ML16154A450
| ML16154A450 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/02/2016 |
| From: | Ann Marie Stone NRC/RGN-III |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2016008 | |
| Download: ML16154A450 (17) | |
See also: IR 05000315/2016008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
June 2, 2016
Mr. Joel Gebbie
Senior VP and Chief Nuclear Officer
Indiana Michigan Power Company
Nuclear Generation Group
One Cook Place
Bridgman, MI 49106
SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2
NRC TEMPORARY INSTRUCTION 2515/191, MITIGATION STRATEGIES,
SPENT FUEL POOL INSTRUMENTATION AND EMERGENCY PREPAREDNESS
REPORT 05000315/2016008; 05000316/2016008
Dear Mr. Gebbie:
On May 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed Temporary
Instruction (TI) 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent
Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/staffing/Multi-
Unit Dose Assessment Plans inspection at your Donald C. Cook Nuclear Power Plant, Units 1
and 2. The NRC inspection team discussed the results of this inspection with you and other
members of your staff. The inspection team documented the results of this inspection in the
enclosed inspection report.
The inspection examined activities conducted under your license as they relate to the
implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049
and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose
Assessment Plans, your compliance with the Commissions rules and regulations, and with the
conditions of your operating license. Within these areas, the inspection involved examination of
selected procedures and records, observation of activities, and interviews with station
personnel.
The NRC inspectors did not identify any findings or violations of more than minor significance.
J. Gebbie -2-
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRC Public Document Room or from the Publicly Available Records (PARS)
component of NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
Ann Marie Stone, Team Leader
Technical Support Section
Docket Nos. 50-315; 50-316
Enclosure:
IR 05000315/2016008; 05000316/2016008
cc: Distribution via LISTSERV
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Docket Nos: 05000315; 05000316
Report No: 05000315/2016008; 05000316/2016008
Licensee: Indiana Michigan Power Company
Facility: Donald C. Cook Nuclear Power Plant, Units 1 and 2
Location: Bridgman, MI
Dates: April 25 through May 12, 2016
Inspectors: B. Bartlett, Project Engineer, Region III (Team Lead)
J. Boettcher, Resident Inspector, Palisades
J. Mateychick, Senior Reactor Inspector, Region IV
S. Sheldon, Project Engineer, Region III
J. Havertape, Region III, Reactor Engineer
L. Kozak, Senior Reactor Analyst, Region III (Observer)
M. Humberstone, Senior Reactor Analyst, HQ (Observer)
Approved by: A. Stone, Team Leader
Technical Support Section
Enclosure
SUMMARY
Inspection Report (IR) 05000315/2016008, 05000316/2016008; 04/25/2016 - 04/29/2016;
Donald C. Cook Nuclear Power Plant, Units 1 and 2: Temporary Instruction 2515/191
Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and
Emergency Preparedness Communication/staffing/Multi-Unit Dose Assessment Plans.
This inspection was performed by three NRC regional inspectors and one resident inspector.
No findings of significance or violations of NRC requirements were identified during this
inspection. The NRC's program for overseeing the safe operation of commercial nuclear power
reactors is described in NUREG-1649, "Reactor Oversight Process," dated February 2014.
NRC-Identified and Self-Revealing Findings
None
Licensee-Identified Violations
None
2
REPORT DETAILS
4. OTHER ACTIVITIES
4OA5 Other Activities (TI 2515/191)
The objective of Temporary Instruction (TI) 2515/191, Inspection of the Implementation
of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency
Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, is to verify
that licensees have adequately implemented the mitigation strategies as described in the
licensees Final Integrated Plan Revision 0 (ADAMS Accession No. ML15169A106) and
Revision 1 (ADAMS ML15280A023) and the NRCs plant safety evaluation (ADAMS
ML15264A851) and to verify that the licensees installed reliable water-level
measurement instrumentation in their spent fuel pools. The purpose of this TI was also
to verify the licensees had implemented Emergency Preparedness (EP) enhancements
as described in their site-specific submittals and NRC safety assessments, including
multi-unit dose assessment capability and enhancements to ensure that staffing is
sufficient and communications can be maintained during such an event.
