L-19-120, Submittal of Revision 21 to Updated Final Safety Analysis Report
Text
FENOC' FirstEnergy Nuclear Operating Company Frank Payne Vice President October 18, 2019 L-19-120 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 Perry Nuclear Power Plant PO. Box 97 10 Center Road Perry, Ohio 44081 440-280-5382 10 CFR 50.71(e) 10 CFR 50.54(a)
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. 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. 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)
L-19-120 List of Document Components on CD-ROM 1 File Name 001 LIST EFF Rev 21.pdf 002 Chapter 00.pdf 003 Chapter 01.pdf 004 Chapter 02.0 to 02.4.pdf 005 Chapter 02.5 to 02E.pdf 006 Chapter 03.pdf 007 Chapter 04.pdf 008 Chapter 05.pdf 009 Chapter 06.pdf 010 Chapter 07.pdf 011 Chapter 08.pdf 012 Chapter 09.pdf 013 Chapter 1 O.pdf 014 Chapter 11.pdf 015 Chapter 12.pdf 016 Chapter 13.pdf 017 Chapter 14.pdf 018 Chapter 15.pdf 019 Chapter 16.pdf 020 Chapter 17.pdf 021 FIG_LIST Rev 20.pdf 022 Figures Section 01.pdf Page 1 of 2 023 Figures Section 02 (2.1-1 to 2.5-46).pdf 024 Figures Section 02 (2.5-47 to 2.5-49).pdf 025 Figures Section 02 (2.5-50 to 2.5-215).pdf 026 Figures Section 020-1 to 020-2.pdf 027 Figures Section 020-3 to 02E-1.pdf Size 128 KB 743 KB 14,119 KB 14,096 KB 38,219 KB 15,636 KB 13,498 KB 13,815 KB 14,248 KB 13,885 KB 13,630 KB 15,440 KB 13,488 KB 13,768 KB 13,744 KB 13,410 KB 13,763 KB 17,359 KB 57 KB 67 KB 257 KB 17,397 KB 27,077 KB 20,215 KB 26,172 KB 19,648 KB 32,280 KB L-19-120 Page 2 of 2 File Name 028 Figures Section 03.pdf 029 Figures Section 04.pdf 030 Figures Section 05.pdf 031 Figures Section 06.pdf 032 Figures Section 07.pdf 033 Figures Section 08.pdf 034 Figures Section 09 (9.1-1 to 9.4-29).pdf 035 Figures Section 09 (9.5-1 to 9.5-26).pdf 036 Figures Section 09 (9A-1 to 9A-34).pdf 037 Figures Section 1 O.pdf 038 Figures Section 11.pdf 039 Figures Section 12.pdf 040 Figures Section 13.pdf 041 Figures Section 14.pdf 042 Figures Section 15.pdf 043 PNPP TS Bases Rev 12.pdf Size 38,780 KB 1,567 KB 4,989 KB 7,501 KB 10,280 KB 3,142 KB 18,426 KB 4,305 KB 7,371 KB 16,540 KB 2,660 KB 16,970 KB 157 KB 241 KB 5,587 KB 872 KB L-19-120 List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed)
File Name 001 LIST_EFF Rev 21.pdf 002 Chapter 00.pdf 003 Chapter 01.pdf 004 Chapter 02.0 to 02.4.pdf 005 Chapter 02.5 to 02E.pdf 006 Chapter 03.pdf 007 Chapter 04.pdf 008 Chapter 05.pdf 009 Chapter 06.pdf 010 Chapter 07.pdf 011 Chapter 08.pdf 012 Chapter 09.pdf 013 Chapter 10.pdf 014 Chapter 11.pdf 015 Chapter 12.pdf 016 Chapter 13.pdf 017 Chapter 14.pdf 018 Chapter 15.pdf 019 Chapter 16.pdf 020 Chapter 17.pdf 021 FIG_LIST Rev 20.pdf 022 Figures Section 01.pdf Page 1 of 2 023 Figures Section 02 (2.1-1 to 2.5-46).pdf 024 Figures Section 02 (2.5-47 to 2.5-49).pdf 025 Figures Section 02 (2.5-50 to 2.5-215).pdf 026 Figures Section 02D-1 to 02D-2.pdf 027 Figures Section 02D-3 to 02E-1.pdf Size 126 KB 1,008 KB 14,117 KB 14,268 KB 38,213 KB 15,632 KB 13,498 KB 13,815 KB 14,243 KB 13,884 KB 13,629 KB 15,436 KB 13,488 KB 13,767 KB 13,796 KB 13,410 KB 13,762 KB 17,358 KB 57 KB 67 KB 256 KB 3,161 KB 27,077 KB 20,214 KB 26,171 KB 19,647 KB 32,280 KB L-19-120 Page 2 of 2 File Name 028 Figures Section 03.pdf 029 Figures Section 04.pdf 030 Figures Section 05.pdf 031 Figures Section 06.pdf 032 Figures Section 07.pdf 033 Figures Section 08.pdf 034 Figures Section 09 (9.1-1 to 9.4-29).pdf 035 Figures Section 09 (9.5-1 to 9.5-26).pdf 036 Figures Section 09 (9A-1 to 9A-34).pdf 037 Figures Section 1 O.pdf 038 Figures Section 11.pdf 039 Figures Section 12.pdf 040 Figures Section 13.pdf 041 Figures Section 14.pdf 042 Figures Section 15.pdf 043 PNPP TS Bases Rev 12.pdf Size 27,864 KB 1,567 KB 4,989 KB 7,311 KB 10,280 KB 2,746 KB 17,806 KB 4,245 KB 601 KB 16,540 KB 2,660 KB 1,909 KB 157 KB 241 KB 5,586 KB 859 KB 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.
COMMITMENT NUMBER/SOURCE/DATE PY-800656 PY-CEI/NRR-1034L, 7/20/1989 GL 89-08, 5/2/1989 PY-L01262 PY-CEI/NRR-1221L, 9/24/1990 GL 83-28, 07/08/1983 GL 90-03, 03/20/1990 PY-L01548 PY-CEI/NRR-1044L, 7/31/1989 GL88-01, 1/25/1988 L-19-120 Commitment Change Summary Report April 2017 - July 2019 COMMITMENT DESCRIPTION Issue a plant administrative procedure for erosion/corrosion examination program by December 1989 The vendor technical manual control procedure incorporates a periodic vendor/manufacturer contact. Periodic vendor contact is made with vendors of pre-determined "key" safety related components and with the NSSS vendor.
The NRC staff position on sample expansion contained in GL 88-01 for identification of IGSCC in BWR piping systems was accepted.
Page 1 of 1 CHANGE Closed.
Closed.
In lieu of these requirements, the sample expansion criteria of BWRVIP-75-A, BWR Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules, may be used.
REASON FOR CHANGE This commitment tracked the action to issue a procedure, which was completed.
The long-term aspect of the erosion/corrosion monitoring program is governed and maintained by nuclear operating equipment reliability procedures that follow current industry guidance for equipment monitoring.
Improved communication technology, such as internet websites and electronic mail, and updated programs and processes (that is, 10 CFR 21 reports, Maintenance Rule Program, OE, BWROG communications, NSSS technical bulletins, nuclear safety advisory letters, service information letters) provide a more effective and efficient means of ensuring key safety-related vendor manuals are current.
BWRVIP-72-A is an NRG-approved alternative to GL 88-01 for inspection schedules and sample expansion. This is used to modify the inspection schedule for Category C and E welds.