PLA-6381, Response for Additional Information for Review of License Renewal Application (LRA) Sections B.2.39, 3.5, & 4.6

Response for Additional Information for Review of License Renewal Application (LRA) Sections B.2.39, 3.5, & 4.6

ML082040626
Person / Time
Site:	Susquehanna
Issue date:	07/08/2008
From:	Mckinney B Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6381
Download: ML082040626 (11)

Text

If 1 Britt T. McKinney Sr. Vice President

& Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com I% I N pp%0 4 JUL 0 8 208 U. S. Nuclear Regulatory Commission Document Control Desk Mail Stop OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (LRA)SECTIONS B.2.39, 3.5, and 4.6 PLA-6381 Docket Nos. 50-387 and 50-388

References:

1) PLA-6110, Mr. B. T McKinney (PPL) to Document Control Desk (USNRC),"Application for Renewed Operating License Numbers NPF-14 and NPF-22, dated September 13, 2006.2) Letter from Ms. E. H. Gettys (USNRC) to Mr. B. T. McKinney (PPL),"Request for Additional Information for the Review of the Susquehanna Steam Electric Station, Units 1 and 2 License Renewal Application, "dated June 17, 2008.In accordance with the requirements of 10 CFR 50, 51, and 54, PPL requested the renewal of the operating licenses for the Susquehanna Steam Electric Station (SSES)Units 1 and 2 in Reference 1.Reference 2 is a request for additional information (RAI) related to License Renewal Application (LRA) Sections B.2.39, 3.5, and 4.6. The enclosure to this letter provides the additional requested information.

There are no new regulatory commitments contained herein as a result of the attached RAI responses.

If you have any questions, please contact Mr. Duane L Filchner at (610) 774-7819.

V-2 -Document Control Desk PLA-6381 I declare, under penalty of perjury, that the foregoing is true and correct.Executed on: B. T. McKinney

Enclosure:

PPL Responses to NRC's Request for Additional Information (RAI)Copy: NRC Region I Ms. E. H. Gettys, NRC Project Manager, License Renewal, Safety Mr. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. A. L. Stuyvenberg, NRC Project Manager, License Renewal, Environmental Enclosure to PLA-6381 PPL Responses to NRC's Request for Additional Information (RAI)

Enclosure to PLA-6381 Page 1 of8 RAI B.2.39-1 In the LRA, AMP B.2.40 "RG 1.127 Water-Control Structures Inspection" states under the "acceptance criteria" program element that the structures monitoring program will be enhanced to include acceptance criteria as delineated in the Gall Report Section XI.S7 for water control structures.

Please explain why the AMP B.2.39 "Structures Monitoring Program". "acceptance criteria" program element does not include the enhancements pertaining to Regulatory Guide (RG) 1.127, Rev. 1 for water-control structures.

PPL Response: SSES LRA Section B.2.39, Structures Monitoring Program, is amended as follows to include the Acceptance Criteria for Regulatory Guide (RG) 1.127, Water-Control Structures Inspection under the Required Enhancements section.B.2 Aging Management Programs B.2.39 Structures Monitoring Program Required Enhancements

>, The fourth bullet in the Required Enhancements discussion in Section B.2.39 (LRA page B-1 17) is revised by addition (bold italics).* Scope, Parameters Monitored or Inspected, Acceptance Criteria -The Structures Monitoring Program procedure will be enhanced to include RG 1.127 inspection elements for water-control structures.

Enclosure to PLA-6381 Page 2 of 8 RAI 3.5-1 In Table 3.5.2-10 "Aging Management Review Results -Bulk Commodities," there are several line items for stainless steel material exposed to weather environment which refer to GALL Volume 2 items III.B2-7 & III.B4-7, and Volume 1 item 3.5.1-50.

The GALL Report recommends the structures monitoring program to manage aging effects of loss of material/pitting and crevice corrosion.

These SSES LRA items have the same component, material, and environment combination as in the GALL Report. Please provide the technical basis for not following the GALL Report recommendation.