The inspection verified that plans for complying with NRC Orders EA-12-049, Order
Modifying Licenses with Regard to Requirements for Mitigation Strategies for
Beyond-Design-Basis External Events (ADAMS Accession No. ML12229A174) and
EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool
Instrumentation (ADAMS Accession No. ML12056A044) are in place and are being
implemented by the licensee. Additionally, the inspection verified implementation of
staffing and communications information provided in response to the March 12, 2012,
request for information letter and multiunit dose assessment information provided per
COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency
Preparedness for Japan Lessons Learned, dated March 27, 2013, (ADAMS Accession
No. ML12339A262).
The team discussed the plans and strategies with plant staff, reviewed documentation,
and where appropriate, performed plant walk downs to verify that the strategies could be
implemented as stated in the licensees submittals and the NRC staff prepared safety
evaluation. For most strategies, this included verification that the strategy was feasible,
procedures and/or guidance had been developed, training had been provided to plant
staff, and required equipment had been identified and staged. Specific details of the
teams inspection activities are described in the following sections.
1. Mitigation Strategies for Beyond-Design Basis External Events
a. Inspection Scope
The team examined the licensees established guidelines and implementing procedures
for the beyond-design basis mitigation strategies. The team assessed how the licensee
coordinated and documented the interface/transition between existing off-normal and
emergency operating procedures with the newly developed mitigation strategies. The
team selected a number of mitigation strategies and conducted plant walk downs with
licensed operators and responsible plant staff to assess: the adequacy and
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completeness of the procedures; familiarity of operators with the procedure objectives
and specific guidance; staging and compatibility of equipment; and the practicality of the
operator actions prescribed by the procedures, consistent with the postulated scenarios.
The team verified that a preventive maintenance program had been established for the
Diverse and Flexible Coping Strategies (FLEX) portable equipment and that periodic
equipment inventories were in place and being conducted. Additionally, the team
examined the introductory and planned periodic/refresher training provided to the
Operations staff most likely to be tasked with implementation of the FLEX mitigation
strategies. The team also reviewed the introductory and planned periodic training
provided to the Emergency Response Organization personnel. Documents reviewed are
listed in the attachment.
b. Assessment
Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the FLEX strategy as described in the
plant specific submittal(s) and the associated safety evaluation and determined that the
licensee is generally in compliance with NRC Order EA-12-049. The inspectors verified
that the licensee satisfactorily:
strategies for postulated external events;
- integrated their FSGs into their existing plant procedures such that entry into and
departure from the FSGs were clear when using existing plant procedures;
- protected FLEX equipment from site-specific hazards;
- developed and implemented adequate testing and maintenance of FLEX equipment
to ensure their availability and capability;
- trained their staff to assure personnel proficiency in the mitigation of
beyond-design basis events; and
- developed the means to ensure that the necessary off-site FLEX equipment would
be available from off-site locations.
The inspectors verified that non-compliances with current licensing requirements, and
other issues identified during the inspection were entered into the licensee's corrective
action program as appropriate.
c. Findings
No findings were identified.
2. Spent Fuel Pool Instrumentation
a. Inspection Scope
The team examined the licensees newly installed spent fuel pool instrumentation.
Specifically, the inspectors verified the sensors were installed as described in the plant
specific submittals and the associated safety evaluation and that the cabling for the
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power supplies and the indications for each channel are physically and electrically
separated. Additionally, environmental conditions and accessibility of the instruments
were evaluated. Documents reviewed are listed in the attachment.
b. Assessment
Based on samples selected for review, the inspectors determined that the licensee
satisfactorily installed and established control of the spent fuel pool (SFP)
instrumentation as described in the plant specific submittal(s) and the associated safety
evaluation and determined that the licensee is generally in compliance with NRC Order
EA-12-051. The inspectors verified that the licensee satisfactorily:
- installed the SFP instrumentation sensors, cabling and power supplies to provide
physical and electrical separation as described in the plant specific submittal(s) and
safety evaluation;
- installed the SFP instrumentation display in the location, environmental conditions
and accessibility as described in the plant specific submittal(s); and
- trained their staff to assure personnel proficiency with the maintenance, testing, and
use of the SFP instrumentation.
