ML18341A172
ML18341A172 | |
Person / Time | |
---|---|
Site: | San Onofre ![]() |
Issue date: | 12/19/2018 |
From: | Troy Pruett Division of Nuclear Materials Safety IV |
To: | Bauder D Southern California Edison Co |
E. Simpson | |
References | |
EA-18-155 IR 2018005 | |
Download: ML18341A172 (38) | |
See also: IR 05000206/2018005
Text
December 19, 2018
Mr. Doug Bauder
Vice President and Chief Nuclear Officer
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
SUBJECT: ERRATA: SAN ONOFRE NUCLEAR GENERATING STATION - NRC SPECIAL
INSPECTION REPORT 050-00206/2018-005, 050-00361/2018-005,
050-00362/2018-005, 072-00041/2018-001 AND NOTICE OF VIOLATION
Mr. Bauder:
It was identified that the U.S. Nuclear Regulatory Commission (NRC) Special Inspection Report
No. 050-00206/2018-005, 050-00361/2018-005, 050-00362/2018-005, 072-00041/2018-001,
dated November 28, 2018 Agency Document and Management System (ADAMS) (ADAMS
Accession No. ML18332A357) and Notice of Violation (Notice) incorrectly identified the cited
violation against 10 CFR 72.192, regarding Operator training and certification program, in
lieu of citing the violation against 10 CFR 72.190, Operator requirements. The corrected
inspection report and Notice shall refer to 10 CFR 72.190 in all applicable areas. As specified
in 10 CFR 72.13, the regulation identified under 10 CFR 72.190 is applicable to a general
licensee, which is the type of license held by Southern California Edison Company. The
inspection report and all its enclosures, including the Notice, is reissued in its entirety under the
same inspection report number and is enclosed.
The change to the citation in the Notice involving training and certification of personnel does
not change the content of the inspection report, or the two apparent violations. As such, the
communications provided in the November 28, 2018, inspection report regarding your
opportunity to request a predecisional enforcement conference (PEC) or alternative dispute
resolution (ADR) remains in effect from the date of the original inspection report,
November 28, 2018. On December 10, 2018, SONGS informed the NRC that it requested a
PEC. My staff is working with your staff to schedule the PEC.
D. Bauder 2
In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedure, a
copy of this letter, its enclosures, and your response (if any), will be made available
electronically for public inspection in the NRC Public Document Room and from the NRCs
ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
If you have any questions concerning this matter, please contact Dr. Janine F. Katanic, CHP, of
my staff at 817-200-1151.
Sincerely,
/RA/
Troy W. Pruett, Director
Division of Nuclear Materials Safety
Docket Nos.: 50-206; 50-361; 50-362;72-041
License Nos.: NPF-10; NPF-15; DPR-13
Enclosure:
Revised NRC Special Inspection
Report 050-00206/2018-005,
050-00361/2018-005, 050-00362/2018-005,
and 072-00041/2018-001
SUNSI Review ADAMS: Sensitive Non-Publicly Available Keyword
By: EJS Yes No Non-Sensitive Publicly Available NRC-002
OFFICE DNMS:FCDB DNMS:CFCDB D:DNMS
NAME ESimpson JFKatanic TPruett
SIGNATURE /RA/ /RA/ /RA/
DATE 12/12/18 12/18/18 12/19/18
REVISED
SAN ONOFRE NUCLEAR GENERATING STATION
NRC SPECIAL INSPECTION REPORT 050-00206/2018-005,
050-00361/2018-005, 050-00362/2018-005, 072-00041/2018-001
AND REVISED NOTICE OF VIOLATION
Enclosure
December 19, 2018
Mr. Doug Bauder
Vice President and Chief Nuclear Officer
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
SUBJECT: REVISED NRC SPECIAL INSPECTION REPORT 050-00206/2018-005,
050-00361/2018-005, 050-00362/2018-005, 072-00041/2018-001 AND REVISED
NOTICE OF VIOLATION
Mr. Bauder:
This letter refers to the Special Inspection conducted on September 10-14, 2018, at your facility
in San Clemente, California. The inspection was conducted in response to the misalignment of
a loaded spent fuel storage canister as it was being downloaded into the storage vault at the
San Onofre Nuclear Generating Station (SONGS). Based on the criteria specified in
Management Directive 8.3, NRC Incident Investigation Program, the Nuclear Regulatory
Commission (NRC) initiated a Special Inspection in accordance with Inspection
Procedure 93812, Special Inspection. The basis for initiating the Special Inspection and the
focus areas for review are detailed in the Special Inspection Charter (Enclosure 3), dated
August 17, 2018 (Agencywide Document Access and Management System (ADAMS)
Accession ML18229A203).
The enclosed report documents the results of the inspection. The inspectors discussed the
preliminary inspection findings with Mr. Thomas Palmisano and members of your staff on
September 14, 2018, at the conclusion of the onsite portion of the inspection. A final exit
briefing was conducted telephonically with Mr. Palmisano and members of your staff on
November 1, 2018.
Based on the results of the Special Inspection, two apparent violations were identified and are
being considered for escalated enforcement action in accordance with the NRC Enforcement
Policy. The current Enforcement Policy is included on the NRC Web site at
http://www.nrc.gov/about-nrc/regulatory/enforcement/enforce-pol.html. The circumstances
surrounding these apparent violations, the significance of the associated issues, and the need
for corrective actions were discussed with Mr. Palmisano at the conclusion of the onsite
inspection and during the final telephonic exit briefing. The apparent violations involved the
failure to: (1) ensure important-to-safety equipment was available to provide redundant drop
protection features for a spent fuel canister during downloading operations; and (2) make a
timely notification to the NRC Headquarters Operations Center for the August 3, 2018, disabling
of important-to-safety equipment.
D. Bauder 2
The NRC is concerned about apparent weaknesses in management oversight of the dry cask
storage operations. Your staff did not perform adequate direct observational oversight of
downloading activities performed by your contractor, ensure adequate training of individuals
responsible for performing downloading operations, provide adequate procedures for
downloading operations, or ensure that conditions adverse to quality were entered into the
corrective action program. The NRC identified that a causal factor for the misalignment incident
involved management weakness in the oversight of dry cask storage operations.
Before the NRC makes its enforcement decision, we are providing you with an opportunity to:
(1) request a predecisional enforcement conference (PEC) or (2) request alternative dispute
resolution (ADR). If a PEC is held, it will be open for public observation and the NRC will issue
a press release to announce the time and date of the conference.
If you choose to request a PEC, the conference will afford you the opportunity to provide your
perspective on these matters and any other information that you believe the NRC should take
into consideration before making an enforcement decision. The decision to hold a PEC does
not mean that the NRC has determined that a violation has occurred or that enforcement action
will be taken. This conference would be conducted to obtain information to assist the NRC in
making an enforcement decision.
The topics discussed during the conference may include information to determine whether a
violation occurred, information to determine the significance of a violation, information related to
the identification of a violation, and information related to any corrective actions taken or
planned. In presenting your corrective actions, you should be aware that the promptness and
comprehensiveness of your actions will be considered in assessing any civil penalty for the
apparent violations. The guidance in NRC Information Notice 96-28, Suggested Guidance
Relating to Development and Implementation of Corrective Action, may be helpful and can be
obtained at the NRC Web site at http://pbadupws.nrc.gov/docs/ML0612/ML061240509.pdf.
In lieu of a PEC, you may also request ADR with the NRC in an attempt to resolve this issue.
Alternative dispute resolution is a general term encompassing various techniques for resolving
conflicts using a neutral third party. The technique that the NRC has decided to employ is
mediation. Mediation is a voluntary, informal process in which a trained neutral mediator works
with parties to help them reach resolution. If the parties agree to use ADR, they select a
mutually agreeable neutral mediator who has no stake in the outcome and no power to make
decisions. Mediation gives parties an opportunity to discuss issues, clear up
misunderstandings, be creative, find areas of agreement, and reach a final resolution of the
issues.
Additional information concerning the NRCs program can be obtained at
http://www.nrc.gov/about-nrc/regulatory/enforcement/adr.html. The Institute on Conflict
Resolution at Cornell University has agreed to facilitate the NRCs program as a neutral third
party. Please contact the Institute on Conflict Resolution at 877-733-9415 within 10 days of the
date of this letter if you are interested in pursuing resolution of these issues through ADR.
Alternative dispute resolution sessions are not conducted with public observation though the
outcome of the ADR agreement is made public.
A PEC should be held within 30 days and an ADR session within 45 days of the date of this
letter. Please contact Dr. Janine F. Katanic at 817-200-1151 within 10 days of the date of this
letter to notify the NRC of your intended response.
D. Bauder 3
In addition, please be advised that the number and characterization of apparent violations
described in the enclosed inspection report may change as a result of further NRC review.
You will be advised by separate correspondence of the results of our deliberations on this
matter.
The NRC determined that three Severity Level IV violations of NRC requirements occurred.
These violations were evaluated in accordance with Section 2.2.2 of the NRC Enforcement
Policy. The NRC determined the issuance of a Notice of Violation (Notice) is appropriate
because the actions to restore compliance have not been fully developed and implemented,
and the actions must be effective prior to beginning fuel handling activities.
