ML20206N378
| ML20206N378 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/11/1986 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20206N366 | List: |
| References | |
| 50-458-86-22, NUDOCS 8608260244 | |
| Download: ML20206N378 (10) | |
See also: IR 05000458/1986022
Text
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APPENDIX C
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/86-22
License:
Docket:
50-458
Licensee: Gulf States Utilities (GSU)
P. O. Box 220
St. Francisville, Louisiana 70775
Facility Name:
River Bend Station (RBS)
Inspection At:
RBS, St. Francisville, Louisiana
Inspection Conducted: June 30 through July 3,1986
Inspector:
J
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[M
R6 E. Baer, Radiation Specialist, Facilities
Date
Radiological Protection Section
M
Approved:
4_/
Biaine Murray, Chieft Facilities Radiological
Date
Protection Section
Inspection Summary
Inspection Conducted June 30 through July 3,1986 (Report 50-458/86-22)
Areas Inspected:
Routine, unannounced inspection of the licensee's solid
radioactive waste and transportation activities program including:
organization and management controls, training and qualifications, low-level
radioactive waste storage, audits, transportation activities, and solid waste
management.
Results: Within the area inspected, one violation and one deviation were
identified (see paragraphs 6 and 9).
8608260244 860820
ADOCK 05000458
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DETAILS
1.
Persons Contacted
GSU
- W. J. Cahill, Jr., Senior Vice President
- J. C. Deddens, Vice President, River Bend Nuclear Group
- T. F. Plunket Plant Manager
T. P. Anthony, Senior Mechanical Engineer
- R. E. Bailey, Supervisor, Quality Control
- J. P. Bleau, Radwaste Specialist
L. N. Campo, Radwaste Specialist
- E. M. Cargill, Supervisor, Radiological Programs
- J. W. Cook, Environmental Analyst
^*T. C. Crouse, Manager, Quality Assurance (QA)
S. Desai, Chemical Process Engineer
- R. G. Easlick, Radwaste Supervisor
- D. R. Gipson, Assistant Plant Manager, Operations
- B. R. Hall, Plant Service Supervisor
- K.
C. Hodges, Supervisor, Quality Engineer
- R. J. King, Licensing Engineer
- J. M. McGhee, Radwaste Foreman
C. L. Nash, Chemistry Supervisor
- K. Ormstedt, QA Engineer
- E. R. Oswood, Senior QA Engineer
- K. E. Suhrke, Manager Projects, Planning
- P.
F. Tomlinson, Director, Quality Services
- M. E. Walton, Technical Assistant
Others
D. K. Carner, Solidification Technician, Chem-Nuclear
D. J.-Jeffrey, Solidification Technician, Chem-Nuclear
D. D. Chamberlain, Senior Resident Inspector, NRC
W.
B.' Jones, Resident Inspector, NRC
The NRC inspector also interviewed several other licensee and contractor
employees.
- Denotes those individuals present during the exit interview on July 3,
1986.
2.
Inspector Observations
The following is an observation the NRC inspector discussed with the
licensee during the exit interview on July 3, 1986. This observation is
neither a violation nor unresolved item. This item was recommended for
licensee consideration for program improvement, but it has no specific
regulatory requirement. The licensee stated this item would be reviewed.
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- Radioactive Waste Segregation' Program - The licensee had not implemented a
radioactive vaste segregation program. See paragraph 9 for additional
details.
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3.
Organizat' ion and Management Controls
The NRC inspector reviewed this licensee's staff functional assignments
relating to solid radioactive waste and transportation activity
organization and management controls for compliance with Inspection and
Enforcement (IE)Bulletin 79-19, Technical Specification (TS) 6.2 and
commitments in Section 13.1.2.1.1 of the Final Safety Analyses
Report (FSAR).
The licensee had not issued the GSU Radioactive Waste. Management Policy
Statement (RWMPS) at the time this inspection commenced. This issue had
been addressed in NRC Inspection Report 50-458/85-82, at which time the
licensee stated the RWMPS had not been issued because of some ninor
changes that needed to be addressed. The NRC inspector discussed with
licensee representatives the delay in the issuance of the RWMPS and that
procedure ADM-0038, " Radioactive Waste Management Program," Revision 3,
May 29, 1986, Attachment 1 contains a RWMPS which would lead an individual
to believe this statement had been issued. As a result of these
discussiens, the licensee issued the RWMPS on July 3, 1986.