The inspectors verified that non-compliances with current licensing requirements, and
other issues identified during the inspection were entered into the licensee's corrective
action program.
c. Findings
No findings were identified.
3. Staffing and Communication Request for Information
a. Inspection Scope
Through discussions with plant staff, review of documentation and plant walk downs,
the team verified that the licensee has implemented required changes to staffing,
communications equipment and facilities to support a multi-unit extended loss of offsite
power (ELAP) scenario as described in the licensees staffing assessment and the NRC
safety assessment. The team also verified that the licensee has implemented multi-unit
dose assessment (including releases from spent fuel pools) capability using the
licensees site-specific dose assessment software and approach as described in the
licensees multi-unit dose assessment submittal. Documents reviewed are listed in the
attachment.
b. Assessment
The inspectors reviewed information provided in the licensees multi-unit dose submittal
and in response to the NRCs March 12, 2012, request for information letter and verified
that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task
Force Recommendation 9.3 response to a large scale natural emergency event that
results in an extended loss of all AC power to all site units and impedes access to the
site. The inspectors verified the following:
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- licensee satisfactorily implemented required staffing change(s) to support a multi-unit
ELAP scenario;
- EP communications equipment and facilities are sufficient for dealing with a
multi-unit ELAP scenario; and
- implemented multi-unit dose assessment capabilities (including releases from spent
fuel pools) using the licensees site-specific dose assessment software and
approach.
The inspectors verified that non-compliances with current licensing requirements, and
other issues identified during the inspection were entered into the licensee's corrective
action program.
4OA6 Management Meeting
.1 Exit Meeting Summary
On May 12, 2016, the inspectors presented the inspection results to Mr. J. Anderson of
the licensees staff. The licensee acknowledged the issues presented. The inspectors
confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT: SUPPLEMENTAL INFORMATION
6
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
J. Gebbie, Chief Nuclear Officer
S. Lies, Site Vice-President
M. Scarpello, Regulatory Assurance Manager
R. Wynegar, Regulatory Assurance
S. Mitchell, Regulatory Assurance Supervisor
V. Gupta, Performance Improvement Supervisor
J. Ross, Plant Manager
L. Baun, PA Director
K. Simpson, EP Supervisor
S. Wiederwax, EP
D. Etheridge, Ops
R. Strasser, Severe Accident Management Team (SAMT)
D. Burris, SAMT
L. Bush, SAMT
J. Anderson, SAMT
B. Lewis, Ops
J. Cross, Maintenance
U.S. Nuclear Regulatory Commission
J. Cameron, Branch Chief, Reactor Projects Branch 4
T. Brown, Branch Chief, Japan Lessons Learned Division
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None
Attachment
LIST OF DOCUMENTS REVIEWED
The following is a list of documents reviewed during the inspection. Inclusion on this list
does not imply that the NRC inspectors reviewed the documents in their entirety, but
rather, that selected sections of portions of the documents were evaluated as part of the
overall inspection effort. Inclusion of a document on this list does not imply NRC
acceptance of the document or any part of it, unless this is stated in the body of the
inspection report.
