IR 05000255/2019011: Difference between revisions

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{{Adams
{{Adams
| number = ML19210D402
| number = ML19336C651
| issue date = 07/29/2019
| issue date = 11/27/2019
| title = Ltr. 07/29/19 Palisades Nuclear Plant - Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000255/2019011 (DRS-D.Szwarc)
| title = Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000255/2019011
| author name = Szwarc D
| author name = Daley R
| author affiliation = NRC/RGN-III/DRS
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = Arnone C
| addressee name = Corbin D
| addressee affiliation = Entergy Nuclear Operations, Inc
| addressee affiliation = Entergy Nuclear Operations, Inc
| docket = 05000255
| docket = 05000255
Line 12: Line 12:
| document report number = IR 2019011
| document report number = IR 2019011
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter
| page count = 6
| page count = 8
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:uly 29, 2019
{{#Wiki_filter:ber 27, 2019


==SUBJECT:==
==SUBJECT:==
PALISADES NUCLEAR PLANTINFORMATION REQUEST FOR NRC TRIENNIAL EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS (50.59)
PALISADES NUCLEAR PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000255/2019011
BASELINE INSPECTION; INSPECTION REPORT 05000255/2019011


==Dear Arnone:==
==Dear Mr. Corbin:==
On October 28, 2019, the U.S. Nuclear Regulatory Commission (NRC) will begin a 50.59 Baseline Inspection at the Palisades Nuclear Plant. This inspection will be performed in accordance with the NRC baseline Inspection Procedure 71111.17T. The onsite portion of the inspection will take place during the week of October 28, 2019.
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.


Experience has shown that these baseline inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection. These documents have been divided into three groups.
The NRC inspectors did not identify any finding or violation of more than minor significance.


* The first group of information is necessary to ensure that the inspection team is adequately prepared for the inspection. This information should be made available via CD and delivered to the regional office no later than September 16, 2019. The inspection team will review this information and, by September 30, 2019, will request specific items that should be provided for review in the regional office by October 14, 2019.
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.
 
* The second group of requested documents contains additional items that the team will review, or need access to, during the inspection. Certain documents contained within Group II (i.e., Item (1)), will be requested for review in the regional office prior to the inspection by October 14, 2019, as identified above. The remaining documents should be available by the first day of the onsite inspection, October 28, 2019.
 
* The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
 
C. Arnone  -2-The lead inspector for this inspection is Mr. Dariusz Szwarc. We understand that our regulatory contact for this inspection is Ms. Barb Dotson of your organization. If there are any questions about the inspection or the material requested, please contact the lead inspector at 630-829-9803 or via e-mail at Dariusz.Szwarc@nrc.gov.
 
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
 
This letter and its enclosure 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, Part 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely,
Sincerely,
/RA Alan Dahbur Acting for/
/RA/
Dariusz Szwarc, Senior Reactor Inspector Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-255 License No. DPR-20 Enclosure:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 05000255 License No. DPR-20
Document Request for 50.59 Inspection cc: Distribution via LISTSERV
 
C. Arnone  -3-Letter to Charles Arnone from Dariusz Szwarc dated July 29, 2019.
 
SUBJECT: PALISADES NUCLEAR PLANTINFORMATION REQUEST FOR NRC TRIENNIAL EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS (50.59)
BASELINE INSPECTION; INSPECTION REPORT 05000255/2019011 DISTRIBUTION:
Douglas Dodson RidsNrrPMPalisades Resource RidsNrrDorlLpl3 RidsNrrDirsIrib Resource Darrell Roberts John Giessner Jamnes Cameron Allan Barker DRPIII DRSIII ADAMS Accession Number: ML19210D402 OFFICE RIII NAME ADahbur for DSzwarc:cl DATE 07/29/19 OFFICIAL RECORD COPY
 
DOCUMENT REQUEST FOR 50.59 INSPECTION Inspection Report:  05000255/2019011 Inspection Dates:  October 28, 2019, through November 1, 2019 Inspection Procedure: 71111.17T, Evaluations of Changes, Tests, and Experiments Lead Inspector:  Dariusz Szwarc 630-829-9803 Dariusz.Szwarc@nrc.gov I. Information Requested for In-Office Preparation Week The following information is requested by September 16, 2019, or sooner, to facilitate the selection of specific items that will be reviewed during the onsite inspection week.
 