The NRC inspector expressed concern and discussed with licensee
representatives the apparent lack of management commitment to the
radioactive waste management program. The licensee indicated that they
would review the inspector's concern.
No violations or deviations were identified.
4.
Training and Qualifications
The NRC inspector reviewed the licensee's training program for personnel
involved in solid radioactive waste activities and transportation of
radioactive materials to determine compliance with this requirement of
IE Lulletin 79-19, TS 6.4 and commitments in Section 13.2 of the FSAR.
The NRC inspector reviewed the qualifications and training for personnel
responsible for radioactive material transportation-activities and
reviewed the regulatory awareness training program which personnel are
required to attend.
The NRC inspector noted that the radwaste supervisor maintains a roster of
radwaste qualified radiation protection technicians to ensure that those
persons performing transportation activities are qualified by training.
Procedure RWS-0203, " Personnel Qualifications for Radwaste Section,"
contains the qualification requirements for all personnel assigned to the
radioactive waste management organization and support personnel who perform
transportation activities.
No violaticns or deviations were identified.
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5.
Low-Level Radioactive Waste Storage Facility
The1TRC inspector reviewed the status of the low-level radioactive
waste (LLRW) storage facility for compliance with the facility license
conditions and the recommendations of NRC Generic Letter 81-38,
NRC IE Circular 80-18, NRC Regulatory Guide (RG) 1.143 and NUREG-0800.
The licensee had not constructed, or planned for the construction of a
LLRW storage facility. Section 11.4.2.7 of the final safety analysis
report addresses the storage capacities for reactor operations.
No violations or deviations were identified.
6.
Waste Generator Requirements 10 CFR 20 and 10 CFR 61
The NRC inspector reviewed the licensee's program for disposal of LLRW to
determine compliance with the requirements of 10 CFR Parts 20.311, 61.55,
and 61.56.
The licensee presently uses scaling factors as described in the procedure
" Methodologies for Classification of Low-Level Radioactive Waste from
Nuclear Power Plants," issued by the Atomic Industrial Forum. The
licensee had issued a purchase requisition for a vendor to provide for the
determination of sample locations and for the analysis of samples to meet
the requirements of 10.CFR Part 61.
On May 19, 1986,, Gulf States Utilities shipped 70 millicuries of byproduct
material, designated as Low Specific Activity (LSA), in the form of solid
metal oxides on resin solidified in cement.- The shipment was made by a
Common Carrier on a tractor-trailer containing two type 14-195 liners. On
May 23, 1986, a representative of the South Carolina Department of Health
and Environmental Control inspected the shipment. The inspection
consisted of a review of shipping papers, placarding, marking and
labeling, radiation measurements, selective contamination surveys, and
examination of the packages and the vehicle.
A copy of the report prepared by the representative of South Carolina
Department of Health and Environmental Control is enclosed as
Attachment 1.
The report indicates that the shipment contained liquids in
excess of the allowable limits specified by Condition 32.B of the
South Carolina Radioactive Material License No. 097.
10 CfR Part 30.41(c) prchibits transfer of byproduct material unless it is
in a form authorized by the recipient's NRC or Agreement State License.
Condition 32.B of South Carolina Radioactive Material License No. 097,
Amendment 41, an Agreement State License issued to Chem-Nuclear Systems,
Inc., prohibits the receipt of solidified waste with " detectable free
standing liquid" which is defined as liquid in excess of 0.5 percent by
waste volume of non-corrosive liquids per container.
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According to the state representative, approximately 55 gallons of liquid
was found within the liner. Apparently, the liquid observed was released
from the solidification media used to solidify the waste. The 55 gallons
of free standing liquid represents approximately 3.7 percent by waste
volume; therefore, the transfer of byproduct material on May 19, 1986, to
Chem-Nuclear Systems, Inc., containing free standing liquid in excess of
Chem-Nuclear license limits is an apparent violation of 10 CFR Part 30.41(c) -(458/8622-01) .
