ML23214A247
| ML23214A247 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/22/2023 |
| From: | Paul Krohn Decommissioning, ISFSI, and Reactor Health Physics Branch |
| To: | Trice K Holtec Decommissioning International |
| References | |
| EA-23-076 IR 2023002 | |
| Download: ML23214A247 (1) | |
See also: IR 05000219/2023002
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
475 ALLENDALE ROAD, SUITE 102
KING OF PRUSSIA, PA 19406-1415
August 22, 2023
Kelly Trice
President
Holtec Decommissioning International, LLC
Krishna P. Singh Technology Campus
1 Holtec Boulevard
Camden, NJ 08104
SUBJECT:
HOLTEC DECOMMISSIONING INTERNATIONAL, LLC, OYSTER CREEK
NUCLEAR GENERATING STATION - NRC INSPECTION REPORT NO.
Dear Kelly Trice:
On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program, at
the permanently shut down Oyster Creek Nuclear Generating Station (Oyster Creek). The
inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and the conditions of your license. The
inspection consisted of observations by the inspectors, interviews with site personnel, a review
of procedures and records, and plant walk-downs. The results of this inspection were discussed
with Jeffrey Dostal, Site Vice President, and other members of your staff on July 11, 2023, and
are described in the enclosed report.
Based on the results of this inspection, an apparent violation (AV) was identified and is being
considered for escalated enforcement action, including a civil penalty, in accordance with the
NRC Enforcement Policy. The current Enforcement Policy is available on the NRCs Web site at
http://www.nrc.gov/about-nrc/regulatory/enforcement/enforce-pol.html. The AV involves the
failure by Holtec Decommissioning International, LLC (HDI) staff at Oyster Creek to design and
prepare radioactive materials for shipment so that under conditions normally incident to
transportation the radiation level does not exceed 200 mrem/hr at any point on the external
surface of the package, as required by Title 49 of the Code of Federal Regulations (49 CFR)
173.441. Pursuant to 10 CFR 71.5, licensees who transport licensed materials on public
highways must comply with the requirements of the U.S. Department of Transportation
regulations in 49 CFR Parts 170 through 189.
Before the NRC makes its enforcement decision, you may provide a written response to the
NRC regarding the AV and HDIs corrective actions. The written response should include:
(1) the reason for the AV or, if contested, the basis for disputing the AV; (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.
If you choose to provide a written response, it should be sent to the NRC within 30 days of the
date of this letter. You should clearly mark the response as a Response to Apparent Violation
K. Trice
2
in NRC Report No. 05000219/2023002; EA-23-076, and send it to the U.S. Nuclear Regulatory
Commission, ATTN: Document Control Desk, Washington, DC 20555-0001 with a copy to the
Regional Administrator, NRC Region I, 475 Allendale Road, Suite 102, King of Prussia, PA
19406-1415. If an adequate response is not received within the time specified or an extension of
time has not been granted by the NRC, the NRC will proceed with its enforcement decision or
schedule a pre-decisional enforcement conference (PEC).
In lieu of providing a written response, you may choose to provide your perspective on this
matter, including the significance, cause, and corrective actions, as well as any other
information that you believe the NRC should take into consideration, by requesting a PEC to
meet with the NRC and provide your views in person.
If you choose to request a PEC, the meeting should be held within 30 days of the date of this
letter. The conference will include an opportunity for you 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 PEC 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. 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.
In presenting your corrective actions in a written response or at a PEC, you should be aware
that the promptness and comprehensiveness of your actions will be considered in assessing
any civil penalty for the AV. The guidance in NRC Information Notice 96-28, Suggested
Guidance Relating to Development and Implementation of Corrective Action, at
https://www.nrc.gov/docs/ML0612/ML061240509.pdf, may be helpful.
Finally, in lieu of a PEC, you may also request Alternative Dispute Resolution (ADR) mediation
with the NRC in an attempt to resolve this issue. ADR 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; 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 NRC ADR program can be obtained at
http://www.nrc.gov/about-nrc/regulatory/enforcement/adr.html . The Institute on Conflict
Resolution (ICR) at Cornell University has agreed to facilitate the NRC program as a neutral
third party. Please contact ICR at 877-733-9415 within 10 days of the date of this letter if you
are interested in pursuing resolution of this issue through ADR. The ADR mediation session
should be held within 45 days of the date of this letter.
