IR 05000341/2021001

Integrated Inspection Report 05000341/2021001

ML21124A128
Person / Time
Site:	Fermi
Issue date:	05/04/2021
From:	Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4
To:	Peter Dietrich DTE Electric Company
References
IR 2021001
Download: ML21124A128 (18)

Text

May 4, 2021

SUBJECT:

FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2021001

Dear Mr. Dietrich:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi 2. On April 27, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Fermi 2.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Fermi 2. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Néstor J. Féliz Adorno, Chief Branch 4 Division of Reactor Projects

Docket No. 05000341 License No. NPF-43

Enclosure:

As stated

Inspection Report

Docket Number:

05000341

License Number:

NPF-43

Report Number:

05000341/2021001

Licensee:

DTE Electric Company

Facility:

Fermi 2

Location:

Newport, MI

Inspection Dates:

January 01, 2021 to March 31, 2021

Inspectors:

T. Briley, Senior Resident Inspector

T. Taylor, Resident Inspector

Approved By:

Néstor J. Féliz Adorno, Chief

Branch 4

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Fermi 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Improper Storage of Nitrogen Bottles in the Reactor Building Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2021001-01 Open/Closed

[H.12] - Avoid Complacency 71111.15 The inspectors identified a finding of very low safety significance (Green) with an associated NCV of Technical Specifications (TS) 5.4.1, "Procedures," for the improper storage of material in the reactor building. Specifically, on multiple occasions the inspectors discovered carts of compressed gas cylinders near safety-related equipment that were not restrained in accordance with plant procedures. Examples included missing chocks, inappropriate standoff distance, storage of equipment not in accordance with existing engineering analyses, and exceeding restraint weight limits.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000341/2020-002-00 LER 2020-002-00 for Fermi 2, Valid Actuation of Emergency Diesel Generators During Partial Loss of Offsite Power.

71153 Closed

PLANT STATUS

Unit 2 began the inspection period at rated thermal power. On March 5, 2021, the unit was down powered to 62 percent rated thermal power for planned maintenance and control rod pattern adjustment. The unit was returned to rated thermal power the following day. The unit remained at or near rated thermal power for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-19),resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Division 2 residual heat removal (RHR) while Division 1 RHR and RHR service water was out of service for maintenance during the week ending January 16, 2021

(2) Division 1 control complex heating ventilation and air conditioning (CCHVAC) while Division 2 CCHVAC was out of service for maintenance during the week ending January 30, 2021

(3) Division 1 emergency diesel generators (EDG) 13 and 14 while Division 1 mechanical draft cooling tower was out of service for maintenance during the week ending February 13, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Radwaste building, second floor and mezzanine, balance of plant switchgear room on January 22, 2021

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Partial)

The inspectors evaluated readiness and performance of:

(1)

(Partial)

P4400B001A heat exchanger on Division 1 emergency equipment cooling water (EECW)

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during power maneuvers for a planned down power on March 5, 2021

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a licensed operator requalification graded scenario in the control room simulator on March 10, 2021

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Partial)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1)

(Partial)

Spent fuel pool level instrumentation

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Emergent work and preparations for alternate diesel fire pump installation due to diesel fire pump blow-by test failure, fire water suppression system jockey pump pressure regulator repair, and combustion turbine generator (CTG) 11-1 ground indication troubleshooting during the week ending January 30, 2021

(2) Emergent work on EDG 12 fuel rack abnormal position, visual annunciator system power supply low voltage, and planned high pressure coolant injection (HPCI) system maintenance during the week ending February 20, 2021

(3) Planned maintenance on CTG system (CTGs 11-1, 11-2, 11-3, and 11-4 out of service) and emergent work on west gland seal exhauster following abnormal operation during the week ending March 6, 2021

(4) Condensate storage tank vortex suppressor installation during the week ending March 27, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Operability and functionality of Division 1 64B and 64C 4160-volt safety bus degraded voltage relays following identification of a design calculation error, as documented in condition assessment resolution document (CARD) 21-20658

(2) Operability and functionality of the diesel fire pump following failed blow-by test, as documented in CARD 21-20687

(3) Operability and functionality of hydraulic control units and Division 2 safety-related instrumentation due to improper storage of nitrogen bottle carts, as documented in CARDs 21-21373 and 21-21805

(4) Operability and functionality of CTG 11-1 following low lubricating oil temperature, as documented in CARD 21-22139

