ML20004D165
| ML20004D165 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/05/1981 |
| From: | Book H, North H, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20004D164 | List: |
| References | |
| 50-312-81-13, NUDOCS 8106080505 | |
| Download: ML20004D165 (14) | |
See also: IR 05000312/1981013
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U. S. !;UCLEAR RECUIATORY CCMMISSIO:i
h
0FFICE OF I::SEECTIO i A!iD E!! FORCE!E!.T
REGIO:1 V
Raport :o.
50-312/81-13
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Do'cket fo.
50-312
License tio.
OPR-54
Safeguards croup
Licensee:
Sacrarento Municioal Utility District
P. O. Box 15830
Sacramento California 95813
racility ::a=e:
Rancho Seco
Inspection at:
Clay Station, California
Inspection conduct d: April 6-9,1981
. I he
,/i'[f/f/
Inspectors: 4
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{i. S. North, Radiation Spgcialist
D$te'S igned
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Approved By:
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F. A. Wenslawski, Chief
Dftc'SiSned
Reactor Radiation Protection Section
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Date Si ned
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Approved By:
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H. E. Bo'ok, Chief, Radiological Safety Branch
D.ite Signed
S u ==a rf :
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Insoection on April 6-9, 1981 (Report No. 50-312/81-13)~
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Routine, unannounced inspection by a regional' based inspect.or
Areas Inspected:
of the radiation protection program organization, response to refueling activities
including procedures, exposure control, out of holder film badge exposure,
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respiratory protection, posting and control, surveys and radioactive and'
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contaminated material control and transportation activities including periodic
maintenance of packagings, management controls, implementation, prepa' ration
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for shiprent, delivery to and loading on carrie.rs, receipt of packages, incident
reporting, examination of packages, and followup on inspection report items,
reportable occurrences and facility tour.
The inspection involved 33 inspector-hours on , site by one NRC inspector.
Results: Of the nineteen areas inspected no items of noncompliance or deviations
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were identified.
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DETAILS
1.
Persons Contacted
R. Columbo - Technical Assistant, Nuclear Operations
- R. Miller - Chemical and Radiation Supervisor (CRS)
- F. Kellie - Assistant Chemical and Radiation Supervisor (ACRS)
- R. Wichert - Plant Mechanical Engineer
D. Gardiner - Senior Chemical and Radiation Assistant (SCRA)
J. Newey - SCRA
- W. Wilson - SCRA
- T. Perry - QA Supervisor
- Q. Coleran - QA Inspector
- H. Heckert - Nuclear Engineering Technician
- R. Bowser - Chemistry Radiation Assistant (CRA)
D. Streta:s - Senior Typist Clerk
B. Gaines, Typist Clerk
Various CRAs and contract technicians
- Denotes attendance at exit interview.
2.
Radiation Protection - Organization
The former nuclear chemist has been selected to fill the position of
ACRS. The establishment of this position was previously discussed in
IE Inspection Report No. 50-312/80-32.
The ACRS is responsible for
technical supervision of the SCRAs providtrg an increase in the opportunity
for job site supervision. The positions of nuclear chemist and health
physicist are presently vacant. The position of health physicist has
been vacant for six months. The licensee is continuing efforts to fill
the health physicist position.
The licensee reportad that as a result of changes in previously scheduled
outage work more contract radiation protection technicians (CRPT) were
available than were required.
In addition certain work required less
technician coverage than originally planned. As a result the radiation
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protection staff was never short of technicians when they were needed.
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All CRPT resumes' were checked and found to be substantially correct,
apparently having been prepared by the CRPT's themselves. The licensee
reported favorably on the quality of CRPTs available during the outage.
No items of noncompliance are identified.
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3.
Procedures
New or recently revised, reviewed and approved procedures were examined
and discussed with the licensee:
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AP305-1, Restricted Area Access Reouirements, revised to delete medical
examination requirements, states administrative controls applicable
to all individuals on initial entry.
