ML20127A598
| ML20127A598 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/14/1985 |
| From: | Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20127A587 | List: |
| References | |
| 50-409-85-01, 50-409-85-1, NUDOCS 8506210184 | |
| Download: ML20127A598 (5) | |
See also: IR 05000409/1985001
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-409/85010(DRSS)
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 (LACBWR)
Inspection At:
LACBWR Site, Genoa, WI
Inspection Conducted:
May 21-23 and 29, 1985
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Inspector: A.G.banuska
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Date
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Approved By:
M. C. Schumacher, Chief
Independent Measurements and
Date
Environmental Protection Section
_ Inspection Summary
Inspection on May 21-23 and 29, 1985 (Report No. 50-409/85010(DRSS))
Areas Inspected:
Routine, unannounced inspection of licensee followup of open
items, regulatory improvement items and items of noncompliance identified in
previous inspections; and implementation of 10 CFR Part 20 and 10 CFR Part 61
requirements for disposal of low level radioactive wastes including management
controls, quality control, tour of facility and implementation of waste form
and waste classification requirements.
The inspection involved 24 inspector-
hours onsite by one NRC inspector.
Results:
No apparent items of noncompliance were identified.
8506210184 850614
ADOCK 05000409
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DETAILS
1.
Persons Contacted
1J. Parkyn, Plant Superintendent
1P. Shafer, Radiation Protection Engineer
1L. Nelson, Health and Safety Supervisor
2R. Wery, Quality Assurance Supervisor
T. Sprester, Quality Control Technician
1 Attended exit interview on May 23, 1985.
2 Telephone contact on May 29, 1985.
2.
Licensee Action on Previous Inspection Findings
a.
(Closed) Violation Severity Level V (409/83-18-02) and repeat
Violation Severity Level V (409/84-15-04):
Failure to implement
written procedure HSP 13.1 " Counting Techniques and Data Handling,"
as required by Technical Specification 6.8.1.a.
Corrective actions
1 and additional
found to be incomplete during a previous inspection
corrective actions contained in the licensee's reply to Violation
409/84-15-04 have been adequately addressed.
Existing Internal
Proportional Counters (IPCs) have been recalibrated for all
geometries.
Two new IPCs, have been received onsite and the
licensee is in the process of ordering a third IPC.
Individual IPC
log books which contain a plot of daily efficiency checks using new
Cs-137 standards were in use, up to date and indicated periodic
management review.
b.
(0 pen) Open Item (409/82-17-04):
Improve quality control of
environmental monitoring analytical measurements.
Procedure
HSP-03.2 "Interlaboratory Comparisons for Radioenvironmental
Monitoring Program" was rewritten to include radiochemistry analysis
and reissued as HSP-02.13 "Interlaboratory Comparison Program for
Environmental and Radiochemistry Analysis" Issue Notice O dated
December 3, 1984.
The licensee is engaged in cross check programs
with a contractor and has expanded his program with the EPA to
include alpha, beta, Sr-90, and Cs-137 in an air particulate and
alpha / beta, H-3, I-131 and a gamma scan each in liquid.
January
results of alpha / beta in liquid were acceptable and March and April
air particulate and I-131 in liquid respectively have not been
received.
The licensee now lists specific MDAs as required in his annual
environmental monitoring report and is revising HSP 03.1 and his
ODCM to include the requirement for vegetation sampling so the
description of the REMP program agrees with the program required
by new technical specifications.
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Inspection Report 50-409/83-18
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c.
(Closed) Open Item (409/84-15-01):
Document various criteria used
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for rejection of environmental results determined by the ifcensee.
Procedure HSP-03.4 " LAC 8WR Environmental Monitoring Program - Sample
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Preparation, Analysis, and Data Review" Section 4 prescribes the
steps necessary to be performed in preparing the gamma spectroscopy
system for counting (energy i 1 kev and activities * 6%) and
Section 6 states the parameters to be reviewed for each printout
to ensure accuracy of reported results (identifying peak i 1.5 kev
and FWHM less than specific values dependent on peak energy).
The
analytical printout, in addition to being reviewed by the Health
Physics analyst, is reviewed by the Health and Safety Supervisor (HSS)
and results approved or disapproved. Any results disapproved by the
HSS, or at the request of.the Radiation Protection Engineer (RPE) or
corporate office Director of Environmental Affairs based their review
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of the draft annual REMP report will be noted on the individual
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printout with an explanation and the initials of the HSS.
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d.
(Closed) Open Item (409/84-15-02):
Explore background variability
at.the environmental detector (Detector No. 3) by taking additional
measurements during the day.