(5) Operability and functionality of Division 1 EECW due to temperature control valve controller abnormal operation and trip of Division 1 CCHVAC, as documented in CARD 21-21951

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Main steam line 'A' and 'C' low reactor steam dome pressure setpoint change (permanent)

(2) Installation of alternate diesel fire pump (temporary)

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) Division 1 non-interruptible air system testing following air dryer relay replacement during the week ending January 16, 2021

(2) Agastat time-delay relay calibration prior to replacement in HPCI valve control circuit during the week ending January 9, 2021

(3) Division 2 CCHVAC testing following system maintenance during the week ending January 30, 2021

(4) Division 1 EECW make-up water tank outlet isolation motor operated valve testing and diagnostics following preventative maintenance during the week ending March 27, 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Division 1 nuclear steam supply shutoff system (NSSSS) reactor low water level 1 and 2 channel functional testing during the week ending January 16, 2021

(2) Review of change in surveillance frequency for procedure 44.030.254, "ECCS-Reactor Vessel Water Level (Levels 1, 2, and 8), Division 2, Channel D Functional Test" during the week ending March 27, 2021

Inservice Testing (IP Section 03.01) (2 Samples)

(1) Standby liquid control pump and valve testing during the week ending January 16, 2021

(2) Reactor core isolation cooling system pump and valve testing during the week ending February 6, 2021

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) Emergency preparedness tabletop drill on February 4,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01)===

(1) Unit 2 (January 1, 2020 - December 31, 2020)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (1 Sample)

(1) Unit 2 (January 1, 2020 - December 31, 2020)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 03.03) (1 Sample)

(1) Unit 2 (January 1, 2020 - December 31, 2020)

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04) (1 Sample)

(1) Unit 2 (January 1, 2020 - December 31, 2020)

===71153 - Follow-up of Events and Notices of Enforcement Discretion

Event Report (IP Section 03.02)===

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 2020-002, "Valid Actuation of Emergency Diesel Generators During Partial Loss of Offsite Power" (ADAMS Accession No. ML20244A365). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.

INSPECTION RESULTS

Improper Storage of Nitrogen Bottles in the Reactor Building Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems

Green NCV 05000341/2021001-01 Open/Closed

[H.12] - Avoid Complacency 71111.15 The inspectors identified a finding of very low safety significance (Green) with an associated NCV of TS 5.4.1, "Procedures," for the improper storage of material in the reactor building.

Specifically, on multiple occasions the inspectors discovered carts of compressed gas cylinders near safety-related equipment that were not restrained in accordance with plant procedures. Examples included missing chocks, inappropriate standoff distance, storage of equipment not in accordance with existing engineering analyses, and exceeding restraint weight limits.

Description:

On February 12, 2021, the inspectors identified a cart containing 12 nitrogen gas bottles that was not restrained in accordance with plant procedures to reasonably ensure it would not adversely impact nearby safety-related equipment during a seismic event. During operation, the nitrogen is used to periodically recharge the hydraulic control units (HCUs), which helps position or scram the control rods and contain safety-related components. The cart was stored adjacent to an opening leading down to one of the reactor building corner rooms.

Several safety-related instruments associated with the RHR system and reactor recirculation system were directly below this opening. This cart was at a location that was not one of two engineering-approved locations for the storage of nitrogen carts. In addition, it was not restrained in accordance with procedure MOP23, "Plant Storage," Revision 6. Specifically, the cart did not have a required wheel chock and was tied off to a handrail that the procedure stated was acceptable for up to 400 pounds when the cart weight was 2,600 pounds. The inspectors notified the licensee, who then moved the cart away from the floor opening.

In the following days, the inspectors identified additional nitrogen carts improperly stored adjacent to the HCUs. The carts were missing the required number of chocks and staged too close to the HCUs given their width and height per the requirements contained in MOP23.

One of the extra nitrogen carts was subsequently moved and attached to a concrete wall nearby pending removal from the building. However, a few days later the inspectors identified that the cart was missing one of the required restraints for that temporarily approved storage location. The licensee subsequently discovered that one of the two normal staging locations for the HCUs had been previously moved without engineering approval as required by MOP23.

Corrective Actions: The permanently approved location that had been moved was analyzed by the licensee for the new location and found to be acceptable. All nitrogen carts located outside of the permanently approved locations were removed from the reactor building. The licensee also performed several walkdowns of the reactor building to eliminate any remaining storage concerns with other equipment. Additionally, the licensee initiated a common-cause analysis to further review the issue.