AP305-4, Radiation Work Permit (RWP) Procedure, revised existing procedure
for worker badge icentification and job planning.
Improved schedule
and task orientation of RWP's. Required job planning meetings for tasks
estimated to result in one or more man-rem exposure.
AP305-5, Protective Clothing and Equipment Use, revised to update, clarify
and delete equipment no longer in use.
AP305-6, Personnel Chance Roon Use, revised to improve personnel flow
in change room and to document use of a grade level change room and
entry area during outages.
AP305-30, Use of LeadJhieldinc, issued to specify the proper use and
limitations on use of lead shielding, sheets, bricks, blankets and shot.
AP305-31, Oparating Procedure for the RIX Air Comaressor Syttem, issued
to detail operating instructions and precautions :oth for dinct and
cascade SCBA bottle charging.
Identified precautions, overprc3surization,
internal combustion engine exhaust, flannable material or chemical storage
and bottle fill rate. Provides for routine air quality sample analysis
for 0 , CO, C07 and condensed hydrocarbons in accordance with an establis5ed
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surveillance procedure.
The previously reported technician zone coverage system used in the
reactor building during the outage (IE Inspection Report No. 50-312/
81-02, paragraph 4) resulted in improved morale on the part of contract
workmen in containment and the plant chemistry-radiation protection
staff. The system provided increased opportunity to identify poor radiation
protection practices however no quantifiable benefit had been identified
(81-02-02 Closed).
No items of noncompliance were identified.
4.
Exposure Control
The licensee personnel monitoring practice and procedures were examined
and reported in IE Inspection Report No. 50-312/81-02, paragraph 8.
The records of personnel exposures for 1980 and January and February
1981 were examined. The March 1981 film badge report had not been received
from Landauer. The licensee's practice and exposure limitations were
found to be in compliance with the following requirements based on an
examination of selected records:
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10 CFR 20.101(a) and (b) Radiation dose standards for individuals in
restricted areas;
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10 CFR 20.102 Determination of prior dose; and
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10 CFR 20.202 Personnel Monitoring.
The personnel monitoring program provides badges for a plant staff of
approximately 225 and 300-350 contract work force.
During the refueling
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975 individuals were subject to personnel monitoring controls.
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The records established that personnel received the required training
prior to being permitted access to controlled areas. Occupational exposure
histories were obtained prior to issuing personnel monitoring devices.
When occupational exposure histories supplied by a previous employer
were not available, such information was obtained from the employee.
The licensee implemented the administrative controls program requiring
successive management approvals for increasing) exposure levcis (e.g.
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100 mrem / week, 300 mrem / week and 1 rem / quarter .
Individually maintained
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records of pocket ionization chamber (PIC) readings were used to account
for exposures between badge change periods.
Initial and termination
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whole body counts were perfonned and documented. A sample of individual
exposure records selected from specific RWPs were examined.
The licensee reported the results of personnel monitoring and whole
body counting to terminated individuals and the Comission as required
by 10 CFR 19.13 and 10 CFR 20.408. The licensee reported under letter
dated February 27, 1981 the information required by 10 CFR 20.407(a)
(1) and (b) and the annual tabulation of exposure based on work and
job function as required by Technical Specification Section 6.9.2.
Based on an examination of exposure records the maximum individual exposure
received during 1980 was 2790 mrem.
No items of noncompliance were identified.
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5.
Out of Holder-Film Badge Exposure-December 1980
IE Inspection Report No. 50-312/81-02, paragraph 8, reported that the
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December 1980 film badges supplied by Landauer had been exposed out of
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the holder.
On December 15, 1980 the licensee submitted two film badges
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(Nos. 99245 and 99293) for vly processing along with an unused visitor's
badge as a control (No. 99016). Landauer reported the following exposures:
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Badge No.
Function
Reported Exposure
99245
Personnel
m (less than minimum detectable)
99292
Personnel
0.090 rem
99016
Control
0.990 rem
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The licensee then submitted additional unused badges for evaluation,
which showed random and unexplained exposures.
