IR 05000272/2022011
| ML23006A022 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/06/2023 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Carr E Public Service Enterprise Group |
| References | |
| IR 2022011 | |
| Download: ML23006A022 (1) | |
Text
January 6, 2023
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000272/2022011 AND 05000311/2022011
Dear Eric Carr:
On December 1, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2 and NRC discussed the results with Dave Sharbaugh, Site Vice President, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Mel Gray, Chief Engineering Branch 1 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:
Report Numbers:
05000272/2022011 and 05000311/2022011
Enterprise Identifier: I-2022-011-0023
Licensee:
Facility:
Salem Nuclear Generating Station
Location:
Hancocks Bridge, NJ
Inspection Dates:
November 13, 2022 to December 1, 2022
Inspectors:
J. Brand, Reactor Inspector
K. Mangan, Senior Reactor Inspector
A. Turilin, Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) at Salem Nuclear Generating Station, 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.
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.
REACTOR SAFETY
===71111.21N.02 - Design-Basis Capability of Power-Operated Valves (POV) Under 10 CFR 50.55a Requirements
POV Review (IP Section 03)===
The inspectors:
a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Determined whether the sampled POVs are capable of performing their design-basis functions.
c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) Residual Heat Removal Heat Exchanger Component Cooling Outlet Valve, S1CC-11CC16
- (2) Fan Service Water Outlet Valve, S2SW -25SW223-AO
- (3) Containment Sump Suction Valve, S1SJ-12SJ44
- (4) Residual Heat Removal to Charging/Safety Injection Pumps Stop Valve, S1SJ-12SJ45
- (5) Residual Heat Removal Pump Suction Valve, S2RHR-21RH4
- (6) Residual Heat Removal Common Suction Valve, S2RHR-2RH1
- (7) Service Water Pump Discharge Header Crossover Valve, S2SW-21SW17
- (8) Charging Header Stop Valve, S1CVC-1CV68
- (9) Diesel Generator Service Water Inlet to Cooler Valve, S1SW -12SW39-AO
- (10) Closed Loop Cooling Heat Exchanger Service Water Inlet Valve, S2SW -22SW122-AO
- (11) Auxiliary Feed Pump Start/Stop Valve, S1MS -1MS132-AO
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 1, 2022, the inspectors presented the design basis assurance inspection (programs) results to Dave Sharbaugh, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
21SW17
Midas Calc Results 21SW17
Revision 4
2RH1
Midas Calc Results 2RH1
Revision 4
Calc # S2SW -
2SW122
ACE Calculation for S2SW -22SW122 Salem Unit 2
Revision 0
Calc S1MS -
1MS132
ACE Calcuation for S1MS-1MS132 - Salem Unit 1
Revision 0
Calc S1SW-
2SW39
ACE Calculation for S1SW-12SW39
10/22/2022
S-C-MS-NDC-
2136
1/2 MS and Turbine Bypass Aux Fd Pmp Turb. S
2/23/14
Corrective Action
Documents
A00122412
Corrective Action
Documents
Resulting from
Inspection
20920684
20921147
20921148
20921237
20921238
20922280
20922286
20922980
20924049
Engineering
Evaluations
ES.18.006 (Q)
Selection of TOL Heater Elements Units 1 and 2, Safety
Related MOVs
Revision 0
S-C-SW-MDC-
2365
Service Water System Normal Operation
Revision 0
Miscellaneous
S-C-ZZ-SDC-
1419
Salem Generation Station Environmental Design Criteria
Revision 0
S-EPM-GEN-066
MOV Gear Case Lube Inspection and Stem Lubrication
Revision 12
ACE Data Sheet S2SW-25SW223
11/2/2022
Work Orders
30043843
30126192
30131853
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
30151338
30172250
30172487
206980
207071
254188
254211
279106
50104254
50167219
220540
224451
224812
236141
236862
237297
60149339