The three Severity Level IV violations are cited in the enclosed Notice and the circumstances
surrounding them are described in detail in the subject inspection report. The violations
involved failures to: (1) identify conditions potentially adverse to quality for placement into your
corrective actions program; (2) assure that operations of important to safety equipment were
limited to trained and certified personnel or under direct supervision; and (3) provide adequate
procedures for dry cask storage operations involving downloading operations.
In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedure, a
copy of this letter, its enclosures, and your response, will be made available electronically for
public inspection in the NRC Public Document Room and from the NRCs ADAMS, accessible
from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible,
your response should not include any personal privacy or proprietary information so that it can
be made available to the public without redaction.
If you have any questions concerning this matter, please contact Dr. Janine F. Katanic, CHP, of
my staff at 817-200-1151.
Sincerely,
/RA/
Troy W. Pruett, Director
Division of Nuclear Materials Safety
Docket Nos.: 50-206; 50-361; 50-362;72-041
License Nos.: NPF-10; NPF-15; DPR-13
Enclosures:
1. Notice of Violation
2. Revised NRC Special Inspection
Report 050-00206/2018-005,
050-00361/2018-005,
050-00362/2018-005, and
072-00041/2018-001
3. Special Inspection Charter dated
August 17, 2018 (ML18229A203)
NOTICE OF VIOLATION
Southern California Edison Company Docket Nos.: 050-00206, 050-00361,
San Clemente, CA 050-00362, 072-00041
License Nos.: NPF-10; NPF-15; DPR-13
During an NRC Special Inspection conducted September 10 through November 1, 2018, three
violations of NRC requirements were identified. In accordance with the NRC Enforcement
Policy, the violations are listed below:
A. 10 CFR 72.172 requires, in part, that, licensees establish measures to ensure that
conditions adverse to quality, such as failures, malfunctions, deficiencies, and
deviations, are promptly identified and corrected.
Contrary to the above, from January 30 to August 3, 2018, the licensee failed to
establish measures to ensure that conditions adverse to quality, such as failures,
malfunctions, deficiencies, and deviations, were promptly identified and corrected.
Specifically:
1. On July 22, 2018, the loading crew experienced difficulty in aligning canister 28 for
downloading into the independent spent fuel installation vault. However, the licensee
failed to enter this deviation in downloading conditions into its corrective action
program to determine the cause of the misalignment problem and develop corrective
actions to preclude reoccurrence.
2. From January 30 to August 3, 2018, during canister downloading, contact between
the canister and vault components frequently occurred. However, the licensee failed
to enter instances of contact into its corrective action program and perform an
assessment to disposition the exterior conditions of the downloaded canisters and
vault components.
This is a Severity Level IV violation (NRC Enforcement Policy Section 6.3).
B. 10 CFR 72.190 requires, in part, that the operation of equipment and controls that have
been identified as important to safety in the Safety Analysis Report and in the license
must be limited to trained and certified personnel or be under the direct supervision of an
individual with training and certification in the operation. The HI-STORM UMAX
SYSTEM Final Safety Analysis Report (FSAR), Revision 4, dated August 14, 2017,
specifies, in part, that the operations at the independent spent fuel storage installation
are governed by the HI-STORM FW SYSTEM FSAR, Revision 5, dated June 20, 2017,
which specifies that the multipurpose canister lifting slings and multipurpose canister lift
attachments are designated as important to safety equipment.
Contrary to the above, from January 30 to August 3, 2018, the licensee failed to assure
that operations of equipment and controls that had been identified as important to safety
in the Safety Analysis Report were limited to trained and certified personnel or were
under the direct supervision of an individual with training and certification in the
operation. Specifically:
Enclosure 1
1. The training program failed to adequately train and certify the rigger/spotter position
involved in the important to safety downloading operation.
2. The training program for the vertical cask transporter operator position failed to have
adequate proficiency testing, on the controls related to the load indicating device and
downloading operations.
This is a Severity Level IV violation (NRC Enforcement Policy Section 6.3).
C. 10 CFR 72.150, requires, in part, that the licensee prescribe activities affecting quality by
documented instructions or procedures of a type appropriate to the circumstances and
must include appropriate quantitative or qualitative acceptance criteria for determining
that important activities have been satisfactorily accomplished.
Contrary to the above, from January 30 to August 3, 2018, the licensee failed to
prescribe activities affecting quality by documented instructions or procedures of a type
appropriate to the circumstances and include appropriate quantitative or qualitative
acceptance criteria for determining that important activities have been satisfactorily
accomplished. Specifically:
1. Procedure HPP-2464-400, Multi-Purpose Canister Transfer at SONGS,
Revision 15, step 7.6.23, failed to provide qualitative and quantitative directions for
the vertical cask transporter operator to monitor control panel indications that would
identify a canister had become misaligned during downloading operation.
2. Procedure HPP-2464-400, Multi-Purpose Canister Transfer at SONGS,
Revision 15, step 7.6.23, failed to include adequate instructions for the rigger/spotter
to monitor the downloading slings for a slack condition.
This is a Severity Level IV violation (NRC Enforcement Policy Section 6.3).
Pursuant to the provisions of 10 CFR 2.201, Southern California Edison Company is hereby
required to submit a written statement or explanation to the U.S. Nuclear Regulatory
Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the
Regional Administrator, U.S. Nuclear Regulatory Commission, Region IV, 1600 E. Lamar Blvd.,
Arlington, TX 76011, within 30 days of the date of the letter transmitting this Notice of Violation
(Notice).
This reply should be clearly marked as a Reply to a Notice of Violation, EA-18-155 and should
include, for each violation: (1) the reason for the violation, or, if contested, the basis for disputing
the violation or severity level; (2) the corrective steps that have been taken and the results
achieved; (3) the corrective steps that will be taken; and (4) the date when full compliance will
be achieved. Your response may reference or include previous docketed correspondence, if
the correspondence adequately addresses the required response. If an adequate reply is not
received within the time specified in this Notice, an order or a Demand for Information may be
issued requiring information as to why the license should not be modified, suspended, or
revoked, or why such other action as may be proper should not be taken. Where good cause is
shown, consideration will be given to extending the response time.
2
If you contest this enforcement action, you should also provide a copy of your response, with
the basis for your denial, to the Director, Office of Enforcement, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
Your response will be made available electronically for public inspection in the NRC Public
Document Room or in the NRCs Agencywide Documents Access and Management System
(ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To
the extent possible, your response should not include any personal privacy or proprietary
information so that it can be made available to the public without redaction.
If personal privacy or proprietary information is necessary to provide an acceptable response,
then please provide a bracketed copy of your response that identifies the information that
should be protected and a redacted copy of your response that deletes such information. If you
request withholding of such material, you must specifically identify the portions of your response
that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g.,
explain why the disclosure of information will create an unwarranted invasion of personal
privacy or provide the information required by 10 CFR 2.390(b) to support a request for
withholding confidential commercial or financial information).
Dated this 19th day of December 2018
3
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket Nos.: 50-206; 50-361; 50-362;72-041
License Nos.: NPF-10; NPF-15; DPR-13
Report No.: 050-00206/2018005; 050-00361/2018005; 050-00362/2018005;
and 072-00041/2018001
Enterprise Identifier: I-2018-001-0138
Licensee: Southern California Edison Company
Location: San Clemente, CA 92674-012
Inspection Dates: Onsite September 10-14, 2018
In-office review through November 1, 2018
Exit Meeting Date: November 1, 2018
Inspectors: Eric Simpson, CHP, Health Physicist
Fuel Cycle and Decommissioning Branch
Division of Nuclear Materials Safety, Region IV
Marlone Davis, Senior Inspector
Inspections and Operations Branch
Division of Spent Fuel Management
W. Chris Smith, Reactor Inspector
Engineering Branch 1
Division of Reactor Safety, Region IV
Accompanied By: Janine F. Katanic, PhD, CHP, Chief
Fuel Cycle and Decommissioning Branch
Division of Nuclear Materials Safety, Region IV
Patricia Silva, Chief
Inspections and Operations Branch
Division of Spent Fuel Management
Troy W. Pruett, Director
Division of Nuclear Materials Safety, Region IV
Approved By: Troy W. Pruett, Director
Division of Nuclear Materials Safety, Region IV
Attachment: Supplemental Inspection Information
Enclosure 2
EXECUTIVE SUMMARY
NRC Special Inspection Report 050-00206/2018005; 050-00361/2018005;
050-00362/2018005; and 072-00041/2018-001
On September 10-14, 2018, the U.S. Nuclear Regulatory Commission performed an announced
Special Inspection of the independent spent fuel storage installation at the decommissioning
San Onofre Nuclear Generating Station in San Clemente, California. The inspection continued
with an in-office review of training material, licensee analyses, procedures, and other materials
gathered during the onsite inspection through November 1, 2018. The Southern California
Edison Company, the licensee and owner of San Onofre Nuclear Generating Station, has an
NRC General License for its independent spent fuel installation under Title 10 of the Code of
Federal Regulations (10 CFR) Part 72. The scope of the inspection was to evaluate the facts
and circumstances involved in the August 3, 2018, misalignment incident, and review the
licensees follow-up investigation, causal evaluation, and planned corrective actions.
