IR 05000272/2024001: Difference between revisions

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No findings or violations of more than minor significance were identified during this inspection.
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 (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
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 (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely, Brice A. Bickett, Chief Projects Branch 3 Division of Operating Reactor Safety
Sincerely, Brice A. Bickett, Chief Projects Branch 3 Division of Operating Reactor Safety


Docket Nos. 05000272 and 05000311 License Nos. DPR- 70 and DPR-75
Docket Nos. 05000272 and 05000311 License Nos. DPR-70 and DPR-75


===Enclosure:===
===Enclosure:===
Line 40: Line 40:
Docket Numbers: 05000272 and 05000311
Docket Numbers: 05000272 and 05000311


License Numbers: DPR- 70 and DPR-75
License Numbers: DPR-70 and DPR-75


Report Numbers: 05000272/2024001 and 05000311/2024001
Report Numbers: 05000272/2024001 and 05000311/2024001
Line 78: Line 78:


==INSPECTION SCOPES==
==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.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on -site portions of IPs. 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.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on -site portions of IPs. 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.
Line 97: Line 97:
: (2) Unit 2, 100' elevation auxiliary building, relay and battery room, FP-SA-2551, February 23, 2024
: (2) Unit 2, 100' elevation auxiliary building, relay and battery room, FP-SA-2551, February 23, 2024
: (3) Unit 1, 100' elevation auxiliary building, 1A emergency diesel generator (EDG) area, FP-SA-1555, February 26, 2024
: (3) Unit 1, 100' elevation auxiliary building, 1A emergency diesel generator (EDG) area, FP-SA-1555, February 26, 2024
: (4) Unit 2, 100' elevation auxiliary building, inner piping penetration area and chiller rooms, FP-SA- 2556, March 28, 2024
: (4) Unit 2, 100' elevation auxiliary building, inner piping penetration area and chiller rooms, FP-SA-2556, March 28, 2024