Landauer was unable to
identify any acceptable background reduction method which would permit
use of the December badges. Accordingly the licensee submitted to Landauer
a sumary of personnel exposures based on PIO data for all exposed individuals
as a replacement for the invalid December 1980 film badge data. The
licensee reported that the December 1980 badges when received, had not
been inadvertently processed through the Rancho Seco security x-ray
machine.
Landauer reported that the badge exposures were to soft x-rays
of unexplained origin. Landauer suggested that it was possible that
an airport may have been using an older x-ray machine to scan mail but
offered no additional supporting information.
The PIC data supplied to Landauer ranged up to a maximum of 290 mrem
for December 1980. The maximum 4th quarter exposure was 760 mrem.
The licensee's records were found to contain correspondence with Landauer
relating to the occurrence however no sumary for historical purposes
was contained in the file. The advantage of such a sumary was identified
to the licensee during the exit interview (81-02-03 closed) .
No items of noncompliance were identifie.d.
6.
Respiratory Protection Program
The licensee's program is based on routine and special air samples and
the use of full face filter and air supplied respirators. The licensee's
practice is to limit individual exposures to less than 25% of MPC (10 CFR 20
Appendix B Table I Column I) values on a daily and weekly basis. Low
All low volume and high volume air
and high volume samplers are used.
samples indicating greater than 2 x 10-gAC1/ml on gross counting are
subject to laboratory analysis.
Result of air sample analysis is documented
on survey records, RWP's and individual laboratory air sample analysis
data sheets. RWP's specify respiratory protection equipment required.
Engineered control measures are used in selected cases.
During the
outage, tents were used for entry into the upper manway of steam generator
"A" and en the decay heat piping modification.
For smaller jobs vacuum
cleaners are used to control particulate material generated by work
such as grinding.
Issuance of respirators is controlled by a junior technician at the
access control point.
Verification of respirator training is required
before masks are issued. The licensee's respirator training, fittin
and operational testing were examined during an earlier inspection (g
Inspection Report No. 50-312/81-02 paragraph 7). Cleaning and maintenance
of respirators is performed by trained craft helpers and selected laborers.
Following cleaning, maintenance and survey, respirators are individually
plastic bagged for reuse.
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A number of RWP's were selected for detailed examination of respiratory
controls and the implementation of the respiratory protection program.
Records of selected individuals, both temporary and permanent plant
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staff, identified on the RWPs were examined to confirm completion of
the required training, fitting and medical qualification prior to respirator
issuance. Examples of licensee's calculations of airborne concentrations
were confirmed.
Records confirmed that individuals were whole body
counted prior to respirator use and termination. No significant whole
body depositions were identified (81-02-04 closed).
No items of noncompliance were identified.
7.
Posting and Control
A tour and survey of the waste storage facility confirmed that posting
and labeling conformed to regulatory requirements. A Xetex 305B, Serial
No. 8174, NRC 008334, due for calibration on June 30, 1981; was used.
It was noted that posting of the Tank Farm controlled area boundary
had been increased te better identify the controlled area (IE Inspection
Report flo. 50-312/81-02 paragraph 10). A number of RWPs which were
examined were previously discussed in paragraphs 4 and 6.
No items of noncompliance were identified.
8.
Surveys
Records relating to survey information are contained in routine and
special survey records, the health physics shift log and laboratory
counting data sheets. Some survey records relating to specific RWP's
were filed with the RWPs while others were contained in survey record
files or laboratory counting record files. The availability of technician
personnel including the zone control technicians resulted in an increase
in the number of individual survey records produced. The shift log
was examined for the period February 1-22, and ?> arch 16-17, 1981. The
record provided information concerning specific problems or occurrences.
