IR 05000245/1986006
| ML20198Q866 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/16/1986 |
| From: | Clemons P, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20198Q841 | List: |
| References | |
| 50-245-86-06, 50-245-86-6, 50-336-86-06, 50-336-86-6, IEB-79-19, NUDOCS 8606090399 | |
| Download: ML20198Q866 (8) | |
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l U.S. NUCLEAR REGULATORY COMMISSION
REGION I
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Report Nos.
50-245/86-06 50-336/86-06
Docket Nos.
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50-336 l
License No. OPR-21 Priority Category C DPR-65 Priority __
Category C
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Licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Point Nuclear Power Station, Units 1 and 2 Inspection At: Waterford, Connecticut Inspection Conducted: March 24-27, 1986
'l to SL Inspectors:
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P. Clemons, Radiation Specialist
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Approved by: N N
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W. Pasciak, Chief. Effluent Radiation da(e Protection Section Ins
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Inspection on March 24-27, 1986 Combined Report Nos.
!id pection Summary:24578F06 and 60-336/86-06 Areas _ Inspected:
Routine unannounced safety inspection of the licensee's transportation program by a regionally based inspector including:
shipments of radioactive material, package selection, procedures, Part 61, training, quality control and management control.
Results:
Five apparent violations were identified (package not labeled properly, para. 4; personnel not trained, para. 5; copies of documents not maintained, para. 6; procedure did not contain specifics as required by the technical specifications, para. 7; quality control program did not assure compliance with 10 CFR 61.56, para. 8),
i 8606090399 060530 PDR ADOCK 00000245 n
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DETAILS
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1.0 Personnel Contacted 1.1 Licensee personnel I
W. Romberg, Station Superintendent
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J. Kangley, Radiological Services Supervisor B. Granados, Health Physics Supervisor
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F. Libby, Supervisor Operations Quality Assurance D. Stands, Acting Radioactive Materials Handling Supervisor M. Sforza, Engineer, Operations Quality Assurance 1.2 NRC Personnel T. Rebelowski, Senior Resident Inspector
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Other licensee personnel were contacted and interviewed during this
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inspection.
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2.0 Purpose The purpose of this routine safety inspection was to review the Itcensee's program with respect to the following elements:
l Management controls;
Shipments of radioactive materials;
- Training;
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Records;
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10 CFR61 process control program;
I Package selection; and
Quality Control.
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l 3.0 Management Control l
The licensee's management controls were reviewed to determine if clear
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designation of responsibilities of personnel for transportation activities had been delineated. The licensee has designated Procedure No. ACP-QA-1.02, " Organization and Responsibilities", for this purpose.
The Radiological Services Supervisor has the overall responsibility for
the program. The Health Physics Supervisor has been charged with the
responsibility for implementing the program, and the Radiological Materials Handling Supervisor is responsible to the Health Physics
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j Supervisor for the implementation of the program, goals, and objectives,
on a day to day basis, i
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l With the scope of this review, no violations were identified.
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4.0 Shipments of Radioactive Material The transportation of licensed material was reviewed against the criteria contained in 10 CFR 71, " Packaging and Transportation of Radioactive Material", and 49 CFR Parts 170 through 189.
The licensee's performance relative to these criteria was determined from discussions with the Health Physics Supervisor, the Acting Radiological Materials Handling Supervisor, the principal Radioactive Matarials Handler, and by reviewing appropriate documents.
Within the scope of this review, the following apparent violation was identified.
On March 5,1986, the licensee transported 488 Curtes of licensed material in Package No. CNSI 8-120-5 to a burial site in South Carolina. On
March 7,1986, a representative of the South Carolina Department of Health and Environmental Control inspected the shipment at Barnwell, South Carolina.
The representative of the State noted that the package was labeled as Radioactive Yellow II.
The representative also noted that the licensee had listed the Transport Index as 3.
The representative also observed that the vehicle transporting the package was not placarded.
10 CFR 71.5, " Transportation of licensed material", states, "Each licensee who transports licensed material outside of the confines of its plant or other place of use, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the regula-tiens appropriate to the mode of transport of DOT in 49 CFR Parts 170 through 189."