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7.
Audits
The NRC inspector reviewed audits performed by the licensee of the
radwaste management. system to determine compliance with TS,
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Sect,1on 6.5.3.8s
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The NRC inspector reviewed audits 86-02-I-PCON, " Process Control Program"
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conducte'd during the period February 11-18, 1986, and 86-06-I-RWMP
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" Radioactive Waste Management Program," conducted June 17-27, 1986. The
NRC inspector attended the exit interview held on June 30, 1986, for
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audit 86-06-I-RWMP.
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The NRC inspector reviewed the audit checklist for both audits. The NRC
inspector noted that all items identified in audit 86-02-I-PCON had been
satisfactorily resolved.
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No violations or deviations were identified.
8.
Transportation Activities
The NRC inspector reviewed the licensee's transportation program to
determine compliance with 10 CFR Parts 20 and 71, and DOT Regulations
40 CFR Parts 170-189.
a.
Quality Assurance Program
The NRC inspector determined that the licensee had submitted a QA
program for approval to the NRC to comply with 10 CFR Part 71,
Subpart H.
The licensee had received NRC Form 311, Quality Assurance
Program Approval, approval number 0566, Revision 0, dated January 13,
1986, with an expiration date of January 31, 1991.
b.
Procedure and Selection of Packaging
The NRC inspector reviewed the licensee's program for procurement and
seicetion of packaging for compliance with the requirements of 10 CFR
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Parts 71.12 and 71.43 and 49 CFR Part 173.
The NRC inspector reviewed the licensee's procurement of DOT and NRC
certified packaging. The licensee had available appropriate
documentation on design, use, maintenance, testing, and NRC/ DOT
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certification. The licensee had applied for and received approval to
be placed on the users list for these packages.
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The NRC inspector noted the licensee had not made any shipments which
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required DOT and NRC certified packaging.
c.
Preparation of Packages for Shipment
The NRC inspector reviewed the licensee's program for preparation of'
packages for shipment to determine compliance with the requirements
of 10 CFR Parts 20.311, 71.12,.and 40 CFR Parts 172 and 173.
The NRC inspector noted that the licens'ee, in accordance with written
procedures, assures that prior to each use the package: is proper
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for the contents to be shipped; is in unimpaired physical condition;
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is properly marked; complies with the radiation level ILmits at the
surface of the package; and removable non-fixed contamination is
below the regulatory limits.
d.
Delivery of Completed Packages to Carrier
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The NRC inspector reviewed the licensee's program for delivery of
completed packages to a carrier for transport to determine compliance
with 10 CFR Parts 20.311, 71.55 and 49 CFR Parts 170 to 178.
The NRC inspector noted the licensee uses a shipment checklist to
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verify that regulatory requirements are being met.
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e.
' Receipt of Packages
The NRC inspector reviewed the licensee's program for receipt of
packages containing radioactive material to deternine compliance with
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- The licensee's activities for receipt of radioactive material are
governed by procedure RSP-0205, " Receipt of Radioactive Material"
Revision 2, June 15, 1985. The NRC inspector reviewed this procedure
for consistency with regulatory requirements and to determine whether
it covired all aspects of the work being performed.
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Records, Reports and Notifications
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The NRC inspector reviewed the records for 9 of the 10 radioactive
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material shipments"made during the calendar year 1985 and 23 of the
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37. radioactive material shipments made during the period January
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through June 30, 1986, for compliance with the requirements of 10 CFR Parts 20.311'and 61.80. The licensee maintains records of all
radioactive material shipments as required. The records were
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complete with all shipping documentation, including the receipt and
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shipping radiation survey data.
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The NRC inspector reviewed the licensee's procedures for the radioactive
material handling and shipping program listed in Attachment 2.
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RNo violations or' deviations were identified.
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9.
Solid Waste Management
The NRC inspector reviewed the licensee's solid radioactive waste
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management program for compliance with TS 6.9.1.8, 6.10.2, 6.13 and 6.15'
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and commitments contained in Section 11.4 of the FSAR.