The inspection team will select specific items from the information requested below and submit a list to your staff by September 30, 2019. We will request that certain items be made available to the regional office prior to the inspection by October 14, 2019. We request that the remaining items selected from the lists be available and ready for review on the first day of inspection. All requested information should identify the associated system and cover the time frame from the receipt of information for the last MOD/50.59 inspection to the present.
 
The required information identified below should be provided on CD. Please provide three copies of each CD submitted (i.e., one for each inspector). The preferred file format is a searchable pdf file. The CDs should be indexed and hyper-linked to facilitate ease of use, if possible. If you have any questions regarding this information, please call the inspection team leader as soon as possible.
 
(1) List of all Title 10 of the Code of Federal Regulations (CFR), Part 50.59 completed evaluations involving (a) calculations, (b) procedure revisions, (c) changes to the facility (modifications), (d) non-routine operating configurations, or (e) departures in methods of analyses. This list should include 50.59 evaluations for the following:
a. Changes that have been made under the provisions of 10 CFR 50.59 that have been updated in accordance with 10 CFR 50.71(e)(4) since the last MOD/50.59 inspection; b. Modifications that are field work complete; and c. Changes to calculations (or initiation of new calculations) that have been issued. The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies). The list should NOT include any evaluations in which prior U.S. Nuclear Regulatory Commission approval was sought and obtained.
 
Enclosure
 
DOCUMENT REQUEST FOR 50.59 INSPECTION (2) A list of all 10 CFR 50.59 changes that have been screened out as not requiring a full evaluation involving: (a) calculations; (b) procedure revisions; (c) changes to the facility (modifications); (d) non-routine operating configurations; or (e) departures in methods of analyses.
 
The list should contain the number and title of each document, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies).
 
(3) A list of any modifications, procedure revisions, or Updated Final Safety Analysis Report (UFSAR) changes where it was determined that 10 CFR 50.59 did not apply.
 
(4) A list of calculation changes that have been issued for use.
 
(5) A list of corrective action documents (open and closed) that address 10 CFR 50.59 issues, concerns, or processes. These documents should also include the corrective action documents associated with the modification and the 50.59 change implementation.
 
The list should contain the number, title and revision (or date) of each document, the affected system and corresponding documentation (if applicable), and should be sorted in order of significance.
 
(6) Copies of procedures addressing the following: modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modification testing, 10 CFR 50.59 evaluations and screenings, and UFSAR updates.
 
(7) UFSAR updates submitted in accordance with 10 CFR 50.71(e)(4). Provide copies of the complete submittal.


(8) Copy of the UFSAR change log or a synopsis of the changes. This should include all of the changes made to the UFSAR that were incorporated in the last 10 CFR 50.71(e)(4) submittal.
===Enclosure:===
As stated


(9) Electronic copy of the UFSAR and technical specifications, if available.
==Inspection Report==
Docket Number: 05000255 License Number: DPR-20 Report Number: 05000255/2019011 Enterprise Identifier: I-2019-011-0048 Licensee: Entergy Nuclear Operations, Inc.


(10) Name(s) and phone numbers for the regulatory and technical contacts.
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 Enclosure


(11) Current management and engineering organizational chart.
=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.


II. Information Requested to be Available Prior to Inspection. Requests will be Made for Specific Item (1) Documents by September 30, 2019 for Availability of Requested Item (1) Documents in Regional Office by October 14, 2019, and Items (2), (3) and (4) Documents on First Day of Inspection (October 28, 2019).
List of Findings and Violations No findings or violations of more than minor significance were identified.


(1) Copies of all selected items from Section I. This includes copies of associated documents such as calculations, modification packages (including description), 10 CFR 50.59 evaluations or screenings, and any corrective action documents
Additional Tracking Items None.


DOCUMENT REQUEST FOR 50.59 INSPECTION (2) Copies of these documents do not need to be solely available to the inspection team as long as the inspectors have easy and unrestrained access to them.
=INSPECTION SCOPES=


a. Updated Final Safety Analysis Report, if not previously provided; b. Original FSAR Volumes; c. Original SER and Supplements; d. Final Safety Analysis Report Question and Answers; e. Quality Assurance Plan; f. Technical Specifications, if not previously provided; g. Latest IPE/PRA Report; h. Vendor Manuals; and i. The latest 10 CFR 50.59 UFSAR Update Submittal.
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.