Please contact Anthony Dimitriadis, Chief, Decommissioning, ISFSI, and Reactor Health
Physics Branch, NRC Region I, at 610-337-6953 within 10 days of the date of this letter to notify
the NRC of which of the above options you choose. If you do not contact the NRC within the
time specified, and an extension of time has not been granted by the NRC, the NRC will
proceed with its enforcement decision.
K. Trice
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.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
enclosure, and your response (if any) will be made available electronically for public inspection in
the NRC Public Document Room or from the NRC document system Agencywide Document
Access and Management System (ADAMS), accessible from the NRC website at
http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not
include any personal privacy, proprietary, or safeguards information so that it can be made
available to the public without redaction.
Current NRC regulations and guidance are included on the NRCs website at www.nrc.gov;
select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations,
Guidance and Communications. The current Enforcement Policy is included on the NRCs
website at www.nrc.gov; select About NRC, Organizations & Functions; Office of
Enforcement; Enforcement documents; then Enforcement Policy (Under Related
Information). You may also obtain these documents by contacting the Government Printing
Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST,
Monday through Friday (except Federal holidays).
Please contact Andrew Taverna of my staff at 610-337-5119 if you have any questions
regarding this matter.
Sincerely,
Paul G. Krohn, Director
Division of Radiological Safety and Security
Docket No:
05000219
License No: DPR-16
Enclosure: Inspection Report 05000219/2023002
w/Attachment
cc w/encl: Distribution via ListServ
Paul G. Krohn
Digitally signed by Paul G.
Krohn
Date: 2023.08.22
10:49:49 -04'00'
K. Trice
4
SUBJECT:
HOLTEC DECOMMISSIONING INTERNATIONAL, LLC, OYSTER CREEK
NUCLEAR GENERATING STATION - NRC INSPECTION REPORT NO.
05000219/2023002 DATED AUGUST 22, 2023
Distribution:
J Peralta, OE
N Hasan, OE
D Bradley, OE
M Simon, OGC
M Burgess, NMSS
R Lorson, RI
D Collins, RI
P Krohn, DRSS, RI
R1DRSSMAILRESOURCE
J Quichocho, DRSS, RI
A Taverna, DRSS, RI
K Warner, DRSS, RI
A Dimitriadis, DRSS, RI
D Screnci, PAO-RI / N Sheehan, PAO-RI
B Klukan, ORA, RI
R1Enforcement
E Spangler, RI
Region I OE Files (with concurrences)
DOCUMENT NAME: https://usnrc.sharepoint.com/teams/Region-I-Decommissioning-Branch/Inspection
Reports/Inspection Reports - Draft/OC_2Q2023_draft.docx
SUNSI Review Complete: A. Taverna
ADAMS ACCESSION NO. ML23214A247
After declaring this document An Official Agency Record it will be released to the Public.
SUNSI Review/ MMM
X Non-Sensitive
Sensitive
X Publicly Available
Non-Publicly Available
OFFICE
RI: DRSS
RI: ORA
RI: DRSS
RI: ORA
RI: ORA
NAME
ATaverna
MMcLaughlin
ADimitriadis
RSusko NLO
JNick
DATE
08/02/2023
08/21/2023
08/03/2023
08/03/23
08/21/23
OFFICE
RI: DRSS
NAME
D Bradley
R Sun
M Simon NLO w edits PKrohn
DATE
08/15/2023
08/15/2023
08/15/2023
08/22/23
OFFICIAL RECORD COPY
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Docket No:
050-00219
License No:
Report No:
Licensee:
Holtec Decommissioning International, LLC
Facility:
Oyster Creek Nuclear Generating Station
Location:
Forked River, New Jersey
Dates:
January 1, 2023 - June 30, 2023
Inspectors:
A. Taverna, Health Physicist
Decommissioning, ISFSI and Reactor Health Physics Branch
Division of Radiological Safety and Security
K. Warner, CHP, Senior Health Physicist
Decommissioning, ISFSI and Reactor Health Physics Branch
Division of Radiological Safety and Security
R. Turtil, Senior Financial Analyst,
Financial Assessment Branch
Division of Rulemaking, Environmental, and Financial Support
Office of Nuclear Material Safety and Safeguards
Approved by:
Anthony Dimitriadis, Chief
Decommissioning, ISFSI and Reactor Health Physics Branch
Division of Radiological Safety and Security
2
EXECUTIVE SUMMARY
Holtec Decommissioning International, LLC (HDI)
Oyster Creek Nuclear Generating Station
NRC Inspection Report No. 05000219/2023002
A routine, announced decommissioning inspection was completed on June 30, 2023, at the
permanently shut down Oyster Creek Nuclear Generating Station (OC). A combination of
on-site and remote inspection activities were performed over the inspection period. On-site
inspection activities were conducted on May 22, and June 26 - 29, 2023. The inspection
included safety reviews, design changes, and modifications at permanently shutdown reactors,
problem identification and resolution, decommissioning performance, and status reviews;
occupational radiation exposure; and solid radioactive waste management and transportation of
radioactive materials. The inspection consisted of observations by the inspectors, interviews
with site personnel, a review of procedures and records, and plant walk-downs. The U.S.