Several cases of minor personnel contamination were identified along
with specific decontamination procedures used and the results of surveys
and/or whole body counting used to establish the effectiveness of the
decontamination. The log recorded that the service air had been checked
to assure grade "D" quality on February 21, 1981.
Survey records for February 1931 were examined. These records included
routine and special surveys.
It was noted that the survey records were
written in ink, signed or initialed, identified the date and time of
the survey and the instrument (s), serial number and type used and the
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calibration due date. Survey data was well documented and supported,
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when appropriate, with diagrams and sketches.
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No items of noncompliance were identified,
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9.
Radioactive and Contaminated Material Control
The licensee had established and maintained a tool and equipment monitoring
station at the access control point. Procedure AP305-9 Removal of Tools
and Equipment from Controlled Areas, specifies the limits applicable
for uncontrolled release.
The contract technician assigned to this
station was familiar with the procedure and was able to specify the
applicable limits without reference to the procedure.
No items of noncompliance were identified.
10.
Periodic Maintenance of Packagings
The licensee is a registered user of four casks for which certificates
of compliance have been issued. A controlled copy of a cask book has
been supplied by the vendor which contains specific information on each
cask, a copy of the certificate of compliance and records of registry
of Sacramento Municipal Utility District as an authorized user. The
licensee owns no casks for which a certificate of compliance has been
issued. The licensee is authorized to use the following vendor supplied
casks:
Cask Model
Certificate of Compliance
Required Maintenance
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CNSI-14-195-H
9094
gasket inspection prior to
shipment-replace if defective
or annually
CN6-80A
9111
nere specified
B-3
6058
"0" ring inspection prior to
shiptrent-replace if defective
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or annually
B-2
6144
gasket inspection prior to
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shipment-replace if defective
or annually
The licensee has documented the required ga'sket inspections prior to
each shipment. The licensee stated that gasket replacement because of
damage had not been required at Rancho Seco and that annual replacement
was accomplished by the cask supplier / vendor.
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No items of noncompliance were identified.
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11. Transportation Activities
a.
Management Controls
By memorandum from the CRS dated October 31, 1980 an SCRA was assigned
responsibility for Radwaste Control. The assigned responsibilities
and duties include, "getting dry waste packaged, wet waste solidified,
contaminated clothing laundered, contaminated items cleaned, final
evaluation of all radioactive releases and control of all radioactive
shipments; operation of solidification equipment and the tritium
evaporator will be under his control as will the supervision of
special decon parties, etc." The licensee has prepared written
procedures governing the receipt, packaging, transfer / delivery
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to a carrier and transport of radioactive material:
AP305-10 Radioactive Waste Disposal Inplant, Rev. 5
AP305-11 Licensed Radioactive Material Handling, Rev. 2
AP305-12A Shipments of Radioactive Materials Offsite, Rev. 5
AP305-12B Bulk Radioactive liquid Shipment, Original
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AP305-12C Radioactive Solidified Waste Shipment, Original
AP305 Radiation Control Manual _, Section 3.8 Procurement, Use and
Shioment of Radioactive Material and Section 3.9 Radioactive Waste
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Control.
The licensee has recently revised procedures AP305-10 and AP305-12A.
Procedure AP305-128 is no longer applicable in that the licensee
no lenger disposes of bulk liquid radioactive waste by shipment
and transfer.
The licensee's training program incorporates both 10 CFR 71 and
Graziano's Tariff as a part of the training of CRAs.
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In response to IE Bulletin No. 79-19 (item 7), the licensee stated
that a revision of SMUD Nuclear Quality Assurance Audit Progrant
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(QCI-2) was in progress and would be completed by October 9, 1979.
Ouality _ Element Checklist, Check List No. 30, Audit Activity Transfer _,
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packing and transport of low level radwaste, approved September 14,
1979 was in effect. Check List No. 30 identified 49 CFR Par';s 170-
179 and 10 CTR Parts 19 to 71 as reference documents and based
specific audit element characteristics on specific items in those
documents and in IE Bulletin No. 79-19. Audits pursuant to Check
List No. 30 were performed on October 2,1979 (Audit No. 0-259)
and January 28 (Audit No. 0-275) and December 29, 1980 (Audit No.