(3) Please ensure that other supporting documents for the selected items have been located and are readily retrievable as the inspection team will likely be requesting these documents during the inspection. Examples of supporting documents are:
==REACTOR SAFETY==
a. Drawings supporting the modifications; b. Procedures affected by the modifications; and c. UFSAR change papers generated due to a 10 CFR 50.59 evaluation.


(4) Assessment and Corrective Actions:
===71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01) ===
a. The most recent 50.59 Quality Assurance audit and/or self-assessment; and b. Corrective action documents (e.g., condition reports, including status of corrective actions) generated as a result of the most recent 50.59 Quality Assurance audit and/or self-assessment.
{{IP sample|IP=IP 71111.17|count=26}}
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


III. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the inspection teams questions or queries during this inspection.
==INSPECTION RESULTS==
No findings were identified.


(2) Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provide daily during the inspection to each inspection team member).
==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.


If you have any questions regarding the information requested, please contact the inspection team leader.
=DOCUMENTS REVIEWED=


3
Inspection Type              Designation    Description or Title                                      Revision or
Procedure                                                                                            Date
71111.17T Calculations      EA-EC171743-01 Flow Accelerated Corrosion, 1R25 Non-Safety Related Wall  0
Thinning Evaluations
EA-EC171743-02 Flow Accelerated Corrosion, 1R25 Safety Related Wall      0
Thinning Evaluations
EA-EC171743-03 Engineering Analysis of Component ES-GB-2-E023            0
EA-WJB-00-01  Spent Fuel Pool Dilution Analysis                        2
Corrective Action CR-PLP-2016-  Licensing Review of the NRC 4th Quarter 2015 Integrated  03/07/2016
Documents        01143          Inspection Report
CR-PLP-2016-  Temporary Shield Requests for the Charging Pump Cubicles  10/21/2016
05054          Beyond Allowed Installation Time
CR-PLP-2017-  Documentation Deficiencies in Process Applicability      01/30/2017
00364          Determination Forms
CR-PLP-2017-  Legacy Shielding Installed in Evaporator Concentrate Tank 09/14/2017
225          and Pump Rooms
CR-PLP-2019-  Remove Temporary Measuring and Test Equipment within      01/24/2019
00387          90 Days of Installation Or Perform 50.59 Screening for
Measuring and Test Equipment to Remain Installed Beyond
Days
CR-PLP-2019-  ADMIN 7.14 Does Not Address Extending Temporary          05/07/2019
01872          Shielding Request Beyond Approved Duration
CR-PLP-2019-  Pre-NRC Inspect Audit Identified, Identified Improperly  09/10/2019
03552          Completed Process Applicability Determination
WT-WTPLP-      Evaluate Addressing Maintaining the Seismic Adequacy of  01/31/2017
2017-00011    the Chemical and Volume Control System
Corrective Action CR-PLP-2019-  PAD Log Number 17-0139 had Incorrect Boxes Checked        10/30/2019
Documents        04362
Resulting from    CR-PLP-2019-  Calculation Incorrectly Set to Historical in Electronic  10/31/2019
Inspection        04379          Database
CR-PLP-2019-  Configuration Enhancements were Identified Related to    10/31/2019
04381          Seismic Requirements in the Equipment Database
Inspection Type          Designation    Description or Title                                        Revision or
Procedure                                                                                            Date
Engineering  76687          V-24A/B/C/D Emergency Diesel Generator Rooms                0
Changes                      Ventilation Fans Modify Control Circuit to Resolve CR-PLP-
2016-03456
76688          V-27A/B/C/D Engineered Safeguards Rooms Cooler Fans        0
Modify Control Circuit to Resolve CR-PLP-2016-03456
2059          MO-3010 Spring Hanger, Reconcile Setting Basis              0
Miscellaneous Licensing Basis Revise Final Safety Analysis Report Section 5.5.1 to Delete 10/06/2016
Document        Site Specific Tornado Missiles
Change Request
16-048
Licensing Basis Clarify Section 5.5.1 of Final Safety Aanalysis Report      04/24/2017
Document        (Tornado Missiles) to Accurately Reflect Licensing and
Change Request  Design Bases of Plant
17-0010
Procedures    EN-CS-S-008-    Pipe Wall Thinning Structural Evaaluation                  2
MULTI
EN-DC-214      Freeze Seal Evaluations                                    3
EN-LI-100      Process Applicability Determination                        26
EN-MA-119-01    Control, Storage, and Inspection of Lifting Equipment      9
EN-MA-159      Anchor Bolt Installation                                    1
EN-QV-137      Supplier Commercial Grade Survey Procedure                  2
Work Orders  52705342-01    Spent Fuel Pool Level and Temperature Instrument            01/02/2018
Checkout
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
6
}}
}}

