L-19-120, Submittal of Revision 21 to Updated Final Safety Analysis Report

Submittal of Revision 21 to Updated Final Safety Analysis Report

ML19298C673
Person / Time
Site:	Perry
Issue date:	10/18/2019
From:	Payne F FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML19298C581	List: L-19-120, Submittal of Revision 21 to Updated Final Safety Analysis Report
References
L-19-120
Download: ML19298C673 (8)

Text

FENOC' Perry Nuclear Power Plant PO. Box 97 10 Center Road Perry, Ohio 44081 FirstEnergy Nuclear Operating Company Frank Payne 440-280-5382 Vice President October 18, 2019 L-19-120 10 CFR 50.71(e) 10 CFR 50.54(a)

ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , DC 20555-001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Submittal of the Updated Final Safety Analysis Report (UFSAR), Revision 21 In accordance with the requirements of 10 CFR 50.71 (e), the FirstEnergy Nuclear Operating Company (FENOC) is hereby submitting to the Nuclear Regulatory Commission (NRC) the Perry Nuclear Power Plant (PNPP) Updated Final Safety Analysis Report (UFSAR), Revision 21, in CD-ROM format. This submittal reflects facility and procedure changes implemented between April 3, 2017 (the end of refueling outage 16), and April 6, 2019 (the end of refueling outage 17), along with several changes implemented after refueling outage 17.

In accordance with 10 CFR 50.4(b)(6), revision 21 of the PNPP UFSAR is submitted electronically on a total replacement basis. As required by NRC guidance for electronic submissions, Attachments 1 and 2 provide a listing of the document components that make up the two enclosed CD-ROMs. In addition to the UFSAR, the first enclosed CD-ROM includes the Technical Specification Bases, revision 12, submitted to satisfy TS 5.5.11, "Technical Specifications (TS) Bases Control Program ," which requires submittal of TS Bases changes implemented without prior NRC approval.

The second enclosed CD-ROM includes the PNPP UFSAR, and TS Bases with information identified 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," removed.

Attachment 3 includes a summary of information removed from the USAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03 , "Guidelines for Updating Final Safety Analysis Reports," Revision 1.

Attachment 4 includes a summary of regulatory commitment changes to be submitted in accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes,"

Revision 0, as endorsed by NRC RIS 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff."

Perry Nuclear Power Plant L-19-120 Page 2 This certifies, to the best of my judgment and belief, that Revision 21 of the PNPP UFSAR accurately presents changes made since the previous submittal that are necessary to reflect information and analysis submitted to the Commission or pursuant to Commission requirements.

This submittal contains no new regulatory commitments. If you have any questions regarding this report, please contact Mr. Phil H. Lashley, Acting Manager - Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.

Frank~. ;:!~

Attachments:

1. List of Document Components on CD-ROM 1

2. List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed)

3. Information Removed from the PNPP UFSAR

4. Commitment Change Summary Report

Enclosures:

A. Perry Nuclear Power Plant UFSAR, and Technical Specification Bases (on CD-ROM 1)

B. Perry Nuclear Power Plant UFSAR With Information Identified Per RIS 2015-17 Removed, and Technical Specification Bases (on CD-ROM 2) cc: NRC Region Ill Administrator (without Enclosure 8)

NRC Resident Inspector (without Enclosure 8)

NRC Project Manager (without Enclosure 8)

