ML17278B057

Notice of Violation from Insp on 860811-21,0902-05 & 15-19

ML17278B057
Person / Time
Site:	Columbia
Issue date:	10/20/1986
From:	Scarano R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17278B056	List: ML17278B055 ML17278B057
References
50-397-86-28, NUDOCS 8611040409
Download: ML17278B057 (6)

Text

APPENDIX A NOTICE OF VIOLATION Mashington Public Power Supply System Docket Number 50-397 P.

O. Box 968 Richland Washington 99352 As a result of the inspection conducted during the period of August ll to September 19, 1986, and in accordance with NRC Enforcement Policy 10 CFR Part.

2, Appendix C, the following violations were identified.,

A.

Technical Specifications, Section 6.8.1 reads in part:

"written procedures shall be established, implemented and maintained covering the activities referenced below:,(a)'he applicable procedures recommended in Appendix A of Regulatory Guide (R.G.) 1.33, Revision 2, 1978."

RG 1.33, Appendix A, item 8(a)(2) lists examples of equipment for which procedures should be provided to insure measur'ing and testing devices are properly controlled, calibrated, and adjusted at specified periods to maintain, accuracy.

Item 8(a)(2)(aa), includes equipment such as area, portable and airborne radiatidn monitoring 'instruments.

Health Physics Program Description (HPD) 3.l,9, Revision 1, dated 9-11-81, paragraph 3.1.'9-3, "Portable Monitoring Instrumentation,"

reads:

"Portable radiation monitoring instruments shall be calibrated every six months as a minimum and any time a field check indicates an out-of-date calibration condition."

Contrary to the above, On August 11,

1986, Remote Area Monitor (RM) - 16, Serial Number RM-104, located on the 501'evel of the Reactor Building, was in operation and not in current calibration.

Calibration was due on June 4, 1986.

2).

On August 12,

1986, Beta Air Monitor, Serial Number, C005739 in operation on the 441'evel of the Turbine Building was not in current calibration.

Calibration was due on February 1,

1986.

This is a Severity I.evel IV Violation (Supplement 1).

B).

Technical Specifications, Section 6.12, "High Radiation Areas," requires that each area in which the intensity of radiation is greater than 100 mrem/hr shall be barricaded and conspicuously posted as a High Radiation Area.

Contrary to the above, on September 16, 1986, the NRC inspectors identified the following:

1)

In the northeast stairwell of the Turbine Building whole body radiation levels up to 110 mrem/hr were measured between the 441'nd 471'evel and the area was not posted as a High Radiation Area.

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2).

A work platform located immediately adjacent to the Main Condenser (south side, center, between pillars 10 and

11) on the 441'evel of the Turbine Building, having whole body radi'ation levels measured at up to 140 mrem/hr, was not posted as a high radiation area.

1 3).

A doorway (No. T-306), 'located on the 501'evel of the Turbine Building providing access to the low pressure turbine area of the 501'evel having general whole body radiation levels measured at up to 800 mrem/hr, was not posted as a high radiation area.

This is a Severity Level IV Violation (Supplement 1).

C).

10 CFR Part 20.203(b),

"Caution. Signs, Labels, Signals, and Controls,"

requires that each area"in which a major portion, of the body could receive in any one hour a dose in excess of 5 mrem, or in any fiv'e consecutive days a dose in excess, of 100 mrem shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words.

u Caution Radiation. Area Contrary to the above, on September 16, 1986, the personnel access leading to the Main Condenser area 'and its adjoining stairwell on the 441'evel of the Turbine Building having whole body radiation levels measured at 3 to 100 mrem/hr, was not conspicuously posted as a radiation area in that the posting was on the swing gate and could not be seen because the gate was open against a wall.

This is a Severity Level IV Violation (Supplement IV).

D) 10 CFR 20.201(b) requires that surveys be made as may be necessary to comply with all sections of 10 CFR Part 20.

As defined in 10 CFR 20.201(a),

"survey" means an evaluation of the radiation hazards incident to the production, use, release,

disposal, or presence of radioactive materials or other sources of radiation under a specific set of conditions.

Contrary to this requirement, surveys were not made as necessary to assure compliance with 10 CFR Part 20.101(a),

"Radiation Dose Standards for Individuals in Restricted Areas."

Specifically, as of the day of this inspection, September 16, 1986, radiation surveys were not made in the Northeast Stairwell of the Turbine Building between January 1 and September l5, 1986, as necessary to adequately control personnel exposures to radiation (see item B.l above).

This is a Severity Level IV Violation (Supplement IV).

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Pursuant to the provisions of 10 CPR 2.201, Washington Public Power Supply System is hereby required to submit to this office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation:

(1) the reason for the violation if

admitted, (2) the corrective steps which have been taken and the results

achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

Where good, cause is shown, consideration will be given to extending the response time.

OCT 20 >986 H

Dated

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R. A. Scarano, irector Division of Radiation Safety and Safeguards'l lI L

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