Nuclear Regulatory Commissions (NRCs) program for overseeing the safe decommissioning of
a shutdown nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561,
Decommissioning Power Reactor Inspection Program.
Apparent Violation
One apparent violation was identified for HDIs failure to properly prepare and ship a package
containing radioactive material in a manner that assured, under conditions normally incident to
transport, conformance with U.S. Department of Transportation (DOT) radiation level limitations
specified by Title 49 of the Code of Federal Regulations (49 CFR) 173.441 on any external
surface of the package. Specifically, inadequate radiological surveys performed at OC indicated
that the package conformed with DOT limits. However, when the shipment arrived at Indian
Point Energy Center (IPEC) on May 3, 2023, the maximum radiation dose rate on the external
surface of the package (topside) was measured as 450 millirem per hour (mrem/h), exceeding
the DOT limit of 200 mrem/h.
3
REPORT DETAILS
1.0
Background
On September 25, 2018, Oyster Creek certified the permanent removal of fuel from the
reactor vessel (Agencywide Document Access and Management System (ADAMS)
Accession No. ML18268A258). This met the requirements of 10 CFR 50.82(a)(1)(i) and
50.82(a)(1)(ii). On October 1, 2018, the NRC notified the licensee that the Operating
Reactor Assessment Program had ceased, and that implementation of the
Decommissioning Power Reactor Inspection Program would begin on October 1, 2018
(ADAMS Accession No. ML18274A221). On July 1, 2019, an amended license was
issued transferring the license from Exelon Generation Co., LLC to Holtec
Decommissioning International, LLC (ADAMS Accession No. ML19164A157). OC is
currently in the Actively Decommissioning, No Fuel in the Spent Fuel Pool (SFP) phase
of decommissioning as described in IMC 2561.
2.0
Active Decommissioning Performance and Status Review
2.1
Inspection Procedures 37801, 40801, 71801, 83750
a. Inspection Scope
The inspectors performed on-site decommissioning inspection activities on May 22, and
June 26 - 29, supplemented by in-office reviews and periodic phone calls during the
inspection period. The inspection consisted of observations by the inspectors, interviews
with site personnel, a review of procedures and records, and plant walk-downs.
The inspectors assessed the implementation and effectiveness of HDIs corrective action
program (CAP) for OC by reviewing a sampling of issues, and conditions adverse to
quality entered in the CAP.
The inspectors attended select management meetings, including station oversight
committee and management review committee meetings. Inspectors reviewed
documentation and met with OC management to discuss staffing, status of
decommissioning and upcoming activities to determine if HDI had conducted activities
in accordance with regulatory requirements. The inspectors performed several plant
walk-downs to assess field conditions and decommissioning activities by evaluating
material condition of structures, systems, and components; housekeeping; system
configurations; and worker level of knowledge and procedure use and adherence. These
walk-downs included the new radwaste building, reactor building, Low Level Rad Waste
Storage Facility (LLRWSF), and the Radiologically Controlled Area (RCA). Additionally,
the inspectors observed select pre-job briefings and associated work activities, including
but not limited to spraying contaminant fixative to the walls of the SFP and movement of
a liner containing used filters.
The inspectors observed activities, reviewed documentation, and interviewed personnel
associated with occupational radiation exposure to evaluate the licensees protection of
worker health and safety as well as the staffing of the radiological protection department.
The inspectors conducted site walk-downs, including radiologically controlled areas, to
examine and verify radiological postings, and airborne and contamination controls. The
inspectors reviewed radiation work permits (RWPs) and As Low As Reasonably
4
Achievable (ALARA) work plans to determine if radiation work activities were
pre-planned effectively to limit worker exposure. Inspectors also attended various
briefings where radiological and industrial safety during work activities were discussed.
The inspectors observed radiation protection (RP) staff perform work activities. The
inspectors observed the RP coverage during the following work activities: (1) lifting
and movement of the liner and (2) spray painting contaminant fixative in the SFP.