49 CFR 172.403(c) " Radioactive Material" requires that packages must be labelled with a Radioactive Yellow-III label if the
Transport Index is greater than 1.0.
In addition, 49 CFR 172.504 requires the vehicle be placarded if the vehicle contains packages of
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licensed material that are labelled Yellow-III.
The failure to properly label the package, and placard the vehicle transporting the package is an apparent violation of 10 CFR 71.5
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(50-245/86-06-01 and 50-336/86-06-01).
5.0 Training The training of Radioactive Materials Handling personnel was reviewed against Criterion II, " Quality Assurance Program", Appendix B, Part 50, and IE Bulletin 79-19, " Packaging of Low-Level Radioactive Waste for Transport and Durial".
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a The Itcensee's performance relative to these criteria for Radioactive
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Materials Handling personnel was determined by discussions with the Health
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Physics Supervisor, the Acting Radioactive Materials Handling Supervisor, and the principal Radioactive Materials Handler, i
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th he scope of this review, the following apparent violation was On March 24, 1986, the inspector discussed the March 5, 1986 shipment with
Radioactive Materials Handler.the Acting Radioactive Materials Handling The inspector asked the two licensee i
March 5,1986 shipment occurred. representatives to explain how the violation
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Both individuals stated that, "I missed
l Supervisor had been in his present position for about'a y
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j received no training, formal or otherwise, since assuming his present i
position.
Prior to assuaiing this position, he was an Instructor providing health physics. training at the Corporate Office, a position i
which he occupied for several years.
The Acting Radioactive Materials Handling Supervisor was scheduled for a 2-3 day training program in trans-
i portation activities during the week of March 31, 1986.
The inspector determined that the principal Radioactive Materials Handler had been in his present position approximately 12-15 months, and had
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received training over a two day period shortly after becoming a Radio-active Materials Handler.
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Criterion II, Appendix B, Part 50 states, in part, that the licensee shall
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affecting quality as necessary to assure that suitable p i
achieved and maintained.
f The failure to provide indoctrination and training as necessary to assure that suitable proficiency was achieved and maintained for the Acting Radioactive Materials Handling Supervisors and the principal Radioactive
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t Appendix 8, Part 50 (50-245/86-06-02 and 50-336/86-06
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6.0 Records
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Several shipments of radioactive material were reviewed against the
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criteria contained in 10 CFR 71.12, " General license:
NRC approval tl package".
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i The 11censees performance relative to these criteria was determined by discussion with the Acting Radioactive Materials Handling Supervisor, and the principal Radioactive Materials Handler, and by reviewing appropriate
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records.
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Within the scope of this review, the following apparent violation was identified.
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i The inspector determined that on March 5, 1986, the licensee shipped 438 l
Curies of radioactive material in package Model No. CNS 8-120, Certificate of Compliance (C of C) No. 6601, and on March 14, 1986, the licensee shipped 4.1 curies of radioactive material in package Model No. CNS 21-300, C of C No. 9096.
10 CFR 71.12(a), " General license:
NRC approved package" states "A general license is hereby issued to any licensee of the Commission to transport, or to deliver to a carrier for transport, licensed material in a package l
for which a license, certificate of compliance, or other approval has been l
issued by the NRC."
10 CFR 71.12(c) states "This general license applies only to a licensee
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who:
(1) Has a copy of the specific license, certificate of compliance, or other approval of the package and has the drawings and other documents j
referenced in the approval relating to the use and maintenance of the l
packaging and to the actions to be taken prior to shipment."
For the shipment made on March 5, 1986, the licensee did not have copies of the drawings or other documents referenced in the C of C relating to the use and maintenance of the package.
The licensee did not have copics of the drawings referenced in the C of C for the package used in the shipment on March 14, 1986.
The failure to have copies of the referenced drawings and other documents represents an apparent violation of 10 CFR 71.12 (50-245/86-06-03 and 50-336/86-06-03).
7.0 process Control Program The licensee's process control program for the solidification process used was reviewed against critoria contained in 10 CFR 61.56, " Waste Charac-
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teristics" and Technical Specification 6.16. " Radioactive Waste Treatment."