Procedures
1-OHP-4021-082-036; Removal and Restoration of Power to 250V DC Distribution
Cabinet 1-DBOP; Revision 2
1-OHP-4022-001-007; Earthquake; Revision 21
12-OHP-4022-001-010; Severe Weather; Revision 17
1-OHP-4025-LS-3; Steam Generator 2/3 Level Control; Revision 5
1-OHP-4023-E-0; Reactor Trip or Safety Injection; Revision 39
1-OHP-4023-ECA-0.0; Loss of All AC Power; Revision 34
1-OHP-4027-FSG-1; Long Term RCS Inventory Control; Revision 2
1-OHP-4027-FSG-2; Alternate AFW Suction Source; Revision 1
1-OHP-4027-FSG-3; Alternative Low Pressure Feedwater; Revision 2
1-OHP-4027-FSG-4; ELAP Power Management; Revision 3
1-OHP-4027-FSG-5; Initial Assessment and FLEX Equipment Staging; Revision 2
1-OHP-4027-FSG-6; Alternate CST Makeup; Revision 1
1-OHP-4027-FSG-7; Loss of Vital Instrument or Control Power; Revision 2
1-OHP-4027-FSG-8; Alternate RCS Boration; Revision 2
1-OHP-4027-FSG-9; Low Decay Heat Temperature Control; Revision 1
1-OHP-4027-FSG-10; Passive RCS Injection Isolation; Revision 1
1-OHP-4027-FSG-14; Shutdown RCS Makeup; Revision 2
1-OHP-4027-FSG-201; Alternate AFW Suction Source Equipment Deployment;
Revision 3
1-OHP-4027-FSG-301; Alternative Low Pressure Feedwater Equipment Deployment;
Revision 2
1-OHP-4027-FSG-401; ELAP Power Management Equipment Deployment;
Revision 2
1-OHP-4027-FSG-601; Alternate CST Makeup Equipment Deployment; Revision 1
1-OHP-4027-FSG-801; RCS Boration/Makeup Equipment Deployment; Revision 1
1-OHP-4027-FSG-1401; Shutdown RCS Makeup Equipment Deployment; Revision 2
2-OHP-4023-ECA-0.0; Loss of All AC Power; Revision 34
2-OHP-4027-FSG-1; Long Term RCS Inventory Control; Revision 1
2-OHP-4027-FSG-2; Alternate AFW Suction Source; Revision 2
2-OHP-4027-FSG-3; Alternate Low Pressure Feedwater; Revision 2
2-OHP-4027-FSG-4; ELAP Power Management; Revision 3
2-OHP-4027-FSG-5; Initial Assessment and FLEX Equipment Staging; Revision 1
2-OHP-4027-FSG-6; Alternate CST Makeup; Revision 1
2-OHP-4027-FSG-7; Loss of Vital Instrument or Control Power; Revision 1
2-OHP-4027-FSG-8; Alternate RCS Boration; Revision 1
2-OHP-4027-FSG-9; Low Decay Heat Temperature Control; Revision 1
2-OHP-4027-FSG-10; Passive RCS Injection Isolation; Revision 1
2-OHP-4027-FSG-14; Shutdown RCS Makeup; Revision 1
2
2-OHP-4027-FSG-201; Alternate AFW Suction Source Equipment Deployment;
Revision 1
2-OHP-4027-FSG-201; Alternate AFW Suction Source Equipment Deployment;
Revision 2
2-OHP-4027-FSG-301; Alternative Low Pressure Feedwater Equipment Deployment;
Revision 1
2-OHP-4027-FSG-401; ELAP Power Management Equipment Deployment; Revision 2
2-OHP-4027-FSG-601; Alternate CST Makeup Equipment Deployment; Revision 0
2-OHP-4027-FSG-801; RCS Boration/Makeup Equipment Deployment; Revision 2
2-OHP-4027-FSG-1401; Shutdown RCS Makeup Equipment Deployment; Revision 1
12-OHP-4022-018-001; Loss of Spent Fuel Pit Cooling; Revision 22
12-OHP-4027-FSG-2BD; Alternate AFW Suction Source; Revision 0
12-OHP-4027-FSG-11; Alternate SFP Makeup and Cooling; Revision 3
12-OHP-4027-FSG-311; FLEX Lift Pump Operation; Revision 1
12-OHP-4027-FSG-312; FLEX Booster Pump Operation; Revision 2
12-OHP-4027-FSG-412; FLEX 250/350 KW DG Operation; Revision 0