0-344). Audit No. 0-275 was conducted as a followup of open items
identified in the earlier audit. A review of the Audit Reports
indicated a strong emphasis on administrative rather than performance
requirements as shown by the following summary of audit elements
addressed.
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Audit Eleme@
Audit Nos,
0 S59
0-275
0-344
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Verify (posting pursuant to 10 CFR 19.11 a) Posting of notices to
workers.
Verify equipment available to perform
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X
pursuant to 10 CFR 20.201, Surveys.
Verify availability of appropriate
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materials pursuant to 10 CFR 20.203,
Caution signs, labels, sionals and
controls.
Verify maintenance of records
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X
pursuant to 10 CFR 20.401, Records
of surveys, radiation monitoring
and disposal.
Verify required reports made pursuant
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to 10 CFR 20.402, Reports of theft
or loss of licensed material.
Verify required reports cade pursuant
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to 10 CFR 20.403, Notification of
incidents.
Verify availability of current copies
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X
of MRC and DOT regulations maintained,
IE Bulletin No. 79-19 item 1.
Verify copy of appropriate agreement
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State burial site requirements
(licenses) available, IE Bulletin
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No. 79-19 item 2.
Verify availability of management
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approved instructions and operating
procedures relating to low level
radioactive waste, IE Bulletin No. 79-19 item 4.
Verify training and retraining in
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NRC and D0T and burial license
requirements and instructions and
operating procedures for personnel
involved in transfer, packaging and
transport of radioactive material,
IE Bulletin No. 79-19 item S.
Verify training and retraining of
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operators of processes which generate
waste, IE Bulletin No. 79-19 item 6.
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Other audit elements, including some appearing in Check List No. 30,
which had not been included in audits conducted to the date of this
inspection, would appear to provide a better indication to licensee
management of the effectiveness of the packaging, transport and
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transfer of low level radioactive waste. This ratter was discussed
during the exit interview.
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No iters of noncompliance were identified,
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b.
Imolenwntation
Curing the first quarter of 1981 the licensee has delivered to
a carrier for shiprent 11 exclusive use loads of LSA material contained
in new 17H steel drums or strong, tight wooden boxes. Certain
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of these shipments were made in packagings for which certificates
of compliance had been issued and for which the licensee was a
registered user (see paragraph 10).
Examination of waste drums
prepared for shiprent confirmed that the 17H steel drums used were
new and undamaged. Strong, tight boxes fabricated by the licensee,
according to a specification drawing, are constructed to contain
approximately 128 cubic feet. The boxes of 3/4 inch plywood internally
reinforced with 2 x 4 inch continuous blocking assembled with nails
and glue are sealed with RTV sealant and lined with tape sealed
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plastic sheeting which overlaps the exterior sides of the box to
protect against exterior contamination. The bor
are provided
with 4 x 4 inch fork lift blocks.
The licensee's use of reusable, vendor supplied packagings was in
conformance with the certificate of compliance with respect to
weight and thermal leadings and gasket inspections. The licensee
had a current copy of the vendor procedures for cask loading and
raintained a record on a checkoff sheet of individual steps taken
in loading and preparing the package for shipment.
Based on an
examination of selected records of shipments, full load, exclusive
use shipment of LSA material conformed to the requirements of 49
CFR 173.392(a)-(d).
No items of noncompliance were identified.
c.
Preparation of Packages for Shipment
The inspector verified that the licensee had written procedures
which required preuse inspection of certified packaging, after loading
verification of adequate shielding and proper closing of packages.
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Adherence to procedures was documented on procedure based check
off sheets. The licensee had made no shipments of liquid waste
during 1981 but was planning to dispose of a drun of liquid scintillator
vials by shipment to the Washington State disposal site in accordance
with State requirements.