The licensee's performance relative to these criteria was determined by discussion with the Acting Radioactive Materials Handling Supervisor, the principal Radioactive Materials Handler, and by reviewing appropriate documents.
Within the scope of this review, the following apparent violation was identified.
The inspector determined that on February 13, 1986, the licensee shipped 943 Curies of radioactive material contained in Thermal Shield Pins
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solidified in Envirostone.
The solidification operation was performed by a vendor.
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The licensee's Process Control Program For The Millstone Power Station,
" Commitments", Item 4, states, " Approved station or vendor procedures will include the following detailed information:
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A general description of laboratory mixing of a sample of the waste l
to arrive at process parameters prior to commencing the solidifica-tion process.
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A general description of the solidification process including types l
of solidification agent, process control parameters, parameter
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boundary conditions, proper waste form properties, and assurance the l
solidification systems are operated within established process parameters, c.
A general description of sampling of at least one representative sample from every-tenth batch to ensure solidification and action to be taken if the sample falls to verify solidification.
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Provisions to verify the absence of free liquid, e.
Provision to process containers in which free liquids are detected, f.
Specification of the process control parameters which must be met prior to capping the container if the solidification is exothermic."
The licensee had a copy of the vendors Topical Report for solidification that apparently had been submitted to the NRC on June 27, 1984.
The Topical Report contained the vendors process control program, but the vendors program did not meet the licensee's requirements as specified above.
The failure to conduct a process control program as required represents an apparent violation of Technical Specification 6.16 (50-245/86-06-04 and 50-336-/86-06-04).
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8.0 Quality _ Control The licensco's quality control program for waste characterization was reviewed against criteria contained in 10 CFR 20.311(d)(3), " Transfer for l
disposal and manifests".
The licensee's performance relative to these criteria was determined by discussions with the Acting Radioactive Materials Handling Supervisor, the principal Radioactive Materials Handler, the Quality Assurance / Quality I
l Control Supervisor, a Quality Control Inspector, and by reviewing appropriate documents.
Within the scope of this review, the following apparent violation was identified.
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The inspector determined that the licensee shipped 4.1 Curies of radio-active material in evaporator bottoms, solidified in cement, on March 14, 1986.
The licensee used a second vendors Topical Report and process control program contained in Procedure No. STD-P-05-025, in this shipment. This process control program met the licensee's Techr.ical Specification 6.16 requirements.
The inspector noted that the process control program contained numerous parameters that appeared to require quality' control surveillance. The Quality Assurance / Quality Control Supervisor informed the inspector that only the following acceptance criteria was verified by the Quality Control Inspectors:
The sample solidifications are considered acceptable if there is no visual or drainable free water, and i
If upon visual inspection the waste appears that it would hold its shape if removed from the mixing vessel, and
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It resists penetration, j
The verification of solidification alone of the vendors process control t
program, by the licensee's Quality Control Inspectors, is not sufficient
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to verify that the numerous parameters associated with the solidification process are incorporated into a quality control program, i
The failure to conduct a quality control program to assure compliance with
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10 CFR 61.56 represents an apparent violation of 10 CFR 20.311(d)(3)
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[50-245/86-06-05and50-336/86-06-06]
9.0 Package Selection The licensee's program for selection of packages was reviewed against the
i requirements of 10 CFR Parts 71.12, 71.13 and 71.14, and the DOT require-
ments of 49 CFR Part 173, i
The licensee's performance relative to these criteria was determined by j
discussion with the Acting Radioactive Materials Handling Supervisor and j
the principal Radioactive Materials Handler.
Within the scope of this review, no violations were identified.
10.0 Exit Interview
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The inspector met with the Ilcensee representatives (denoted in paragraph 1) at the conclusion of the inspection on March 27, 1986.
The inspector summarized the scope of the inspection, and the findings.
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Copies of the following documents were given to the licensee during this inspection:
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Regulatory Guide 7.10. " Establishing Quality Assurances Programs For Packaging Used In The Transport Of Radioactive Material".
B.
Final Waste Classification And Waste Form Technical Position Papers.
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