NRC Special Inspection of San Onofre Nuclear Generating Station Canister Misalignment
Incident of August 3, 2018
- The licensees actions that led to disabling the important to safety downloading slings
and removal of redundant drop protection features were identified as an apparent
violation of Technical Specification 5.2.c.3 requirements. (Section 3.1.1)
- The NRC team identified missed opportunities where the licensee could have addressed
the potential for a downloading misalignment. For example, on July 22, 2018, one of the
crews experienced misalignment difficulty resulting in a prolonged downloading
operation. The licensee did not enter the adverse condition into the corrective action
program to determine the cause and develop appropriate corrective actions. This was
identified as a Severity Level IV violation of 10 CFR 72.172 requirements. (Section 3.1.1)
- Personnel lacked the proper training, proficiency testing, and certifications to operate
important to safety equipment identified in the HI-STORM UMAX SYSTEM Final Safety
Analysis Report, Revision 4, dated August 14, 2017. This was identified as a Severity
Level IV violation of 10 CFR 72.190 requirements. (Section 3.1.2)
- Dry cask storage procedures did not provide adequate directions for how to determine
the downloader slings were slack. Slack in the slings was an indicator of a loss-of-load.
Further, procedures did not include qualitative or quantitative means to determine when
a canister had become misaligned. These procedure inadequacies were identified as a
Severity Level IV violation of 10 CFR 72.150 requirements. (Section 3.1.3)
- No licensee or contractor oversight staff were in direct visual observation of important to
safety activities during downloading operations on August 3, 2018. Licensee oversight
was not a part of communications between the cask loading supervisor, the
rigger/spotter, and vertical cask transporter operator during downloading operations.
(Section 3.1.3)
2
- The licensee concluded and the NRC agreed that the minor removal of divider shell
coating during downloading operations did not affect the design functions for shielding,
structural, and thermal safety functions. The licensees plan to address future inspection
of the divider shells in their aging management program is acceptable. (Section 3.1.4)
- The licensee failed to make the required 24-hour NRC notification of the August 3, 2018,
incident where important to safety equipment was disabled when required to mitigate the
consequences of an accident and no redundant equipment was available to perform the
safety function. This failure was identified as an apparent violation of 10 CFR 72.75(d)
requirements. (Section 3.1.4)
- The causal evaluations performed by the licensee and its contractor identified apparent
and root causes for the August 3, 2018, canister misalignment incident that included
inadequate training, inadequate procedures, poor utilization of the corrective action
program, and insufficient management oversight. (Section 3.1.5)
- The licensees consequence analysis resulting from a hypothetical 25-foot canister drop
determined that the canister integrity would be maintained. The NRC will continue to
inspect the licensees consequence analysis. (Section 3.1.5)
- The licensee provided an analysis to demonstrate that wear on canister 29 during the
downloading incident would meet established acceptance criteria. The NRC determined
that more analysis was required to accept that the canister meets design requirements.
This charter item will be reviewed during a future NRC inspection. (Section 3.1.6)
- All associated corrective actions for the August 3, 2018, incident had not been fully
developed and implemented by the licensee. The NRC will review the licensees revised
procedures, training plans, equipment modifications, and performance testing (dry runs)
of its dry cask storage operations during a future inspection to determine the
effectiveness of corrective actions for the incident. (Section 3.1.7)
3
REPORT DETAILS
1 Inspection Scope
On September 10-14, 2018, the NRC performed an announced Special Inspection at the
San Onofre Nuclear Generating Station (SONGS) in San Clemente, California, which
was followed by in-office reviews of additional information provided by the licensee
through November 1, 2018. The scope of the inspection was to interview personnel
associated with the August 3, 2018, misalignment incident to independently evaluate the
circumstances of the canister misalignment; identify and review all pertinent records,
documents, and procedures related to the licensees downloading operations; evaluate
procedure adequacy and adherence; evaluate the reportability requirements; and to
evaluate the root cause analyses and corrective actions to prevent recurrence.
2 Background
2.1 General Description of Multi-purpose Canister Downloading Operations
On November 8, 2018, the NRC conducted a public meeting webinar (NRCs
Agencywide Documents Access and Management System (ADAMS)
Accession ML18319A139). The presentation provides a summary of a downloading
operation.
A vertical cask transporter (VCT) is used for transporting the transfer cask and
multi-purpose canister (MPC or canister) loaded with spent fuel onto the independent
spent fuel storage installation (ISFSI) pad. Dry cask storage workers manipulate the
VCT to align the transfer cask over the ISFSI vertical ventilated module (VVM or vault) in
which the canister will be stored. Once alignment has been achieved and the transfer
cask is securely bolted to a mating device, the transfer cask is disconnected from the
VCT. Lifting slings are connected to the top of the canister and the VCT overhead lift
beam. The VCT lift beam is raised until the load of the canister is supported and no
longer resting on the bottom of the transfer cask.
While the canister is being supported by the lift beam and slings, a drawer on the mating
device is opened. Once the drawer is open, the VCT operator lowers the lift beam,
which lowers the canister into the storage vault. The VCT can be moved during the
download to make fine adjustments for canister alignment within the vault. While the
canister is being lowered, it passes through a divider shell assembly. The divider shell
has a shield ring that the canister must pass through as it is being lowered into the vault.
When fully downloaded, the canister will be seated on a pedestal in the cavity enclosure
container in the vault.
2.2 August 3, 2018 Canister Misalignment
On August 3, 2018, as the loaded canister was being lowered into the vault, personnel
failed to notice that the canister was misaligned. The licensee and its contractor
continued to lower the VCT lift beam until staff believed that the canister had been fully
lowered to the bottom of the vault. Staff involved in the download failed to recognize the
lifting slings were slack. A radiation protection technician identified radiation readings
that were not consistent with a fully lowered canister. The licensee then identified that
the loaded spent fuel canister was resting on a shield ring near the top of the vault,
4
preventing it from being lowered, and that the rigging and lifting slings were slack and no
longer bearing the load of the canister.
With the slings slack, the lifting equipment was no longer capable of performing its
important to safety function of holding and controlling the loaded canister. The canister
could have experienced an approximately 17-18 foot drop into the storage vault if the
canister had slipped off the shield ring. This load drop accident is not a condition
analyzed in the dry fuel storage systems Final Safety Analysis Report (FSAR).
The licensee restored the control of the load to the slings and lifting devices. The
estimated time the canister was in an unsupported position was approximately
45 minutes. The licensee repositioned and lowered the canister into the vault. The
licensee subsequently halted all dry fuel storage movement operations in order to fully
investigate the incident and develop corrective actions to prevent recurrence.
The licensee informed Region IV staff of the misalignment incident on August 6, 2018.
Region IV discussed the licensees plans for evaluation and follow-up for the incident
and the status of fuel loading operations. The licensee agreed to suspend fuel loading
operations until such time as their senior management was satisfied with their corrective
actions, the NRC completed their inspection, and the NRC determines that corrective
actions are sufficient to prevent a similar occurrence. Region IV chartered a Special
Inspection Team to review the incident, any relevant background information, causal and
risk assessments conducted by the licensee, and proposed and completed corrective
actions.
3 Special Inspection Charter (IP 93812)
3.1 Inspection Scope
Following the notification to NRC Region IV of the August 3, 2018, misalignment
incident, the NRC evaluated the information provided against the criteria for a reactive
inspection. Based on the criteria in Management Directive 8.3, NRC Incident
Investigation Program, and Inspection Manual Chapter 0309, Reactive Inspection
Decision Basis for Reactors, a decision was made to perform a Special Inspection. The
Special Inspection Charter is provided in Enclosure 3.
The Special Inspection was conducted onsite from September 10-14, 2018, and
continued with in-office review until November 1, 2018. The Special Inspection focused
on understanding the August 3, 2018, misalignment incident. The inspection included
interviewing personnel involved in the incident, developing a timeline, and assessing the
licensees immediate corrective actions.
The sections below provide inspection details for each of the Special Inspection Charter
items.
5
3.1.1 Charter Item 5
Inspection Scope
Interview personnel associated with the August 3, 2018, misalignment incident to
develop a timeline to ensure the licensees investigation contained all necessary
information to identify all contributing factors and develop adequate corrective actions.
The NRC team interviewed licensee and contractor staff involved or present during the
August 3, 2018, misalignment incident. The NRC also reviewed records related to dry
cask storage operations.
Observations and Findings
Based on interviews and records reviewed, the following timeline was developed:
Date/Time (+/- 30 minutes) Activity
August 3, 2018
12:40 p.m. Downloading begins for canister 29:
All dry cask storage supervision and licensee oversight,
including radiation protection staff exited the ISFSI pad
to stand in a low-dose area on the ISFSI pad ramp
(approximately 150 feet away from the operations).
Only the rigger/spotter in the motor-powered boom lift
device man-basket (JLG) and the VCT operator
remained on the ISFSI pad.