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The NRC inspector reviewed as installed and operational solid radwaste
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system to determine agreement with the FSAR, Section 11.4.2.1, " General
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- Description" Amendment 20, June 1985 and as depicted in Figure 11.4-1,
" System 604 Radwaste-Solid," Amendment 21, July 1985.
The NRC inspector noted that waste sludge tank and associated equipment
described in FSAR Section 11.4.2.2 had been completed, with the exception
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of a sample valve, but was not operational. The licensee had installed a
temporary bypass and spent resins were transferred to the Chem-Nuclear
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Systems, Inc. (CNSI) portable solidification system which is different
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than the system depicted in Figure 11.4.1.
Section 11.4.2.3.1 of the FSAR
states "GSU identifies the curie content and radionuclide identification
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for waste to be solidified prior to delivery to CNSI."
However, the NRC
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inspector noted that the method used by the licensee is to transfer the
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vaste to CNSI and then take a sample from the waste and cement six for
curie content and radionuclide identification.
Section 11.4.2.3.3 of the FSAR identifies a waste compactor and discusses
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the operation of the compactor. However, the NRC inspector noted that the
licensee has not installed this waste compactor.
The NRC inspector discussed with licensee representatives the status of
the solid radwaste system and the scheduled completion of the system
described in the FSAR. The NRC inspector stated that the failure to have
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a solid radwaste system operational as described and depicted in the FSAR,
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Section 11.4 was considered an apparent deviation from this commitment
(458/8622-02).
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The NRC inspector discussed with licensee representatives the radioactive
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vaste segregation program. The licensee had implemented a waste
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segregation program after initial fuel loading and had segregated a small
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amount of ~ waste, but had not released any material from the facility. The
licensee was presently accumulating all material from the radiologically
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controlled area and placing this material in steel containers or ateel
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d rums. The licensee had approximately 5000 cubic feet of unoegregated,
uncompacted waste at the time of this inspection stored in various plant
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The NRC inspector expressed concern and discussed with licensee management
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the' excessive amount of dry uncompacted, unsegregated waste that was being
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accumulated at a rate of 15 to 30 cubic feet per day. The licensee stated
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that they had designated space to store approximately 3000 cubic feet of
waste. 'During the exit interview on July 3, 1986, the licensee committed
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'to implement.a waste segregation program prior to the October 1986
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maintenance outage or dispose of the excess waste.
10.
Exit Interview
The NRC inspec'or met with the licensee representatives denoted in
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paragraph 1 at the conclusion of the inspection on July 3, 1986. The NRC
inspector summarized the inspection scope and findings.
The licensee committed to the NRC inspector to implement a waste
segregation program prior to the October 1986 maintenance outage or
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dispose of excess waste.
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ATTACIDIENT 1
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awwan wwwt.Ana ur.rAKint.Nr OFur.AMs AND F.HV AKUnnr. MAL wnanOL
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Bureau of Radiological Realth
Division of Radioactive Material Licensing and Compliance
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n=diametive Shipment Inspecties Esport
/semeral Inforesties:
Emport No. 86-05-47
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/ 1.
Shipper Culf States Utilities-River Bend Station Address St. Francisville. LA
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2.
Carrier Tri-State Motor
Tractor f 2313
Trailer #345315
Type Platbed
3.
Type PackageigEIk 2 liners
EIER Containing solidified resin in cement
B.
Skipping Documsstation:
1.
ASI 43264
Volume Allocation f 0586-126-A
Permit # 0232-17-86-X
2.
Shipping Esse & Class: Radioactive u=*arialT LSA. mas
M Id.f W 2912 (172.202(a))
3.
Total Burial Vol.: 412
ftJ(172.202(c) Total curies: 0.06962
(172.203(d))
4.
Radionnelides:Cr-51. Ih-54. Co-58460. Pw-59. En-65. Er-95. Es & La 140
(172.203(d))
5.
Describe chem./phy. media: solid metal oxides on resin solidified in cement (172.203(d))
6.
Chelating Agente(%)t... ek.- nghippers Certification: State N
DOT N
(172.204)
7.
