IR 05000327/2021002

Integrated Inspection Report 05000327/2021002 and 05000328/2021002

ML21209A026
Person / Time
Site:	Sequoyah
Issue date:	07/27/2021
From:	Tom Stephen NRC/RGN-II/DRP/RPB5
To:	Jim Barstow Tennessee Valley Authority
T Francis
References
IR 2021002
Download: ML21209A026 (16)

Text

July 27, 2021

SUBJECT:

SEQUOYAH, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000327/2021002 AND 05000328/2021002

Dear Mr. Barstow:

On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah, Units 1 and 2. On July 20, 2021, the NRC inspectors discussed the results of this inspection with Mr. Tom Marshall and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

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/

Thomas A. Stephen, Chief Reactor Projects Branch #5 Division of Reactor Projects

Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000327 and 05000328

License Numbers:

DPR-77 and DPR-79

Report Numbers:

05000327/2021002 and 05000328/2021002

Licensee:

Tennessee Valley Authority

Facility:

Sequoyah, Units 1 and 2

Location:

Soddy Daisy, TN 37379

Inspection Dates:

April 01, 2021 to June 30, 2021

Inspectors:

N. Childs, Resident Inspector

S. Downey, Senior Reactor Inspector

D. Hardage, Senior Resident Inspector

Approved By:

Thomas A. Stephen, Chief

Reactor Projects Branch #5

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Sequoyah, Units 1 and 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

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power (RTP). On April 5, 2021, the unit entered end of life coast down, and on April 10, 2021, the unit was shutdown from 95 percent RTP for refueling outage 1R24. On May 10, 2021, the reactor was started up and the unit returned to RTP on May 14, 2021. On May 24, 2021, the reactor tripped on power range nuclear instrument negative rate due to a failure of the Control Bank B Group 2 stationary gripper phase control card. The unit was returned to RTP on June 1, 2021 and remained at or near RTP for the remainder of the inspection period.

Unit 2 operated at or near RTP for the entire 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 (COVID-19), resident and regional 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, increasing the amount of time on site as local COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; 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 a portion 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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal summer temperatures including review the material condition of the plants offsite AC power systems and onsite alternate AC power systems including the switchyard and transformers on May 26, 2021.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 1 residual heat removal system (RHRS) with both trains in service for cooldown in Mode 5 with reactor coolant system (RCS) level below the flange on April 13, 2021

(2) Unit 1 RHRS with both aligned for low pressure safety injection in Mode 1 following realignment from 1R24 on May 23, 2021

(3) Unit 1 auxiliary feedwater (AFW) system following replacement of 1B AFW pump on June 11, 2021

(4) Unit 1 emergency core cooling system pumps and 1A emergency diesel generator (EDG) with 1B-B EDG inoperable due to failure to start on June 28, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

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) Unit 1 Reactor Building, Lower Containment, Elevation 679 on May 3, 2021

(2) Unit 1 Reactor Building, Upper Containment, Elevation 734 on May 5, 2021

(3) Unit 2 Auxiliary Building (Non-RCA), Elevation 734 on June 10, 2021

(4) Unit 1 and Unit 2 Auxiliary Building, Elevation 653 on June 24, 2021

(5) Unit 1 and Unit 2 Auxiliary Instrument Rooms, Control Building Elevation 685 on June 28, 2021

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade performance in response to a fire in 1B AFW pump on May 27, 2021.

===71111.08P - Inservice Inspection Activities (PWR)

PWR Inservice Inspection Activities Sample (IP Section 03.01)===

(1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from May 10 to May 14, 2021:

1. Liquid Penetrant Examination

a. RHRHXH-18-A-2-IA, Integral attachment to Residual Heat Removal Heat Exchanger 1A, ASME Class 2 b. Weld 0-ER-1715A, Pipe to elbow weld, ASME Class 3. This included a review of the associated welding activities.

c. Weld 1-RX-2134A, Transition piece to elbow weld, ASME Class 1.