1:05 p.m. VCT operator and rigger/spotter notify cask loading
supervisor (CLS) that the canister has been fully
lowered into the ISFSI vault.
1:12 p.m. The radiation protection technician (RPT) determines
radiation levels indicate that the canister was not fully
lowered.
Work activities were stopped to plan recovery actions
with the radiation protection supervisor and CLS.
The rigger in charge (RIC) began making preparations
to enter the JLG.
6
1:15 p.m. Notifications were made to Holtec management.
The RIC was escorted to the JLG by an RPT.
The RIC recognized the downloading slings were slack
and bundled on the ground near the base of the VCT.
1:33 p.m. The RIC observed the top of the canister was about
4 feet from the top of the transfer cask and not lowered
into the vault.
The RIC directed the VCT operator to lift the canister.
1:41 p.m. The canister load was fully supported by the VCT and
downloading slings.
1:50 p.m. An alternate CLS arrived and began to direct operations
for downloading to the VCT operator.
The alternate CLS and RIC noted that during
downloading operations the canister experienced
interference twice and had to be re-aligned.
2:22 p.m. Downloading operations completed.
6:00 p.m. Licensee places hold on all lifting operations.
August 6, 2018 At approximately 4 pm (CDT), the licensee informally
contacted NRC Region IV to discuss the
August 3, 2018, misalignment incident.
August 7, 2018 NRC Region IV and licensee management agreed that
ISFSI operations would cease until the NRC performed
an inspection and reviewed the licensees corrective
actions to resume work.
September 14, 2018 At 4 pm (ET) the licensee made a formal notification per
10 CFR 72.75(d)(1) to the NRC Headquarters
Operations Center regarding the August 3, 2018,
misalignment incident.
Violation of 10 CFR 72.172, Corrective Actions
Interviews with Williams Industrial Services Group and Sonic Systems (Holtec
International subcontractors) employees indicated that of a loss-of-load condition or a
canister misalignment issue was experienced during dry run evolutions and known to
several dry cask storage workers. The Special Inspection team identified a prior canister
misalignment issue that occurred on July 22, 2018, in which downloading operations
lasted 90 minutes, instead of the expected 15 minutes for downloading canister 28. This
incident was documented in a Production Traveler. A Production Traveler is a document
that the licensee uses to track the performance of dry fuel storage operations by the
7
contractor, Holtec International. The Production Travelers were used to track how well
the contractor was providing their contracted services to the licensee. The licensee did
not enter this condition adverse to quality into its corrective action program.
Licensee oversight generally waited for Holtec staff to initiate a field condition report
(FCR) before writing a corresponding condition report. In the Production Traveler for
canister 28, the 90 minute delay was related to adjustments that were needed for the
VCT towers as canister weight started to lower prematurely before the downloading was
complete. This type of misalignment also occurred during the August 3, 2018, incident.
On July 22, 2018, the downloading crew for canister 28, noted the reduction in the
canister weight and corrected the alignment error. The canister was never unsupported
by the slings. No condition report or FCR was generated by either the licensee or
contractor.
Through interviews with licensee and contractor staff, the NRC determined that between
January 30 and August 3, 2018, the downloading activity often involved contact between
the canister and other vault components during downloading. The licensee and its
contractor did not enter the misalignment and contact events into the corrective action
program. Consequently, actions to assess and disposition the exterior conditions of the
downloaded canisters and other components within the vault, such as the divider shell
assembly, were not performed. The licensee is responsible to ensure the important to
safety components continue to meet their original design criteria and address any aging
management concerns the changes could impact. Any deviations, such as scratches or
removal of coatings are required to be evaluated to ensure the deviations are not
detrimental to the system.
Interviews with individuals involved in dry cask loading operations in August 2018,
revealed that the difficulty in aligning the canister was not shared with others, nor was it
incorporated into procedures or formal training programs. The VCT operator and the
rigger/spotter in charge of downloading operations during the August 3, 2018, incident
indicated that they did not know until afterwards that the condition they experienced was
something that should have been anticipated.
Title 10 CFR 72.172 requires, in part, that, licensees establish measures to ensure that
conditions adverse to quality, such as failures, malfunctions, deficiencies, and deviations
are promptly identified and corrected. Contrary to the above, the licensee failed to
establish measures to ensure that conditions adverse to quality, such as failures,
malfunctions, deficiencies, and deviations were promptly identified and corrected.
Specifically:
1. On July 22, 2018, the crew experienced difficulty in aligning canister 28 for
downloading into the ISFSI vault. However, the licensee failed to enter this
deviation in downloading conditions into its corrective action program to
determine the cause of the misalignment problem and develop corrective actions
to preclude reoccurrence.
2. From January 30 to August 3, 2018, during canister downloading, contact
between the canister and the vault components frequently occurred. The
licensee failed to enter instances of contact into its corrective action program and
perform an assessment to disposition the exterior conditions of the downloaded
canisters and vault components.
8
The team determined that this violation was more than minor because the failure to
implement corrective actions contributed to the misalignment incident of August 3, 2018.
Additionally, the failure to evaluate and disposition wear marks on a canister, if left
uncorrected, could impact the adequacy of the aging management program. The
Special Inspection team assessed and dispositioned this violation in accordance with
Section 2.2.2 of the NRC Enforcement Policy. The team characterized the violation as a
Severity Level IV violation. The NRC determined the issuance of a Notice is appropriate
because the actions to restore compliance have not been fully developed and
implemented, and the actions must be effective prior to beginning fuel handling activities.
(VIO 07200041/2018-001-01, Failure to identify and correct conditions adverse to
quality)
Apparent Violation of Technical Specification 5.2.c.3, Redundant Lifting
Equipment
On August 3, 2018, the licensee performed operations involving movement of a loaded
spent fuel storage canister into its ISFSI vault. As the loaded spent fuel canister was
being lowered into the vault, licensee and contractor personnel failed to notice that the
canister was misaligned and the weight of the canister was not being supported by the
redundant important to safety slings (See Sections 2.1 and 2.2).
Title 10 CFR 72.212(b)(3) requires, in part, that each cask used by the general licensee
conforms to the terms, conditions, and specifications of a Certificate of Compliance listed
in 10 CFR 72.214. Title 10 CFR 72.214 includes a list of all the approved spent fuel
storage casks that can be utilized under the conditions specified in a specific Certificate
of Compliance, including Amendment 2 of Certificate of Compliance 072-01040.
Certificate of Compliance 072-01040, Amendment 2, Condition 4, HEAVY LOADS
REQUIREMENTS, requires that lifting operations outside of structures governed
by 10 CFR Part 50 must be in accordance with Technical Specifications, Appendix A,
Section 5.2.
Technical Specification, Appendix A, Section 5.2.c.3 requires that the transfer cask,
when loaded with spent fuel, may be lifted and carried at any height during multi-purpose
canister transfer operations provided the lifting equipment is designed with redundant
drop protection features which prevent uncontrolled lowering of the load.
Contrary to the above, on August 3, 2018, the licensee failed to ensure that redundant
drop protection features were available to prevent uncontrolled lowering of the load.
Specifically, the licensee inadvertently disabled the redundant important to safety
downloading slings while lowering canister 29 into the storage vault. During the
approximately 45 minute time-frame, the canister rested on a shield ring unsupported by
the redundant downloading slings at approximately 17-18 feet above the fully seated
position. This failure to maintain redundant drop protection placed canister 29 in an
unanalyzed condition because the postulated drop of a loaded spent fuel canister is not
analyzed in the FSAR.
The licensees failure to ensure the systems designed redundant drop protection
features were available to prevent uncontrolled lowering of the loaded canister was
identified as an apparent violation of Technical Specification 5.2.c.3.
(AV 07200041/2018-001-02, Failure to ensure redundant drop protection features are
available)
9
Conclusions
The licensee failed to adequately implement the corrective action program for ISFSI
operations. This failure resulted in missed opportunities to resolve misalignment errors
during canister downloading operations between January 30 and August 3, 2018, and a
violation of 10 CFR 72.172.
On August 3, 2018, the licensee failed to recognize that a misalignment of a canister
during downloading operations caused redundant drop protection (slings) to be disabled
and an apparent violation of Technical Specification 5.2.c.3.
3.1.2 Charter Item 1
Inspection Scope
Identify and review all pertinent records, documents, and procedures related to the
licensees downloading operations at the ISFSI pad including but not limited to: worker
training and qualifications; rigging equipment qualification, testing, and preventative
maintenance; and lifting equipment qualification, testing, and preventative maintenance.
Evaluate the adequacy of the above noted procedures, worker training, and equipment
testing and preparation.
The Special Inspection team reviewed licensee rigging procedures and NUREG-0612
Control of Heavy Loads at Nuclear Power Plants, training modules. The team
reviewed the qualifications for the dry cask storage workers including the records for the
workers involved in the August 3, 2018, misalignment incident. The team reviewed the
inspection and maintenance records for special lifting devices used during dry fuel
storage operations and the qualification records for rigging equipment. The team
reviewed procedures used during canister downloading operations.
