IR 05000255/2019011
| ML19336C651 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/27/2019 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Corbin D Entergy Nuclear Operations |
| References | |
| IR 2019011 | |
| Download: ML19336C651 (8) | |
Text
November 27, 2019
SUBJECT:
PALISADES NUCLEAR PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000255/2019011
Dear Mr. Corbin:
On November 1, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant and discussed the results of this inspection with Mr. Dale Lucy and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
Docket No. 05000255 License No. DPR-20
Enclosure:
As stated
Inspection Report
Docket Number:
05000255
License Number:
Report Number:
Enterprise Identifier: I-2019-011-0048
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Palisades Nuclear Plant
Location:
Covert, MI
Inspection Dates:
October 28, 2019 to November 01, 2019
Inspectors:
J. Neurauter, Senior Reactor Inspector
G. O'Dwyer, Reactor Engineer
D. Szwarc, Senior Reactor Inspector
Approved By:
Robert C. Daley, Branch Chief
Engineering Branch 3
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Palisades Nuclear Plant 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
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for Title 10 of the Code of Federal Regulations (10 CFR) 50.59 from 2016 to 2019.
(1)17-0122, Changes to Technical Specification Bases 3.8.3 Concerning the Fuel Oil Transfer System, Revision 0 (2)19-021, EC 76687 / V24A/B/C/D Emergency Diesel Generator Room Ventilation Fans Modify Control Circuit to Resolve CR-PLP-2016-03456, Revision 0 (3)19-022, EC 76688 / V-27A/B/C/D Engineering Safeguards Room Ventilation Fans Modify Circuit to Resolve CR-PLP_2016-03456, Revision 0 (4)17-0030, EC 44749 - Calculation Spent Fuel Pool Dilation Analysis (Calculation EA-WJB-00-01 Revision 2), Revision 0 (5)16-0230, MSM-M-29, Lifting Equipment, Rigging and Tackle Inspection, Revision 0 (6)17-0060, EN-QV-137, Supplier Commercial Grade Survey Procedure, Revision 0 (7)17-0193, EN-DC-214, Freeze Seal Evaluations, Revision 0 (8)18-0191, EN-MA-159, Concrete Anchor Bolt Installation, Revision 0 (9)19-0093, EC 82734 - Temporary Modification to Block CV-3223, Shutdown Cooling Heat Exchanger Inlet Valve, Open during VOP-3223 Removal for Overhaul, Revision 1 (10)16-0201, Licensing Basis Document Change Request (LBDCR 16-048) for Final Safety Analysis Report Section 5.5, Revision 0 (11)18-0090, Technical Specifications Bases Limiting Condition for Operation 3.7.6, Revision 0 (12)17-0094, EC [Engineering Change] 72434: TSR [Temporary Shielding Request]
2017-095 "P-55B Charging Pump Discharge Line (Elbow on South End and Support Bracket Above FE-0212):, Revision 0 (13)19-028, EC 81574 Evaluate Station Battery Remaining Life Capacity Relative to Ambient Temperature, Revision 0 (14)16-0248, Revise RT-35, Inservice Inspection of Safety Related Components, Revision 0 (15)17-0081, EC 1743, 1R25 Flow Accelerated Corrosion Evaluations, Revision 0 (16)17-0089, Long Term Scaffold 17-026 in 607 Component Cooling Water, Revision 0 (17)17-0139, ACADIA 4 Software Application, Revision 0 (18)18-0135, EC 78263, Revise Calculation EA-GL-8910-02 Torque Loss Calculation for Motor Operated Valves at Elevated Temperatures, Revision 0 (19)18-0143, EC 78472, Temporary Leak Repair of Two 2 Elbow Fittings on Steam Trap Drain Line Upstream of MV-CD190, Isolation Valve for Condensate Return from Main Steam Lines Steam Traps, Revision 0 (20)19-0018, EN-CS-S-008-MULTI, Pipe Wall Thinning Structural Evaluation, Revision 0 (21)19-0046, EC 82059, MO-3010 Spring Hanger, Reconcile Setting, Revision 0 (22)16-0110, EAR [Engineering Assistance Request] 199-0081, "Chemical and Volume Control Declassification", Revision 0 (23)19-0010, Revision of EN-DC-315, Rev 15, Flow Accelerated Corrosion Program; Revision 0 (24)19-0034, change to FSAR Section 9.4.2.1, System Description, to add floating filter used to clear spent fuel pool water; Revision 0 (25)19-0056, COP-2, Chemical and Volume Control System Chemistry, Revision 67; Revision 0 (26)19-0113; Procedure Change SOP-24, Ventilation and Air Conditioning System; Revision