This included a review of the associated welding activities.

2. Magnetic Particle Examination

a. Weld RFDW-2, Steam Generator 2 Feedwater Nozzle to Shell weld, ASME Class 2

3. Radiographic Examination

a. Weld SIF-196, Pipe to valve Weld, ASME Class 1

4. Ultrasonic Examination

a. Weld AFWF-150, Pipe to reducer weld, ASME Class 2 b. Weld RFDW-2, Steam Generator 2 Feedwater Nozzle to Shell weld, ASME Class 2 c. Weld RCS-032, Pipe to elbow weld, ASME Class 1 d. Weld SI-1693, socket weld, ASME Class 1 e. Weld SIF-196, Pipe to valve weld, ASME Class 1

5. Visual Examination

a. Bare metal visual (remote) examination of Reactor Pressure Vessel Closure Head and penetrations, ASME Class 1

The Inspectors also evaluated the licensees boric acid corrosion control program performance.

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 main control room during shutdown activities for U1R24 refueling outage on April 9 - 10, 2021.

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

(1) The inspectors observed and evaluated a simulator examination scenario on June 14, 2021.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

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

(1) Failure of 1-FCV-67-344, essential raw cooling water (ERCW) to 1B-B pipe chase cooler, to open during surveillance testing on November 23, 2020

(2) Auxiliary building secondary containment enclosure isolation damper 2-FCO-30-272 failed to close on auxiliary building isolation actuation on February 19, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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) Unit 1, Yellow shutdown risk week of April 11 - 17, 2021, while RCS level was below Reactor (Rx) flange level and during Rx core offload, including review of defense in depth protected equipment for U1R24.

(2) Unit 1, Yellow shutdown risk week of April 18 - 23, 2021, during reactor core offload concurrent with maintenance on the A RHR train, including review of defense in depth protected equipment for U1R24.

(3) Unit 1, Yellow shutdown risk week of May 2-8, 2021, while RCS level was below Rx flange level and RCS heat up from Mode 5 to normal operating temperature including review of defense in depth protected equipment for U1R24.

(4) Unit 1 and 2, week of May 23-29, 2021, including a reactor trip on Unit 1 and Yellow shutdown risk following a fire in the 1B AFW pump, including protection equipment reviews for emergent maintenance and a conservative operations alert.

(5) Unit 1 and 2, week of June 6-12, 2021, including protection equipment reviews for planned maintenance on the B auxiliary air compressor and emergent maintenance on D air compressor.

(6) Unit 1 and 2, week of June 27-30, 2021, including planned replacement of 1B start bus and emergent maintenance on 1B EDG, including protection equipment reviews for the emergent maintenance and a conservative operations alert.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1)1B Centrifugal Charging Pump Gear Oil Cooler has lower than expect flow on May 5, 2021 (CR 1691745)

(2) ERCW leak on internal coils of the 2B 669 pipe chase cooler on May 12, 2021 (CR 1693400)

(3)1B motor driven auxiliary feedwater (MDAFW) pump differential pressure below acceptance criteria on May 29, 2021 (CR 1697633)

(4) Prompt determination of operability request for 1-FCV-68-333 power operated relief valve block valve on April 23, 2021 (CR 1688783)

(5) Nuts found loose on flange of containment vacuum relief valve 1-VLV-30-47 on April 30, 2021 (CR 1688414)

(6) Conduit for power range nuclear instrument N41 detector filled with borated water on May 4, 2021 (CR 1690093)

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)

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

(1) Work Order (WO) 121287367, ERCW header 1A isolation valve 1-BCTD-3-116A clean square D contactor on April 7, 2021

(2) WO 121157462, Repack outboard end of Unit 1 turbine driven auxiliary feedwater (TDAFW) pump due to cocked gland on April 9, 2021

