L-15-269, Submittal of Revision 19 to the Updated Final Safety Analysis Report

From kanterella
Jump to navigation Jump to search

Submittal of Revision 19 to the Updated Final Safety Analysis Report
ML15314A217
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 10/23/2015
From: Harkness E
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15314A214 List:
References
L-15-269
Download: ML15314A217 (8)
v • d • e


Text

FENOCo First Energy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97 10 Center Road Perry, Ohio 44081 Ernest J. Harkness Vice President 440-280-5382 Fax: 440-280-8029 October 23, 2015 LI15-269

.10 CER 50.71(e) 10 CFR 50.54(a)

TS 5.5.11 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant, Unit No. I Docket No. 50-440, License No. NPF-58 Submittal of Revision 19 to the Updated Final Safety Analysis Report 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) Revision 19 to the Perry Nuclear Power Plant (PNPP), Unit No. 1 Updated Final Safety Analysis Report (UFSAR) in CD-ROM format. This submittal reflects facility and procedure changes implemented between May 16, 2013 (the end of the spring 2013 refueling outage) and April 24, 2015 (the end of the spring 2015 refueling outage), along with several changes implemented after the spring 2015 refueling outage.

In accordance with 10 CFR 50.4(b)(6) the PNPP UFSAR Revision 19 is being submitted electronically on a total replacement basis. As requested by NRC guidance for electronic submissions to the Commission, Attachment 1 provides a listing of document components that make up the enclosed CD-ROM. In addition to the UFSAR, the enclosed CD-ROM includes the following:

Perry Nuclear Power Plant, Unit No. 1 Li15-269 Page 2 In accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes,"

as endorsed by NRC Regulatory Issue Summary (RIS) 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," a summary of regulatory commitment changes is provided in Attachment 3.

This certifies, to the best of my judgment and belief, that Revision 19 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.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

Fleet Licensing, at (330) 315-6810.

Sincerely, Ernest J. Harkness Attachments:

1. Document Components on CD-ROM
2. Information Removed from the PNPP UFSAR
3. Commitment Change Summary Report

Enclosure:

PNPP UFSAR, TS Bases, FENOC QAPM (on CD-ROM) cc:

NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager

Attachment I L-1 5-269 Document Components on CD-ROM Page 1 of 2

  • File Name 001 List_EFF Rev 19.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 19.pdf 022 Figures Section 01.pdf 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 136 KB 956 KB 14,103 KB 14,083 KB 38,213 KB 15,561 KB 13,498 KB 13,808 KB 14,181 KB 13,880 KB 13,611 KB 15,446 KB 13,474 KB 13,759 KB 13,734 KB 13,392 KB 13,759 KB 15,563 KB 19 KB 28 KB 4,646 KB 3,798 KB 25,701 KB 20,152 KB 25,879 KB 19,580 KB 32,226 KB L-1 5-269 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 10.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 10.pdf 044 FENOC QAPM Rev 19.pdf Size 37,955 KB 1,405 KB 4,681 KB 7,495 KB 10,003 KB 2,533 KB 17,440 KB 4,004 KB 6,564 KB 14,660 KB 2,428 KB 20,009 KB 126 KB 200 KB 5,527 KB 2,502 KB 2,874 KB L-1 5-269 Information Removed from PNPP UFSAR Page 1 of 3 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees are required to 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 UFSAR and the basis for removal.

1.Removed information from Section 15.6.2.5, Radiological Consequences, from the active UFSAR. The section was designated as historical, not to be updated in the future, as a result of implementation of license Amendment 166 issued on March 30, 2015 involving use of an alternative accident source term for design basis radiological dose calculations. This was simplification of information involving analytical information that is not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance with relevant regulatory and industry standards.

2.

Removed the reference to component 2P43D0004 and the "to be installed later" note included with it from Figure 9.2-4 Sheet 3. This component is a non-safety flange that was never installed. The information being removed would have no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design functions.

3.

Removed unnecessary descriptive information pertaining to Perry Nuclear Power Plant (PNPP) Unit No. 2 from Chapter 1, Introduction and General Description of Plant; Chapter 3, Design of Structures, Components, Equipment, and Systems; Chapter 5, Reactor Coolant Systems and Connected Systems; Chapter 6, Engineered Safety Features; Chapter 8, Electric Power; Chapter 9, Auxiliary Systems; Chapter 11, Radioactive Waste Management; and Chapter 13, Conduct of Operations. As described in Chapter 1, PNPP Unit No. 2 was abandoned. The removed information is not pertinent to the existing plant. This was 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.