Additionally, the inspectors observed staff donning and doffing protective clothing and
using portal exit monitors out of the RCA. During the inspectors walk-down of the
reactor building and new radwaste building, a sample of instruments was checked for
their condition and calibration.
The inspectors reviewed documentation and interviewed personnel associated with
safety reviews, design changes, and modifications. The review included the sites safety
review process and procedures for identifying changes to technical specifications,
determining if the site had appropriate level of staffing and training for its safety review
process, and a review of design basis documents for consistency with design changes
made at the site. Additionally, a sample of design changes and screenings was
reviewed.
The inspectors reviewed documentation and discussed with HDI the overall financial
status of decommissioning for OC and evaluated the use of decommissioning trust funds
to determine if they were appropriately used in accordance with regulatory requirements.
The inspectors also discussed any significant changes to the estimated cost for, and any
potential significant delays to, the decommissioning schedule.
b. Observations and Findings
The inspectors determined that issues had been identified, entered into the CAP, and
evaluated commensurate with their safety significance through document review,
interviews, and observation of several management review committee and station
oversight committee meetings.
The inspectors noted that during this inspection period, the site continued
decommissioning and dismantlement activities in the new radwaste building. The
inspectors noted that for the areas of the plant toured, the material condition and
housekeeping was adequate. The inspectors determined through plant tours, document
reviews, and observations of activities that HDI conducted activities in accordance with
the regulatory requirements. The inspectors noted that workers were knowledgeable of
and adhered to plant procedures and work plans, and pre-job briefings were thorough
and highlighted specific safety concerns.
The inspectors verified that the RWPs, ALARA work plans, and micro-ALARA plans
were implemented to limit worker exposure. The inspectors determined that RP staff
effectively controlled observed work activities and used appropriate equipment during
those work activities. Inspectors noted during the liner movement, the RP personnel
conducted continuous instrument dose rate measurements, had effective communication
for individuals to move to low dose areas, and had proper controls during the movement
such as postings and guards were appropriate in identifying the magnitude and extent of
the radiological hazard. The licensee plans for the work were commensurate with the
risk of the work and associated hazards. The inspectors verified that selected
instruments during walk-downs were in calibration and in working condition.
5
The inspectors determined that screenings and design changes were properly
performed in accordance with the sites safety review process and procedures and in
accordance with 10 CFR 50.59. The inspectors determined the licensees safety review
process committee was appropriately staffed and had a training program consistent with
site requirements. Inspectors determined design basis documents were appropriately
consistent with design changes.
The inspectors reviewed financial assurance documentation, including HDIs annual
report on the status of decommissioning funding and met with HDI staff to determine
whether the funds were used as expected and if any changes could significantly impact
the sites decommissioning financial assurance. The inspectors noted that the annual
report included a notification of schedule change in accordance with 10 CFR 50.82(a)(7).
This schedule change related to a delay of activities and partial site release but did not
impact the milestones for the overall scheduled license termination dates. An open item
was initiated to track the NRCs continued review of sampled withdrawals from the
decommissioning trust funds to determine if such withdrawals were in accordance with
regulatory requirements (Open Item 05000219/2023002-01), Continued review of
decommissioning trust fund withdrawals).
c. Conclusions
No violations of more than minor safety significance were identified.
2.2
Inspection Procedure 86750, Solid Radioactive Waste Management and Transportation
of Radioactive Materials
a. Inspection Scope
On May 22, 2023, the inspectors reviewed activities and documentation, performed site
walk-downs, and observed work activities associated with the possession, processing,
storage, and shipment of licensed radioactive material.
The inspectors performed a focused review of the circumstances surrounding a
May 3, 2023, radioactive material shipment (Shipping Manifest Number OC-23-0208)
from OC to IPEC. The radioactive material shipment (two packages via an Exclusive
Use open transport vehicle) was received at IPEC on May 3, 2023. Upon receipt, one of
the packages, which contained contaminated equipment (a Class B/C waste alignment
fixture), was found to have radiation levels on the external surface (topside) in excess of
the DOT radiation limit for external surface of packages shipped by Exclusive Use open
transport vehicles, as specified in 49 CFR 173.441. Specifically, 49 CFR 173.441 limits
the radiation level on the surfaces of such packages to 200 mrem/h. When received at
IPEC, the radiation level on the surface of one of the packages was measured as 450
mrem/h. Upon identification, HDI documented the issue in its CAP as OYS-03315.