Attachment 1 L-19-120 List of Document Components on CD-ROM 1 Page 1 of 2 File Name Size 001 LIST EFF Rev 21.pdf 128 KB 002 Chapter 00.pdf 743 KB 003 Chapter 01.pdf 14,119 KB 004 Chapter 02.0 to 02.4.pdf 14,096 KB 005 Chapter 02.5 to 02E.pdf 38,219 KB 006 Chapter 03.pdf 15,636 KB 007 Chapter 04.pdf 13,498 KB 008 Chapter 05.pdf 13,815 KB 009 Chapter 06.pdf 14,248 KB 010 Chapter 07.pdf 13,885 KB 011 Chapter 08 .pdf 13,630 KB 012 Chapter 09.pdf 15,440 KB 013 Chapter 1O.pdf 13,488 KB 014 Chapter 11.pdf 13,768 KB 015 Chapter 12.pdf 13,744 KB 016 Chapter 13.pdf 13,410 KB 017 Chapter 14.pdf 13,763 KB 018 Chapter 15.pdf 17,359 KB 019 Chapter 16.pdf 57 KB 020 Chapter 17.pdf 67 KB 021 FIG_LIST Rev 20.pdf 257 KB 022 Figures Section 01.pdf 17,397 KB 023 Figures Section 02 (2.1-1 to 2.5-46) .pdf 27,077 KB 024 Figures Section 02 (2.5-47 to 2.5-49).pdf 20,215 KB 025 Figures Section 02 (2.5-50 to 2.5-215).pdf 26,172 KB 026 Figures Section 020-1 to 020-2.pdf 19,648 KB 027 Figures Section 020-3 to 02E-1.pdf 32,280 KB L-19-120 Page 2 of 2 File Name Size 028 Figures Section 03.pdf 38,780 KB 029 Figures Section 04.pdf 1,567 KB 030 Figures Section 05.pdf 4,989 KB 031 Figures Section 06.pdf 7,501 KB 032 Figures Section 07.pdf 10,280 KB 033 Figures Section 08.pdf 3,142 KB 034 Figures Section 09 (9.1-1 to 9.4-29).pdf 18,426 KB 035 Figures Section 09 (9.5-1 to 9.5-26).pdf 4,305 KB 036 Figures Section 09 (9A-1 to 9A-34).pdf 7,371 KB 037 Figures Section 1O.pdf 16,540 KB 038 Figures Section 11.pdf 2,660 KB 039 Figures Section 12.pdf 16,970 KB 040 Figures Section 13.pdf 157 KB 041 Figures Section 14.pdf 241 KB 042 Figures Section 15.pdf 5,587 KB 043 PNPP TS Bases Rev 12.pdf 872 KB

Attachment 2 L-19-120 List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed)

Page 1 of 2 File Name Size 001 LIST_EFF Rev 21.pdf 126 KB 002 Chapter 00.pdf 1,008 KB 003 Chapter 01.pdf 14,117 KB 004 Chapter 02 .0 to 02.4.pdf 14,268 KB 005 Chapter 02.5 to 02E.pdf 38,213 KB 006 Chapter 03.pdf 15,632 KB 007 Chapter 04 .pdf 13,498 KB 008 Chapter 05.pdf 13,815 KB 009 Chapter 06.pdf 14,243 KB 010 Chapter 07.pdf 13,884 KB 011 Chapter 08.pdf 13,629 KB 012 Chapter 09.pdf 15,436 KB 013 Chapter 10.pdf 13,488 KB 014 Chapter 11.pdf 13,767 KB 015 Chapter 12.pdf 13,796 KB 016 Chapter 13.pdf 13,410 KB 017 Chapter 14.pdf 13,762 KB 018 Chapter 15.pdf 17,358 KB 019 Chapter 16.pdf 57 KB 020 Chapter 17.pdf 67 KB 021 FIG_LIST Rev 20.pdf 256 KB 022 Figures Section 01 .pdf 3,161 KB 023 Figures Section 02 (2.1-1 to 2.5-46).pdf 27,077 KB 024 Figures Section 02 (2.5-47 to 2.5-49).pdf 20,214 KB 025 Figures Section 02 (2.5-50 to 2.5-215) .pdf 26,171 KB 026 Figures Section 02D-1 to 02D-2 .pdf 19,647 KB 027 Figures Section 02D-3 to 02E-1.pdf 32,280 KB L-19-120 Page 2 of 2 File Name Size 028 Figures Section 03.pdf 27 ,864 KB 029 Figures Section 04.pdf 1,567 KB 030 Figures Section 05 .pdf 4,989 KB 031 Figures Section 06.pdf 7,311 KB 032 Figures Section 07.pdf 10,280 KB 033 Figures Section 08.pdf 2,746 KB 034 Figures Section 09 (9.1-1 to 9.4-29).pdf 17,806 KB 035 Figures Section 09 (9.5-1 to 9.5-26).pdf 4,245 KB 036 Figures Section 09 (9A-1 to 9A-34).pdf 601 KB 037 Figures Section 1O.pdf 16,540 KB 038 Figures Section 11.pdf 2,660 KB 039 Figures Section 12.pdf 1,909 KB 040 Figures Section 13.pdf 157 KB 041 Figures Section 14.pdf 241 KB 042 Figures Section 15.pdf 5,586 KB 043 PNPP TS Bases Rev 12.pdf 859 KB

