ML20206M458
| ML20206M458 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/20/1986 |
| From: | Clemons P, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20206M377 | List: |
| References | |
| 50-309-86-06, 50-309-86-6, NUDOCS 8607010189 | |
| Download: ML20206M458 (5) | |
See also: IR 05000309/1986006
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-309/86-06
Docket No.
50-309
License No.
Category
C
Licensee: Maine Yankee Atomic Power Company
83 Edison Drive
Augusta, Maine 04336
Facility Name: Maine Yankee Nuclear Generating Station
Inspection At: Wiscasset, Maine
Inspection Conducted:
May 5-8, 1936
Inspector:
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P. Clemo s,
Radiation Specialist
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Approved by:
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W. Pasclak, Chief, Effluents Radiation
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Protection Section
Inspection Summary:
Inspection on May 5-8, 1986 (Report No. 50-309/86-06)
Areas Inspected:
Routine, unannounced safety inspection of the transportation
activities including:
purpose, management controls, training, procedures,
shipments of radioactive material, quality control, package selection, low
level waste storage facility, and outstanding items.
Results: One violation was identified relating to omissions of iron-55 in
shipping documents (failure to indicate the radionuclide identity, quantity,
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and total activity on waste manifests, paragraph 5)
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DETAILS
1.0 Persons Contacted
1.1 Licensee Personnel
J. Garrity, Plant Manager
E. Boulette, Assistant Plant Manager
G. Cochrane, Radiological Controls Section Hesd
L. Lawson, Quality Assurance Section Head
G. Pillsbury, Assistant to Manager, Technical Support
R. Wills, Hazardous Waste Coordinator
1.2 NRC Personnel
L. Tripp, Chief, Reactor Project Section 3A
C. Holden, Senior Resident Inspector
2.0 Purpose
The purpose of this routine inspection was to review the licensee's
program with respect to the following areas:
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Status of previous inspection findings;
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Review of shipments of radioactive material;
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Review of procedures;
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Review of training;
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Review of package selection;
Review of low level waste storage facility; and
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Review of management control.
3.0 Status of Previous Inspection Findings
(Closed) Inspector Followup Item (369/83-11-01):
No acceptance criteria
for comparing QC samples. The inspector determined that the licensee had
revised a chemistry procedure incorporating the acceptance criteria for
QC samples. The procedure appeared to be adequate.
(Closed) Unresolved (309/84-04-02):
Technical adequacy of retest for
respiratory filters.
The inspector reviewed the test requirements
specified by the licensee and determined that following the licensee's
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requirements would assure that the adequacy of the retesting requirements
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would be acceptable.
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(Closed) Unresolved (309/84-26-04):
Check Section XVI and Procedure
DDH-84-092.
The inspector reviewed Section XVI of the Application for
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the cask and Procedure DDH-84-092 which appeared to satisfy the cask
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maintenance requirements.
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(Closed) Violation (309/85-04-02):
Procedure not reviewed and approved
by PORC. The inspector determined that all appropriate procedures are
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reviewed and approved by PORC.
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(Closed) Inspector Followup Item (309/85-04-03):
Followup on IE Bulletin
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79-19 training.
The inspector reviewed a letter that was submitted to
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the NRC further defining the training, and personnel that would be
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trained.
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(Closed) Inspector Followup Item (309/85-17-01):
Determine that " hands-on
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training" is now required for personnel.
The inspector determined that the
licensee's practical factors is now including " hands-on" training for all
personnel.
(Closed) Violation (309/85-31-01): Determine that training is being
provided annually.
The inspector determined that the Chemistry Tech-
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nicians are being trained annually as required.
(Closed) Inspector Followup Item (309/85-35-01): Assure that H.P. Tech-
nicians have been trained.
The inspector reviewed documents that verified
that the licensee H.P. Technicians are being trained as required.
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4.0 Management Control
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The licensee has documented the management control for radioactive waste
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management in the Job Description Manual.
This manual states that the
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Radiological Controls Section Head is responsible for developing and
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implementing controls, methods, and practices as may be necessary to
assure radioactive waste releases and shipments are maintained within
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applicable federal state and local limits, and as low as reasonably
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achievable,
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The Radiological Controls Section Head has delegated the day-to-day
responsibility for radioactive waste to the Hazardous Waste Coordinator.