==71111.06 - Flood Protection Measures==
==71111.06 - Flood Protection Measures==
Line 196: Line 196:
205204, Sheet 1 No. 1 Unit Turbine Drains 37
205204, Sheet 1 No. 1 Unit Turbine Drains 37
71111.05 Corrective Action 2095 Salem Pre-Fire Plan for Unit 2 Diesel Generator Area (FP- 02/28/2024
71111.05 Corrective Action 2095 Salem Pre-Fire Plan for Unit 2 Diesel Generator Area (FP- 02/28/2024
Documents SA- 2555) Incorrectly States That There are Floor Drains
Documents SA-2555) Incorrectly States That There are Floor Drains
Resulting from Used to Discharge Water Out of Area
Resulting from Used to Discharge Water Out of Area
Inspection 20957959 Salem Pre-Fire Plan for Unit 1 Diesel Generator Area (FP- 02/28/2024
Inspection 20957959 Salem Pre-Fire Plan for Unit 1 Diesel Generator Area (FP- 02/28/2024
SA- 1555) Incorrectly States That There are Floor Drains and
SA-1555) Incorrectly States That There are Floor Drains and
a Sump That are Used to Discharge Water Out of Area
a Sump That are Used to Discharge Water Out of Area
2097485 Fire Department Notes for Continuous Firewatch Were 02/26/2024
2097485 Fire Department Notes for Continuous Firewatch Were 02/26/2024
Line 211: Line 211:
20502815,
20502815,
20939968
20939968
OP.SA-102-106- Master List of Timed Actions 7
OP.SA-102-106-Master List of Timed Actions 7
F1
F1
S-C-ZZ-SDC- Moderate Energy Line Break Analysis 3
S-C-ZZ-SDC-Moderate Energy Line Break Analysis 3
203
203
S1.OP-AB.ZZ- Flooding 4
S1.OP-AB.ZZ-Flooding 4
000s
000s
S2.OP-SO.DG- 2C Diesel Generator Sump 1
S2.OP-SO.DG-2C Diesel Generator Sump 1
0004
0004
SA-PRA-012 Salem Generating Station Probabilistic Risk Assessment 6
SA-PRA-012 Salem Generating Station Probabilistic Risk Assessment 6
Line 223: Line 223:
SA-PRA-012A Salem Generating Station Probabilistic Risk Analysis Internal 0
SA-PRA-012A Salem Generating Station Probabilistic Risk Analysis Internal 0
Flood Walkdown Notebook
Flood Walkdown Notebook
SI.OP.AB.SW- Loss of Service Water Header Pressure 18
SI.OP.AB.SW-Loss of Service Water Header Pressure 18
0001
0001
Inspection Type Designation Description or Title Revision or
Inspection Type Designation Description or Title Revision or
Line 234: Line 234:
Documents
Documents
Corrective Action 20956219 Struthers Dunn Relays for 21, 22, and 23 Charging Pumps 02/13/2024
Corrective Action 20956219 Struthers Dunn Relays for 21, 22, and 23 Charging Pumps 02/13/2024
Documents Installed Beyond 16- year Replacement Preventive
Documents Installed Beyond 16-year Replacement Preventive
Resulting from Maintenance
Resulting from Maintenance
Inspection
Inspection
Line 242: Line 242:
Accordance with Maintenance Rule
Accordance with Maintenance Rule
80130005-0100 De-activation of 2$ Full Flow Test and Existing WOs 07/05/2022
80130005-0100 De-activation of 2$ Full Flow Test and Existing WOs 07/05/2022
30346154 and 30346155 for Non- Safety-Related 4th AFW
30346154 and 30346155 for Non-Safety-Related 4th AFW
Pump
Pump
Miscellaneous Maintenance Plan 3M Performance of PM to Perform MSPI 4th AFW Pump
Miscellaneous Maintenance Plan 3M Performance of PM to Perform MSPI 4th AFW Pump
Line 258: Line 258:
Procedures ER-AA-310 Implementation of Maintenance Rule 16
Procedures ER-AA-310 Implementation of Maintenance Rule 16
SC-MRULE-001 Salem Maintenance Rule Risk Ranking 6
SC-MRULE-001 Salem Maintenance Rule Risk Ranking 6
SC.OP-PT.AF- Testing the MSPI Pump and Diesel 1
SC.OP-PT.AF-Testing the MSPI Pump and Diesel 1
0001
0001
SC.OP-SO.AF- Feed Steam Generators with MSPI AFW Pump 2
SC.OP-SO.AF-Feed Steam Generators with MSPI AFW Pump 2


Inspection Type Designation Description or Title Revision or
Inspection Type Designation Description or Title Revision or
Line 287: Line 287:
Manual 433266
Manual 433266
Procedures OP-SA-108-116 Operability Assessment and Equipment Control Program 5
Procedures OP-SA-108-116 Operability Assessment and Equipment Control Program 5
S1.OP-ST.CVC- Inservice Testing - 11 Charging Pump 27
S1.OP-ST.CVC-Inservice Testing - 11 Charging Pump 27
0003
0003
Work Orders 30371216
Work Orders 30371216
Line 300: Line 300:
Inspection Type Designation Description or Title Revision or
Inspection Type Designation Description or Title Revision or
Procedure Date
Procedure Date
71111.24 Procedures S1.OP-SO.CVC- Charging Pump Operating 45
71111.24 Procedures S1.OP-SO.CVC-Charging Pump Operating 45
0002
0002
S2.OP-PT.TRB- Main Turbine Valve Stroke Time Testing 22
S2.OP-PT.TRB-Main Turbine Valve Stroke Time Testing 22
0003
0003
Work Orders 30381432
Work Orders 30381432

Latest revision as of 16:18, 4 October 2024

Integrated Inspection Report 05000272/2024001 and 05000311/2024001
ML24127A178
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/07/2024
From: Brice Bickett
NRC/RGN-I/DORS
To: Mcfeaters C
Public Service Enterprise Group
References
IR 2024001
Download: ML24127A178 (1)


Text

May 7, 2024

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2024001 AND 05000311/2024001