Observations and Findings
The equipment used for dry cask storage operations met applicable inspection
requirements specified in the Holtec HI-STORM UMAX FSAR. The special lifting
devices used to transport the transfer cask and to perform downloading operations were
designed and tested according to American National Standards Institute (ANSI) N14.6,
American National Standard for Radioactive Materials - Special Lifting Devices for
Shipping Containers Weighing 10,000 Pounds or More. The slings used during
downloading had a sufficient load rating for the maximum credible load imposed by the
canister. The slings were tested according to the safety requirements of American
Society of Mechanical Engineers (ASME) B30.9, Slings. The purchase specifications,
qualifications, and maintenance records for the VCT, downloading slings, canister lift
cleats, lift lugs, and lift links were satisfactory.
Violation of 10 CFR 72.190, Training and Certification Qualifications
The NRC team reviewed the qualifications of workers involved in the August 3, 2018,
incident. Interviews with the individuals primarily responsible for verifying that the
canister was properly downloaded into the ISFSI vault showed that the licensees
training program was inadequate for the positions that are designated as rigger/spotter
and VCT operator. The VCT operator training program qualifications did not establish
10
adequate required proficiency training exercises for downloading operations. The VCT
operator on August 3, 2018, had never been tested on or exercised with the canister
simulator during a pre-operational testing, dry run downloading operation. The
August 3, 2018, misalignment incident was the first time the VCT operator had actually
completed downloading operations as the VCT operator.
Neither the rigger/spotter nor VCT operator was properly trained in determining a
loss-of-load condition during downloading operations. The VCT operator stated that he
was knowledgeable of the VCT human-machine interface (HMI) screens and that
indications provided a digital reading that could allow the operator to determine if the
canister was not supported by the slings. However, the VCT operator stated that he did
not use the VCT HMI screen to monitor the load of the canister at any time during the
August 3, 2018, downloading operations. The VCT operator indicated that he only
utilized the HMI screen to determine how evenly the VCT lift beam was descending.
From his position on the VCT, the VCT operator could not see the canister downloader
slings. The only indication of a loss-of-load would come from monitoring the VCT
hydraulic beam pressure digital reading on the VCT HMI screen, which was not
performed. Since the operator had not performed any proficiency training with the VCT
during a dry run downloading operation, the individual was inexperienced with the use of
the HMI screen to monitor load loss.
The licensees training program did not provide a formal process to be qualified for the
rigger/spotter position during downloading operations. The rigger/spotter stated that he
was not trained on and did not know his roles and responsibilities during the
downloading evolution. The August 3, 2018, misalignment incident was the first time the
rigger/spotter had attempted to perform downloading operations as the rigger/spotter in
the JLG.
The NRC teams interview with the foreman indicated that the rigger/spotter was
selected primarily because of his low accumulated radiation dose. From interviews with
licensee and contractor staff, an experienced RIC was usually the individual placed in
the JLG and acted as the rigger/spotter for the downloading operations. On
August 3, 2018, it was the RIC who eventually entered the JLG after the misalignment
and directed the VCT operator to lift the canister with the VCT lift beam to regain the
load on the slings. The RIC had immediately recognized that the canister was not
downloaded into the ISFSI vault when he arrived and saw the condition of the
downloader slings.
The failure to ensure operators are adequately qualified and proficiency tested when
operating important to safety equipment and directing critical lift operations is a
performance deficiency. The licensees training program that allowed the rigger/spotter
and VCT operator to be placed into a situation where their lack of training rendered them
incapable of meeting the requirements for the job represented a failure of the licensees
training program.
Title 10 CFR 72.190 requires, in part, that the operation of equipment and controls that
are identified as important to safety in the Safety Analysis Report must be limited to
trained and certified personnel or be under the direct supervision of an individual with
training and certification in the operation. The HI-STORM UMAX SYSTEM FSAR,
Revision 4, dated August 14, 2017, specifies, in part, that the operations at the ISFSI are
11
governed by the HI-STORM FW SYSTEM FSAR, Revision 5, dated June 20, 2017,
which specifies that the MPC lifting slings and MPC lift attachments are designated as
important to safety equipment. Contrary to the above, from January 30 to August 3,
2018, the licensee failed to assure that operations of equipment and controls that had
been identified as important to safety in the Safety Analysis Report were limited to
trained and certified personnel or were under the direct supervision of an individual with
training and certification in the operation. Specifically, the licensees training program:
1. Failed to adequately train and certify the rigger/spotter position involved in the
important to safety downloading operation.
2. Failed to have adequate proficiency testing on the controls related to the load
indicating device and downloading operations for the VCT operator position.
The team determined that this violation was more than minor because the licensees
failure to establish an adequate training program contributed to the misalignment
incident on August 3, 2018. The team assessed and dispositioned this violation in
accordance with Section 2.2.2 of the NRC Enforcement Policy. The team characterized
the violation as a Severity Level IV violation. The NRC determined the issuance of a
Notice is appropriate because the actions to restore compliance have not been fully
developed and implemented, and the actions must be effective prior to beginning fuel
handling activities. (VIO 07200041/2018-001-03, Failure to establish adequate training
program)
The team identified that the simulator canister used for training and dry run
demonstrations had a specified outer diameter that was less than that of the actual spent
fuel storage canisters being downloaded into the vault. The simulator canister provided
approximately 0.75 inch more clearance than the actual canisters loaded with spent fuel.
This difference may be acceptable for the dry run activities; however, the difference was
not noted in any of the licensees training materials for rigger/spotters or the VCT
operators. This represents a situation of negative training that may have contributed to
the August 3, 2018, misalignment incident.
Conclusions
The important to safety lifting equipment and special lifting devices being used for dry
cask storage operations met applicable regulatory requirements.
Personnel lacked the proper training, proficiency testing, and certifications to operate
important to safety equipment identified in the HI-STORM UMAX SYSTEM FSAR,
Revision 4, dated August 14, 2017. This was identified as a violation of 10 CFR 72.190
requirements.
12
3.1.3 Charter Items 2 and 4
Inspection Scope
Evaluate the adequacy of the loading procedure(s) with respect to verification of the
movement, centering, lowering, and positioning the canister within the ISFSI vault and
procedure adherence. Interviews with personnel involved in the ISFSI loading
operations should be conducted to evaluate licensee and contractor communications
between crane/VCT operators, rigging and spotting staff, cask loading supervisors,
radiation protection staff, and licensee oversight personnel. Evaluate the adequacy of
pre-job briefings that may have taken place prior to fuel loading operations.
Based on the review of the procedures and interviews of personnel involved with
loading operations, evaluate the adequacy of procedure adherence.
The Special Inspection team reviewed Holtec Procedure HPP-2464-400, Multi-Purpose
Canister Transfer Operations at SONGS, Revision 15; Holtec
Procedure HPP-2464-600, Responding to Abnormal Conditions, Revision 6; SONGS
Procedure SO123-0-A7, Notification and Reporting of Significant Events, Revision 46;
and other applicable procedures related to the August 3, 2018, misalignment incident.
The team reviewed the pre-job briefing in use by the CLSs. The team discussed ISFSI
communications during downloading operations with the licensee and contractor staff.
Observations and Findings
Violation of 10 CFR 72.150, Procedures
The VCT is not equipped with a load-cell to provide the weight of the canister. A
hydraulic pressure indication for the lift beam could be used to provide a qualitative
means for determining if the slings are not supporting the canisters weight. This
pressure indication is displayed on the VCT HMI control panel.
The team identified examples of a violation of 10 CFR 72.150, Instructions, Procedures,
and Drawings. Holtec Procedure HPP-2464-400 provided direction and guidance for
verifying canister movement, canister centering operations, and for lowering the canister
into the vault. Many steps in the procedure provided direction without quantitative or
qualitative means to verify that important to safety steps had been achieved, including
detection of a loss-of-load condition and final verification that the canister had been fully
downloaded into the vault. For example, step 7.6.12 instructed the VCT operator to
continue to raise the VCT lift beam slowly until the full weight of the canister is on the
VCT.
However, there is no quantitative direct measurement for the VCT operator to determine
when the full weight of the canister is indicated on the VCT HMI control panel. The
procedure contained a note that the load on the VCT HMI screen may be used to
determine if downloader slings had become slack. However the procedure did not direct
the VCT operator to monitor the HMI control panel nor provide a qualitative or
quantitative value that would notify the VCT operator that the canister had become
misaligned and that the VCT was no longer bearing the load of the canister.
13
Holtec Procedure HPP-2464-400, step 7.6.23, states, if at any time the download slings
become slack prior to the canister being in the full down position then immediately stop
lowering the canister. During downloading operations there was only one position who
could determine whether or not the slings had gone slack. That position was the
rigger/spotter who is responsible to monitor the movement of the canister during
downloading operations from the elevated JLG basket. The rigger/spotter was
observing the slings during the August 3, 2018, downloading evolution. However, the
rigger/spotter was only observing the slings for slack at the top of the transfer cask.