Corrective Action References: CARDs 21-21805, 21-21373, and 21-22200

Performance Assessment:

Performance Deficiency: The inspectors determined that the licensees failure to properly restrain nitrogen carts stored in the reactor building was contrary to licensee procedure MOP23, "Plant Storage," Revision 6, and was a performance deficiency. Examples included missing chocks, inappropriate standoff distance, storage of equipment not in accordance with existing engineering analyses, and exceeding restraint weight limits.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to properly restrain nitrogen carts stored in the reactor building led to reasonable doubt regarding the operability of nearby safety-related components.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined the finding was of very low safety significance (Green) based on answering 'no' to all the questions in Section A of Exhibit 2. Specifically, the licensee performed engineering evaluations and reasonably determined the operability/functionality of equipment would be maintained under worst-case seismic conditions.

Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the licensee made assumptions regarding the acceptability of the storage of nitrogen carts in the reactor building. Further, the licensee did not recognize and plan for the possibility of additional storage issues as evidenced by the additional issues identified by the inspectors after their initial notification of the issue to the licensee.

Enforcement:

Violation: TS 5.4.1, "Procedures," requires, in part, that written procedures shall be established, implemented. and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.

Contrary to the above, since at least February 12 to February 26, 2021, the licensee failed to implement a procedure recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Specifically, Section 9 of Regulatory Guide 1.33 states, in part, that maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. The licensee established procedure MOP23, "Plant Storage," Revision 6, to implement storage and staging requirements of equipment during, in part, maintenance activities that could affect the performance of safety-related equipment. However, the licensee did not implement MOP23 when preplanning and performing maintenance activities involving compressed gas cylinders as evidenced by the following examples:

• The procedure required carts in the reactor building to be chocked and imposed spacing requirements between the carts and safety-related components based on cart dimensions. However, multiple compressed gas cylinder carts in the reactor building were not chocked and staged too close to safety-related components given their dimensions.

• A compressed gas cylinder cart was tied off to a handrail that MOP23 stated was acceptable for up to 400 pounds. However, the cart weight was 2,600 pounds.

• Procedure MOP23 required the storage of compressed gas cylinders in the reactor building to be approved by engineering. However, a compressed gas cylinder cart was stored at a location that had not received prior engineering approval for that purpose.

• Compressed gas cylinders temporarily used in the reactor building were required by MOP23 to be tightly mounted to structures with at least two restraints. However, a temporarily secured compressed gas cylinder cart in the reactor building was mounted to a structure with only one restraint.

The start date of the violation was unknown because information was not available to reasonably determine or estimate when the licensee first stored the compressed gas cylinder carts in the reactor building as described above. The inspectors identified the violation on February 12, 2021, and the licensee restored compliance on February 26, 2021.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On April 27, 2021, the inspectors presented the integrated inspection results to Mr. P. Dietrich, Chief Nuclear Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Drawings

6M721-5734

Emergency Diesel Generator System Functional Operating

Sketch

BL

M-2847

Control Center Air Conditioning Air Side Reactor Building

Z

M-4325

Water Side and MISC Chiller Inst Control Center A/C

System

AG

71111.05

Drawings

A-2033

Radwaste Building 2nd Floor Plan El 613'-6" & 2nd Floor

Mezz El 628'6"