12-OHP-4027-FSG-501; FLEX Equipment Staging; Revision 3
12-OHP-4027-FSG-501; FLEX Equipment Staging; Revision 4
12-OHP-4027-FSG-511; FLEX Equipment Refueling Operation; Revision1
12-OHP-4027-FSG-811; FLEX Boric Acid Pump Operation; Revision 0
12-OHP-4027-FSG-1101; Alternate SFP Makeup Equipment Deployment; Revision 2
12-OHP-5030-FSG-322; FLEX Booster Pump Functional Test; Revision 1
12-OHP-5030-FSG-523; FLEX Equipment Inventory and Checks; Revision 7
12-IHP-6030-018-001; Spent Fuel Pool Level Indication Diagnostic Checks;
Revision 1
12-EHP-5040-MOD-009; Engineering Change Reference Guide; Revision 58
OHI-4023, Abnormal/Emergency Procedure Users Guide, Revision 37
PMP-4027-FSG-001; FSG Maintenance; Revision 4
PMP-4027-FSG-002; FLEX Equipment Program; Revision 4
PMP-4027-FSG-003; FLEX Program; Revision 2
RMA-4027-FSG-004; Final Integrated Plan Management; Revision 0
PMI-4023; DC Cook Nuclear Plant Accident Procedure Program; Revision 5
PMI-5030; Preventive Maintenance; Revision 15
MMDG.401; In-Storage preventive Maintenance Instruction PUMPS; Revision 2
PMID 00126927-03; Booster Pump Capability Test; No date
PMP-4100-SDR-001, Plant Shutdown Safety and Risk Management, Revision 39
PMP-4027-FSG-003, FLEX Program; Revision 2
OHI-4000; Conduct of Operations: Standards; Revision 103
TPD-600-FLEX, FLEX Training Program Description; Revision 2
PMP-2080-EPP-100; Emergency Response; Revision 33
RMT-2080-EOF-002, Emergency Termination and Recovery; Revision 6
RMT-2080-EOF-001; Activation and Operation of the EOF; Revision 34
RO-C-EOP15; FLEX Response; Revision 0
SAFER Response Plan for Donald C. Cook Nuclear Plant; Revision 3
SPP-2060-SFI-308; Tests of Security Related Equipment; Revision 3
Action Requests - NRC Identified
GT 2016-5194; FSG-401 Attachment 3 Title Error; 04/25/16
AR 2016-5222; FLEX Support Guide; Add Overall Map and Deployment Path; 04/25/16
AR 2016-5280; Copy of FSG-511 Located at ISFSI Fuel Mule Not Current; 04/26/16
3
AR 2016-5281; DC Deep Load Shed Breakers are Inconsistently Labeled; 04/26/16
AR 2016-5287; Tracking of CAT Loaders While they are in Use; 04/26/16
AR 2016-5288; Assess if Recovery Procedure EOF-002 Can be Improved; 04/26/16
AR 2016-5290; Procedure 1-OHP-4027-FSG-201, Figure 3, Depicts a Hose Storage
Location Incorrectly; 04/26/16
AR 2016-5291; Mismatch Between Procedure and Breaker Label; 04/26/16
AR 2016-5292; Procedure 2-OHP-4027-FSG-201, Figure 3, Depicts a Hose Storage
Location Incorrectly; 04/26/16
AR 2016-5293; FLEX Storage Box Stored too Near to TDAFWP Piping; 04/26/16
AR 2016-5317; Add direction to FSG-311 to Provide Strainer Backwash Direction;
04/27/16
AR 2016-5334; Error in FLEX Equipment Staging Procedure on Alternate Power
Source; 04/27/16
AR 2016-5339; Assess the Deep Load Shed Procedure to see if Operating Crews can
be Given Additional Time for Decision Making; 04/27/16
AR 2016-5340; Procedures 1(2)-OHP-4027-FSG-6; Alternative CST Makeup; does
not include use of the CST Crosstie Valve, 04/27/16
AR 2016-5343; Add Labeling for FLEX to Several Hose Reels; 04/27/16
AR 2016-5344; ECA 0.0 Takes the Time to Strip Loads off of Buses that are not
Required; 04/27/16