(3) WO 120868165, 1-FCV-74-3, '1A' RHR pump suction valve failed seat leak test, rework valve on April 29, 2021

(4) WO 122073016, Nuts found loose on bolting surface of 1-VLV-30-46, Containment Vacuum Relief Valve on May 6, 2021

(5) WO 117818333, Replace unit 1 reactor coolant pump #2 seal on May 8, 2021

(6) WO 119467102, 1-VLV-1-516 remove valve for testing offsite and replace gaskets on May 8, 2021

(7) WO 122074616, Replace 1-VLV-063-0559, safety injection loop 2 hot leg check valve, on May 8, 2021

(8) WO 122153643, Replace 1B-B AFW pump on May 29, 2021

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated U1R24 outage activities from April 10 to May 11, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1)1-SI-SXP-003-202.A, MDAFW 1A-A Comprehensive Performance Test on April 7, 2021 (2)1-SI-OPS-088-001.0, Phase A Isolation Test on April 11, 2021 (3)1-SI-SXP-003-202.S, TDAFW Comprehensive Performance Test on April 9, 2021

Inservice Testing (IP Section 03.01) (2 Samples)

(1)0-SI-SXV-001-859.0, Testing and Setting of Main Steam Safety Valves on April 7, 2021

(2) 1-SI-SXP-003-202.B, MDAFW 1B-B Comprehensive Test on May 31, 2021

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1)0-SI-SLT-043-258.1, Containment Isolation Valve Local Leak Rate Test Post Accident Sampling on April 19, 2021

Ice Condenser Testing (IP Section 03.01) (1 Sample)

(1)0-SI-MIN-061-109.0, Ice Condenser Intermediate and Lower Inlet Doors and Vent Curtains on May 2,

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 02.01)===

(1) Unit 1 (April 2020 - March 2021)

(2) Unit 2 (April 2020 - March 2021)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (April 2020 - March 2021)

(2) Unit 2 (April 2020 - March 2021)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (April 2020 - March 2021)

(2) Unit 2 (April 2020 - March 2021)

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends related to ice condenser ice baskets being frozen in place which might be indicative of a more significant safety issue.

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Unit 1 Reactor Vessel Head Vent Degradation

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

Event Follow up (IP Section 03.01)===

(1) The inspectors evaluated licensee performance in response to a fire in 1B-B AFW pump on May 27, 2021.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated licensee performance in response to Unit 1 reactor trip on May 24,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On July 20, 2021, the inspectors presented the integrated inspection results to Mr. Tom Marshall and other members of the licensee staff.

• On May 13, 2021, the inspectors presented the ISI Exit Meeting inspection results to Chris Reneau, Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Procedures

0-PI-OPS-000-

006.1

Summer Operation

Revision 9

AOP-P.07

Degraded Grid or Abnormal Voltage Conditions

Revision 17

NPG-SPP-07.1.6

On Line Work Control Power Systems Alerts/Offsite Power

Revision 8

71111.04

Miscellaneous

0-PE-2021 / 1-82-

0006

Protected Equipment/Clearance Section for 1B-B D/G

Inoperable

06/28/2021

Procedures

0-SO-74-1

Residual Heat Removal System

Revision 109

1-SO-3-2

Auxiliary Feedwater System

Revision 61

71111.05

Corrective Action

Documents

CR 1697239

Report of sparks coming from 1B-B MDAFW pump

05/27/2021

CR 1697332

Fire Emergency Response: 1B MDAFW pump

05/27/2021

CR 1700545

Temporary Cat5e Cable routed within the 1-foot boundary of

safety related cable trays and conduit

06/11/2021

Fire Plans

AUX-0-653-00

Pre-Fire Plan Auxiliary Building El 653

Revision 9

AUX-0-734-01

Pre-Fire Plan Auxiliary Building El 734 Unit 1 Side

Revision 10

AUX-0-734-02

Pre-Fire Plan Auxiliary Building El 734 Unit 2 Side

Revision 9

CON-0-685-00

Pre-Fire Plan, Control Building El. 685

Revision 6

RXB-0-679-02

Pre-Fire Plan for Reactor Building (Elevation 679)