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The inspector verified by examination of records and procedures,
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discussion with licensee personnel and observation of packages
prepared for shipment that package markings were correct and conformed
to regulatory requirements.
In addition records of surveys for
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radiation levels and contamination of individual packages and loaded
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transport vehicles were performed and documented.
Licensee procedures
provide for and the licensee prepared proper shipping paper documentation.
Documentation established that prior to loading, full load, exclusive
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use vehicles were inspected and surveyed and that after loading surveys
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were performed. The inspector confirmed by discussion with licensee
personnel and examination of records and procedures that in the
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case of filters or other materials shipped with shielding, only
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the weight of the radioactive material or component was used in
the calculation of specific activity. Questions raised in IE Inspection
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Report flo. 50-312/80-02 concerning records of waste and labeling
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practices viere resolved and are considered closed (80-02-03).
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No items of noncompliance were identified.
d.
Delivery of Packages to Carriers and loading of Packaces on Curriers
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During the inspection the documentation relating to shipments
81-1, 81-2, 81-3, 81-4, 81-8 and 81-10 was examined. The documentation
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of shipment 81-1 included copies of the following items:
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State of Washington, Low-level Radioactive Waste Shipment Certification
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for Commercial Generator / Packagers, and Brokers and Carriers,
(AP305-12C-5)
Radioactive Solid Waste Shipment Information Sheet (AP305-12C-6)
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User Check Sheet - Cask user procedure document
Radioactive Paterial Shipment - (AP305-12A enclosure 4.1) Identifies,
and describes individual packages by number, contents, weight /
volume, form, nuclide(s), activity, radiation / contamination levels
and includes material certification.
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Radioactive Solid Waste Shipping Checkoff List, (AP305-12C enclosun
5.1) survey, posting, labeling, shipment authorization signatures,
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record of receipt by driver of documents
Radioactive Waste Shipment and Disposal Form - NECO,
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Bill of Lading - shippers copy - full load
Vehicle Inspection Sheet - (AP305-12A enclosure 4.3) Tractor / trailer,
license No., State, deficiencies
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Prior Notification of Shipment of Low-Level Solid Waste to NECO
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Beatty, Nevada or Hanford, Washington, documents telephone notification
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CNSI/ Broker Inspection Report
Cask Smear Form
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Bill of Lading, arrival of empty cask.
Photographs of loaded and placarded vehicle.
Documentation for other shipments was similar.
No items of noncompliance were identified.
e.
Receiot of Packages
Licensee procedures;
AP305, Radiation Control Manual, section 3.8, Procurement, Use
and Shipment of Radioactive Material,
AP305-11, Licensed Radioactive Material Handling,
and
AP305-16, Receipt of Radioactive Material,
provide for prompt receipt and monitoring, safe opening and carrier
and NRC notification if regulatory limits are exceeded.
No items of noncompliance were identified.
f.
Incident Reporting
With respect to accidents involving carriers of radioactive waste
shipments to burial sites, the licensee instructs drivers to report
accidents by collect telephone call to the Shift Supervisor, Rancho
Seco, and further to report any unusual circumstances associated
with the load during transit, e.g., "... leaks, detention for any
radiological reason, etc." These instructions are provided in
addition to Emergency Procedures and Reporting Plans for Tri-State
and U. S. Ecology, enclosure 4.10 to AP350-12A. The licensee stated
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that there had been no incidents associated with the shipment of
radioactive waste nor were there instances where the effectiveness
of packaging was substantially reduced during use.
No items of noncompliance were identified,
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g.
Examination of Packages
During the inspection, a 17H drum of waste package for shipment
and assembled with others as a "dumnly" lead awaiting transport
was selected for inspection. Drum tio.81-311, packed on March 16,
1981 weighing 290 pounds was opened on April 9,1981. The contents
consisted of dry, plastic bagged, compressed waste. The drum was
labeled " Radioactive LSA" on opposite sides of the drum.