During an inspection at IPEC May 16 - 18, 2023, the inspectors witnessed the
as-received condition of the OC shipment in the Unit 3 vapor containment. The
inspectors observed the conduct of radiological surveys of the package conducted by
IPEC RP personnel, and the radiological controls implemented to open and examine the
package contents. In addition, the inspectors reviewed shipping documentation,
including all receipt surveys conducted by IPEC personnel.
6
b. Observations and Findings
The inspectors performed walk-downs of several radioactive materials storage areas,
including the LLRWSF and RCA yard, and determined that radioactive material was
adequately stored, and the areas were posted in accordance with regulatory
requirements. The inspectors observed portions of radiological surveys for an outgoing
shipment and determined that RP staff performed their surveys in accordance with site
procedures. The inspectors noted that no abnormal dose rates were identified.
Apparent Violation
One apparent violation was identified for HDIs failure to properly prepare and ship a
package containing radioactive material in a manner that assured, under conditions
normally incident to transport, conformance with DOT radiation level limitations specified
by 49 CFR 173.441, i.e., 200 mrem/h on any external surface of the package.
Inadequate radiological surveys were performed at OC that indicated that the package
conformed with the DOT regulatory requirements. However, when the shipment arrived
at IPEC on May 3, 2023, the maximum radiation dose rate on the external surface of the
package (topside) was measured as 450 mrem/h.
On May 3, 2023, HDI shipped reactor segmentation tooling (a Class B/C waste
alignment plate) to IPEC as Low Specific Activity Category II (i.e., LSA-II) material using
Exclusive Use controls in an open transport vehicle. The segmentation tooling was
packaged in an Industrial Package Type IP-1 package (i.e., a polyethylene bag). The
radiation survey used to verify that the contact dose rates on the loaded package were
under regulatory limits was performed on the packaged tool prior to the package being
strapped down in its final shipping configuration. The April 28, 2023, survey documented
in the shipping package identified a maximum contact dose rate of 120 mrem/h. Upon
receipt, on May 3, 2023, IPECs initial radioactive survey identified a maximum contact
dose rate of 450 mrem/h on top of the package. A confirmatory survey of the package
was performed by IPEC personnel on May 4, 2023, which identified maximum contact
dose rates of 215 and 555 mrem/h at two separate spots on top of the package.
The inspectors noted that the OC procedures did not require that a final shipping survey
be conducted when the package was in its final shipping configuration prior to shipment.
A note in Section 5.3.1 of OC procedure RP-AA-601, Surveying Radioactive Material
Shipments, Revision 21, states: Survey data obtained during package survey(s) may be
used when appropriate for vehicle surveys to reduce re-surveying activities. HDIs
apparent cause evaluation documented that the lack of adequate procedural guidance,
especially for soft-sided packages, as well as a lack of questioning attitude, resulted in a
failure to alert workers of potential geometry changes contributing to this event.
Title 10 CFR 71.5 requires each licensee who transports licensed materials on public
highways to comply with the requirements of the DOT regulations in 49 CFR Parts 170
through 189. Title 49 CFR 173.441 requires that each package of radioactive material
offered for transportation, including those transported by Exclusive Use shipment in an
open transport vehicle, be designed and prepared for shipment so that, under conditions
normally incident to transportation, the radiation level does not exceed 200 mrem/h at
any point on the external surface of the package.
7
Contrary to the above, on May 3, 2023, HDI failed to design and prepare a package of
radioactive material offered for transportation such that, under conditions normally
incident to transportation, the radiation level did not exceed 200 mrem/h at any point on
the external surface of the package. Specifically, the licensee shipped a package
containing radioactive material using Exclusive Use controls in an open transport
vehicle. When the shipment arrived at IPEC, radiation levels of 450 mrem/h were
measured on top of the external surface of the alignment fixture package during the
receipt survey, exceeding the regulatory requirement of 200 mrem/h.
Upon identification, OC documented the condition in issue report OYS-03315; completed
an apparent cause evaluation (ACE-OYS-003315); and identified corrective actions.
These included several procedure revisions to evaluate the potential for soft-sided
package geometry to be changed during the shipping process and to require a
verification shipping survey when the package has been secured to the trailer in its final
configuration prior to transport. Additional corrective actions include a training or briefing
on soft-sided package geometry considerations to be provided to both drivers and staff
associated with shipping activities, as well as distributing a communication to workers
at all HDI sites to strengthen shipping communications. Pending final significance
determination, this violation is identified as an apparent violation, (AV 05000219/2023002-02, Radioactive Material Shipment Package Dose Rate
Exceeded.)
c. Conclusions
One apparent violation was identified that is being considered for escalated
enforcement.