The procedure did not provide adequate direction to the rigger/spotter to observe the
slings near the base of the VCT, which had become slack and were bundling up on the
ground. Additionally, the procedure did not provide direction for the rigger/spotter to
monitor the height of the canister in relation to the height of the lift beam.
Title 10 CFR 72.150, requires, in part, that the licensee prescribe activities affecting
quality by documented instructions or procedures of a type appropriate to the
circumstances and must include appropriate quantitative or qualitative acceptance
criteria for determining that important activities have been satisfactorily accomplished.
Contrary to the above, from January 30 to August 3, 2018, the licensee failed to
prescribe activities affecting quality by documented instructions or procedures of a type
appropriate to the circumstances and include appropriate quantitative or qualitative
acceptance criteria for determining that important activities have been satisfactorily
accomplished. Specifically:
1. Procedure HPP-2464-400, Multi-Purpose Canister Transfer at SONGS,
Revision 15, step 7.6.23, failed to provide qualitative and quantitative directions
for the VCT operator to monitor control panel indications that would identify a
canister had become misaligned during downloading operation.
2. Procedure HPP-2464-400, Multi-Purpose Canister Transfer at SONGS,
Revision 15, step 7.6.23, failed to include adequate instructions for the
rigger/spotter to monitor the downloading slings for a slack condition.
The team determined that this violation was more than minor because the licensees
failure to prescribe adequate procedures contributed to the August 3, 2018,
misalignment incident. The team assessed and dispositioned this violation in
accordance with Section 2.2.2 of the NRC Enforcement Policy. The team characterized
the violation as a Severity Level IV violation. The NRC determined the issuance of a
Notice is appropriate because the actions to restore compliance have not been fully
developed and implemented, and the actions must be effective prior to beginning fuel
handling activities. (VIO 07200041/2018-001-04, Failure to provide adequate instructions
of procedures)
Communications
During downloading on August 3, 2018, radiation protection staff directed the CLS and
licensee oversight personnel to relocate to a low dose area off of the ISFSI pad. The
low dose waiting area was located approximately 150 feet away from the ISFSI
operations on the heavy haul path that is approximately 8 feet lower in elevation. From
the low dose area, neither the contractor nor licensee oversight staff could observe the
14
downloading activities. The NRC determined that the removal of oversight staff in an
effort to minimize radiation dose without other compensatory measures resulted in
inadequate supervisory oversight of important to safety lifting operations.
The communication protocols used by the CLS, VCT operator, and the rigger/spotter
was reviewed by the team. The CLS was in direct communications via radio and
headsets with the VCT operator and rigger/spotter. The radios provided adequate
communication in the noisy environment of the VCT. Communication between the CLS,
VCT operator, and the rigger/spotter during the downloading operation was informal.
The CLS did not request a reading of the HMI control panel to determine hydraulic
pressure and repeat-backs of the location of canister during the downloading process
were misunderstood.
Radiation Protection staff were not provided headsets for communications. Radiation
Protection staff were able to communicate concerns directly with the CLS, who could
communicate radiological concerns to workers, if necessary.
The licensees oversight personnel were not provided headsets during downloading
operations. The licensee did not provide direct oversight of downloading operations.
During the August 3, 2018, misalignment incident, neither licensee oversight nor
contractor supervision were in a position to directly monitor the downloading operations
or the actual condition of the canister.
Conclusions
Dry cask storage procedures did not provide adequate directions for how to determine
the downloader slings were slack. The downloading procedure did not include
qualitative or quantitative means for determining when a canister had become
misaligned. These procedure inadequacies were identified as examples of a violation
of 10 CFR 72.150 requirements.
No licensee or contractor oversight personnel were in direct visual observations of the
important to safety activities during downloading operations on August 3, 2018. All
personnel except the rigger/spotter and VCT operator left the ISFSI pad during
downloading operations. Licensee oversight was not a part of the communications
between the CLS, the rigger/spotter, and VCT operator during canister downloading
operations. Without adequate communications and visual observation, the licensee and
the contractor were unable to verify that important to safety dry cask storage activities
were adequately performed.
3.1.4 Charter Items 3 and 8
Inspection Scope
Review and evaluate the licensees immediate corrective actions taken after the
incident for adequacy and notifications to the NRC and safety assessments performed
immediately following the incident. Review the licensees inspection documentation
15
and/or analysis to determine whether the vaults divider shell experienced any damage
that would inhibit the component from performing its designed safety function.
Investigate the licensees procedures for reportability to the NRC and determine if the
licensee made the correct decision regarding notifications made to the NRC for this
incident.
The Special Inspection team reviewed the licensees initial assessment of the incident
through presentations and discussions provided by the licensee. The team reviewed all
condition reports and entries made into the licensees and dry cask storage vendors
corrective action programs regarding the canister misalignment incident, and the
condition of the divider shell and canister 29. The team reviewed the notification
requirements of 10 CFR 72.75 against the conditions experienced during the
August 3, 2018, misalignment incident and reviewed licensee Procedure SO123-0-A7,
Notification and Reporting of Significant Events, Revision 46.
Observations and Findings
Divider Shell Assessment
The licensee immediately stopped all dry cask storage operations following the
misalignment incident of August 3, 2018, pending a root cause evaluation to be
performed by their dry cask storage vendor, Holtec International. The licensee initiated
an apparent cause evaluation to determine if problems in its organization may have
contributed to the misalignment incident.
The misalignment incident was entered into the corrective action program by Holtec
as FCR 2464-1189. The Holtec FCR was initiated to investigate the August 3, 2018,
incident as a human performance issue. This FCR prompted the licensee to initiate
Action Request 0818-76588. This action request included an assessment of the
condition of the divider shell and canister.
Action Request 0818-76588 described the removal of paint/coating from the divider
shell. The action request concluded that the incidental transfer of divider shell coating to
the canister shell did not affect the canisters design functions of confinement, shielding,
structural, thermal, and criticality. Future actions to address coating presence will be
included in the licensees ISFSI aging management plan. The NRC team reviewed the
licensees assessment for the divider shell and concluded the component can perform its
safety functions. Additionally, the licensees plan to address future inspection of the
divider shells in its aging management program was acceptable.
Apparent Violation 10 CFR 72.75, Reporting
The team identified an apparent violation of 10 CFR 72.75 for late notification of 24-hour
reporting requirements involving important to safety equipment that was disabled or
failed to function as designed when the equipment is required by license condition and
no redundant equipment is available and operable to perform the required safety
function.
On August 3, 2018, during downloading operations associated with canister 29 the
licensee disabled the important to safety slings while downloading a canister (See
16
Section 2.1 and 2.2). The canister was placed in a potential load drop condition for
approximately 45 minutes before the licensee was able to restore the load onto the
important to safety slings, thereby restoring the redundant drop protection features.
After the incident, the licensee provided a courtesy notification to the NRC Region IV
office at approximately 4 p.m. CDT on the afternoon of August 6, 2018.
Section 10 CFR 72.75(d)(1), would have allowed for notification to be made to the
NRC Operations Center as late as 0800 EDT on Monday, August 6, 2018. The courtesy
notification made to the regional office did not satisfy the reporting requirements
of 10 CFR 72.75. During the August 6, 2018, call, the NRC informed the licensee that a
formal report to the NRC was likely required.
Notification of the NRC Operations Center did not occur until the licensee was prompted
by the NRC team on September 14, 2018. The condition was reported to the NRC
Headquarters Operations Center on September 14, 2018, at 1600 EDT (Event
Notification 53605).
Title 10 CFR 72.75(d)(1) requires, in part, that each licensee shall notify the NRC within
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the discovery of any of the following events involving spent fuel in which
important to safety equipment is disabled or fails to function as designed when: (i) the
equipment is required by regulation, license condition, or certification of compliance to
be available and operable to mitigate the consequences of an accident; and (ii) no
redundant equipment was available and operable to perform the required safety
function.
Contrary to the above, from August 6 to September 14, 2018, the licensee failed to notify
the NRC after discovery of important to safety equipment being disabled and failing to
function as designed when required by the Certificate of Compliance to provide
redundant drop protection features to prevent and mitigate the consequences of a drop
accident and no redundant equipment was available and operable to perform the
required safety function.
The licensees failure to make the required 24-hour notification to the NRC within the
required timeframe was identified as an apparent violation of 10 CFR 72.75(d).
(AV 07200041/2018-001-05, Failure to make 24-hour notification)
Conclusions
The licensee concluded that the incidental removal of divider shell coating during
downloading operations did not affect the design functions for shielding, structural, and
thermal safety functions. The NRC has reviewed the licensees assessment for the
divider shell and has concluded the component can perform its safety functions.
Additionally, the licensees plan to address future inspection of the divider shells in their
aging management program is acceptable.
The licensee failed to make the required formal 24-hour NRC notification of the
August 3, 2018, event where important to safety equipment was disabled when the
equipment was required to mitigate the consequences of an accident and no redundant
equipment was available to perform the safety function. This failure was identified as an
apparent violation of 10 CFR 72.75(d) requirements.