Latest revision as of 22:40, 15 March 2020

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000255/2019011
ML19336C651
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/27/2019
From: Robert Daley
Engineering Branch 3
To: Corbin D
Entergy Nuclear Operations
References
IR 2019011
Download: ML19336C651 (8)
v • d • e


Text

ber 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: DPR-20 Report Number: 05000255/2019011 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 Enclosure

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)

Main article: IP 71111.17

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations EA-EC171743-01 Flow Accelerated Corrosion, 1R25 Non-Safety Related Wall 0

Thinning Evaluations

EA-EC171743-02 Flow Accelerated Corrosion, 1R25 Safety Related Wall 0

Thinning Evaluations

EA-EC171743-03 Engineering Analysis of Component ES-GB-2-E023 0

EA-WJB-00-01 Spent Fuel Pool Dilution Analysis 2

Corrective Action CR-PLP-2016- Licensing Review of the NRC 4th Quarter 2015 Integrated 03/07/2016

Documents 01143 Inspection Report

CR-PLP-2016- Temporary Shield Requests for the Charging Pump Cubicles 10/21/2016

05054 Beyond Allowed Installation Time

CR-PLP-2017- Documentation Deficiencies in Process Applicability 01/30/2017

00364 Determination Forms

CR-PLP-2017- Legacy Shielding Installed in Evaporator Concentrate Tank 09/14/2017

225 and Pump Rooms

CR-PLP-2019- Remove Temporary Measuring and Test Equipment within 01/24/2019

00387 90 Days of Installation Or Perform 50.59 Screening for

Measuring and Test Equipment to Remain Installed Beyond

Days

CR-PLP-2019- ADMIN 7.14 Does Not Address Extending Temporary 05/07/2019

01872 Shielding Request Beyond Approved Duration

CR-PLP-2019- Pre-NRC Inspect Audit Identified, Identified Improperly 09/10/2019

03552 Completed Process Applicability Determination

WT-WTPLP- Evaluate Addressing Maintaining the Seismic Adequacy of 01/31/2017

2017-00011 the Chemical and Volume Control System

Corrective Action CR-PLP-2019- PAD Log Number 17-0139 had Incorrect Boxes Checked 10/30/2019

Documents 04362

Resulting from CR-PLP-2019- Calculation Incorrectly Set to Historical in Electronic 10/31/2019

Inspection 04379 Database

CR-PLP-2019- Configuration Enhancements were Identified Related to 10/31/2019

04381 Seismic Requirements in the Equipment Database

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering 76687 V-24A/B/C/D Emergency Diesel Generator Rooms 0

Changes Ventilation Fans Modify Control Circuit to Resolve CR-PLP-

2016-03456

76688 V-27A/B/C/D Engineered Safeguards Rooms Cooler Fans 0

Modify Control Circuit to Resolve CR-PLP-2016-03456

2059 MO-3010 Spring Hanger, Reconcile Setting Basis 0

Miscellaneous Licensing Basis Revise Final Safety Analysis Report Section 5.5.1 to Delete 10/06/2016

Document Site Specific Tornado Missiles

Change Request

16-048

Licensing Basis Clarify Section 5.5.1 of Final Safety Aanalysis Report 04/24/2017

Document (Tornado Missiles) to Accurately Reflect Licensing and

Change Request Design Bases of Plant

17-0010

Procedures EN-CS-S-008- Pipe Wall Thinning Structural Evaaluation 2

MULTI

EN-DC-214 Freeze Seal Evaluations 3

EN-LI-100 Process Applicability Determination 26

EN-MA-119-01 Control, Storage, and Inspection of Lifting Equipment 9

EN-MA-159 Anchor Bolt Installation 1

EN-QV-137 Supplier Commercial Grade Survey Procedure 2

Work Orders 52705342-01 Spent Fuel Pool Level and Temperature Instrument 01/02/2018

Checkout

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

6

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