AR 2016-5356; Improve the Usability and Efficiency of Various Strategy Options;
04/27/16
AR 2016-5397; Evaluate if Establishing Temperature Checks in the FLEX Storage
Building is Appropriate; 04/28/16
AR 2016-5398; Prioritization of Hydrogen Ignitor Energization Enhancement; 04/28/16
AR 2016-5374; A Non-installed Valve was Incorporated into 1-OHP-4027-FSG-2;
04/28/16
ARs reviewed
AR 2014-14395; Flood Hazard Reevaluation; 11/12/14
AR 2014-14592; BAST Will Not Meet 2X Seismic Re-evaluation; 11/12/14
AR 2015-2319; Spent Fuel Pool Level Indication Power Quality; 02/17/15
AR 2015-3609; Spent Fuel Pool Level Indication(a)(1) Monitoring; 03/18/15
AR 2015-6904; Spent Fuel Pool Level Indication Digital Display Not Functioning;
05/20/15
AR 2015-8090; Reduce FLEX Equipment Pre-Staging; 06/17/15
AR 2015-14002; TRM 8/11/2 Entry Missed for FLEX Equipment Connection; 10/28/15
AR 2015-9532; Improve the Vent Path Size for Shutdown RCS Makeup; 07/21/15
AR 2015-9534; The FLEX Procedures Contain Core Cycle Specific Boron
Concentration Values; 07/21/15
GT 2015-9535; Adverse Containment Values Associated with FSGs; 07/21/15
GT 2015-9536; Revise Procedure Direction Regarding TDAFWP Control; 07/21/16
AR 2015-9649; Fish Trap Cleaning Changed from a 2Y to a 1Y; 7/24/2015
AR 2016-4140; Add Guidance on TDAFP Suction Supply Pressure; 04/06/16
AR 2016-4570; TRM Change Presented to PORC was Inconsistent with OE; 04/13/16
GT 2014-10503; PMCR - FLEX Boric Acid Pump; 09/07/14
GT 2015-4988; PMCR - FLEX Blended RCS Makeup Pumps; 04/08/15
GT 2014-10502; PMCR - FLEX Booster Pump; 09/07/14
GT 2014-12877; PMCR - FLEX Lift Pumps; 10/18/14
GT 2014-9664; PMCR - FLEX Diesel Generators; 08/17/14
4
GT-2013-4702-54; Track Updating CNPs Drill and Exercise Schedule After INPO 88-019 is Revised and Issued
GT-2013-4702-55; Implement the FLEX Drill Demonstration Objectives
GT-2016-1728; GT to Perform Impact Review of NEI 12-06 Rev 2; 02/12/16
FLEX Training Documents
FX-C-00; FLEX Overview; Revision 3
FX-C-OP00; Loss of AC Power-FLEX Strategies; Revision 0
FX-C-OP01; Core Cooling - SG Feedwater Supply; Revision 3
FX-C-OP03; RCS Makeup; Revision 2
FX-C-OP05; Spent Fuel Cooling; Revision 4
FX-C-OP06; Long Term Core and Containment; Revision 3
FX-C-OP07; FLEX Modes 5 and 6; Revision 5
FX-I-002; FLEX Equipment; Revision 1
FX-I-003; FLEX Update; Revision 0
FX-I-005; Unit 2 FLEX Implementation; Revision 0
Calculations reviewed
MD-12-CST-001-N; Condensate Storage Tank Usable Volume and Vortexing
Calculation; Revision 1
MD-12-FLEX-002-S; DC Cook FLEX Core Cooling and SFP Makeup Hydraulic
Analysis; Revision 1
Calculation 13Q3208-CAL-001; Seismic Hazard and Expedited Seismic Evaluation
Process Seismic Services For DC Cook Nuclear Plant; Revision 0
Calculation 13Q3208-CAL-003; DC Cook FLEX Haul Path Soil Liquefaction Triggering
Evaluation; Revision 1
Drawings reviewed
OP-12-5148A-27; Flow diagram auxiliary building ventilation; Revision 27
OP-1-5106A-61; Flow diagram auxiliary feedwater; Revision 61
OP-1-5113-100; Flow diagram essential service water; Revision 100
OP-1-5106A-61; Aux Feedwater; Revision 61
OP-2-5106A-56; Aux Feedwater; Revision 56