The contents
of the drum were identified as Cs-137, Co-58 and 60, Mn-54 and
Cr-51 with dose rates of 20 and 3 nr/hr at contact and 3 feet respectively.
The dose rate measurements were confirmed by the inspector using
a Xetex 305B, G-M type survey meter, serial number 8174 NRC 008334,
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due for calibration June 30, 1981. The licensee representative
reported that as a precaution, a layer of absorbent material was
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placed in the bottom of all druos prior to the addition and compaction
of waste for shipment.
It was noted that the packages prepared
for shipr:ent were in unimpaired physical condition, with locking
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rings secured and a lock nut in place.
No items of noncompliance were identified.
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h.
Indoctrination and Training Program
Inspection of this aspect of the licensee's program will be completed
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and reported during a subsequent inspection (81-13-01).
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12.
Inspection Report Followup Items
Comconent Cooling Water (CCW) Contamination (81-02-01)
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IE Inspection Report flo. 50-312/81-02 in paragraph 2, reported that
the licensee had identified contamination from an unidentified source
in this system and had performed a safety evaluation pursuant to 10 CFR
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50.59 concerning the continued operation of this system in its contaminated
conditicn.
IE Inspection Report No. 50-312/81-04 paragraph 8.A. reported
,
that the source of the leak was identified to be the "A' let down cooler.
Discussion with licensee personnel disclosed that the "A" letdown cooler
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was subsequently isolated. Special Test Procedure 094 was prepared
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tc ccer the removal of the water from the CCW system and transfer to
holdup tank T950A, demineralization and return to the CCW system. The
i
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licensee plans to operate the plant with letdown cooler "A" isolated
but if required may use the "A" cooler. A replacement for the "A" cooler
is available and is scheduled for installation during 1982. No health
and safety problems were identified in connection'with this occurrence.
This matter is considered closed.
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NUREG-0578, TMI-2 Lessons Learned
IE Inspection Report No. 50-312/80-36 reported that several procedures
required by item 2.1.6.a. Integrity of Systems Outside Containment Likely
to Contain Radioactive Materials, had not been prepared, reviewed and
approved.
It was determined that with the exception of, SP 201.12B
Waste Gas System Leak Test Surveillance Procedure, these procedures
procedure will be determined during the next inspection (81-13-02)plete
haa Deen preparea, reviewea ar.a approvea.
Tne status of the incom
.
No items of noncompliance were identified.
13.
Followup on Reportable Occurrences
Four reportable occurrences, 81-05, 81-15 and 81-20 concerning pH limits
and 81-18 concerning chlorir.e concentration were reviewed. The reports
were submitted in accordance with Technical Specification Appendix B
sections 2.4 (pH) and 5.6.2c (chlorine) requirements. These matters
are considered closed (81-05-EO, 81-15-EO, 81-18-E0 and 81-20-E0).
No items of noncompliance were identified.
14.
Followup on a Significant Event
Activation of Onsite Emergency Plan, December,1980
IE Inspection Report No. 80-38, paragraph 9, reported that on December 22,
1980, the licensee activated the onsite emergercy plan and evacuated
personnel to the onsite assembly area in response to several spurious
monitoring system alarms. The licensee elected to use this occurrence
to satisfy the requirement for the fourth quarter,1980, drill of the
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emrgency plan. A critique of the evacuation was conducted on December 22,
1980 and was documented in a memo to file dated March 9, 1981.
No items of noncompliance were identified.
15.
Exit Interview
At the conclusion of the inspection the inspection findings were summarized
for those individuals denoted in paragraph 1.
The liceasee was advised
that no items of noncompliance had been identified.
The licensee was informed that the audits of transportation activities
(paragraph 11.a.) appeared to lack the depth necessary to identify possible
problems associated with packaging and transporting radioactive materials.
In addition the need to complete the klaste Gas System Leak Test Surveillance
Procedure during the outage was identified (paragraph 12).
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