4.

Removed obsolete and unnecessary functional locations for temporary strainers from Figure 9.4-20 Sheet 1 and Figure 9.4-22 Sheet 1. An unnecessary system identifier, 1 P56A, was removed from Figure 9.5-3. This descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

L-1 5-269 Page 2 of 3

5.

Removed obsolete and unnecessary functional locations for temporary strainers from Figure 9.2-13. Removed spare connections for electrical supply 1 N64K0620 from Figure 11.3-2 Sheet 3 because it was considered excessive and unnecessary detail. This descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

6.

Removed excessive detail from Sections 9.1.4.2, 9.2.8.2, 9.4.1.5, 9.4.9.2.3, and 9.5.5.2. A list of specific tools used to remove or install the reactor head was removed from the fuel handling section (9.1.4.2). Explicit sub-headers in Section 9.2.8.2 were removed because of ambiguity. Unnecessary details regarding closure of the drain valve were removed from the Section 9.4.1.5 description of ventilation systems with charcoal filter beds protected by deluge systems.

Outdated and unnecessary statements regarding the degree of leakage predicted were removed from Section 9.5.5.2. This descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

7.

Removed Figure 15.4-7 because the table provides analytical information that is not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance to regulatory or industry standards.

Removed Table 15.7-2 that contained excessive detail. The design information was such that, if changed during the life of the plant, would have no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design basis functions. Removed information from Figures 15A.6-12, 15A6-18, 15A6-20, 15A6-24, 15A6-26, 15A6-28, 15A6-29, 15A6-35, 15A6-37, and 15A6-38 regarding the auxiliaries supporting the residual heat removal system suppression pool cooling system function because it is redundant to information contained elsewhere in the UFSAR. Removed an undefined symbol from Figure 1 5A6-30. The symbol had no effect on the interpretation of the figure. The removed information provides analytical information that is not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance to regulatory or industry standards.

8.

Removed a trade name used in Section 4.5.1.2 and an erroneous cross-reference in Section 12.3.3.1. The removed descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

9.

Removed excessive detail from Sections 4.5.1.1 and 4.6.1.1 regarding the materials and trade names associated with subcomponents of the control rod drive mechanisms. The removed descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

L-1 5-269 Page 3 of 3

10. Removed unit designators on computer points from Figure 11.5-1 Sheets 1, 2, and 3 and removed computer points no longer in use. With the abandonment of Unit 2 and use of a single computer, this descriptive information is excessive and not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.
11.

Removed Figures 5.3-2 Sheets 1, 2, 3, 4, 5, and 6, which contained the reactor pressure-temperature curves. The pressure-temperature curves are contained in the PNPP Technical Specifications. The UFSAR was also revised to include a reference to the technical specifications as to where the pressure-temperature curves are located. The removal of these figures does not result in removal of information required to be included in the UFSAR. The remaining UFSAR content provides sufficient understanding of the design bases, safety analyses or operation.

L-1 5-269 Commitment Change Summary Report May 2013 - July 2015 Page 1 of 1 COMMITMENT NUMBER I SOURCE I DATE COMMITMENT DESCRIPTION CHANGE REASON FOR CHANGE PY-B00680 Letter PY-CEI/NRR-1 11 5L 10/28/1989 PY-B00681 Letter PY-CEI/NRR-11I15L 10/28/1989 In response to NRC GL 89-10, Safety-Related Motor Operated Valve (MOV) Testing and Surveillance, a design-basis review for the operation of each MOV will be prepared, resulting in a design base file for each valve contained in the scope of the letter.

In response to NRC GL 89-10, establish correct switch settings by diagnostic static and dynamic testing.

Commitment closed.

Commitment closed.

The initial review was completed and the NRC staff closed the review of the GL 89-10 program at PNPP in IR 96005 based on verification of the design-basis capability of safety-related MOVs at PNPP.

Switch settings were established. Static and dynamic testing was performed. The NRC staff closed the review of the GL 89-10 program at PNPP in IR 96005.