OP-12-98315; Spent Fuel System Control Elementary Diagram; Revision 15
1-5220-2; U1 FLEX Portable Equipment; Revision 2
Modifications
EC 0000053227; Radio Communications Systems Upgrades; Revision 0
EC 0000052892; Spent Fuel Pool Level for NRC Order EA-12-051; Revision 0
EC 53165; Unit 1 FLEX Generator to 600V MCC ABD-B for N-Train Charger (1-EL-03);
Revision 0
Work Orders
55465872-01; MTRI, 1-RLI-502-CRI, Replace Unit; 06/09/15
1-0410-15; SFPI Installation Checklist; 08/26/14
55462958-01; Large FLEX Diesel Driven Booster Pump Functional Test; 09/25/15
5
55455157-01; Booster Pump Capability Test; Model WO 55431240-04; 2-EL-01 FLEX Generator Phase Checks; 03/17/15
55431244-20; 2-EL-03 FLEX Generator Phase Checks; 02/16/15
55432175-14; Perform Phase Rotation Accumulator Tank #4 Outlet Valve; 04/08/15
55432175-15; Perform Phase Rotation Accumulator Tank #2 Outlet Valve; 04/08/15
55432175-16; Perform Phase Rotation Accumulator Tank #1 Outlet Valve; 04/08/15
55432175-17; Perform Phase Rotation Accumulator Tank #3 Outlet Valve; 04/08/15
55432305-04; Perform (Bump) Rotation for Both BA Pump/Motors; 09/19/14
55437624-05; Perform Phase Rotation Check of 1-11D2; 09/28/14
55437627-44; Perform Run In on 5 Flex Diesel Generators and Document Phase
Rotation; 06/30/14
55437627-58; Perform Load Testing on 5 Flex Diesel Generators and Document
Loading Characteristics; 09/18/14
55437627-69; 480/600VAC Step up XFMR Testing; 10/12/14
55437696-17; Perform Phase Rotation Test at 1-EZC-A-5C; 10/14/14
55437696-18; Perform Phase Rotation Test at 1-EZC-B-1C; 10/14/14
55437696-19; Perform Phase Rotation Test at 1-EZC-C-5C; 10/14/14
55437696-20; Perform Phase Rotation Test at 1-EZC-D-1C; 10/14/14
55263614-04; Install Winterization: (Non-Power Block)
Miscellaneous Documents
GT-2016-0604-6; FLEX TSA Validation Documentation - Validation Item Results
Letter AEP-NRC-2013-13; Donald C. Cook Nuclear Plant Unit I and Unit 2 Overall
Integrated Plan In Response to March 12, 2012, Commission Order Modifying Licenses
with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External
Events (Order Number EA-12-049); Dated February 27, 2013
Letter AEP-NRC-2015-22; Donald C. Cook Nuclear Plant Units 1 and 2
Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for
Beyond-Design-Basis External Events (Order Number EA-12-049); Dated
June 16, 2015
Letter AEP-NRC-2015-83; Donald C. Cook Nuclear Plant Units 1 and 2 Revision 1 of
Final Integrated Plan Regarding March 12, 2012, U.S. Nuclear Regulatory Commission
Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order
Number EA-12-049); Dated October 1, 2015
Letter AEP-NRC-2015-107; Donald C. Cook Nuclear Plant Units 1 and 2 Corrected
Values in Final Integrated Plan for Mitigation Strategies for Beyond-Design-Basis
External Events and Spent Fuel Pool Level Indication Status Report; Dated
November 6, 2015
12-OHP-4027-FSG-2BD; Plant Specific Background Document, Alternate AFW
Suction Source; Revision 0
IC-C-F001; Flex Spent Fuel Pool Instrumentation Training Module; Revision 0
RQ-C-3863; Licensed Operator Requalification Training Module; Revision 0
RO-C-01800; Spent Fuel Pit Cooling and Cleanup Training Module; Revision 8