PPL Response: The line items for stainless steel material exposed to weather environment are amended to align with the GALL Report recommendations and applicable SSES Aging Management Programs.Table 3.5.2-10 is amended as follows to indicate the Aging Effect Requiring Management as "Loss of Material" and the Aging Management Program as "Structures Monitoring Program" or "ISI-IWF" for the following stainless steel Components/

Commodities with the Environment, "Exposed to Weather".Anchorage

/ Embedments

[Stainless Steel];Component and Piping Supports (ASME Class 1, 2, 3 and MC) [Stainless Steel];Equipment Component Supports [Stainless Steel];Pipe Supports [Stainless Steel];Anchor Bolts [Stainless Steel];Anchor Bolts (ASME Class 1, 2, 3 and MC Supports Bolting) [Stainless Steel];Expansion Anchors [Stainless Steel]3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORTS Table 3.5.2-10, Aging Management Review Results -Bulk Commodities The Components/Commodities in Table 3.5.2-10 (LRA pages 3.5-111, 3.5-114, 3.5-117, 3.5-122, 3.5-126, 3.5-127, 3.5-129 and 3.5-138) are revised by addition (bold italics) and deletion (stiiketlweugh).

Enclosure to PLA-6381 Page 3 of 8 Table 3.5.2-10 Aging Management Review Results -Bulk Commodities Component/

Intended Aging Effect Aging NUREG-1801 Commodity Function 1 Material Environment Requiring Management Volume 2 Table 1 Item Notes Management Programs Item III.B2-8 ProtctedfromIll.B3-5 Protected from None None 3.5.1-59 A weather II1.B4-8 Anchorage SNS, SRE, Stainless Steel 1II.B5-5 Embedments SSR Exposed to NEoe Loss of Nope Structures 1l1.B2-7 0&22 weather material Monitoring 3.5.1-50 Program 1I1.B4-7 A, 0528 Ill.B1.1-9 Protected from None None Ill.B1.2-7 3.5.1-59 A weather Ill.B31.3-7 Noe os f I.B2-7 0,52-2 Exposed to weather e Loss of Nne~ ISI-IWF 3.5.1-50 Component and material 111.B4-7 E, Piping Supports SNS, SRE, SSR Stainless Steel 0528 (ASME Class 1,2, 3 and MC) ISI-IWF Exposedtotreated Loss of material 1Il..1.1-11 3.5.1-49 A water BWR Water Chemistry Program Exposed to raw Loss of material ISI-IWF VII.C3-7 3.3.1-78 E, water 0523 Enclosure to PLA-6381 Page 4 of 8 Table 3.5.2-10 Aging Management Review Results -Bulk Commodities Component/

Intended Aging Effect Aging NUREG-1801 Commodity Function 1 Material Environment Requiring Management Volume 2 Table 1 Item Notes Management Programs Item II1.B2-8 Protected from IIl.B3-5 None None 3.5.1-59 A weather Il1.134-8 Equipment SNS, SRE, B11.15-5 Component SSR Stainless Steel Supports SSR Exposed to NeRe Loss of NGne Structures 111.B2-7 3510 weather material Monitoring

.4-7 3.5.1-50 A, Program 0528 Protected from II.B2-8 None None 3.5.1-59 A weather I11.14-8 SNS, SRE, Exposed to NeRe Loss of Neoe Structures 111.B2-7 0520 Pipe Supports 'S Stainless Steel wethe mtera Monitoring 3.5.1-50 SSR Sweaer maea Program I11.B4-7 A, 0528 Structures Loss of material Monitoring 111.B5-7 3.5.1-39 A weather Program Enclosure to PLA-6381 Page 5 of 8 III.B2-8 Protected from II1. B3-5 weater None None B4-5 3.5.1-59 A weather 118III.Anchor Bolts SNS, SRE, Stainless Steel 11135-5 SSR Exposed to NeRe Loss of NeRe Structures III.B2-7 0522 weather material Monitoring 3.5.1-50 Program III. B4-7 A, 0528 Ill.B1.1-9 Protected from None None III.B1.2-7 3.5.1-59 A weather Ili.B1.3-7 Anchor Bolts Exposed to Nene Loss of IlI.B2I7 0520 (ASME Class Exposed Ne~e ISI-IWF 3.5.1-50 1,2, 3 and MC SSR Stainless Steel weather material III.B4-7 E, Supports 0528 Bolting)ISI-IWF Exposed to Loss of material 1Il.1.1-11 3.5.1-49 A treated water BWR Water Chemistry Program Enclosure to PLA-6381 Page 6 of 8 Table 3.5.2-10 Aging Management Review Results -Bulk Commodities Component/