List of Abbreviations Used GL IR NRC PNPP Generic Letter NRC Inspection Report Nuclear Regulatory Commission Perry Nuclear Power Plant

FENOCo First Energy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97 10 Center Road Perry, Ohio 44081 Ernest J. Harkness Vice President 440-280-5382 Fax: 440-280-8029 October 23, 2015 LI15-269

.10 CER 50.71(e) 10 CFR 50.54(a)

TS 5.5.11 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant, Unit No. I Docket No. 50-440, License No. NPF-58 Submittal of Revision 19 to the Updated Final Safety Analysis Report 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) Revision 19 to the Perry Nuclear Power Plant (PNPP), Unit No. 1 Updated Final Safety Analysis Report (UFSAR) in CD-ROM format. This submittal reflects facility and procedure changes implemented between May 16, 2013 (the end of the spring 2013 refueling outage) and April 24, 2015 (the end of the spring 2015 refueling outage), along with several changes implemented after the spring 2015 refueling outage.

In accordance with 10 CFR 50.4(b)(6) the PNPP UFSAR Revision 19 is being submitted electronically on a total replacement basis. As requested by NRC guidance for electronic submissions to the Commission, Attachment 1 provides a listing of document components that make up the enclosed CD-ROM. In addition to the UFSAR, the enclosed CD-ROM includes the following:

Perry Nuclear Power Plant, Unit No. 1 Li15-269 Page 2 In accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes,"

as endorsed by NRC Regulatory Issue Summary (RIS) 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," a summary of regulatory commitment changes is provided in Attachment 3.

This certifies, to the best of my judgment and belief, that Revision 19 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.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

Fleet Licensing, at (330) 315-6810.

Sincerely, Ernest J. Harkness Attachments:

1. Document Components on CD-ROM
2. Information Removed from the PNPP UFSAR
3. Commitment Change Summary Report

Enclosure:

PNPP UFSAR, TS Bases, FENOC QAPM (on CD-ROM) cc:

NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager

Attachment I L-1 5-269 Document Components on CD-ROM Page 1 of 2

  • File Name 001 List_EFF Rev 19.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 19.pdf 022 Figures Section 01.pdf 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 136 KB 956 KB 14,103 KB 14,083 KB 38,213 KB 15,561 KB 13,498 KB 13,808 KB 14,181 KB 13,880 KB 13,611 KB 15,446 KB 13,474 KB 13,759 KB 13,734 KB 13,392 KB 13,759 KB 15,563 KB 19 KB 28 KB 4,646 KB 3,798 KB 25,701 KB 20,152 KB 25,879 KB 19,580 KB 32,226 KB L-1 5-269 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 10.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 10.pdf 044 FENOC QAPM Rev 19.pdf Size 37,955 KB 1,405 KB 4,681 KB 7,495 KB 10,003 KB 2,533 KB 17,440 KB 4,004 KB 6,564 KB 14,660 KB 2,428 KB 20,009 KB 126 KB 200 KB 5,527 KB 2,502 KB 2,874 KB L-1 5-269 Information Removed from PNPP UFSAR Page 1 of 3 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees are required to 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 UFSAR and the basis for removal.

1.Removed information from Section 15.6.2.5, Radiological Consequences, from the active UFSAR. The section was designated as historical, not to be updated in the future, as a result of implementation of license Amendment 166 issued on March 30, 2015 involving use of an alternative accident source term for design basis radiological dose calculations. This was simplification of information involving analytical information that is not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance with relevant regulatory and industry standards.

2.

Removed the reference to component 2P43D0004 and the "to be installed later" note included with it from Figure 9.2-4 Sheet 3. This component is a non-safety flange that was never installed. The information being removed would have no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design functions.

3.

Removed unnecessary descriptive information pertaining to Perry Nuclear Power Plant (PNPP) Unit No. 2 from Chapter 1, Introduction and General Description of Plant; Chapter 3, Design of Structures, Components, Equipment, and Systems; Chapter 5, Reactor Coolant Systems and Connected Systems; Chapter 6, Engineered Safety Features; Chapter 8, Electric Power; Chapter 9, Auxiliary Systems; Chapter 11, Radioactive Waste Management; and Chapter 13, Conduct of Operations. As described in Chapter 1, PNPP Unit No. 2 was abandoned. The removed information is not pertinent to the existing plant. This was 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.

4.