AC

Fire Plans

FP-RDWST

Radwaste Building Zones 22, 23, 24, and 25

Procedures

MOP11

Fire Protection

71111.11Q Miscellaneous

Power Profile

March 5, 2021 Downpower

SS-OP-904-2101

Evaluation Scenario

Procedures

2.000.03

Power Operation 25% to 100% to 25%

106

23.107

Reactor Feedwater and Condensate Systems

154

23.108

Extraction Steam and Heater Drains

23.109

Turbine Operating Procedure

71111.12

Corrective Action

Documents

Resulting from

Inspection

21-22263

NRC Identified - Concern with the Ability to Evaluate

Emergency Action Level for Lowering Spent Fuel Pool Level

03/11/2021

Engineering

Changes

EDP 37088

Install Spent Fuel Pool Level Instrumentation to Comply with

NRC Order EA-12-051 Guidance

71111.13

Corrective Action

Documents

21-20649

Fire Header Pressure Low After Replacing P80-F407 Fire

Header Jockey Pump Discharge Backpressure Regulator

01/22/2021

21-20687

Diesel Fire Pump P8000C001 Failed Blow-By Test

01/25/2021

21-20761

Received Main Control Room Alarm 11D64 CTG 11

Transformer Trouble

01/27/2021

21-21476

Fuel Rack at Max Fuel on EDG 12 with Machine Shutdown

2/16/2021

21-21496

MTG Accidental Energization Relay Tripped

2/16/2021

21-21497

Received 4D65 Generator Protective Relaying Operated

2/16/2021

21-21498

While Performing 4D65 Initiating Device IPCS Point for

Reverse Power is Incorrect

2/16/2021

21-21537

Received 5D28

2/17/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

21-21542

Low Alarm Power Found on VAS Paddleboard 7RD-6

2/17/2021

21-21850

Temporary Loss of Brest Bay Feed to Tag Line

2/28/2021

Drawings

6SD721-2500-02

One Line Diagram 13.8KV

BE

Engineering

Changes

80127

ECCS Pump CST Vortex Suppression Device

C

Miscellaneous

210301

T-1 Schedule Evaluation (03/01/2021 03/07/2021)

CTG-11-1

Clearance: R1100-000574

03/01/2021

Transformer - 11

Clearance: R1200-000129

03/01/2021

Troubleshooting

Plan

Referencing CARD 21-21497

2/17/2021

Procedures

11D64

CTG 11 Transformer Trouble

23.106

Control Rod Drive Hydraulic System

118

MWC15

Elevated Risk Management

Work Orders

53877347

DCP-80127 Install a Vortex Suppressor on the CST Core

Spray / SBFW Standpipes P1100

03/23/2021

71111.15

Calculations

DC-6447

Auxiliary Power System Analysis [PROPRIETARY]