Intended Aging Effect Aging NUREG-1801 Commodity Function' Material Environment Requiring Management Volume 2 Table I Item Notes Management Programs Item II1.1B2-8 Protected from None None 3.5.1-59 A weather II1.B4-8 Expansion SNS, SRE, Stainless Steel III.B5-5 Anchors SSR Sist Exposed to Ne~o Loss of NeRe Structures II.B2-7 weather material Monitoring 3.5.1-50 ProgramI.B4-7 A, 0528 Plant-Specific Notes: 0528 This aging effect was determined not applicable in aging management review since SSES is located in an in-land rural environment and is not exposed to aggressive environmental conditions.

However, it is conservatively made consistent to the listed GALL items. The identified AMP is used to manage aging effects for the period of extended operation.

Enclosure to PLA-6381 Page 7 of 8 RAI 4.6.2-1 In the LRA Section 4.6.2 "Downcomer Vents and Safety Relief Valve Discharge Piping," the applicant summarized the maximum cumulative usage factors (CUF) for the downcomers in Table 4.6-1. The staff noted that the Operational Cases 4 and 6 are identical, while the CUF values are different.

Please explain this discrepancy.

PPL Response: SSES LRA Table 4.6-1, Maximum Cumulative Usage Factors for Downcomers is incorrect and will be revised to be consistent with SSES Units 1 and 2 Design Assessment Report (DAR), Table 7-3. The SSES LRA is amended as follows to change Operational Case 6 to be "Emergency/Faulted

-SBA: CHUG + SSE(6)'.4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATION FATIGUE ANALYSES Table 4.6-1, Maximum Cumulative Usage Factors for Downcomers

> The sixth Operational Case in Table 4.6-1 (LRA page 4.6-2) is revised by addition (bold italics) and deletion (,trketwouh).

Table 4.6-1 Maximum Cumulative Usage Factors for Downcomers Operational Case(1) Cumulative Usage Factor 40 Years and 60 Years(8)1 -Normal/Upset -SRV1 (2)+S RV2(3)+OB E(4) 0.0083 2-Normal/Upset -SRV1 +SRV2+CHUG(7) 0.608 3-Normal/Upset -SRV1 +SRV2 0.774 4-Emergency/Faulted -SBA:SRV(5)+CHUG 0.774 5-Emergency/Faulted -SBA:SRV(5)+CHUG+SSE(6) 0.791 6-Emergency/Faulted -SBA:,RV()+CHUG+SSE(6) 0.782 Enclosure to PLA-6381 Page 8 of 8 RAI 4.6.3-1 In the LRA, Section 4.6.3 "Safety Relief Valve Quenchers," the last sentence of the second paragraph references a "Code Paragraph NF" component support. Please identify this Code Paragraph NF as it is not referenced elsewhere in the LRA.PPL Response: SSES LRA Section 4.6.3 is incorrect and "Code Paragraph NF" will be revised to "Code Subsection NF". The SSES LRA is amended as follows: 4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATION FATIGUE ANALYSES 4.6.3 Safety Relief Valve Quenchers The second paragraph in the Safety Relief Valve Quencher discussion in Section 4.6.3 (LRA page 4.6-3) is revised by addition (bold italics) and deletion The component parts of a quencher installation are the sphere, arms, support stub, and base support. The quencher was designed in accordance with the requirements of ASME Section II1. 1977 Edition, including Summer, 1977 Addenda. Code Paragraph NC-3200, Appendix XIII, and Appendix XIV were used in the design and analyses of all components of the quencher, except for the base support, which was designed as a Code P-Fagaph Subsection NF component support.