ML19257C394
| ML19257C394 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/18/1979 |
| From: | Fisher W, Greger L, Peck C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19257C390 | List: |
| References | |
| 50-295-79-25, 50-304-79-23, NUDOCS 8001290046 | |
| Download: ML19257C394 (7) | |
See also: IR 05000295/1979025
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-295/79-25; 50-304/79-23
Docket No. 50-295; 50-304
Licensee: Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
Facility Name:
Zion Nuclear Power Station, Units 1 and 2
Inspection At:
Zion Site, Zion, IL
_
Inspection Conducted: November 19 and 20, 1979
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Inspectors:
L
R. Gre er
,
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C. C. Peck
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Approved By:
W. L. Fisher, Chief
Fuel Facility Projects and
Radiation Support Section
Inspection Summary
Inspection on November 19 and 20, 1979 (Report No.50-295/79-25; 50-304/79-23
Areas Inspected:
Nonroutine, announced inspection of licensee actions taken
in response to IE Bulletin 79-19 " Packaging of Low-Level Radioactive Waste for
Transport and Burial" and, as agreed with the State of South Carolina, verifi-
cation that identified packaging discrepancies were corrected before resumption
of radwaste shipments to Barnwell, South Carolina.
The inspection involved 28
inspector-hours onsite by two h3C inspectors.
Results: No items of noncompliance or deviations were identified.
8001200 C'4 C
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DETAILS
1.
Persons Contacted
L. Bloxsom, Training Instructor
- G.
Geer, Radwaste Planner
R. Krueger, Radwaste Foreman
- P. Kuhner, Quality Assurance Engineer
- B. Meyer, Health Physicist
R. Mika, Engineer
- F.
Rescek, Lead Health Physicist
C. Schultz, Training Supervisor
- C. Schuman, Assistant Superintendent, Operations
- L.
Soth, Assistant Superintendent, Administrative
- N. Wandke, Station Superintendent
.
R. Hahn, Hittn.an Nuclear and Development Representative
The inspectors also contacted several other licensee employees,
including members of the technical and engineering staffs.
- Denotes those attending the exit interview. (J. Kohler, Resident
Inspector, also attended the exit interview).
2.
General
This inspection was conducted to examine the licensee's treatment,
packaging, transfer, and transport of radioactive waste materials in
response to IE Bulletin 79-19 and to verify that certain procedural
modifications instituted in response to issues raised by the South
Carolina Department of Health and Environmental Control were imple-
mented before resumption of radwaste shipments to Barnwell, South
Carolina.
An Order from the South Carolina Department of Health and Environmental
Control, dated October 12, 1979, prohibited further shipment of radio-
active waste to South Carolina by Commonwealth Edison Company until
certain corrective actions concerning packa,ing of the waste materials
were completed.
In a meeting attended by NRC (RIII), South Carolina
Bureau of Radiological Health, and Commonwealth Edison Company personnel
in Columbia, South Carolina on Novemb2r 2, 1979, Region III agreed to
review the first radwaste shipment from each Commonwealth Edison Company
plant to Barnwell, South Carolina following rescission of the shipping ban.
An Order rescinding the October 12, 1979, Order was issued on November 9,
1979.
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3.
Regulations and Licenses
,
The inspectors verified that the licensee possessed current
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of the commercial burial sites and current copies of the Der
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Transportation and Nuclear Regulatory Commission regulations
transfer, packaging, and transport of radioactive matet al.
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for maintaining these documents current had been established b
licensee.
4.
Designation of Responsibilities
Procedure QP 13-52 from the Commonwealth Edison Company Quality Assurance
Manual delineates responsibilities by general job description for the
transfer, packaging, and transport of radioactive matarial. These respon-
sibilities are furth2r defined, by specific job titles applicable to the
Station. in Zion Station Adainistrative Procedure ZAP 13-52-8.
No problems
were no;ed regarding implementation of the transfer, packaging, and trans-
port re;ponsibilities.
,
5.
Procedures and Checklists
The inspectors selectively reviewed the following orocedures related to
the transfer, packaging, and transport of radioactive waste material.