All of the activities are governed by procedures which specify methods
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for handling, processing, sampling, and analyses of liquid radioactive
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waste; directions for operating plant systems to control and process
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radioactive waste; and methods for control and processing of solid
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radioactive waste.
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Within the scope of this review, no violations were identified.
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5.0 Shipments of Radioactive Material
The transportation of licensed material was reviewed against the criteria
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contained in 10 CFR 71, " Packaging and Transportation of Radioactive
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Material", and 10 CFR 20.311, " Transfer for disposal and manifests."
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The licensee's performance relative to these criteria was determined from
discussions with the Hazardous Waste Coordinator, and by reviewing
shipping documentation.
Within the scope of this review, the following violation was observed.
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10 CFR 20.311(b) requires, in part, that the manifest accompanying
radwaste shipments indicate'as completely as practicable the radio-
nuclide identity and quantity, and the total radioactivity of the
shipments.
The licensee failed to identify the radionuclide iron-55, and its activ-
ity, on the following radwaste shipment manifests:
Shipment No.
Description
Total Activity (Curies)
D,.te
0785-257-A
Dewatered Resin
73.2
7/24/85
0386-151-A
Dewatered Resin
72.3
3/04/86
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The licensee's vendor analyses of various dewatered resin samples
identified the presence of iron-55, and provided the scaling factor
relative to cobalt-60 for iron-55 activity as being 0.5.
The licensee determines the percent isotopic composition for the energetic
gamma-emitting radionuclides (e.g. cobalt-60) based on gamma spectroscopic
analysis. The licensee did not calculate the activity of iron-55, by using
the scaling factor provided in the vendors analytical report.
For the shipment made on March 4, 1986, the licensee reported that the
activity for cobalt-60 was 1.34E4 millicuries.
Using the scaling factor
cited above, we determined the activity for iron-55 to bc 0.67E4 millicuries.
Since iron-55 was not identified, and its activity determined for each
shipment, the manifests accompanying each shipment contained incorrect
total activities for those shipments.
Failure to identify iron-55, determine its activity in each shipment, and
include the radionuclide in the total radioactivity of]the shipment con-
stitutes a violation of 10 CFR 20.311(b) [309/86-06-01.
6.0 Selection of Packaging
The licensee's program for the selection of packages was reviewed against
the requirements of 10 CFR 71.12, " General License:
NRC Approved Package"
and the Department of Transportation (DOT) requirements of 49 CFR 173,
" Shippers - General Requirements for Shipments and Packaging."
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The licensee's performance relative to the criteria was determined by
interviews of the Hazardous Waste Coordinator, examinations of documents,
procedures, shipping records, and observations during plant tours.
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Within the scope of this review, no violations were noted.
7.0 Low Level Waste Storage Facility
The licensee has completed the construction of its low level waste
storage facility at the Wiscasset, Maine site.
The facility is designed
to store waste up to five years.
The facility is presently being used to box dry active waste, and con-
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taminated equipment.
There is very little of either being stored at
this time.
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Within the scope of this review, no violations were identified.
8.0 Procedures
The adequacy and effectiveness of the licensee's procedures were reviewed
against the criteria contained in Technical Specification 6.8, "Proce-
dures".
The licensee's performance relative to these criteria was determined by
discussion with the Hazardous Waste Coordinator, and by reviewing certain
procedures.
Within the scope of this review, no violations were identified.
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9.0 Training
Personnel training in transportation activities was reviewed against the
criteria contained in 10 CFR 71.105, " Quality Assurance Program", and IE
Bulletin No. 79-19, " Packaging of Low-Level Radioactive Waste for Trans-
port and Burial."
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The licensee's performance relative to these criteria was determined by
discussion with training personnel, and by reviewing appropriate
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documents.
Within the scope of this review, no violations were identified.
10.
Exit Interview
The inspector met with the licensee representatives (denoted in Para-
graph 1) at the conclusion of the inspection on May 8, 1986.
The
inspector summarized the scope of the inspection and findings as
described in this report.
At no time during this inspection was written material provided to the
licensee by the inspector.
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