3.0
Exit Meeting
On July 11, 2023, the inspectors presented the inspection results to Jeffrey Dostal,
Site Vice President, and other members of the Oyster Creek staff. No proprietary
information was retained by the inspectors or documented in this report.
ATTACHMENT: SUPPLEMENTAL INFORMATION
Attachment
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Oyster Creek Personnel
J. Dostal, HDI Oyster Creek Site Vice President
S. Johnson, Site Licensing Manager
W. Straka, Project Manager
M. Hassler, Decommissioning Manager
K. Leonard, Waste Controls Manager
J. Sisak, Decommissioning Facility Manager
M. Carlson, Site Engineering Manager
E. OBrian, Environmental Spec/Safety
K. Wolf, Radiation Protection, Chemistry, and Environmental Manager
F. Miranda, Shipping Specialist
K. Zadroga, Radiation Protection, Chemistry Supervisor
ITEMS OPENED, CLOSED, AND DISCUSSED 05000219/2023002-01
Open Item
Continued review of decommissioning trust
fund withdrawals05000219/2023002-02
Radioactive Material Shipment Package Dose Rate
Exceeded
PARTIAL LIST OF DOCUMENTS REVIEWED
Condition Reports
OYS-03315, OYS-03349, OYS-03350, OYS-03351, OYS-03353, OYS-03321,
OYS-03354, OYS-03352, OYS-03355, OYS-03356, OYS-03357, OYS-03358,
OYS-03359, OYS-03360, OYS-03361, OYS-03362, OYS-03364, OYS-03363,
OYS-03365, OYS-03408, OYS-03388, OYS-03389, OYS-03315-04
Miscellaneous
Apparent Cause Evaluation for OYS-03315, Radioactive Shipment to Indian Point Energy
Center (IPEC) found to have radiation measurements on contact with the packages above
the Shipping Limit, June 8, 2023
Shipping Package, OC-23-0208
TQ-DC-105-F020, Trainee Course/Qualification Selection and Course Attendance Sheet,
Revision 7
101.2 R82, LS-DC-128-F-01, Fire Protection Change Regulatory Review, Revision 0
101.2 R82, AD-AA-101-F-01, Document Site Approval Form, Revision 7
OC-2022-EC-0005, LS-AA-104-1001, 50.59 Review, Revision 4
OC-2022-S-0001, LS-AA-104-1003, 50.59 Screening Form, Revision 4
OC-2020-EC-0010, LS-AA-104-1001, 50.59 Review, Revision 4
OC-2023-S-0002, LS-AA-104-1003, 50.59 Screening Form, Revision 4
Revised Post-Shutdown Decommissioning Activities Report
Revised Site-Specific Decommissioning Cost Estimate
2
Procedures
RP-AA-600, Radioactive Material Waste Shipments, Revision 18
RP-AA-601, Surveying Radioactive Material Shipments, Revision 21
RP-AA-602, Packaging of Radioactive Material Shipments, Revision 21
RP-AA-603, Inspection and Loading of Radioactive Material Shipments, Revision 10
ALARA Plan Number 23-905_SFP, RP-AA-401, Micro-ALARA Plan, Revision 26
Radiological Surveys
YLA-23-907
IPEC survey 023-2-2281 and 023-2-2273
RH3-23-541
RH3-23-241
RH3-23-1181
RH3-23-1229
RH3-23-1216
RH3-23-1259
RH3-23-1260
RH3-23-1261
RH3-23-1271
RH3-23-563
RH3-23-365
RH3-23-442
RH3-23-502
RH3-23-249
RH3-23-1282
LIST OF ACRONYMS USED
Agencywide Document Access and Management System
Alternative Dispute Resolution
As Low As Reasonably Achievable
Apparent Violation
Corrective Action Program
CFR
Code of Federal Regulations
U.S. Department of Transportation
Decommissioning Quality Assurance Program
GPO
Government Printing Office
Holtec Decommissioning International, LLC
Institute on Conflict Resolution
IMC
Inspection Manual Chapter
Indian Point Energy Center
LLRWSF
Low Level Rad Waste Storage Facility
NRC
U.S. Nuclear Regulatory Commission
Oyster Creek
Oyster Creek Nuclear Generating Station
Radiologically Controlled Area
Radiation Protection
Radiation Work Permits
Spent Fuel Pool