ML21125A285
Text
Entergy Nuclear Operations, Inc Palisades Nuclear Plant 27780 Blue Star Memonal Highway Covert, Ml 49043 Tel 269 764 2000 Darrell W Corbin Site Vice President 10 CFR 50.71(e) 10 CFR 50.4(b)(6)
PNP 2021-008 April 14, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Final Safety Analysis Report Update - Revision 35 Palisades Nuclear Plant Docket 50-255 Renewed Facility Operating License No. DPR-20 In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Sections 50.71 (e) and 50.4(b)(6}, Entergy Nuclear Operations, Inc. (Entergy) is providing the Palisades Nuclear Plant (PNP) Final Safety Analysis Report (FSAR) update, Revision 35.
This FSAR update is provided in its entirety on the CD-ROMs in the enclosures. Revision 35 changes, with the exception of typographical corrections and format changes, are denoted by vertical lines in the outboard margins of the text. All changes, other than those involving typographical corrections, fortnat changes, and removed information, were made under the provisions of 10 CFR 50 or in accordance with safety evaluations received from the Nuclear Regulatory Commission (NRC). The FSAR update incorporates changes made to the facility or the procedures described in the FSAR, and all other applicable information and analyses submitted to the NRC or prepared pursuant to NRC Requirements, up to the end of the PNP 1R27 refueling outage on October 20, 2020. contains a list of changes made in the FSAR revision.
For this FSAR update, no information has been removed in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," as endorsed by Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e).D contains a public version of the updated FSAR (Revision 35), with certain information redacted in accordance with NRC Regulatory Issue Summary (RIS) 2015-17, "Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents."
PNP 2021--008 Page2 Enclosure 3 contains a non-public version (non-redacted) of the updated FSAR (Revision 35).
This enclosure contains security-related information, and Entergy requests that this enclosure be withheld from public disclosure under 10 CFR 2.390, "Public Inspections, exemptions, and requests for withholding," paragraph (d)(1).
This letter contains no new regulatory commitments and no revised commitments.
If there are any questions concerning this letter, or additional information is required, please contact Monica Peak at 269-764-2722.
I declare under penalty of perjury that the foregoing is true and correct. Executed on April 14, 2021.
Respectfully,
~i/ 2 DWC/mrp Enclosure 1: Palisades Nuclear Plant Final Safety Analysis Report (FSAR)
Revision 35 List of Changes Enclosure 2: CD-ROM Containing Final Safety Analysis Report - Revision 35 (Public Version)
Enclosure 3: CD-ROM Containing Final Safety Analysis Report - Revision 35 (Non-Public Version) (Security-Related Information, Withhold Under 10 CFR 2.390) cc: NRC Region Ill Regional Administrator (w/o Enclosure 2)
NRC Project Manager, Palisades Nuclear Plant (w/o Enclosures 2 and 3)
NRC Senior Resident Inspector, Palisades Nuclear Plant (w/o Enclosure 2)
ENCLOSURE 1 PNP 2021-008 PALISADES NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT (FSAR) REVISION 35 LIST OF CHANGES 10 Pages Follow
PNP 2021-008 Page 1 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change Section 9.10-3, These changes are reflected in EC 56669 which provides new breakers and 15-0028 Figure 8-5, sheet 1 manually operated control switches in main control room (MCR) panel EC-11A, which allows the operator to trip the pumps during fire scenarios of interest.
This figure was revised per EC74582 to install fuses in the ammeter circuit for EAi-18-004 Figure 8-7, sheet 1 45, to reduce the risk of secondary fire in the cable spreading room as described in OE ICES-305419 and documented in Palisades CR-PLP-2013-04817.
18--028 Figure 9-11, sheet 3 The figure was revised under EC77915 to remove the words "and Vestibule" from the Support Building Lobby wet sprinklers description.
PNP 2021-008 Page 2 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change EC-80404 documents Phase 2 of the Switchyard Upgrade bemg performed by the Transmission Operator, ITC. The major changes being made in the switchyard are:
- A new 33 row will be built that includes one line and two breakers
- The Covert line will be moved from RH31 to RH33. Associated line and breaker relaying will be located on new panels in the ITC Section 8-2, Control Center.19-001 Figure 8-2,
- The Roosevelt line will be moved from FH31 to RH31. Associated Figure 2-2 line and breaker relaying will be located on new panels in the ITC Control Center.