Instructions N
(173.425(b)) Total T.I.
(177.842(a))
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8.
Check for: Radiation Survey 'N T .441)
Contamination Levels N
(173.443)
9.
Compare: Radionuclides w/ resin analysis N
Rad / Contamination Levels w/CESI/BRH N
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shipment Imopection Check List:
N-
Shipment Braced / Blocked (173.425(b)(6)
N Lids (Drum
cask) secure (173.425)(b)
N Visible Leakage (173.425(B)(1)
N Visible Damage (173.425)
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Package Labelina: U-I, Y-II. III(172.403)
EA Cask Defects /Misstag Parts
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(b) & (c) or (Radioactive LSA) (173.425)
T adiation Servey: Cab / sleeper.
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N
Waste Class. Marked
B-C StableUnstabib
trailer / truck (173.441)
Cross Weight Markad @(172.310)
N
'N
Contami=mtion Levels (173.443)
ILSA Exclusive Use Exempt]
e Vehicle Placards (173.425(c) (172.507)
N QType A Type B Package Marked (172.310)
N4 Tiedoens Secare/ Adequate
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Trailer / Tractor Defects
I Offloading Discrepancies
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NA Packages banded / reinforced, ps11etized
D.
Radiaties/ Coat-i-ties Serveys (transport vehicle or package)
(mR/hr)
Surface:
4.0
2 meters:
Surface:
Cab / sleeper
Surface:
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0.1
2 meters:
2 meterar
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Surface:
4.0
2 meters:
0.5
Eighest contamination detected: Arrival 8 alpha
dym/100 cad Belease
dyn/100c 2
16 bete samme
dym/100cm2
dgia/100cm2
E.
Enemits of Inspecties: Summary of violations and discroyancies A Department inspectiam of
t his shionent revealed liould in excess of allowable limits ikSS Drsstemme).
C-=.
M ==11 ann of if anid was drained from this liner wittr en}F P.35 maf3ses mI3esemble. TM
in ennerary to the reeuf r-
nen~of 32.B of S.C. Radioactive Material License 097.;
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A=,nA-.ne
at
==A ennaritures a vioistian of Section 1.2. ta_.-
^ Be_e_=tation 61-83.
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Date:
May 23, 1986
Inspector's Signet e s/ Richard S. Sappington
11 REC 810 (Rev.10 /84)
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ATTACHMENT 2
Procedures reviewed during NRC Inspection 50-458/86-22
ADM-0022
" Conduct of Operations," Revision 7, May 29, 1986
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ADM-0038
" Radioactive Waste Managemsnt Program," Revision 3, May 29, 1986
ADM-0043
"Radwaste Management Plan," Revision 1, January 13, 1986
RWS-0203
" Personnel Qualification for Radwaste Section," Revision 2
July 24, 1985
RWS-0204
" Process Control Program," Revision 1, May 1, 1986
RWS-0305
"Use of the Dry Active Waste Storage Facility (DAWSF),"
Revision 2, May 6, 1986
RWS-0307
" Radioactive Waste Segregation," Revision 1, May 3, 1985
RWS-0308
" Evaluation and Determination of Shipping Container Activity,"
Revision 1, May 30, 1985
RWS-0313
" Receipt Inspection, Storage, and Inventory of Radioactive
Material Shipping Packages," Revision 2, June 17, 1986
PWS-0324
" Shipping Special Form Radioactive Material," Revision 2,
May 6, 1986
Quantities of Radioactive Material," Revision 2,
RWS-0325
" Shipping _,A 2
May 13, 1986
Quantities of Radioactive Material," Revision 2,
RWS-0326
" Shipping _A2
May 17, 1986
RWS-0329
" Shipping Empty Radioactive Containers," Revision 2, June 4,
1986
RWS-0330
" Shipping Limited Quantities of Radioactive Material,"
Revision 2 May 6, 1986
SD-OP-003-518 " Process Control Program for CNSI Cement Solidification Units
River Bend," Revision A. June 30, 1986
COP-0048
" Sampling of Spent Resin," Revision 1, March 25, 1985