IR 05000354/2022012
| ML22251A047 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/08/2022 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Carr E Public Service Enterprise Group |
| Gray M | |
| References | |
| IR 2022012 | |
| Download: ML22251A047 (8) | |
Text
September 8, 2022
SUBJECT:
HOPE CREEK GENERATING STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000354/2022012
Dear Eric Carr:
On August 3, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Hope Creek Generating Station and discussed the results with Edward Casulli 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, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket No. 05000354 License No. NPF-57
Enclosure:
As stated
Inspection Report
Docket Number:
05000354
License Number:
Report Number:
Enterprise Identifier: I-2022-012-0008
Licensee:
Facility:
Hope Creek Generating Station
Location:
Hancocks Bridge, NJ
Inspection Dates:
July 11, 2022 to August 3, 2022
Inspectors:
P. Cataldo, Senior Reactor Inspector
J. Kulp, Senior Reactor Inspector
A. Patel, Senior 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) inspection at Hope Creek Generating Station, 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 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. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) High Pressure Coolant Injection (HPCI) Pump Outboard Discharge Isolation Valve (H1BJ-BJ-JV-F006)
- (2) Turbine Auxiliary Cooling B Inboard Supply Isolation Valve (H1EG-EG-HV-2522B)
- (3) Reactor Core Isolation Cooling Turbine Steam Line Drain Valve (H1FC-FC-HV-F025)
- (4) Containment Instrument Gas Supply Header Cross Connect Isolation Valve (H1KL-KL-5156A)
- (5) Scram Discharge Volume Inboard Vent Valve (H1BF-BF-HV-F010)
- (6) Containment Hardened Vent Valve (GSHV-11541)
- (7) Main Steam Drain Line Isolation Valve (H1AB-AB-HV-F019)
- (8) HPCI Lube Oil Cooling Water Motor Operated Valve (H1BJ-BJ-JV-F059)
- (9) D Service Water Pump Discharge Valve (H1EA -EA-HV-2198D)
- (10) HPCI Turbine Steam Supply Valve (H1FD -FD-HV-F001)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 3, 2022, the inspectors presented the design basis assurance inspection (programs) results to Edward Casulli and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
Midas Calc Results 1BJ-HV-F006
Revision 5a
EG-0046
STACS Operation
Revision 10
H1FC -FC-HV-
F025
ACE Calculation for H1FC -FC-HV-F025
Revision 0
H1KL -KL-HV-
5156A
ACE Calculation for H1KL -KL-HV-5156A
Revision 0
Corrective Action
Documents
20875479
Corrective Action
Documents
Resulting from
Inspection
20908912
20910472
20910478
20910479
20910499
20910500
20910508
20910610
20910783
20910945
20911103
20911109
20911189
20911206
20911657
Miscellaneous
2A6237AB
High Pressure Coolant Injection System Design Spec
Data Sheet
Revision 1
Procedures
Motor Operated Valve Performance Trending
Revision 6
Air Operated Valve Testing Requirements
Revision 8
HC.OP-IS.BJ-
0101(Q)
High Pressure Coolant Injection System Valves -
Inservice Test
Revision 73
HC.OP-LR.AB-
0005(Q)
Containment Isolation Valve Type C Leak Rate Test CIVs
1ABHV-F016 and 1ABHV-F019 Penetration P12: Main
Revision 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Steam Line Drain
Work Orders
30179718
210838
216105
216349