Dear Charles McFeaters:

On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2. On April 25, 2024, the NRC inspectors discussed the results of this inspection with Richard DeSanctis, Plant Manager, 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 (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Brice A. Bickett, Chief Projects Branch 3 Division of Operating Reactor Safety

Docket Nos. 05000272 and 05000311 License Nos. DPR-70 and DPR-75

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000272 and 05000311

License Numbers: DPR-70 and DPR-75

Report Numbers: 05000272/2024001 and 05000311/2024001

Enterprise Identifier: I-2024-001- 0039

Licensee: PSEG Nuclear, LLC

Facility: Salem Nuclear Generating Station, Units 1 and 2

Location: Hancocks Bridge, NJ

Inspection Dates: January 1, 2024 to March 31, 2024

Inspectors: L. Grimes, Senior Resident Inspector E. Garcia, Resident Inspector

Approved By: Brice A. Bickett, Chief Projects Branch 3 Division of Operating Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Salem Nuclear Generating Station, Units 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 operated at or near rated thermal power for the entire inspection period.

Unit 2 began the inspection period at rated thermal power. On February 21, 2024, the unit was down powered to approximately 60 percent to perform turbine valve testing, 22 steam generator feedwater pump repairs, and 21 turbine governor valve repairs. On February 21, 2024, the unit returned to rated thermal power and 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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on -site portions of IPs. 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.

REACTOR SAFETY

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, main steam and turbine drain due to steam leak upstream of 11A drain manifold, January 31, 2024 (Notification (NOTF) 20955615)
(2) Unit 1, main steam system, March 6, 2024
(3) Unit 1, 11 auxiliary feedwater system, March 14, 2024
(4) Unit 2, chilled water system due to lowering chilled water expansion tank level, March 28, 2024

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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 2, 100' elevation auxiliary building, inner penetration area, FP-SA-2556, January 17, 2024
(2) Unit 2, 100' elevation auxiliary building, relay and battery room, FP-SA-2551, February 23, 2024
(3) Unit 1, 100' elevation auxiliary building, 1A emergency diesel generator (EDG) area, FP-SA-1555, February 26, 2024
(4) Unit 2, 100' elevation auxiliary building, inner piping penetration area and chiller rooms, FP-SA-2556, March 28, 2024

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated internal flooding mitigation protections in the Units 1 and 2 EDG rooms.

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 licensed operator performance in the main control room during Unit 1 downpower and activities to address degraded 22 steam generator feedwater pump and 21 turbine governor valve on February 21, 2024.

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

(1) The inspectors observed and evaluated a Unit 2 simulator scenario that included a failed nuclear instrument, dropped control rod, main power transformer open phase condition requiring a reactor trip, and a stuck open pressurizer power-operated relief valve on January 30, 2024.

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) Units 1 and 2, mitigating system performance indicator auxiliary feedwater pump, March 12, 2024
(2) Unit 1, 11 service water pump after pump strainer differential pressure high and not rotating, March 20, 2024 (NOTF 20959960)

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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, emergent work on 13 chiller due to trip on low compressor oil level, January 4, 2024 (NOTF 20954860)
(2) Unit 1, emergent work on 11 and 13 chiller due to 11 chiller trip on low differential pressure and 13 chiller already inoperable, January 26, 2024 (NOTFs 20955583 and

===20955114/WO 60159548)

(3) Unit 2, elevated risk during scheduled repair to 21 turbine governor valve, 21MS29, while at 60 percent power, February 21, 2024 (NOTF 20939146 and WO 60157677)
(4) Unit 2, elevated risk during scheduled repair to 22 steam generator feedwater pump
  1. 1 control oil power unit pump while at 60 percent power, February 21, 2024 (NOTF 20953015 and WO 60159360)
(5) Unit 1, elevated risk during scheduled activity on 1A EDG where technical specification allowed outage time extended from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days due to crediting allowed outage time diesel generators, during week of February 26 - March 2, 2024 (WO 30371216)