F

Calibration

Records

P44K803A-SS

Division 1 Emergency Equipment Cooling Water

Temperature Control

07/24/2016

Corrective Action

Documents

10-22622

CTG 11-1 Lube Oil Tank Temperature Low Alarm

03/26/2010

19-24615

Diesel Fire Pump Engine SWI [Severe Wear Index] > Action

Level B

06/18/2019

20-21494

High SWI on Diesel Fire Pump Engine

2/11/2020

20-25557

NQA - RF20 - Work Order Review of Blow-By Test and Oil

Change of Diesel Fire Pump

05/05/2020

20-30097

Diesel Fire Pump Engine (Spare) High Blow-By Cause

09/10/2020

20-30292

Lessons Learned from Prompt Investigation into Diesel Fire

Pump Engine High Blow-By

09/16/2020

21-20328

DFP Engine SWI High

01/11/2021

21-20658

Unsupported Conclusions for Degraded Voltage Relay

Performance During LOCA Transient DC-6447

01/22/2021

21-20687

Diesel Fire Pump P8000C001 Failed Blow-By Test

01/25/2021

21-21951

Division 1 CCHVAC Chiller Trip

03/02/2021

21-21952

Valve Inoperable

03/03/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

21-21995

Spare HPCI and RCIC Flow Controllers are Obsolete with

Zero in Inventory

03/04/2021

21-22138

CTG 11-1 Unit Trouble on Low Lube Oil Temperature

03/08/2021

21-22139

CTG 11-1 Unit Trouble on Low Lube Oil Sump Temperature

03/09/2021

21-22169

Toolboxes on RB-3 not Stored Properly

03/09/2021

21-22170

Temporary Power Carts Staged on RB-1 Should be

Removed if not Needed

03/09/2021

21-22200

Potential Trend Identified in Storage of Items in the Plant

That do not Meet Requirements of MOP23

03/10/2021

21-22416

ACMP Recommendations not Fully Followed for DFP SWI

03/17/2021

Corrective Action

Documents

Resulting from

Inspection

21-21373

Nitrogen Cart not Stored IAW MOP23 in RB

2/12/2021

21-21805

NRC Concern Nitrogen 12 Pack not Stored IAW MOP23

Requirements

2/25/2021

21-22128

NRC Identified: Various Housekeeping/Plant Storage Issues

Identified on RB-1, RB-B, RBSB SW Areas

03/08/2021

Miscellaneous

ACMP 19-007

Diesel Fire Pump Engine

B

ACMP 21-003

Diesel Fire Pump - Engine

Procedures

23.324.01

Operation of CTG 11-1 From CTG11 Peaker Yard

24.207.08

Division 1 EECW Pump and Valve Operability Test

83A

MMA08

Scaffolding

MOP23

Plant Storage

Work Orders

46574671

Calibrate CTG 11-1 Instruments, Pressure and Temperature

Switches

03/07/2019

54305120

Perform Blow-By Test to Determine Engine Health

07/17/2019

60510990

Replace P44K800A

03/18/2021

71111.18

Corrective Action

Documents

2-24521

Review BWROG SC05-03 Analysis

05/16/2012

19-26921

Alternate DFP, Failed Loss of Offsite Power Test

03/13/2019

21-21167

Alternate Diesel Fire Pump Flow Concern

2/07/2021

Engineering

Changes

37580

Change to Main Steam Line Isolation Low-Pressure Isolation

Setpoint, Analytical Limit, the Allowable Value, and Nominal

Trip Setpoint Revision in Support of Tech Spec and Safety

Limit Change

DCP IP-ENG-001

Alternate Diesel Fire Pump

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

- 21-0001

Fire Plans

FPEE-21-0002

Evaluation of TM-21-0001 - Temporary Diesel Fire Pump

Procedures

ARP 7D2

Diesel Fire Pump Trouble

Work Orders

59086275

Implement EDP-37580 for B21N676A

2/01/2021

59086430

Implement EDP 37580 for B21N676C

2/01/2021

60088154

Installation WO for TM-21-0001 Alternate Diesel Fire Pump

2/05/2021

71111.19

Corrective Action

Documents

21-21949

P4400F602A Stem Nut Lock Nut Found Loose During

Periodic Thrust Test

03/02/2021

Drawings

I-2221-05

HPCI SYS-Pump Discharge Isolation Valves

AD

I-2451-13

NIAS Division 1 Dryer P5002D012 Controls

N

I-2611-34

Main Control Room Multi-Zone Unit Electric Heaters

Division 2

O

Miscellaneous

MCAR G-1

Final Report for Limitorque Motor Operator Valve Stem Lock

Nut Staking Susquehanna Steam Electric Station Units 1

and 2

05/15/1980

Procedures

35.318.007

Time-Delay Relays

Work Orders

53086927

Perform MOV Thrust testing (P4400F602A)

03/01/2021

54714285

Replace Agastat Relay in P50P402A, Division 1 NIAS Dryer

Control Cabinet

01/07/2021

56873119

Replace Agastat Relay R3200S016-057 (PM G240)

01/07/2021

58802759

Replace the M Contactor and CR1 Relay for MCC 72F-5A

Pos 2B-R

01/28/2021

71111.22

Corrective Action

Documents

21-20242

LPIV #3 Card A12 and A14 Slot Location Need Modification

for Installation

01/08/2021

21-20546

44.030.254 Approaching Critical Date and not Scheduled

01/20/2021

21-20547

44.030.252 Approaching Critical Date

01/20/2021

Drawings

M-2082

Standby Liquid Control System

AB

Miscellaneous

ODMI 20-007

Spurious NSSSS Channel D Isolation Signal

TE-B21-20-062

Risk Evaluation for Frequency Extension of ATWS-

RPT/ECCS RPV Level and Pressure Surveillances

Vendor Manual

VMR1-50

Analog Trip Unit

C

Procedures

24.206.01

RCIC System Pump and Valve Operability Test

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

44.030.254

ECCS - Reactor Vessel Water Level (Levels 1, 2, and 8),

Division 2, Channel D Functional Test

Work Orders

54698574

Perform 24.139.02 SLC Pump and Check Valve Operability

Test

01/08/2021

54714301

Perform 44.020.003 NS4 Rx Low Water Level 1 & 2

Division 1, Channel Functional Test

01/11/2021

282654

Install Test Jacks and Jumpers to Support NSSSS

Surveillance

01/11/2021

71114.06

Miscellaneous

ERO Tabletop Session

2/04/2021

Procedures

EP-101

Classification of Emergencies

43A

71151

Miscellaneous

Licensing Performance Indicator Safety System Functional

Failure (SSFF) IRIS Data Entry, Verification, and Approval

01/08/2021

Industry Reporting Information System Performance

Indicator Summary Report

01/21/2021

71153

Corrective Action

Documents

20-27545

Loss of 345kV Due to Mayfly Infestation

07/02/2020

Procedures

27.322

Mayfly Infestation Preparation Plan

0