- The Segreto #3 lme will terminate at Position FH31 .
- Associated line and breaker relaying will be locat~ on new panels in the ITC Control Center.
EC-80404 updates the referenced figures in the FSAR to document the changes completed by the Transformer Operator, ITC.
EC81007 evaluated changing the frequency for testing Capsule W-80 per 10 CFR 50 Append IX H. The requested revision of reactor vessel material surveillance capsule was submitted to the NRC by letter dated June 24, 2019, ADAMS Accession No. ML19175A102. This request proposed withdrawing Capsule W-80 Chapter 4 Reference, (the fifth capsule) from the schedule.19-003 Table 4-20 Surveillance capsules are withdrawn and tested periodically as designed in the withdrawal schedule. Appendix H requires that the proposed schedule be approved prior to implementation. These changes were approved by the NRC in a letter dated December 2, 2019, ADAMS Accession No. ML19318E394.
PNP 2021-008 Page 3 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change These changes reflected in EC81490, which permanently abandons and isolates ;
the fuel oil line HB-5-1 downstream of MV-FO111. This valve isolates the fuel line which feeds M-8 and M-61, plant heating boilers, which are not safety related. MV-Section 9.8.2.1, FO111 is safety related and the design function per Procedure 9.30 (Q-list) is to 19-006 "prevent inadvertent diversion of Emergency Diesel Generator fuel oil supply." This Figure 8.11 change permanently ISOiates the piping downstream of this valve, therefore the safety function of MV-FO111 is not adversely affected.19-008 Figure 9.11, sheet 2 FSAR Figure 9.11 sheet 2 was updated to show the plant's as-built configuration per EC83505. This is an editorial change.
PNP 2021-008 Page 4 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change EC83306 incorporates a revision to the design basis Main Steam Line Break (MSLB) core response analysis (FSAR 14.14). The current MSLB analysis utilizes the Modified Barnett Critical Heat Flux (CHF) correlation to determine the Minimum Departure from Nucleate Boiling Ratio (MDNBR). The revised MSLB analysis utilizes three CHF correlations to cover the range of boundary conditions: Barnett, Biasi, and HTP The revised MSLB analysis, like the previous revision, demonstrates that DNB does not occur for MSLB events. The MSLB event is analyzed to assess the Section 14.1-6, potential for fuel failure due to a departure from nucleate boiling (DNB). A critical 14.1-8, heat flux correlation is used in the analysis to obtain the minimum DNB ratio 14.10-5 (MDNBR) - the ratio of the heat flux at the predicted core conditions that would 14.14-2 result in DNB to the actual heat flux at those conditions. This ratio is verified to be 19--009 above the CHF correlation limit, which includes appropriate uncertainties at an 14.14-10 14.16-6 appropriate confidence interval (i.e.,. 95/95), to ensure the MSLB event does not Table 14.1-1, result in fuel failures due to DNB.
14.1-5 This update revises the discussions of CHF correlations used, clarify the DNB correlation 95/95 limits, reflect the results of the revised MSLB DNB core response analysis, and to reference the revised Cycle 27 safety evaluation.
Portions of this EC were changes that were reviewed under the provisions of 10 CFR 50.59 but have not been previously submitted to the NRC. The 10 CFR 50.59(c)(2) review concluded that the change to use three CHF (Modified Barnett, Biasi, and HTP) instead of one (Modified Barnett) is not a departure from a method of evaluation described in the UFSAR. The change is a change to a method that has been approved by NRC for the intended application.
EC84050 Is an administrative EC to renumber C-903A and C-903B to read C-19-010 Figure 8-1, sheet 1. 912A and C-912B to match the as-built configuration of the plant. Reference EC-63597 (CR-PLP-2019- 02542) for approval, implementation and closure.
PNP 2021-008 Page 5 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change 19-017 Chapter 7, Appendix 7.C, page 3 This is an editorial change of the appendix. It was identified that the Chapter 14 setpoint values all reference "PSIA," and the appendix references PSIG in error EC(s) 84321, 84322, 84323 and 84326 were created to disconnect the thrust Section 10.2.3 3, bearing trips from both Main Feedwater pump turbines. EC84321 is the base EC 19-018 Figure 9-13 for these changes. Resulting from this change, FSAR Section 10.2.3 and Figure 9-13 were updated to show the plant's current configuration.