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01)===

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

(1) Unit 1, 1C EDG due to review of procedural direction to reduce load prior to performance of hot restart surveillance, January 16, 2024
(2) Unit 1, chilled water system due to work windows for 12 chilled water pump, 11 chiller out of service, and 13 chiller degraded, February 7, 2024 (NOTFs 20955583 and

===20954860)

(3) Unit 1, first time use of allowed outage time diesel generators to extend the technical specification action statement due to the 1A EDG online maintenance overhaul, February 26, 2024
(4) Unit 1, 11 charging pump due to indications of degraded service water cooling to lube oil heat exchanger, March 1, 2024 (NOTF 20956598)
(5) Unit 1, 12 service water pump due to failed inservice test on low pump differential pressure, March 21, 2024

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01)===

(1) Unit 2, 22 safety injection pump following failed relay replacement and breaker swap, February 15, 2024
(2) Unit 1, 11 charging pump following 4kV breaker replacement/swap, February 23, 2024 (WO 30329527)
(3) Unit 1, 11 charging pump after planned maintenance, March 28, 2024 (WO

30380539) Surveillance Testing (IP Section 03.01)

(1) Unit 1, S1.OP-ST.DG-0021, "1C Diesel Generator Hot Restart Test,"

January 16, 2023 (WO 50235459)

(2) Unit 2, S2.OP-PT.TRB-0003, "Main Turbine Valve Stroke Testing," February 21, 2024 (WO 30381432)
(3) Unit 1, S1.OP-ST.AF-0003, "13 Auxiliary Feedwater Pump In-service Testing,"

March 19, 2024 (WO 50247937)

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Unit 1, S1.OP-ST.DG-0005(Q), "12 Fuel Oil Transfer System Operability Test," January 12, 2024 (WO 50246185)

71114.06 - Drill Evaluation

Required Emergency Preparedness Drill (1 Sample)

(1) The inspectors observed and evaluated the adequacy and capability of the licensees assessment of performance during a hostile action-based emergency preparedness drill on March 26,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1, January 1, 2023 through December 31, 2023
(2) Unit 2, January 1, 2023 through December 31, 2023

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1, January 1, 2023 through December 31, 2023
(2) Unit 2, January 1, 2023 through December 31, 2023

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1, January 1, 2023 through December 31, 2023
(2) Unit 2, January 1, 2023 through December 31,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On April 25, 2024, the inspectors presented the integrated inspection results to Richard DeSanctis, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings 205203, Sheet 3 No. 1 Unit Main, Reheat and Turbine By-pass Steam 73

205204, Sheet 1 No. 1 Unit Turbine Drains 37

71111.05 Corrective Action 2095 Salem Pre-Fire Plan for Unit 2 Diesel Generator Area (FP- 02/28/2024

Documents SA-2555) Incorrectly States That There are Floor Drains

Resulting from Used to Discharge Water Out of Area

Inspection 20957959 Salem Pre-Fire Plan for Unit 1 Diesel Generator Area (FP- 02/28/2024

SA-1555) Incorrectly States That There are Floor Drains and

a Sump That are Used to Discharge Water Out of Area

2097485 Fire Department Notes for Continuous Firewatch Were 02/26/2024

Incorrect

Fire Plans FP-SA-2556 Salem Pre-Fire Plan, U/2 Inner Piping Penetration Area & 0

Chiller, Room EI 100'

Procedures FP-SA-003 Actions for Inoperable Fire Protection - Salem Station 7

71111.06 Miscellaneous Notifications:

20325499,

20390805,

20502815,

20939968

OP.SA-102-106-Master List of Timed Actions 7

F1

S-C-ZZ-SDC-Moderate Energy Line Break Analysis 3

203

S1.OP-AB.ZZ-Flooding 4

000s

S2.OP-SO.DG-2C Diesel Generator Sump 1

0004

SA-PRA-012 Salem Generating Station Probabilistic Risk Assessment 6

Internal Flood Evaluation Summary Notebook

SA-PRA-012A Salem Generating Station Probabilistic Risk Analysis Internal 0

Flood Walkdown Notebook

SI.OP.AB.SW-Loss of Service Water Header Pressure 18

0001

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 70070053,

70136049,

230176,

60080099

71111.12 Corrective Action 20777337 Internal Damage to the Inner Bonnet of the 1AF175 Valve 10/20/2017

Documents

Corrective Action 20956219 Struthers Dunn Relays for 21, 22, and 23 Charging Pumps 02/13/2024

