ML20039F653

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IE Insp Rept 50-409/81-18 on 811201-03.No Noncompliance Noted.Major Areas Inspected:Licensee Actions Taken in Response to Health Physics Appraisal & Previous Insp Findings
ML20039F653
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 12/22/1981
From: Greger L, Paul R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20039F648 List:
References
50-409-81-18, NUDOCS 8201130190
Download: ML20039F653 (4)


See also: IR 05000409/1981018

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-409/81-18

Docket No. 50-409

License No. DPR-45

Licensee: Dairyland Power Cooperative

2615 East Avenue - South

La Crosse, WI 54601

Facility Name: La Crosse Boiling' Water Reactor

Inspection At: La Crosse Boiling Water Reactor Site, Genoa, WI

Inspection Conducted: _ December 1-3, 1981

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Inspector: R

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L.R.Greger,Ch{iefh. 2'. Yrh/ W

Approved By:

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Facilities Radiation

Protection Section

Inspection Summary:

Inspection on December 1-3,-1981 (Report No. 50-409/81-18)

Areas Inspected: Routine, unannounced inspection of licensee actions

taken in response to Health Physics Appraisal and previous. inspection

findings. The inspection involved 22 inspector-hours onsite by one

NRC inspector.

Results: No items of noncompliance were identified.

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DETAILS

1.

Persons Contacted

  • P.

Shafer, Radiation Protcction Engineer

  • B. Zibung, Health and Safety Supervisor
  • M. Branch, NRC Senior Resident Inspector

The inspector also contacted other licensee employees including members

of the technical and engineering staffs.

  • Denotes those attending the exit meeting.

2.

General

This inspection, which began at 11:30 a.m. on December 1, 1981, was

conducted to examine the licensee's actions in response to Health

Physics Appraisal and previous inspection findings. The inspection

also included a plant tour and visual observations of facilities

and equipment, posting and labeling, and independent radiation

measurements made by tne inspector.

General housekeeping was adequate.

3.

Licenzee Action on Previous Inspection Findings

(Closed) Noncompliance Item (409/80-10-09): Failure to meet Technical Specifications 6.8.1 and 6.11, adherence to radiation protection re-

quirements. Procedures concerning tightening of ring lock nuts on

filled radwaste drums and posting of hot spots have been revised.

(Closed) Noncompliance Item (409/81-19-02): Failure to post a " Caution

Radiation Hot Spot" sign in an area containing a radiation field in

excess of technical specification limits. A locked barrier was in-

stalled, and a new procedure defining the use of hot spot stickers has

been developed.

4.

Monitoring

As noted during previous inspections, certain technical problems

concerning stack sampling need resolution. These items include

replacement of the tygon tubing on the noble gas iodine and

particular monitoring system with hard piping, calibration of the

SPING-4 with noble gas and iodine-131 standards, correction of the

SPING-4 computer memory loss, and revision of SPING-4 procedures

to include calculation of effluent concentrations in case of memory

loss. These matters will be reviewed at a future inspection.

Also, the effect of radiation on the operability of the SPING-4,

during an accident, in its present location was questioned. The

licensee reviewed the possibility of constructing a facility at a

different location to house both the SPING-4 and PING-3 units. On

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the basis of this review, they determined the construction of a new

building to be impractical. During this inspection, the licensee

stated they were still reviewing this matter and would, if necessary,

seek other alternatives to minimize the effect of radiation on monitor

operability during an accident.

(0 pen Item 409/81-11-01)

5.

Health Physirs Training

Since the previous inspection, the licensee has trained Health Physics

Technicians (HPT's) in revised emergency sampling procedures EPP 7

and 8.

Remaining commitments, made in response to the Health Physics

Appraisal (HPA) concerning training, include the rewriting of an

emargency sampling procedure (EPP 6) and the development of a train-

ing manual and implementing procedures.

(0 pen Items 409/81-11-02;

409/81-11-06)

6.

Internal Exposure Control

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Since the previous inspection, the licensee is continuing to upgrade

their internal and external exposure program in the following areas:

TLD beta dose equivalent calibrations; TLD gamma dose comparison with

pocket and film dosimeters; phantom construction for whole body

counter calibrations; new germanium detector calibration; and NIOSH

approved full and half mask respirators evaluations. This matter

will be reviewed further during a future inspection.

(0 pen Item

409/81-19-01)

7.

Instrumentation

Concerning the weaknesses in instrumentation noted during the HPA,

the licensee has revised instrument calibration procedures to include

the recommendations in ANSI N323-1978. Corrective actions still to

be accomplished include providing HP-210 friskers at the exit from the

Waste Treatment Building and calibration of the liquid effluent moni-

tors at m'21tiple poitats using varying concentrations of radionuclides

with similar isotopic compositions.

(0 pen Item 409/81-19-02)

8.

Procedural Adherence

During the HPA, it was noted that there was a need to resolve weak-

nesses concerning procedure coverage and adherence, including incon-

sistencies between Health and Safety Procedures (HSP's) and actual

practices.

The licensee initiated a review of all HSP's in early 1981. Several

have been revised and others will be revised through 1982. Several

of the revised procedures reviewed during this inspection were found

to be significantly improved. This matter will be reviewed during

future inspections.

(Open Item 409/81-18-01)

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9.

Plugged Drain Lines (LER 80-12)

In early November 1980, a drain header beneath the turbine building,

going to the 4500 gallon waste water storage tank, was discovered

blocked. The drain header serves equipment and floor drains in a

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portion cf the turbine building. The blockage apparently was intro-

duced several weeks earlier during injection of grout into voids

beneath the turbine building. Efforts to clean out the drain header

have been unsuccessful. Soil core samples taken beneath the butiding

showed low levels of contamination although. well water samples did

not indicate any radioactivity increases.

In October 1981, the licensee installed a sand point well and hand-

pump to draw water samples at different depths near the west wall

of the turbine building. The licensee located the sampling point

at a position which would provide representative sampling.

Several

attempts to obtain water from the well using 14 feet of tygon tubing

failed. More attempts will be made in the future. This matter was

discussed at the exit interview.

(0 pen Item 409/80-15-01)

10.

Exit Interview

The inspector met with licensee representatives (denoted in Section

1) at the conclusion of the inspection on December 3, 1981. The

inspector summarized the scope and findings of the inspection.

In

response to certain items discussed by the inspector, the licensee:

a.

Acknowledged the inspector's remarks concerning his review of

Health Physics Appraisal significant findings, and inspection

open items.

(Sections 4, 5, 6, 7 and 8)

b.

Stated that more attempts will be made tu collect water samples

from the well to determine if radioactive material had migrated

from under the turbine building.

(Section 9)

c.

Stated that the positica of the Radiation Protection Engineering

Assistant was expected to be filled in early 1982.

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