QP 13-52
(Rev. 2)
Preparation and Shipment of
Radioactive Material
ZAP 13-52-8
(Rev. 6)
Preparation and Shipment of
Radioactive Material
RP 1520-1
(Rev. 7)
Offsite Shipment of Radio-
active Material
RP 1520-2
(Rev. 1)
Radioactive Waste Shipments
RP 1520-3
(Rev. 3)
Calculation of Curie Content
of Radioactive Shipments
RP 1520-4
(Rev. 1)
Surveying Radioactive Shipments
RP 1530-2
(Rev. 3)
Vehicle / Cask Shipment and
Receipt Form
SOI-69
(Rev. 3)
Solid Waste Disposal
S01-70
(Rev. 6)
Demineralizer Resin Removal
No discrepancies from the procedure review and approval format specified
in Section 6 of the Technical Specifications were noted.
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The licensee had completed a review of radiation protection procedures
relating to the transfer, packaging, and transportation of radioactive
material and had commanced a review of pertinetit operating procedures.
As specified in the 5_ptember 21, 1979, respe1se to IE Bulletin 79-19,
the licensee expects to complete the review o. all applicable procedures
by January 1, 1980. According to licensee personnel, completion of the
reviews will be documented.
To date, the licensee has identified needed revisions to RP 1520-1
(Offsite Shipment of Radioactive Material). Additional revisions to
RP 1520-1 were identified by the inspectors. Needed revisions include:
provision for exclusive use instructions to carrier, identification of
carrier, definition of package, and clarification of vehicle contamination
control.
The licensee possessed vendor procedures for handling (inspection,
loading, closing) the specific cask types in use.
According to licen-
see personnel, cask closure devices will receive increased attention
~
to preclude repetition of past problems with loose lid bolts / nuts
upon arrival at the burial site.
According to licensee personnel, these procedures will either be
incorporated into the plant procedures by reference or pertinent
information extracted for direct inclusion in plant procedures.
This matter will be reviewed further during a future inspection in
order to examine the results of the operating procedure review and to
review the revised procedures.
6.
Training
The inspectors reviewed the training of personnel involved in the
treatment, transfer, packaging, and transport of radioactive waste
materials. Although training programs are not presently well developed
in these areas, limited training has been provided to radiation protec-
tion personnel and applicable management personnel regarding regulatory,
license, and procedural shipping requirements. Training on the proper
operation of radioactive waste systems is given to operations personnel.
As specified in the September 21, 1979, response to IE Bulletin 79-19,
the licensee is presently engaged in review and revision of the training
programs for personnel involved in the treatment, transfer, packaging,
and transport of radioactive waste materials. This training effort is
scheduled for completion by early 1980.
This matter will be reviewed further during a future inspection in
order to examine the results of the training reviews and changes
implemented by the licensee.
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7.
Audits
The inspectors reviewed the licensee's audit activities regarding
low-level radioactive waste transfer, packaging, and transport
activities. These areas are audited approximately annually according
to licensee personnel and audit records. Administration of the audit
function was satisfactory regarding audit plans, reports, corrective
actions, qualifications of personnel, etc.
A special audit was conducted by an offsite audit team on September 20-21,
1979. The audit included an examination of Items 1-6 of IE Bulletin 79-19.
One item remained open from the September audit:
the lack of a retraining
program in regulatory requirements for low-level radioactive waste transfer,
packaging, and transport. As noted in Section 6 of this report, this item
will be reviewed further during a future inspection.
8.
Waste Packaging Sytems and Procedures
.
The inspectors observed the licensee's waste packaging systems and
equipment. The install d drumming station, designed for waste .olid-
ification with cement
has not been used for about two years.
A
number of mechanit i problems associated with conveyors, mixing, and
drum capping caused the licensee to resort to an alternate solidifi-
cation process. Major modifications are planned to permit use of the
on-line cement system in the future. The licensee presently uses por-
table demineralizers to cleanup liquids; Hittman Nuclear and Development
Corporation is contracted to solidify the resins in the demineralizer
liners which are shipped in HN-100, 200, and 600 casks. Evaporators,
although installed, are not currently used.