Revision 3

RXB-0-734-02

Pre-Fire Plan for Reactor Building (Elevation 734) and

Annulus (Elevation 740, 759, and 778)

Revision 3

Miscellaneous

Standing Order:

SO-21-017

ACMP Fire Watch Camera Monitoring Plan

05/12/2021

71111.08P

Corrective Action

Documents

CRs (by number)

1463750, 1564272, 1580350, 1584849, 1608941, 1685545,

1686073, 1689057, 1689365, 1693829

NDE Reports

R-0478

Ultrasonic Examination Report for RCS-032

04/13/2021

R-0506

Ultrasonic Examination Report for SI-1693

04/20/2021

R-0513

Magnetic Particle Examination Report for RFDW-2

04/21/2021

R-0519

Visual Examination Report for Reactor Pressure Vessel

Closure Head

04/26/2021

R-0524

Ultrasonic Examination Report for RFDW-2

04/26/2021

Procedures

N-GP-18

Ultrasonic Testing Supplements

Revision

23

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

N-MT-6

Magnetic Particle Examination for ASME and ANSI Code

Components and Welds

Revision

0037

N-UT-19

Ultrasonic Examination of Welds in Vessels Greater than 2-

inches in Well Thickness

Revision

20

N-UT-64

Generic Procedure for the Ultrasonic Examination of

Austenitic Pipe Welds

Revision

0018

N-UT-85

Manual Ultrasonic Examination for the Detection of Thermal

Fatigue in Piping and Components within the Material

Reliability Programs

NPG-SPP-09.7.4

Boric Acid Corrosion Control Program

Revision

0006

Work Orders

Work Orders (by

number)

20593669, 121132022

71111.11Q Miscellaneous

SEG

1. OPL273E2130

LOR Cycle 21-03 Simulator Exam

06/14/2021

Procedures

1-SI-OPS-082-

26.B

Loss of Offsite Power with Safety Injection D/G 1B-B Test

Revision 56

1-SI-OPS-088-

001.0

Phase A Isolation Test

Revision 24

71111.12

Corrective Action

Documents

CR 1654164

Failed valve stroke for 1-FCV-67-344

11/23/2020

CR 1660457

Replace packing gland/packing gland follower, gland stud,

gland stud nut and repack valve

2/23/2020

CR 1661050

Failed PMT valve stroke for 1-FCV-67-344

2/29/2021

CR 1663703

1-FSV-67-344-B basic cause determination

01/12/2021

CR 1672837

2-FCO-30-272 did not go closed with a valid auxiliary

building isolation (ABI) signal present

2/19/2021

CR 1684582

Maintenance rule basic cause documentation of 2-FCO-30-

2

04/07/2021

Miscellaneous

CDE 3125

Cause determination evaluation for 1-FCV-67-344 stroke

failure

03/17/2021

CDE 3132

2-FCO-30-272 failed to close on ABI actuation

Revision 1

Procedures

NPG-SPP-03.4

Maintenance Rule Performance Indicator Monitoring,

Trending and Reporting - 10CFR50.65

Revision 4

TI-4, Attachment

Heating, Ventilation, and Air Conditioning - System 030

Revision 31

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1. 7

Work Orders

21941721;

21990076;

2050297

71111.13

Corrective Action

Documents

CR 1698157

Risk Classification of Works Orders during Forced Outage

06/02/2021

Corrective Action

Documents

Resulting from

Inspection

CR 1704128

Error in online EOOS, 1B EDG not included after failure

06/28/2021

Procedures

0-GO-16

System Operability Checklists

Revision 28

71111.15

Corrective Action

Documents

CR 1686772

Need Engineering review for 1-FCV-68-333 MOV Test Data.

