IR 05000263/1982006
| ML20054K583 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/07/1982 |
| From: | Greger L, Lovendale P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20054K576 | List: |
| References | |
| 50-263-82-06, 50-263-82-6, NUDOCS 8207020346 | |
| Download: ML20054K583 (7) | |
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Northern States Power Company
JUN i s 1967.
contains a full statement of the reasons which are the bases for the
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claim that the information should be withheld from public disclosure.
This section further requires the statement to address with specificity the considerations listed in 10 CFR 2.790(b)(4). The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit.
If we do not hear from you in this regard within the specified periods noted above, a copy of this letter and the enclosed inspection report will be placed in the Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely, Original Signed by,J. R. Miljec J. R. Miller, Chief Technical Inspection Branch l
Enclosure:
Inspection Report
No. 50-263/82-06(DETP)
REGION III==
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Report No. 50-263/82-06(DETP)
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Docket No. 50-263
License No. DPR-22
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Licensee: Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
Facility Name: Monticello Nuclear Generating Plant
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Inspection At: Monticello Site, Monticello, MN
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Inspection Conducted: June 1-4, 1982
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Inspector:
. C. Lo ndale
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Approved By:
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Facilities Radiation
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Protection Section
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Inspection Summary
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Inspection on June 1-4,
1982 (Report No. 50-263/82-06(DETP))
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Areas Inspected: Routine, unannounced inspection of operational radiation
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protection activities including:
effluent control instrumentation; testing
o' air c1 caning systems; reactor coolant water quality; licensee audits;
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rs :lation protection procedures; radiological qualification and training;
exposure control; and in plant radiation protection program. The inspector
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also reviewed the licensee's actions taken in reponse to previous inspec-
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tion findings; and two TMI Action Plan items. The inspection involved 36
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inspector-hours onsite by one NRC inspector.
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Results: No items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted
- W. Shamla, Plant Manager
- M. Clarity, Plant Superintendent, Engineering and Radiation Protection
- F.. Fey, Superintendent, Radiation Protection
- J. Windschill, Lead Health Physicist
G. Mathiasen, Supervisor, Radiological Services
R. Jacobson, Senior Chemist
P. Yurczyk, Radiation Protection Coordinator
J. Peterson, Chemistry Coordinator
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O. Iverson, Production Engineer
L. Nolan, Lead Chemical Engineer
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- C. Brown, Senior Resident Inspector. NRC
A. Madison, Resident Inspector, NRC
The inspector also interviewed other licensee employees including
radiation protection specialists.
- Denotes those present at the exit meeting.
2.
General
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This inspection, which began with a plant tour and visual observation of
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facilities and equipment, posting, labeling, and access controls at 7:30
a.m. on June 1,1982, was conducted to examine routine aspects of the
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radiation protection program during normal operations. During this tour,
the inspector used an NRC survey instrument (Xetec 305-B) to monitor
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selected areas throughout the plant. Measurements made were in agreement
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with posted survey data. Area postings, access controls, and housekeeping-
were very good.
Also, the inspector rev*ewed the licensee's noble gas, iodine, and
particulate monitors against NUREG-0737.
3.
Licensee Action on Previous Inspection Findings
(Closed) Item of Noncompliance (263/80-08-01):
A' radioactive waste
shipment cask was not marked " Radioactive - LSA."
Procedure No. 8110
now requires that all stick-on markings and labels be reinforced with
tape to prevent them from falling off during transit. Also, extra
stick-on markings or labels are supplied to the truck driver with
instructions to apply them as needed. No further problems were noted.
(Closed) Open Item (263/81-07-01; 263/80-14-CC):
Licensee actions in
response to IE Circular No. 80-14.
Check valves have been installed on
demineralized water hose stations located on the refueling floor. Also,
warning signs have been posted at each demineralized water hose station.
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No further problems were noted.
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(Closed) Item of Noncompliance (263/81-15-01): Failure to follow
radiation protection key control procedure. The responsible technician
was reprimanded and the matter was discussed with the entire technician
staff. No further problems were noted.
(Closed) Open Item (263/81-21-02): Worker drank from a slightly con-
taminated condensate storage tank hose. A warning sign was posted and
training personnel instruct workers to drink from water coolers only.
No further problems were noted.
(Closed) Items of Noncompliance (263/81-22-05; 263/81-22-06;
263/81-22-07): Unauthorized removal of radioactive material from
site and radiation levels in an unrestricted area in excess of
allowable limits. Also, failure to expeditiously retrieve the
caterial.