Three hour background spectra (10)
were collected every four hours between February 23, 1985 @ 0152 and
February 24, 1985 0 1352.
Results showed a maximum deviation from
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the average Co-60 (pC1) measured of 20% and an average deviation of
8.7% from which the licensee concluded that the background Co-60
variation is slight and should not significantly affect the
environmental data.
e.
(Closed) Regulatory Improvement Program Open Item (409/RP-000-1):
Establish a program to provide controls for storage, use, transfer,
and disposal of chemicals.
The " Reagent Inventory Checklist" which
indicated that weekly inventories had been missed 33% of the time in
1984 was examined and.found to be complete.
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(Closed) Regulatory Improvement Program Open Item (409/RP-000-2):
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. Modify chemistry log sheets to include limits for all applicable
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parameters.
The licensee determined that the number of analyses
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performed made it~ impractical to preprint all administrative and
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technical limits on the L40 log sheets.
Instead, the licensee has
established a set of plastic covered reference tables showing the
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applicable limits for all analyses performed.
This reference set
will be used by the analyst who will continue to write in the limits
applicable for each L40 log sheet.
g.
(0 pen) Regulatory Improvement Program Open Item (409/RP-00Q-1):
Expand QA program to provide check on quality of radiological and
nonradiological analyses.
The licensee continues to have difficulty
with chloride analyses.
Fourth quarter 1984 cross check results
with the corporate chemistry group although high indicated some
improvement in analysis.
Results performed in May 1985 using a
newly purchased chloride electrode in an attempt to correct this
problem were worse than the previous cross check and were all low.
The inspector discussed independent verification of the adequacy of
the procedure being used, precision tests along with accuracy tests,
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adaptation of another analytical method and the significance of
technician inability to perform an analysis that is common in other
power plants.
The licensee will continue to investigate this
problem.
3.
Organization and Management Controls
The inspector reviewed the administration and management of the licensee's
radwaste program.
Administrative Control Procedure 14.0 " Handling, Storage
and Shipment of Radioactive Material" specifies that the Health and Safety
Supervisor / Radiation Protection Engineer are responsible for ensuring that-
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all aspects of State and Federal regulations concerning handling, storage,
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and shipping of radioactive material are covered while the material is
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located on or. leaving the LACBWR site.
The Health and Safety Department is responsible for the overall operation
during waste shipments which may include the Operations, Maintenance and
Quality Control Departments.
4.
' Waste Classification and Form
The inspector reviewed the status of the licensee's implementation of the
requirements of 10 CFR 20 and 10 CFR 61 applicable to low-level radwaste
classification, waste form and stabilization.
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The licensee has made four shipments to date since December 27, 1983, the
effective date of the new regulations.
The licensee used High Integrity
Containers (HICs) for Class C shipments made to Barnwell, South Carolina
in June 1984 and January 1985.
Two class A shipments were made of waste
compacted in 55 gallon drums, and in high level 17H DOT drums.
The
inspector reviewed the paperwork package of the four shipments.
All
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appeared to have been properly classified.
Procedure HSP-04.1 which governs the shipment of radioactive material is
cumbersome and deals for the most part with the mechanism for physically
preparing a spent resin shipment.
It does not address DAW shipments in
55 gallon drums.
Although this procedure references 10 CFR 20.311 and
10 CFR 61 and contains a modified 10 CFR 61.55 waste classification table
it is inadequate in providing guidance for determining the correct waste
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. classification nor does it direct one to another applicable procedure.
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The licensee is in the process of revising his radioactive materials
shipment procedures to address applicable elements of 10 CFR 61.
(0 pen
Item 409/85010-01)
The licensee has established scaling factors for use in waste classifica-
tion based on SAI analysis of samples from the first shipments.
DAW was
assumed to have the same activity distribution as an SAI analyzed sample
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of reactor coolant with total activity determined from direct radiation
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measurements on the shipped drum.
The ifcensee plans to have the
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contractor analyse one sample per waste stream each year.
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5.
Facility Tour and Quality Control
The inspector toured the licensee's radwaste facility.
No problems were
identified.
Quality Control inspections are performed for each shipment for specific
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line items on attachments 3A and 3B of HSP-04.1 and reviewed by the QA
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Supervisor.
In addition, a vehicle inspection and verifying radiation
survey is performed by QC.
6.
Exit Interview
The inspector reviewed the scope and findings of the inspection with
licensee representatives (Section 1) at the conclusion of the inspection
and during a telephone conversation on May 29, 1985.
In response to
inspector comments the licensee agreed to complete revision of radio-
active materials shipment procedures to reflect specific requirements of
10 CFR 20.311 and 10 CFR 61.
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