The liners contain dis-
posable mixing blades and a dewatering system. After dewatering the
resin liners, a portable mixing head is installed, water is added,
then the mixer is operated as cement is ad' d.
The volumes of water
and cement are predetermined based on res.a volume. Mixing is contin-
ued until the mixer slows or stops, indicating that solidification is
in progress. The mixing head is removed and a nonremovable cap is
installed on the liner opening.
Routine visual inspection of the mix
to confirm the absence of free liquid is not feasible, because of the
absence of a viewing port. The contractor periodically performs labo-
ratory scale tests to confirm that the solidified mix continues to be
acceptable. The inspectors stressed the importance of obtaining a mixture
which does not contain free liquid.
After capping the cask is closed and
the package is ready for survey and inspection using an approved check-off
procedure.
Noncompactible wastes, such as filters,
e packaged in 17-H steel
drums.
Drums used to package filters are prepared by pouring concrete
into the annulus surrounding a metal container centered in the drum.
The filter is placed in the container, then a bag of cement is broken
over the top of the drum to provide absorbent material for any liquid
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in the filter. An air gun is used to close the package.
Drums larger
than 55 gallons are used for filters requiring additional concrete
shielding. The inspectors observed the loading of 18 drums containing
filters into an HN-400 cask as described in Paragraph 9.
Compactible dry active wastes are also packaged in 55-gallon drums
using a conventional compactor. The licensee has procedures for drum
inspection, loading, compacting, and closing.
One drum from an accumu-
lation of several hundred in storaFe was opened for visual examination
by the inspector. The contents were dry, discarded protective clothing
in plastic bags.
E aden boxes have been used in the past for the packaging of dry, active
waste. The licensee stated that these would not be used again until
wcoden box standards are developed and the existing procedure has been
revised.
9.
Radioactive Waste Shipment
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The inspectors examined a radwaste shipment (#94) which was made do-fng
the inspection. Radiation levels associated with the loaded shipment
were independently verified by the inspectors, who also reviewed and.
selectively verified the procedures and checklists associated with the
shipments. Contamination levels were verified in the presence of the
inspectors. There was no documentation readily available to substan-
tiate the 3% efficiency used when counting smears with the GM probe.
This was discussed at the exit interview.
The shipment consisted of 55 gallon drums (eighteen) con'aining filter
elements positioned in the center, with cement occupying the remainder
of the drums. The drums were loaded in the HN-400 (Unit 1) cask.
Total activity was less than one curie. The maximum activity in any
drum was less than 0.2 curies of Transport Group III and IV radio-
nuclides. The most recent st rontium or transuranic analyses results
were greater than one year old. This was discussed at the exit inter-
view. All radiation levels were within regulatory requirements.
The shipment departed the site for transport to a ccmmercial burial
site on November 20, 1979.
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10.
Exit Interview
The inspectors met with licensee representatives (denoted in Paragraph
1) at the conclusion of the inspection on November 20, 1979. The
inspectors summarized the scope and findings of the inspection.
In
response to certain items discusssed by the inspectors, the licensee:
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Stated that procedural changes / additions identified during their
a.
review and the NRC inspectors' review would be effected.
(Para-
graph 5)
b.
Stated that a revised training program for the transfer, packaging,
and trarsport of radioactive waste materials would be developed by
January 18, 1980, and the program implemented by March 31, 1980.
The training review will include radwaste operator training /
retraining considerations.
(Paragraph 6)
c.
Stated that strontium and transuranic analyses of representative
radioactive waste would be canducted approximately quarterly.
(Paragraph 9)
d.
Stated that there would be no shipments of radioactive waste in
wooden containers until a reviev of such shipment methods was
completed and the present procedure for such shipments was revised.
(Paragraph 8)
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e.
Acknowledged the inspectors' comments to pursue methods for
preventing loosening of cask lid bolts / nuts during transportation.
(Paragraph 5)
f.
Acknowledged the inspectors' comments regarding the need for
ensuring solidification of radwaste. (Paragraph 8)
g.
Stated that documentation to substantiate use of a 3% efficiency
with the GM probe used for counting smears would be developed.
(Paragraph 9)
182R020
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