Attachment 3 L-19-120 Information Removed from the PNPP UFSAR Page 1 of 1 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports ," licensees periodically report a brief description of information removed from the Updated Final Safety Analysis Report (UFSAR) and the basis for its removal. The following provides a summary of the information removed from the PNPP UFSAR and the basis for removal.

1. Removed obsolete information from Section 2.2.2.5.c related to the Perry heliport. The heliport was deactivated by the Federal Aviation Administration and the Ohio Department of Transportation Office of Aviation. The removed information is descriptive information that is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

2. Removed obsolete information in Section 7.7.1 .8 that describes options for obtaining data when traversing incore probe measurement locations are inaccessible. Option 1 has not been used since the addition of Option 2, which uses data from the core monitoring system . The removed information is descriptive information that is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

3. Removed redundant, unnecessary depiction of pipe sizes from Figure 5.4-16.

The removed information was not originally provided in the FSAR, but later introduced by incorporation of piping and interconnection diagram (P&IDs) or other detailed drawings as a matter of convenience.

Attachment 4 L-19-120 Commitment Change Summary Report April 2017 - July 2019 Page 1 of 1 COMMITMENT COMMITMENT NUMBER/SOURCE/DATE DESCRIPTION CHANGE REASON FOR CHANGE PY-800656 Issue a plant administrative Closed. This commitment tracked the action to PY-CEI/NRR-1034L, 7/20/1989 procedure for erosion/corrosion issue a procedure, which was completed.

GL 89-08, 5/2/1989 examination program by The long-term aspect of the December 1989 erosion/corrosion monitoring program is governed and maintained by nuclear operating equipment reliability procedures that follow current industry guidance for equipment monitoring.

PY-L01262 The vendor technical manual Closed. Improved communication technology, such PY-CEI/NRR-1221L, 9/24/1990 control procedure incorporates as internet websites and electronic mail, GL 83-28, 07/08/1983 a periodic vendor/manufacturer and updated programs and processes (that GL 90-03, 03/20/1990 contact. Periodic vendor is, 10 CFR 21 reports, Maintenance Rule contact is made with vendors Program, OE, BWROG communications, of pre-determined "key" safety NSSS technical bulletins, nuclear safety related components and with advisory letters, service information letters) the NSSS vendor. provide a more effective and efficient means of ensuring key safety-related vendor manuals are current.

PY-L01548 The NRC staff position on In lieu of these requirements, BWRVIP-72-A is an NRG-approved PY-CEI/NRR-1044L, 7/31/1989 sample expansion contained in the sample expansion criteria alternative to GL 88-01 for inspection GL88-01 , 1/25/1988 GL 88-01 for identification of of BWRVIP-75-A, BWR schedules and sample expansion . This is IGSCC in BWR piping systems Vessel and Internals Project used to modify the inspection schedule for was accepted . Technical Basis for Revisions Category C and E welds.

to Generic Letter 88-01 Inspection Schedules, may be used.