17
3.1.5 Charter Item 6
Inspection Scope
Review the licensees root cause investigation results, to determine whether the review
thoroughly identified all contributing factors and that final corrective actions will be
adequate to prevent reoccurrence. Evaluate whether prior operational experience
relating to complications or issues associated with canister downloading operations was
identified and considered as part of the licensees root cause investigation and corrective
action development.
The Special Inspection team reviewed the causal evaluations that were performed for
the August 3, 2018, misalignment incident. Specifically, the team reviewed Holtec
Internationals Root Cause Analysis Report for the canister downloading incident and the
licensees Apparent Cause Evaluation to assess oversight effectiveness during the
August 3, 2018, download of canister 29.
Observations and Findings:
Holtec Internationals Root Cause Evaluation
The licensee directed Holtec to perform a causal evaluation as a follow-up item in
condition report action request 0818-76588 that the licensee initiated following the
August 3, 2018, misalignment incident. The Holtec causal evaluation identified one root
cause and five contributing causes:
- Root Cause: Holtec Management failed to implement appropriate program
improvements or the necessary level of oversight commensurate with the
complexity and risks associated with downloading operations.
- Contributing Cause 1: Inadequate content in procedures for recognizing special
conditions.
- Contributing Cause 2: Design review process did not ensure that unintended
consequences of design features were captured.
- Contributing Cause 3: Communication protocols with the chain of command
established during canister movement were not well defined.
- Contributing Cause 4: Holtec had not established a continuous learning
environment which promoted the use of internal and external operating
experience.
- Contributing Cause 5: Holtec Training Program did not fully establish
qualification or proficiency requirements for workers performing downloading
operations.
18
Southern California Edison Companys Apparent Cause Evaluation
The licensee initiated an apparent cause evaluation (ACE) to determine how its
organization may have contributed to allowing the August 3, 2018, loss-of-load incident
to occur. The licensees apparent causes were related to deficiencies in procedures,
training, and in oversight of contractor activities.
- Apparent Cause 1: Management failed to establish a process to ensure that site
dry cask storage procedures were technically accurate.
- Apparent Cause 2: Management failed to establish licensee and contractor
training to support procedure implementation.
- Apparent Cause 3: Management failed to sufficiently detail contractor Oversight
Specialist guidance.
- Contributing Cause 1: ISFSI project management was not routinely observing
dry cask storage operations.
- Contributing Cause 2: ISFSI project management was not consistently initiating
condition reports for dry cask storage operations that deviated from normal.
Both the licensee and Holtec causal evaluations reviewed many of the items identified
by the NRC team. Those items being: procedure adequacy; training adequacy;
adequacy of the corrective action program; oversight adequacy; and the inconsistent use
of operational experience during routine dry cask storage operations.
The causal evaluations assessed the severity of the canister misalignment incident. The
licensee determined that in the event of a canister drop accident from 25 feet into the
vault, there was no risk of radioactive exposure to the public. A publicly available
version of the licensees drop analysis summary is available in ADAMS (ADAMS
Accession No. ML18330A003). The NRC will continue to review the adequacy of the
causal analyses, corrective actions, and potential consequences during a follow-up
inspection which is planned to be performed before the resumption of fuel handling
activities.
Conclusions
The apparent and root causes for the August 3, 2018, canister misalignment incident
involved inadequate training, inadequate procedures, poor utilization of the corrective
action program, and insufficient oversight.
3.1.6 Charter Item 7
Inspection Scope
Review the licensees planned actions that will address the point loading condition that
was experienced by the affected canister. If applicable, review the licensees analysis
that demonstrated the canister will continue to perform as designed for continued
storage OR review licensees inspection plan to safely remove or lift the canister from
19
the vault to support inspection of the bottom of the canister to demonstrate the canister
did not receive any damage that would inhibit the component from continuing to perform
as designed.
Observations and Findings
The licensee performed an evaluation to demonstrate the canister continues to meet the
design and performance requirements described in the FSAR. The Special Inspection
team reviewed the licensees initial assessment of the canister 29 condition after the
misalignment incident.
The preliminary evaluation provided by the licensee stated that both the canister and
vault were not expected to have any physical damage that would exceed the pre-defined
limits used during receipt inspection and manufacturer acceptance testing. The NRC
requested additional analysis to ensure that the canister meets design requirements.
Additionally, the licensee is evaluating whether the canister will require increased
surveillance frequency for the aging management program. The licensee had not
completed the evaluation for NRC review prior to the NRCs inspection exit meeting.
This charter item will be reviewed during a future NRC inspection.
Conclusions
The licensee has chosen to provide an analysis to demonstrate that the potential
damage to canister 29 during the downloading would meet established acceptance
criteria. The NRC determined that additional analysis was required for the NRC to
ensure that the canister meets design requirements. This charter item will be reviewed
during a future NRC inspection.
3.1.7 Charter Item 9
Inspection Scope
As directed by regional management, observe resumption of fuel loading operations to
verify that corrective actions were effective in addressing deficiencies that contributed to
the incident. This should include evaluation of procedure and/or equipment
enhancements; review or observation of training and briefings provided to riggers, crane
operators, spotters and observers, supervisors and other personnel involved in fuel
loading operations.
Observations and Findings
The licensee suspended all fuel handling activities following the August 3, 2018,
misalignment incident. The NRC will review the licensees revised procedures, training
plans, equipment modifications, and performance testing (dry runs) of its dry cask
storage operations in a future inspection to determine the effectiveness of corrective
actions for the incident.
Conclusions
All associated corrective actions for the August 3, 2018, incident had not been
completely finalized or implemented by the licensee. The NRC will review the licensees
20
revised procedures, training plans, equipment modifications, and performance testing
(dry runs) of its dry cask storage operations during a future inspection to determine the
effectiveness of corrective actions for the incident.
3.1.8 Charter Item 10
Inspection Scope:
Determine if the inspection should be elevated to an Augmented Inspection Team (AIT)
inspection and promptly notify regional management of any recommendation to escalate
the special inspection to an AIT.
As a daily action item, the NRC Special Inspection Team reviewed NRC Inspection
Manual Chapter 0309, Reactive Inspection Decision Basis for Reactors, Enclosure 2,
to determine whether any of the facts or details uncovered during the course of the
inspection met the deterministic criteria that would require the Special Inspection at
SONGS to be elevated to an AIT.
Observations and Findings
The deterministic criteria for an event to be elevated to an AIT effort are delineated in
Manual Chapter 0309. The Special Inspection Team did not identify any indication that
the August 3, 2018, misalignment incident at SONGS led to a radiological release.
Additionally, the incident did not involve the failure of the spent fuel canister, the release
of radiological contamination, or external radiation levels that exceeded 10 rads/hr.
Consequently, there was no need to elevate the inspection effort to an AIT. The teams
daily re-evaluation was communicated to Regional management during the week of
onsite inspection effort.
Conclusions
The NRC team did not identify any information that would have required the Special
Inspection to be elevated to an AIT effort.
4 Exit Meeting Summary
On September 14, 2018, following the onsite portion of the inspection, the inspectors
provided a debrief of the preliminary results to Mr. Tom Palmisano, former Vice President
and Chief Nuclear Officer and other members of the licensee staff. The licensee
acknowledged the issues presented by the NRC inspection team.
On November 1, 2018, the inspectors presented the final inspection results to Mr. Tom
Palmisano, former Vice President and Chief Nuclear Officer and other members of the
licensee staff. The licensee acknowledged the issues presented.
On November 8, 2018, the NRC performed a public webinar meeting to discuss the
inspection teams preliminary results.