Test Values exceeded acceptance criteria.

04/15/2021

CR 1690524

No ERCW flow indicated on 1B CCP

04/30/2021

CR 1691051

1B-B CCP speed increaser gearing oil cooler has insufficient

cooling flow

05/03/2021

CR 1691423

Document critical thinking related to CR 1690093 (Insulation

resistance of N41 cable met acceptance criteria).

05/04/2021

Engineering

Evaluations

EWR 21-DEM-

003-075

1B-B MDAFW Pump Replacement total developed head

requirement

05/29/2021

EWR-21-DEM-

067-065

Hydraulic Flow Values Associated with 1B-B Cent. Charging

Pump Gear Oil Cooler

05/05/2021

Operability

Evaluations

Prompt Determination of Operability for PER 732852 (2B

Pipe Chase Cooler Leak)

05/31/2013

Prompt Determination of Operability for CR 1611076 (B-B

EGTS Cooler Leak)

05/29/2020

71111.19

Corrective Action

Documents

CR 1697633

1B MDAFW Pump DP below acceptance criteria

05/29/2021

Procedures

0-SI-SXT-000-

201.0

ASME Section XI Inservice Pressure Test

Revision 25

0-SI-SXV-003-

266.0

ASME Code Valve Testing

Revision 51

1-SI-SFT-063-

001.0

Safety Injection System Hot Leg and Cold Leg Injection Flow

Test

Revision 12

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1-SI-SXI-068-

201.0

Leakage Test of the Reactor Coolant System Pressure

Boundary

Revision 16

1-SI-SXP-003-

201.B

Motor Driven Auxiliary Feedwater Pump 1B-B Performance

Test

Revision 18

N-VT-4

System Pressure Test Visual Examination Procedure

Revision 30

Work Orders

WO 120573825

1-SI-SXI-068-201.0 Unit 1 leakage test of the reactor coolant

pressure boundary

05/08/2021

WO 121842073

Perform Seat Leak Test on 1-FCV-74-003

04/29/2021

71111.20

Corrective Action

Documents

CR 1685395

CR to document lessons learned from SI-127 performance

(documentation of cooldown rates)

04/11/2021

Corrective Action

Documents

Resulting from

Inspection

CR 1685321

1-VLV-068-0580 has dry boron

04/10/2021

CR 1685322

1-VLV-068-0557 has dry boric acid on stem

04/10/2021

CR 1685323

White powder (boric acid or borax) under RCPs on floor

04/10/2021

CR 1690093

Fluid Coming Out of Conduit with White Residue around

Joints

04/28/2021

CR 1692251

Ice Condenser Drain Pipe leaking on #4 RCP Platform

05/06/2021

Procedures

1-SI-OPS-082-

26.B

Loss of Offsite Power with Safety Injection D/G 1B-B Test

Revision 56

71111.22

Corrective Action

Documents

CR 1684542

MSSV 1-VLV-001-0516 is suspected of leakage at inlet

flange

04/07/2021

CR 1684653

"B" AFW flow indicator 3-147A is showing zero flow during

comprehensive test

04/07/2021

CR 1697806

MDAFW critical spare exhibited marginal performance

05/31/2021

CR 1697913

Low Margin for MDAFW 1B-B

06/01/2021

Corrective Action

Documents

Resulting from

Inspection

CR 1690959

Unit 1 Ice Condenser Bay 18 RH Lower Inlet Door Spring

Loose

05/02/2021

Drawings

1-47W881 sheet

Mechanical Flow Drawing Water Quality and Sampling

System

Revision 4

71152

Corrective Action

Documents

CR 1691538

Unit 1 Ice Condenser basket trend

05/04/2021

CR 1691616

U1R24 Ice Condenser Partial Bay Melt Out Lessons

Learned

05/04/2021

Procedures

0-SI-MIN-061-

Ice Condenser - Ice Weighing

Revision 13

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

105.0