ML13017A148
| ML13017A148 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/13/2009 |
| From: | Hamrick G Duke Energy Carolinas |
| To: | Document Control Desk, NRC/NMSS/SFPO |
| References | |
| Download: ML13017A148 (9) | |
Text
P Duke GEnergy Carolinas DUKE ENERGY CAROLINAS, LLC Catawba Nuclear Station 4800 Concord Road York, SC 29745 August 13, 2009 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention.: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 and 2 Docket Nos.
50-413 and 50-414 10 CFR 71.95(c) Shipping Cask Report Pursuant to 10 CFR 71.95(c),
the attached report is being submitted to the NRC as a 60-day report due to not meeting the conditions of NRC approval for the cask Certificate of Compliance.
There are no regulatory commitments contained in this letter or its attachment.
This event is considered to be of no significance with respect to the health and safety of the public.
If there are any questions on this report, please contact L.J. Rudy at (803) 701-3084.
Sincerely, George T.
Hamrick LJR/s Attachment 0 ý 7301 www. duke-energy. corn
Document Control Desk Page 2 August 13, 2009 xc (with attachment):
L.A. Reyes Regional Administrator., Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.W.,
Suite 23T85
- Atlanta, GA 30303 J.H. Thompson (addressee only)
NRC Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station Energy Solutions 140 Stoneridge Drive
- Columbia, SC 29210
Catawba Nuclear Station, Units land 2
10 CFR 71.95(c) Shipping Cask Report Prepared by:
Reviewed by:
Approved by:
4~b4~
Date:
D*//30 Date:
Date: :
__________O R.D. Hart J. W. - Foster 1
(c) Each licensee shall submit, in accordance with § 71.1, a
written report required by paragraph (a) or (b) of this section within 60 days of the event or discovery of the event. The licensee shall also provide a copy of each report submit'ted to the NRC to the applicable certificate holder.
Written reports prepared under other regulations may be submitted to fulfill this requirement if the reports contain all the necessary information, and the appropriate distribution is made. Using an appropriate method listed in § 71.1(a), the licensee shall report to: ATTN:
Document Control Desk, Director, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards. These written reports must include the following:
(1) A brief abstract describing the major occurrences during the event, including all component or system failures that contributed to the event and significant corrective action taken or planned to prevent recurrence.
An NRC approved 8-120B shipping cask (package) was shipped to Barnwell Waste Disposal Site without required leak testing of the secondary lid and vent port being performed.
The shipment was made on 6/17/09 and the error was discovered on 6/18/09 during additional reviews of the shipping documents.
Required procedure steps in MP/0/A/7550/011 (Energy Solutions 8-120B Cask Handling,
- Loading,
& Unloading) were not performed by Maintenance personnel as expected.
Immediate corrective actions were to have the leak testing performed by Energy Solutions before the cask was'opened.
Both the secondary lid and the vent port passed the leak test.
Significant corrective actions taken or planned in response to this event are:
- Revise Maintenance procedures involving handling, loading, and unloading shipping casks to include a user checkoff sheet to require a Maintenance supervisor and a Radiation Protection staff person to certify that the cask has been loaded and tested in accordance with approved procedures.
- Radiation Protection shipping procedures to be revised to include additional defense-in-depth for the shipping process by adding involvement of Radiation,"Protection management prior to a shipment leaving the Catawba site.
" Maintenance will revise the appropriate task qualification to add knowledge/skill elements for pressure testing.
" Maintenance will develop and implement an improvement plan concerning Procedure Use and Adherence.
- Personnel corrective actions have been taken commensurate with their inappropriate actions.
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(2) A clear, specific, narrative description of the event that occurred so that knowledgeable readers conversant with the requirements of part 71, but not familiar with the design of the packaging, can understand the complete event. The narrative description must include the following specific information as appropriate for the particular event.
(i)
Status of components or systems that were inoperable at the start of the event and that contributed to the event; All components associated with this event (primary lid, secondary lid, and vent port) were operable during this event.
(ii)
Dates and approximate times of occurrences; The event occurred on 6/17/09 but was discovered during a paperwork review on 6/18/09.
Energy Solutions was notified of the missed leak test by Catawba Nuclear Station at 12:00 on 6/18/09.
(iii)
The cause of each component or system failure or personnel error, if known; The root cause of this event was that a temporary Maintenance supervisor inappropriately N/A'd a procedural step that required a pressure test to be performed on the secondary lid and vent port.
The team had not internalized the value of human performance tools (Procedure Use and Adherence).
There were no component or system failures associated with this event.
(iv)
The failure mode, mechanism, and effect of each failed component, if known; There were no component failures associated with this event.
(v) A list of systems or secondary functions that were also affected for failures of components with multiple functions; No other systems or components are associated with this event.
(vi) The method of discovery of each component or system failure or procedural error; This event was discovered on 6/18/09.