License Amendment Request 268, Revision to Diesel Generator Undervoltage Start Surveillance Requirement, was accepted by the NRG on May 13, 2019, (ADAMS Accession No. ML19107A053). This Amendment revises TS 3.3.5, "Diesel Generator (DG)- Undervoltage start (UV Start)," Surveillance Requirement (SR) 3 3.5.2a by adding channel calibration requirement for the 19-019 Figure 7-14, sheet 3 combined delay set points for the degraded voltage sensing relay and the degraded voltage time delay relay.
Under EC84680, Figure 7-14, sheet 3 was updated to reflect relay time delay values of certain undervoltage relays and timers from .5 second to .65 second.
PNP 2021-008 Page 6 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change The NRC approved Palisades Technical Specification Amendment No. 271 dated December 30, 2019, (ADAMS Accession No. ML19317D855), which adopts an industry standard technical specification change, TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b"19-020 Section 12.3 1 and 12.3.3 Implementation of Amendment No. 271 requires revision to UFSAR Section 12.3, "Plant Procedures." Section 12.3 is revised to reflect that TS Amendment No. 271 adopted a Surveillance Frequency Control Program (SFCP) at Palisades, and that
' revisions to Surveillance Requirement (SR) Frequencies included in the SFCP, made in accordance with the SFCP, are considered to have been previously approved as a part of License Amendment No. 271.19-022 Figure 9-1, sheet 2 EC84869 identifies a discrepancy in a plant drawing This editorial change corrects the plant drawing to show the plant's as-built configuration.
EC85708 evaluated the change in position from open to closed for valves MV-20-002 Figure 11-1, sheet 18 CA147 and MV-CA148. FSAR Figure 11-1, sheet 18 has been updated to reflect the valves position.
It was identified that FSAR table 9-21 incorrectly identifies Diesel Generator Fuel 20-003 Table 9-21 Oil Day Tank room as FA-9. This editorial change revises the room number to the correct room number.
EC84561 decreases the normal operating pressure of the intermediate pressure letdown piping that letdown heat exchanger inlet safety valve RV-2006 is located 20-004 Table 9-18, page 3 on from 460 psig to 410 psIg. UFSAR table 9-18 was updated to change the normal downstream pressure for Letdown Orifices R0-2003, RO-2004 and RO-2005 from 470 psia to 425 psia.
PNP 2021-008 Page 7 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change 20-005 Figure 9-13 This change updates Figure 9-13 to read, "Aux Feedwater pump drain to turbine sump." The change is editorial and provides additional description and clarification.
This change is due to the site updating "Containment Structural Integrity Program 20-006 Section 5.8.10 Section* to revision 2, which replaces ASME code "2004 Edition* with ASME code "2013 Edition."20-008 Section 9.10, page 3 This change incorporates two, nearly identical paragraphs into one. This is an UFSAR-only change. (refonnatting)
Chapter 4 References, EC86031 modif1Cation added two new valves and a sample line to the Primary Section 4.3.1, Coolant System (PCS). The EC also added a different system manual alignment 20-009 Section 4.7, for the PCS to allow for capturing Primary Coolant Pump vapor seal leakage in Figure 11-1, sheet 2 order to quantify and designate the leakage as identified.
During 2020 Design Basis Assurance Inspection, it was identified that Section Chapter 9 References, 9 5.2.5 implies that there is a mitigating function for the High-Pressure Air 20-010 Section 9.5.2 compressors that is not consistent with other sections of the FSAR EC87301 updates to this section provide clarification on the High-Pressure Air system response function in the case that a small break LOCA concurrent wtth a loss of offsite power occurs. (CR-PLP-2020-0888 )
PNP 2021-008 Page 8 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change Wrth the approval of Technical Specification Amendment No. 271, dated December 30, 2019, (ADAMS Accession No. ML19317D855), which adopts an industry standard technical specification change, TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b." A review of Surveillance Test frequencies was performed for RT-BC, "Engineering Safeguards System- Left 20-011 Chapter?, Appendix?A, ?A.1.1.1 Channel," and RT-BD, "Engineering Safeguard System - Right Channel." The surveillance frequencies were updated from "every" outage to "one test performed each refueling outage on a staggered frequency."