6
EPRI FLEX Data Report 004; FLEX - Pump - Horizontal - Mechanical Seal Non-Oil Bath
Tier 3 Diesel Driven; Revision 0
EPRI FLEX Data Report 009; FLEX - Generator - 750KW or Less - T3 EGR Diesel
Driven; No Revision
Letter to the NRC from Joel P. Gebbie; Donald C. Cook Nuclear Plant Units 1 and 2
Phase 2 On-Shift Staffing Assessment Report Requested by the U. S. Nuclear
Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code
of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the
Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated
March 12, 2012; Dated May 23, 2014
Letter to the NRC from Joel P. Gebbie; Donald C. Cook Nuclear Plant Units 1 and 2
Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for
Beyond-Design-Basis External Events (Order Number EA-12-049); Dated
June 16, 2015
Letter to the NRC from Joel P. Gebbie; Donald C. Cook Nuclear Plant Units 1 and 2
Revision 1 of Final Integrated Plan Regarding March 12, 2012, U. S. Nuclear Regulatory
Commission Order Regarding Mitigation Strategies for Beyond-Design-Basis External
Events (Order Number EA-12-049); Dated October 1, 2015
Letter to Senior Vice President and Chief Nuclear Officer at Indiana Michigan Power
Company Nuclear Generation Group from Thomas J. Wengert, NRC/NRR; Donald C.
Cook Nuclear Plant, Units 1 and 2 - Staff Assessment in Response to Recommendation
9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant
Accident (TAC Nos. ME9950 and ME9951); Dated June 6, 2013
Letter to Senior Vice President and Chief Nuclear Officer at Indiana Michigan Power
Company Nuclear Generation Group from Mandy Halter, NRC/NRR; Donald C. Cook
Nuclear Plant, Units 1 and 2 - Safety Evaluation Regarding Implementation of Mitigating
Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and
EA-12-051 (TAC Nos. MF0766, MF0767, MF0761, and MF0762); Dated
November 9, 2015
DIT-B-00197-25; Main Steam Stop Enclosure Area Temperature
FX-C-OP06; Long Term Core and Containment Cooling; Revision 3
MD-12-FLEX-002-S; DC Cook FLEX Core Cooling and SFP Makeup Hydraulic
Analysis; Revision 1
7
LIST OF ACRONYMS USED
ADAMS Agencywide Documents Access Management System
AR Action Request
CAP Corrective Action Program
CFR Code of Federal Regulations
IMC Inspection Manual Chapter
IR Inspection Report
NRC U.S. Nuclear Regulatory Commission
OE Operating Experience
PARS Publicly Available Records System
PI&R Problem Identification and Resolution
QHSA Quick Hit Self-Assessment
SDP Significance Determination Process
WO Work Order
8
J. Gebbie -2-
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRC Public Document Room or from the Publicly Available Records (PARS)
component of NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
Ann Marie Stone, Team Leader
Technical Support Section
Docket Nos. 50-315; 50-316
Enclosure:
IR 05000315/2016008; 05000316/2016008
cc: Distribution via LISTSERV
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ADAMS Accession Number: ML16154A450
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
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DATE 05/31/16 06/02/16 06/02/16
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