A Radiation Protection supervisor was contacted by Energy Solutions.
The Energy Solutions individual informed the supervisor that he needed a copy of the cask user's checklist.
The supervisor requested that a technician review the cask user's checklist because the s~upervisor's signature was required on the document.
Procedure MP/0/A/7550/011 does not have a cask user's checklist.
The entire procedure is typically sent with the shipment in lieu of the checklist.
However, this procedure was not originally sent.
Following the discussion with Energy Solutions, the supervisor 3
reviewed the procedure and determined that all specified tests were not performed on the cask.
The supervisor notified Radiation Protection and Maintenance supervision and then notified Energy Solutions.
A Condition Report was sent from Energy Solutions to Catawba to be completed within thirty days of the incident.
The supervisor forwarded the Condition Report to his management.
The event was documented in the station's corrective action program.
An investigation subsequently determined that the procedural step requiring leak testing of the secondary lid and vent port had been NA'd by a temporary Maintenance supervisor.
There were no component or system failures involved in this event.
(vii) For each human performance-related root cause, a discussion of the cause(s) and circumstances; During this event, personnel failed to follow the process to N/A a procedure step.
The lead Maintenance technician.assumed the role of a temporary Maintenance supervisor in order to approve the N/A of procedure steps.
The technician believed that Maintenance supervisors had left for the day, but he did not verify this.
The lead technician inappropriately determined that the secondary lid and vent port pressure tests were not necessary because the tamper seal had not been disturbed.
He therefore N/A'd the required pressure tests.
(viii)
The manufacturer and model number (or other identification) of each component that failed during the event; and There were no component failures associated with this event.
(ix)
For events occurring during use of a packaging, the quantities and chemical and physical form(s) of the package contents.
This event involved the shipment of:
Radioactive material, Type B(U) package, 7, UN2916, Fissile
- Excepted, RQ - Radionuclides (1) metal cask dewatered mechanical filters.
Physical/Chemical Form: Solid/Metal Oxide Volume: 120.30 cubic feet Waste and Container Weight: 1795.7 lbs 4
Radionuclides:
Security-Related Information Text Withheld under 10 CFR 2.390
(3) An assessment of the safety consequences and implications of the event. This assessment must include the availability of other systems or components that could have performed the same function as the components and systems that failed during the event>
There were no safety consequences or implications associated with this event.
A violation occurred because a leak test was not performed on the secondary lid and vent port prior to the shipment leaving the site.
The tamper seal was not disturbed on the affected cask and the cask was not opened during shipment.
The required pressure tests were performed by Energy Solutions at the disposal site prior to cask unloading.
Both the secondary lid and the vent port passed the leak test when performed by Energy Solutions.
Therefore, at no time was the cask in transport without mee'ting all regulatory requfrements for shipping a Type B cask.
(4)
A description of any corrective actions planned as a result of the event, including the means employed to repair any defects, and actions taken to reduce the probability of similar events occurring in the future.
There were no defects in conjunction with this event.
In order to prevent similar future events, the following actions were taken or will be taken:
- Revise Maintenance procedures involving handling, loading, and unloading shipping casks to include a user checkoff sheet to require a Maintenance supervisor and a Radiation Protection staff person to certify that the cask has been loaded and tested in accordance with approved procedures.
" Radiation Protection shipping procedures to be revised to include additional defense-in-depth for the shipping process by adding involvement of Radiation Protection management prior to a shipment leaving the Catawba site.
This will be accomplished by making the following specific changes:
Add the requirement for review of the checklists and/or procedures provided by groups applicable to the shipping process.
Revise procedure to require completion, qualified Radiation Protection staff person review, and signatures for the sections that 'need to be completed prior to shipment.
Revise procedure to specify that package preparation checklists shall accompany shipments, if required.
" Maintenance Will revise the appropriate task qualification to add knowledge/skill elements for pressure testing.
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- Maintenance will develop and implement an improvement plan concerning Procedure Use and Adherence.
" Personnel corrective actions have been taken commensurate with their inappropriate actions.
(5) Reference to any previous similar events involving the same packaging that are known to the licensee or certificate holder.
There were no previous similar events at Catawba.
(6)
The name and telephone number of a person within the licensee's organization who is knowledgeable about the event and can provide additional information.
Terry R.
Jenkins -
Catawba Nuclear Station Maintenance Superintendent (803) 701-3122 Anthony L.
Peay -
Catawba Nuclear Station Radiation Protection Supervisor (803) 701-3936 Larry D. Schlise -
Catawba Nuclear Station Radiation Protection General Supervisor (803) 701-5182 Timothy V. Wright Catawba Nuclear Station Radiation Protection Supervising Scientist (803) 701-5126 (7)
The extent of exposure of individuals to radiation or to radioactive materials without identification of individuals by name.
There was no unintended exposure to any individuals associated with this event.
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