Documents Installed Beyond 16-year Replacement Preventive

Resulting from Maintenance

Inspection

Drawings 205236, Sheet 2 No. 1 and 2 Units Spare Auxiliary Feed Pump 4

Engineering 70211323 Non-Safety-Related 4th AFW Pump MRule Maintenance 01/22/2020

Evaluations Strategy After Identification it was Not Being Tested in

Accordance with Maintenance Rule

80130005-0100 De-activation of 2$ Full Flow Test and Existing WOs 07/05/2022

30346154 and 30346155 for Non-Safety-Related 4th AFW

Pump

Miscellaneous Maintenance Plan 3M Performance of PM to Perform MSPI 4th AFW Pump

366333 Recirculation Flow Test (Recirculation to/from Demineralized

Water Storage Tank)

Maintenance 8Y Performance of PM to Lube and Inspect 1/2AF174 Valves

Plans 368296 and (MSPI AFW Pump Discharge Manual Globe Valve)

368297

Maintenance 8Y Performance of PM to Lube and Inspection 11-14 and 21-

Plans 368298, 24AF175 Valves (MSPI AFW Pump Discharge to Each S/G)

366326, 366327,

366328, 366329,

366330, 366331,

and 366332

Procedures ER-AA-310 Implementation of Maintenance Rule 16

SC-MRULE-001 Salem Maintenance Rule Risk Ranking 6

SC.OP-PT.AF-Testing the MSPI Pump and Diesel 1

0001

SC.OP-SO.AF-Feed Steam Generators with MSPI AFW Pump 2

Inspection Type Designation Description or Title Revision or

Procedure Date

0001

71111.13 Procedures OP-SA-108-116 Operability Assessment and Equipment Control Program 2

71111.15 Corrective Action 20927785 Excessive Corrosion on Fitting and Tubing Downstream of 02/22/2023

Documents 1SW186 Valve that Provides Indications for SW Inlet

Pressure to Lube Oil Heat Exchanger

Miscellaneous 80131437 - 0100 Tech Evaluation

80134667 - 0200 Tech Evaluation

DCP 80134926

License Emergency Diesel Generator Hot Restart Test Salem 04/12/1994

Amendment Generating Station Unit Nos. 1 and 2

Request NLR-

N94008, LCR 94-

NRC Generic Proposed Staff Actions to Improve and Maintain Diesel

Letter 84-15 Generator Reliability

NRC Information Recent Engine Failures of Emergency Diesel Generators

Notice 85-32

NRC Regulatory Election, Design, and Qualification of Diesel Generator Units 2

Guide 1.9 Used as Standby (Onsite) Electric Power Systems at Nuclear

Power Plants

Operation and Diesel Engine-Generator Sets (ALCO)

Maintenance

Manual 433266

Procedures OP-SA-108-116 Operability Assessment and Equipment Control Program 5

S1.OP-ST.CVC-Inservice Testing - 11 Charging Pump 27

0003

Work Orders 30371216

244970, Performance of 3-month 11 Charging Pump Inservice

244313, and Testing

242574

60159516 and Troubleshooting 13 Chiller Due to Trip on Low Compressor 01/26/2024

60159548 Oil Level on 01/04/2024 and Replace Time-delay Relay by

Cannibalizing 11 Chiller's Time-delay Relay

230854

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.24 Procedures S1.OP-SO.CVC-Charging Pump Operating 45

0002

S2.OP-PT.TRB-Main Turbine Valve Stroke Time Testing 22

0003

Work Orders 30381432

11