21
SUPPLEMENTAL INSPECTION INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
A. Bates, Regulatory and Oversight Manager
M. Morgan, Regulatory and Oversight
L. Bosch, Plant Manager
G. Carter, Westinghouse Project Manager
P. Chaudnary, Vice President of Operations, Holtec
J. Manso, ISFSI Sr. Project Manager
T. Palmisano, former Vice President Decommissioning and Chief Nuclear Officer
J. Pugh, Project Engineer
K. Rod, General Manager Decommissioning Oversight
J. Smith, Project Manager, Holtec
M. Soler, Vice President Quality, Holtec
INSPECTION PROCEDURES USED
IP 93812 Special Inspection
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
072-00041/2018-001-01 VIO Failure to identify and correct conditions adverse to
quality (10 CFR 72.172)
072-00041/2018-001-02 AV Failure to ensure redundant drop protection features
were available (10 CFR 72.212)
072-00041/2018-001-03 VIO Failure to assure that operations of important to safety
equipment were limited to trained and certified
personnel (10 CFR 72.190)
072-00041/2018-001-04 VIO Failure to provide adequate instructions or procedures
072-00041/2018-001-05 AV Failure to make 24-hour notification (10 CFR 72.75)
Discussed
None
Closed
None
Attachment
LIST OF ACRONYMS USED
ADAMS Agencywide Documents Access and Management System
ADR Alternative Dispute Resolution
AIT Augmented Inspection Team
ANSI American National Standards Institute
AV Apparent Violation
ASME American Society of Mechanical Engineers
CFR Code of Federal Regulations
CLS Cask Loading Supervisor
FCR Field Condition Report
FSAR Final Safety Analysis Report
HI-STORM UMAX Holtec International Storage Module Underground Maximum Capacity
HMI Human-Machine Interface
IP Inspection Procedure
ISFSI Independent Spent Fuel Storage Installation
JLG Engine or Motor Powered Boom Lifting Device
NOV Notice of Violation
NRC U.S. Nuclear Regulatory Commission
MPC multipurpose canister
PEC Pre-decisional Enforcement Conference
RIC Rigger-in-charge
RPT Radiation Protection Technician
SL Severity Level
SONGS San Onofre Nuclear Generating Station
TS Technical Specification
VCT Vertical Cask Transporter
VIO Violation
VVM Vertical Ventilated Module or vault
2
INSPECTION CHARTER
TO EVALUATE THE NEAR-MISS LOAD DROP
EVENT AT SAN ONOFRE NUCLEAR
GENERATING STATION DATED
AUGUST 17, 2018
Enclosure 3
August 17, 2018
MEMORANDUM TO: Eric J. Simpson, CHP, Health Physicist
Fuel Cycle and Decommissioning Branch
Division of Nuclear Materials Safety
W. Chris Smith, Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Marlone X. Davis, Transportation & Storage Safety Inspector
Inspections & Operations Branch
Division of Spent Fuel Management
THROUGH: Janine F. Katanic, PhD, CHP, Chief /RA/ LLH for
Fuel Cycle and Decommissioning Branch
Division of Nuclear Materials Safety
FROM: Troy W. Pruett, Director /RA/
Division of Nuclear Materials Safety
SUBJECT: INSPECTION CHARTER TO EVALUATE THE NEAR-MISS LOAD
DROP EVENT AT SAN ONOFRE NUCLEAR GENERATING
STATION
A special inspection has been chartered to review the licensees follow-up investigation,
causal evaluation, and planned corrective actions regarding the near-miss drop event
involving a loaded spent fuel storage canister at the San Onofre Nuclear Generating Station
(SONGS) Independent Spent Fuel Storage Installation (ISFSI) on Friday, August 3, 2018.
(License Nos. NPF-10 and NPF-15, Docket Nos. 50-361, 50-362 and 72-41).
CONTACT: Janine F. Katanic, PhD, CHP, FCDB/DNMS
(817) 200-1151
BACKGROUND AND BASIS
On Friday, August 3, 2018, at approximately 1:30 pm (PST), SONGS was engaged in
operations involving movement of a loaded spent fuel storage canister into its underground
ISFSI storage vault (HI-STORM UMAX storage system). As the loaded spent fuel canister was
being lowered into the storage vault using lifting and rigging equipment, the licensees personnel
failed to notice that the canister was misaligned and was not being properly lowered. The
licensee continued to lower the rigging and lifting equipment until it believed that the canister
had been fully lowered to the bottom of the storage vault. However, a radiation protection
technician identified elevated radiation readings that were not consistent with a fully lowered
canister. The licensee then identified that the loaded spent fuel canister was hung up on a
metal flange near the top of the storage vault, preventing it from being lowered, and that the
rigging and lifting equipment was slack and no longer bearing the load of the canister.
In this circumstance, with the important to safety (ITS) rigging and lifting equipment completely
down in the lowest position, the ITS equipment was disabled from performing its designed
safety function of holding and controlling the loaded canister from a potential canister drop
condition. The licensee reported that the canister was resting on a metal flange within the
storage vault. It was estimated that the canister could have experienced an approximately
17-18 foot drop into the storage vault if the canister had slipped off the metal flange or if the
metal flange failed. This load drop accident is not a condition analyzed in the dry fuel storage
systems Final Safety Analysis Report (FSAR).
In response to the discovery that the canister was not fully lowered, the licensee took immediate
actions to restore control of the load to the rigging and lifting devices. The estimated time the
canister was in an unanalyzed credible drop condition was approximately 45 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
in duration. The licensee regained control of the load, repositioned the canister, and lowered
the canister into the storage vault. The licensee halted all dry fuel storage movement
operations in order to fully investigate the incident and develop corrective actions to prevent a
recurrence. In addition, the licensee has shared the operational experience with another site
with a similar dry fuel storage system.
Region IV became aware of the SONGS near-miss incident on Monday, August 6, 2018, when
the licensee provided a courtesy notification and described it as a near-miss or near-hit
event. The reporting requirements of the incident are still being evaluated by the Region and
discussed with the licensee.
On August 7 and 16, 2018, Region IV and NMSS representatives participated in conference
calls with licensee representatives in order to gather additional facts regarding the
circumstances of the incident and the licensees investigation. Region IV is evaluating the
information provided by the licensee and is coordinating with the Division of Spent Fuel
Management, NMSS.
The NRC is chartering this special inspection pursuant to Management Directive 8.3, NRC
Incident Investigation Program, and NRC Inspection Manual Chapter 0309, Reactive
Inspection Decision Basis for Reactors.
The purpose of the inspection is to investigate the occurrence; interview personnel; observe
equipment; and review relevant documentation, including the results of the licensees
investigation and causal analysis, and development and implementation of actions to prevent
3
recurrence. The licensee has committed to not resume fuel loading operations until after this
special inspection and associated reviews are complete. Once the licensee has confirmed its
plans to resume fuel loading operations, inspectors will also observe the loading operations to
ensure that the corrective actions are adequate. These observations may be conducted as part
of this special inspection or as an independent inspection activity, as directed by regional
management.
SCOPE
The inspection should seek to address the following items at a minimum:
1. Identify and review all pertinent records, documents, and procedures related to the
licensees downloading operations at the ISFSI pad including but not limited to: worker
training and qualifications; rigging equipment qualification, testing, and preventative
maintenance; and lifting equipment qualification, testing, and preventative maintenance.
Evaluate the adequacy of the above noted procedures, worker training and equipment
testing and preparation.
2. Evaluate the adequacy of the loading procedure(s) with respect to verification of MPC
movement, centering the MPC over the ISFSI vault, lowering the MPC, and positioning
the MPC within the ISFSI vault. Interviews with personnel involved in the ISFSI loading
operations should be conducted to evaluate licensee and contractor communications
between crane/VCT operators, rigging and spotting staff, cask loading supervisors,
radiation protection staff, and licensee oversight personnel. Evaluate the adequacy of
pre-job briefings that may have taken place prior to fuel loading operations.
3. Review and evaluate the licensees immediate corrective actions taken after the event for
adequacy of notifications to the licensee and safety assessments performed immediately
following the event. Review the licensees inspection documentation and/or analysis to
determine whether the vaults divider shell experienced any damage that would inhibit the
component from performing its designed safety function.
4. Based on the review of procedures and interviews of personnel involved with loading
operations, evaluate the adequacy of procedure adherence.
5. Interview personnel associated with the event to develop a timeline to ensure the
licensees investigation contained all necessary information to identify all contributing
factors and develop adequate corrective actions.
6. Review the licensees root cause investigation results, to determine whether the review
thoroughly identified all contributing factors and that final corrective actions will be
adequate to prevent reoccurrence. Evaluate whether prior operational experience
relating to complications or issues associated with canister downloading operations was
identified and considered as part of the licensees root cause investigation and corrective
action development.
7. Review the licensees planned actions that will address the point loading condition that
was experienced by the affected canister. If applicable, review the licensees analysis
that demonstrated the canister will continue to perform as designed for continued storage
OR review licensees inspection plan to safely remove or lift the canister from the vault to
support inspection of the bottom of the canister to demonstrate the canister did not
4
receive any damage that would inhibit the component from continuing to perform as
designed.
8. Investigate the licensees procedures for reportability to the NRC and determine if the
licensee made the correct decision regarding notifications made to the NRC for this
event.
9. As directed by regional management, observe resumption of fuel loading operations to
verify that corrective actions were effective in addressing deficiencies that contributed to
the event. This should include evaluation of procedure and/or equipment enhancements;
review or observation of training and briefings provided to riggers, crane operators,
spotters and observers, supervisors and other personnel involved in fuel loading
operations.
10. Determine if the inspection should be elevated to an AIT and promptly notify regional
management of any recommendation to escalate the special inspection to an AIT.
GUIDANCE
The NRC is chartering this special inspection pursuant to Management Directive 8.3, NRC
Incident Investigation Program, and NRC Manual Chapter 0309, Reactive Inspection Decision
Basis for Reactors. The Manual Chapter and Management Directive identify Inspection
Procedure 93812, Special Inspection, for specific use in reviewing events. Planned Dates of
Inspection are September 10-14, 2018.
This inspection should emphasize fact-finding in its review of the circumstances surrounding the
near-miss canister drop event. Safety concerns identified that are not directly related to near-
miss drop event should be reported to NRC management for appropriate action.
Daily briefings with NRC management should occur to discuss the teams progress and
preliminary observations.
In accordance with Manual Chapter 0610, a report documenting the results of the inspection
should be issued within 30-45 days of the completion of the inspection.
This Charter may be modified should NRC inspectors find significant new information that
warrants review. Should you have any questions concerning this charter, please contact
Janine F. Katanic at 817-200-1151.
5