 14, 1982, the licensee reviewed RCP No. 3-705, "Special l

Maintenance Radiological Control Procedure," to improve the shoe-

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cover change points and the reuse of discarded shoe-covers.

No violations were identified.

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3.3 Other Padiation Protection Functions The inspector reviewed selected records and procedures, interviewed personnel, toured the facility and observed the conduct of activ-ities to determine that the following functions were performed in compliance with the regulations and the procedures.

Qualifying and training workers Limiting internal and external exposures Air sampling Surveying Controlling access to hazardous areas Controlling radioactive materials Controlling radiation work practices Planning and preparing for major tasks Providing acceptable instruments and equipmeat No violations were identified.

4.

Inspection of Radioactive Effluent and Waste Systems The inspector reviewed selected records, release permits, effluent reports and procedures, interviewed personnel, and observed the status of the following equipment, to determine compliance with the regulations and accepted guides and standards.

Effluent monitors and control instruments Air cleaning systems and ventilation systems Reactor coolant monitoring and sampling Liquid waste processing and storage Waste gas decay system No unreviewed changes to these system: were identified.

No violations were identified.

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Inspection of the Transportation Program The irspector reviewed selected records and ccpies of licenses, certifi-cates, and drawings maintained by the licensee; and observed the col-lection and packaging of radioactive materials for transport. The inspector surveyed trailers loaded with radioactive materials packages.

No violations were identified.

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Exit Interview The inspeciar met with the licensee representatives, denoted in paragraph 1, at the conclusion of the inspection.

The inspector reviewec the inspection findings documented above.

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