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 1, 2019, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Dale Lucy and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.17T Calculations
EA-EC171743-01
Flow Accelerated Corrosion, 1R25 Non-Safety Related Wall
Thinning Evaluations
EA-EC171743-02
Flow Accelerated Corrosion, 1R25 Safety Related Wall
Thinning Evaluations
EA-EC171743-03
Engineering Analysis of Component ES-GB-2-E023
EA-WJB-00-01
Spent Fuel Pool Dilution Analysis
Corrective Action
Documents
CR-PLP-2016-
01143
Licensing Review of the NRC 4th Quarter 2015 Integrated
Inspection Report
03/07/2016
CR-PLP-2016-
05054
Temporary Shield Requests for the Charging Pump Cubicles
Beyond Allowed Installation Time
10/21/2016
CR-PLP-2017-
00364
Documentation Deficiencies in Process Applicability
Determination Forms
01/30/2017
CR-PLP-2017-
225
Legacy Shielding Installed in Evaporator Concentrate Tank
and Pump Rooms
09/14/2017
CR-PLP-2019-
00387
Remove Temporary Measuring and Test Equipment within
Days of Installation Or Perform 50.59 Screening for
Measuring and Test Equipment to Remain Installed Beyond
Days
01/24/2019
CR-PLP-2019-
01872
ADMIN 7.14 Does Not Address Extending Temporary
Shielding Request Beyond Approved Duration
05/07/2019
CR-PLP-2019-
03552
Pre-NRC Inspect Audit Identified, Identified Improperly
Completed Process Applicability Determination
09/10/2019
WT-WTPLP-
2017-00011
Evaluate Addressing Maintaining the Seismic Adequacy of
the Chemical and Volume Control System
01/31/2017
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2019-
04362
PAD Log Number 17-0139 had Incorrect Boxes Checked
10/30/2019
CR-PLP-2019-
04379
Calculation Incorrectly Set to Historical in Electronic
Database
10/31/2019
CR-PLP-2019-
04381
Configuration Enhancements were Identified Related to
Seismic Requirements in the Equipment Database
10/31/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
76687
V-24A/B/C/D Emergency Diesel Generator Rooms
Ventilation Fans Modify Control Circuit to Resolve CR-PLP-
2016-03456
76688
V-27A/B/C/D Engineered Safeguards Rooms Cooler Fans
Modify Control Circuit to Resolve CR-PLP-2016-03456
2059
MO-3010 Spring Hanger, Reconcile Setting Basis
Miscellaneous
Licensing Basis
Document
Change Request
16-048
Revise Final Safety Analysis Report Section 5.5.1 to Delete
Site Specific Tornado Missiles
10/06/2016
Licensing Basis
Document
Change Request
17-0010
Clarify Section 5.5.1 of Final Safety Aanalysis Report
(Tornado Missiles) to Accurately Reflect Licensing and
Design Bases of Plant
04/24/2017
Procedures
EN-CS-S-008-
MULTI
Pipe Wall Thinning Structural Evaaluation
Freeze Seal Evaluations
Process Applicability Determination
Control, Storage, and Inspection of Lifting Equipment
Anchor Bolt Installation
Supplier Commercial Grade Survey Procedure
Work Orders
2705342-01
Spent Fuel Pool Level and Temperature Instrument
Checkout
01/02/2018
2750453-01
LE/LI-2141 Pre-Refuel Outage Functional Check
09/21/2018
2750454-01
LE/LI-2142 Pre-Refuel Outage Functional Check
09/21/2018
2837472-01
LE/LI-2141 Channel Functional Check
08/20/2019
2837473-01
LE/LI-2142 Channel Functional Check
09/16/2019