Procedures concerning radioactive material storage and
control have been revised and management control of such occurrences
has been strengthened. No further problems were noted.
4.
Effluent Control Instrumentation
The inspector reviewed records of effluent monitoring system calibra-
tions and functional tests conducted to meet technical specification
requirements.
Records for 1981 and 1982 to date were reviewed; no
problems were noted.
Grab sample results of plant effluents are compared with monitor
readings in accordance with technical specifications. Good agreement
is normally achieved.
A review of effluent monitor trip and alarm setpoints indicated
compliance with technical specification requirements.
No items of noncompliance or deviations were identified.
5.
Testing of Air Cleaning Systems
In place filter tests were performed on the Standby Gas Treatment
System (SBGTS) in April 1981. Laboratory methyl iodide tests were
performed on the SBGTS charcoal in July 1981. The in place testing
included DOP tests of HEPA filters, and Freon tests of charcoal
adsorbers.
In place tests of both the "A" and "B" trains indicated
greater than 99 percent removal. The laboratory tests (methyl iodide)
of charcoal samples indicated greater than 99 percent removal. These
results meet the limits specified in Technical Specification 3.7.B.2.
Although not required by technical specifications, the stack filters
(HEPA and charcoal) and offgas compressor suction filter are tested
routinely in accordance with approved test procedures.
However,
other installed filter systems such as the radwaste building exhaust
(V-FU-1 and 2) and the reactor building ventilation (V-FU-5) are not
tested in accordance with the recommendations of Regulatory Guide 1.140,
" Design, Testing, and Maintenance Criteria for Normal Ventilation
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Exhaust System Air Filtration and Absorption Units of Light-Water-
Cooled-Nuclear Power Plants. This matter was discussed during the exit
meeting and will be reviewed during a future inspection.
(263/82-06-01)
No items of noncompliance or deviations were identified.
6.
Reactor Coolant Water Quality
The inspector reviewed selected licensee records to determine compliance
with technical specification requirements for reactor coolant periodic
tests, chemical control, and radioactivity control. Records from CY 1981
to date were reviewed; no problems were noted.
No items of noncompliance or deviations were identified.
7.
Licensee Audits
The inspector reviewed licensee audits of the radiation protection
program and corrective measures for identified problems. The audits
reviewed included an INPO audit conducted in March 1982 and an audit
of radiation protection activities during the 1981 maintenance outage
conducted by the corporate office.
The licensee was responsive to identified problems and corrective
actions appeared effective.
8.
Radiation Protection Procedures
The inspector reviewed changes to the radiation protection procedures
issued in 1981 and 1982 to date. The changes appear to be consistent
with "egulatory requirements and good health physics practices. No
probi.ms were noted.
9.
Radiological Qualification / Training
The inspector reviewed recent changes to the Chemistry and Health
Physics organization. The Lead Chemical Engineer has been trans-
ferred into the Operations Engineering Group. This transfer was
made in order to consolidate all systems engineers into one group.
One radiation protection specialist has been assigned to the training
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department. At present there are openings for one health physicist
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and two radiation protection specialists.
Radiationprotectiontrainingforradiationworpersandtheradiation
protection staff remains as previously stated.1
In addition, radiation
protection specialists are receiving plant systems training from the
training department. No problems were noted.
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Inspection Report No. 50-263/81-07.
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10.
External Exposure Control
The licensee's personal monitoring program remains as previously
described. The inspector selectively reviewed exposure records for
1981 and 1982 to date. No problems were noted.
The licensee spikes ten TLDs each month and then sends them to the
vendor for processing. On the average, the spiked TLDs read ten
percent low, which is nonconservative. The licensee has determined
the cause to be an error in their spiking procedure and is taking
action to correct the problem.
11.
Internal Exposure Control
The licensee's program for control of internal exposures includes
reduction of surface contamination levels and use of engineering
controls, protective clothing and equipment, survey information, and
stay-time calculations. Whole body counting is used to supplement
the routine monitoring program to ensure its effectiveness.
Whole body counting data, respiratory protection training records,
MPC-hour determinations, and air activity surveys from January 1981
to date were reviewed. No exposures greater than the 40 MPC-hour
control measure were indicated.
No items of noncompliance or deviations were identified.
12.
In-Plant Radiation Protection Program
a.
Surveys
The inspector selectively reviewed radiation, contamination, and
airborne radioactivity surveys conducted to meet surveillance re-
quirements and determine radiation work permit requirements. No
problems were noted.
b.