Removed obsolete and unnecessary functional locations for temporary strainers from Figure 9.4-20 Sheet 1 and Figure 9.4-22 Sheet 1. An unnecessary system identifier, 1 P56A, was removed from Figure 9.5-3. This descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

L-1 5-269 Page 2 of 3

5.

Removed obsolete and unnecessary functional locations for temporary strainers from Figure 9.2-13. Removed spare connections for electrical supply 1 N64K0620 from Figure 11.3-2 Sheet 3 because it was considered excessive and unnecessary detail. This descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

6.

Removed excessive detail from Sections 9.1.4.2, 9.2.8.2, 9.4.1.5, 9.4.9.2.3, and 9.5.5.2. A list of specific tools used to remove or install the reactor head was removed from the fuel handling section (9.1.4.2). Explicit sub-headers in Section 9.2.8.2 were removed because of ambiguity. Unnecessary details regarding closure of the drain valve were removed from the Section 9.4.1.5 description of ventilation systems with charcoal filter beds protected by deluge systems.

Outdated and unnecessary statements regarding the degree of leakage predicted were removed from Section 9.5.5.2. This descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

7.

Removed Figure 15.4-7 because the table provides analytical information that is not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance to regulatory or industry standards.

Removed Table 15.7-2 that contained excessive detail. The design information was such that, if changed during the life of the plant, would have no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design basis functions. Removed information from Figures 15A.6-12, 15A6-18, 15A6-20, 15A6-24, 15A6-26, 15A6-28, 15A6-29, 15A6-35, 15A6-37, and 15A6-38 regarding the auxiliaries supporting the residual heat removal system suppression pool cooling system function because it is redundant to information contained elsewhere in the UFSAR. Removed an undefined symbol from Figure 1 5A6-30. The symbol had no effect on the interpretation of the figure. The removed information provides analytical information that is not necessary to provide an understanding of the safety analysis methodology, input assumptions and results, or compliance to regulatory or industry standards.

8.

Removed a trade name used in Section 4.5.1.2 and an erroneous cross-reference in Section 12.3.3.1. The removed descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

9.

Removed excessive detail from Sections 4.5.1.1 and 4.6.1.1 regarding the materials and trade names associated with subcomponents of the control rod drive mechanisms. The removed descriptive information is not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.

L-1 5-269 Page 3 of 3

10. Removed unit designators on computer points from Figure 11.5-1 Sheets 1, 2, and 3 and removed computer points no longer in use. With the abandonment of Unit 2 and use of a single computer, this descriptive information is excessive and not important to providing an understanding of the plant's design and operation from either a general or system functional perspective.
11.

Removed Figures 5.3-2 Sheets 1, 2, 3, 4, 5, and 6, which contained the reactor pressure-temperature curves. The pressure-temperature curves are contained in the PNPP Technical Specifications. The UFSAR was also revised to include a reference to the technical specifications as to where the pressure-temperature curves are located. The removal of these figures does not result in removal of information required to be included in the UFSAR. The remaining UFSAR content provides sufficient understanding of the design bases, safety analyses or operation.

L-1 5-269 Commitment Change Summary Report May 2013 - July 2015 Page 1 of 1 COMMITMENT NUMBER I SOURCE I DATE COMMITMENT DESCRIPTION CHANGE REASON FOR CHANGE PY-B00680 Letter PY-CEI/NRR-1 11 5L 10/28/1989 PY-B00681 Letter PY-CEI/NRR-11I15L 10/28/1989 In response to NRC GL 89-10, Safety-Related Motor Operated Valve (MOV) Testing and Surveillance, a design-basis review for the operation of each MOV will be prepared, resulting in a design base file for each valve contained in the scope of the letter.

In response to NRC GL 89-10, establish correct switch settings by diagnostic static and dynamic testing.

Commitment closed.

Commitment closed.

The initial review was completed and the NRC staff closed the review of the GL 89-10 program at PNPP in IR 96005 based on verification of the design-basis capability of safety-related MOVs at PNPP.

Switch settings were established. Static and dynamic testing was performed. The NRC staff closed the review of the GL 89-10 program at PNPP in IR 96005.

List of Abbreviations Used GL IR NRC PNPP Generic Letter NRC Inspection Report Nuclear Regulatory Commission Perry Nuclear Power Plant

Retrieved from "https://kanterella.com/w/index.php?title=L-15-269,_Submittal_of_Revision_19_to_the_Updated_Final_Safety_Analysis_Report&oldid=5180436"