The corresponding page, Appendix 7A, 7A.1.1.1, was updated in the FSAR to reflect the frequency change.
Chapter 14 Table of Contents, Section 14.1 Table 14.1-4 Table 14.1-5 20-012 Chapter 14 Section 14.16 References Chapter 3 Section 3.3 EC-82400, Cycle 28 Reload Core Design Evaluation, updates Chapter 3 and Chapter 3 Reference Page 3-3 Chapter 14 sections, tables, and references to reflect the Cycle 28 reload core design.
EC88034 permanently moved two environmentally qualified incore cables from two 20-014 Chapter 7, Appendix ?C alternate incore positions, due to a failure to insert into their normal positions during 1R27. Appendix 7C was revised to reflect the alternate incore positions.
PNP 2021-008 Page 9 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, '
Log No. Figures, and Tables Description of Change EC87981 modified control rod drive mechanism nozzles 17 and 34 due to Section 4.3-4, indications found during the 2020 refueling outage. Modifications were performed Section 4.5-13 in accordance wrth relief request RR 5-8, which was verbally authorized by the 20-015 Table 4-3 NRC on October 181 , 2020, as documented in NRC letter dated January 19, 2021, Table 4-15 (ADAMS Accession No Ml.20365A001) . The FSAR sections and table were revised to reflect nozzle modifications.
EC88118 removes MV-SW884, a 1/4" needle valve that was installed at the exhaust 20-016 Figure 9-1, Sheet 1 B port of SV-0847, which in tum slowed the opening of CV-0847 to mitigate water hammer concerns. This change updates Figure 9-1, Sheet 1B to remove MV-SW884.
In June and July of 2020, the recorded monthly mean Lake Michigan elevation at Section 2.2, Calumet Harbor, IL, exceeded the elevation assumed in the external flood hazard.20-017 Section 2 References, EC-87802 provides formal documentation of the increased design basis elevation Section 5.4 and changes the appropnate FSAR sections to reflect the increased elevation and remaining margin available This change corrects a latent error for the Tube Side (letdown) flows In the Operating Parameter- Regenerative Heat Exchanger and in the Operating 20-019 Table 9-18 Parameters - Letdown Heat Exchanger of table 9-18. The error was determined to be a latent error for the incorrect conversion from mass flow rate (lb./hr.) to volumetric flow rate (gpm) during revision 18 of this table. The discrepancy was corrected and documented in CA-33 of WT-WTPLP-20 20-00002 and EC-88411.
Figure 1-2,20-020 Figure 1-4, EC-88292 updates detailed drawings, Figure 1-2, 1-4 and 1-7 to show the correct Figure 1-7 location of F-56.
PNP 2021-008 Page 10 of 10 Palisades Nuclear Plant Final Safety Analysis Report (FSAR) Revision 35 List of Changes Affected FSAR Sections, Log No. Figures, and Tables Description of Change It was identified that the value at the bottom of the tabulation (Section 5.8.5.3.1) is20-021 Section 5.8.5.3.1 incorrectly shown as 43.0Ksi. This error is an editorial transcription from previous FSAR changes. The number was correctly shown in a previous FSAR version.
This change is editorial.
Figure 1-12, Sheet 1, EC62996 replaced ~2. Turbine Analyzer Panel, with a newer version of the 21-003 Figure 8-7, Sheet 2, panel, upgrading all connections, data logging components and removing previous Figure 11-5, Sheet 18 panel forms of local annunciation and data logging components. This change updates Figure 1-12, sheet 1, Figure 8-7, sheet2 and Figure 11-5, sheet 18.
ENCLOSURE 2 PNP 2021-008 CD-ROM CONTAINING FINAL SAFETY ANALYSIS REPORT - REVISION 35 (PUBLIC VERSION) 1 CD-ROM Enclosed
ENCLOSURE 3 PNP 2021-008 CD-ROM CONTAINING FINAL SAFETY ANALYSIS REPORT - REVISION 35 (NON-PUBLIC VERSION)
(SECURITY-REL ATED INFORMATION, WITHHOLD UNDER 10 CFR 2.390) 1 CD-ROM Enclosed