Posting and Access Controls
The inspector reviewed radiation, high radiation, and contamina-
tion area postings within the plant controlled area. All postings
appeared to meet the requirements of 10 CFR 20.203.
c.
Release of Materials for Unrestricted Use
The licensee's procedures for release of materials for unrestricted
use were reviewed.
The licensee does not release materials for
unrestricted use if any detectable activity is found using current
state-of-the-art equipment and methods. Equipment sensitivities are
more restrictive than the minimum sensitivities noted in IE Circular
No. 81-07.
No problems were noted.
No items of noncompliance or deviations were identified.
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13.
Turbine Floor Continuous Air Monitor (CAM)
On the December 2, 1981 night shift, during a maintenance outage, the
turbine building vents were opened to remove welding smoke. The turbine
floor CAM (Eberline PING) was recently installed, but had not been
programmed or calibrated and therefore was not capable of performing its
intended function.
Technical Specification 2.4.4.b requires that a CAM be in operation on
the turbine floor before opening the turbine building roof vents. The
Shift Supervisor was aware the new CAM was running on the turbine floor
and therefore assumed that the technical specification requirement had
been met.
On the morning of December 3, 1981, the error was discovered
by radiation protection personnel. The vent was closed immediately and
the CAM was tagged out of service.
In addition, " secure" tags were
installed on the turbine building vent switches. The tags state that
approval of the Health Physicist is needed before operation of the
turbine building roof vents. Also, the operations requirements section
of the turbine building roof vent procedure was revised to prevent
The licensee's corrective actions appear adequate.
recurrence.
14.
Transportation Activities
The inspector reviewed the licensee's procedures for transportation
of radioactive material. The procedures were current with respect to
burial site criteria and NRC/ DOT regulations. No problems were noted.
Procedures reviewed include:
No. 8075
Revision 4
Procedure for Shipping Radwaste Using
a Model B-2 Cask
No. 8076
Revision 14
Procedure for Shipping Radioactive Waste
Using the CNSI 14-195H Cask
No. 8077
Revision 3
Radioactive Materials Shipment - LSA not
Exceeding Type A Quantity in Exclusive Use
Vehicles
No. 8089
Revision 5
Radioactive Material Shipment - Type A
Quantity, Fissile Exempt
No. 8091
Revision 5
Procedure for Shipping Radwaste to U.S.
Ecology in Washington
No. 8092
Revision 6
Procedure for Shipping Radwaste to Barnwell
The inspector reviewed the licensee's methcd of ensuring that
certificate of compliance maintenance requirements have been met.
The required maintenance is performed by the vendor (cask owner).
Depending on the vendor, a letter is sent to the licensee confirming
that the required maintenance was performed or a sticker is attached
to the packages which indicates that the required maintenance has
been completed. The licensee's procedures require confirmation that
package maintenance has been completed before shipment. No problems
were noted.
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The inspector selectively reviewed records of shipments made during
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1981 and 1982 to date. No problems were noted.
No items of noncompliance or deviations were identified.
15.
TMI Action Plan Items II.F.1.1.B.2'and II.F.1.2.B.2
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a.
Noble Gas Effluent Monitor (II.F.1.1.B.2)
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The licensee has installed four wide range noble gas monitors.
Two monitors sample the offgas stack and two monitors sample
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the reactor building vent. The monitors readout in the control
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room. Digital readouts of release rate or concentration are
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provided, as well as an easily read strip chart recorder. The
inspector reviewed the monitor installations for compliance with
NUREG-0737 requirements. No problems were noted. This item is
closed,
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b.
Sampling and Analysis of Plant Effluents (II.F.1.2.B.2)
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The sampling rack component of the wide range noble gas monitor
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contains filter holders and. valves to allow grab sample collec-
tion of particulates and iodines for isotopic analysis in the
laboratory. The inspector reviewed the licensee's sampling
capabilities for compliance with NUREG-0737 requirements. No
problems were noted. This item is closed.
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16.
Exit Meeting
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The inspector met with licensee representatives (denoted in Section 1)
at the conclusica of the inspection on June 4, 1982. The inspector
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summarized'the scope and findings of the inspection.
In response to
certain items discussed by the inspector, the licensee:
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Stated that the recommendations of Regulatory Guide 1.140 would be
reviewed and compared with present -practices for testing and main--
tenance of air cleaning systems.
(Section 5)
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