ML100760661

RAI Regarding Balance of Plant Scoping and Screening Results for the Salem Nuclear Generating Station Units 1 & 2 (Tac Nos. ME1834 and ME1836)

ML100760661
Person / Time
Site:	Salem
Issue date:	04/14/2010
From:	Ashley D License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
ashley, D J, NRR/DLR/RLRA, 415-3191
References
TAC ME1834, TAC ME1836
Download: ML100760661 (18)

Text

April 14, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING BALANCE OF PLANT SCOPING AND SCREENING RESULTS FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 (TAC NOS. ME1834 AND ME1836)

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC (PSEG), submitted an application pursuant to Title 10 Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License DPR-70 and DPR -75 for Salem Nuclear Generating Station (SNGS) Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with John Hufnagel and other members of your staff during a telephone call on March 29, 2010, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3191 or by e-mail at donnie.ashley@nrc.gov.

Sincerely,

/RA/

Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosure:

As stated cc w/encl: See next page

April 14, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING BALANCE OF PLANT SCOPING AND SCREENING RESULTS FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 (TAC NOS. ME1834 AND ME1836)

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC (PSEG), submitted an application pursuant to Title 10 Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License DPR-70 and DPR -75 for Salem Nuclear Generating Station (SNGS) Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with John Hufnagel and other members of your staff during a telephone call on March 29, 2010, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3191 or by e-mail at donnie.ashley@nrc.gov.

Sincerely,

/RA/

Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosure:

As stated cc w/encl: See next page ADAMS Accession Number: ML100760661 OFFICE LA:DLR PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1 NAME SFigueroa DAshley BPham DAshley DATE 4/08/10 4/12/10 4/13/10 4/14/10 OFFICIAL RECORD COPY

Letter to PSEG Nuclear from D. Ashley, dated April 14, 2010 DISTRIBUTION:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING BALANCE OF PLANT SCOPING AND SCREENING RESULTS FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 (TAC NOS. ME1834 AND ME1836)

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsOgcMailCenter Resource BPham DAshley REnnis MModes, RI DKern, RI JBrand, RI RConte, RI RBellamy, RI PBamford, RI MMcLaughlin, RI

Salem Nuclear Generating Station, Units 1 and 2 cc:

Mr. Robert Braun Mr. Ali Fakhar Senior Vice President Nuclear Manager, License Renewal PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Mr. William Mattingly Station Vice President - Salem Manager - Salem Regulatory Assurance PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Township Clerk Vice President - License Renewal Projects Lower Alloways Creek Township Exelon Nuclear LLC Municipal Building, P.O. Box 157 200 Exelon Way Hancocks Bridge, NJ 08038 Kennett Square, PA 19348 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Ed Eilola Radiation Protection Programs Plant Manager - Salem NJ Department of Environmental PSEG Nuclear LLC Protection and Energy, CN 415 One Alloway Creek Neck Road Trenton, NJ 08625-0415 Hancocks Bridge, NJ 08038 Mr. Brian Beam Mr. Brian Booth Board of Public Utilities Director Nuclear Oversight 2 Gateway Center, Tenth Floor PSEG Nuclear Newark, NJ 07102 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Jeffrie J. Keenan, Esquire 475 Allendale Road Manager - Licensing King of Prussia, PA 19406 PSEG Nuclear LLC One Alloway Creek Neck Road Mr. Greg Sosson Hancocks Bridge, NJ 08038 Director Corporate Engineering PSEG Nuclear LLC Senior Resident Inspector One Alloway Creek Neck Road Salem Nuclear Generating Station Hancocks Bridge, NJ 08038 U.S. Nuclear Regulatory Commission Drawer 0509 Mr. Paul Davison Hancocks Bridge, NJ 08038 Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038

Salem Nuclear Generating Station, Units 1 and 2 cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079

REQUEST FOR ADDITIONAL INFORMATION REGARDING BALANCE OF PLANT SCOPING AND SCREENING RESULTS FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 (TAC NOS. ME1834 AND ME1836) 2.3 Scoping and Screening Results RAI 2.3-01

Background:

License renewal rule 10 CFR 54.21(a) requires applicants to list all component types subject to an AMR. The staff confirms inclusion of all component types subject to an AMR by reviewing components within the license renewal boundary.

Issue:

For the drawing locations identified in the table below, the piping continuations could not be found. In order to assure that all components within the scope of license renewal have been identified, the staff must be able to review the full extent of the license renewal boundary.

License Drawing Number and Continuation Issue Renewal Location System Chemical and LR-205228(SH1) at C-7 Section of (a)(2) piping is continued from Volume Control LR-205328(SH1) at C-7 drawing LR-205213(SH3) which was not System submitted as part of the application.

LR-205228(SH1) at A-6 Section of (a)(2) piping continues to drawing LR-205227(SH2). The continuation could not be located.

LR-205230(SH1) at F-1 Section of (a)(2) piping continues to drawing LR-205349(SH1) which was not submitted as part of the application.

LR-205230(SH1) at G-5 Section of (a)(2) piping is continued from LR-205330(SH1) at G-5 drawing LR-205213(SH3) which was not submitted as part of the application.

Demineralized LR-205246(SH1) at B-2, The 1 (a)(2) line (1-2DR1079) ends without a Water System continuation note.

LR-205246(SH1) at B-3 The 1 (a)(2) line (1-1018) ends without a continuation note.

LR-205246(SH1) at C-8 The 3/4 (a)(2) line (3/4-1040) ends without a continuation note.

LR-205246(SH1) at F-2 The 1 line (1-1087) continues to Panel No.

799 without a drawing number or location.

ENCLOSURE

LR-205246(SH2) at D-4 The 3/4 (a)(2) line (3/4-1020) ends without a continuation note.

LR-205246(SH2) at F-6 Section of (a)(2) piping continues to drawing LR-247729(SH1) which was not submitted as part of the application.

LR-205228(SH1) at C-7 Section of (a)(2) piping continues to drawing LR-205328(SH1) at C-7 LR-205213(SH3) which was not submitted as part of the application.

LR-205246(SH1) at D-7 Section of (a)(1) piping continues from LR-205213 (SH5). The continuation could not be located.

LR-205244(SH2) at C-3, Section of (a)(2) piping continues from drawing D-1, and D-4 LR-205246(SH1). The continuation could not be located.

Fresh Water LR-205216(SH2) at C-1 Section of (a)(2) piping continues from drawing System LR-205324(SH2), which was not submitted as part of the application.

Radioactive LR-205239(SH2) at F-6 Section of (a)(2) piping continues from drawing Drain System LR-205226(SH2). The continuation could not be located.

LR-205227(SH2) at G-5 Section of (a)(2) piping continues from drawing LR-205240(SH3), which was not submitted as part of the application.

LR-205227(SH1) at H-4 Section of (a)(2) piping continues from drawing LR-206967(SH1), which was not submitted as part of the application.

LR-205227(SH1) at H-10 Section of (a)(2) piping continues from the control room emergency air conditioner unit without a continuation drawing.

LR-205227(SH3) at H-4 Sections of (a)(1) piping continue from the No.

through H-11 11, 12, 13, 14, and 15 containment fan units without a continuation drawing.

LR-205327(SH3) at H-4 Sections of (a)(1) piping continue from the No.

through H-11 21, 22, 23, 24, and 25 containment fan units without a continuation drawing.

LR-205227(SH3) at F-4 Sections of (a)(2) piping continue from the No.

LR-205327(SH3) at F-4 11, 12, 21, and 22 iodine removal fans, respectively, without a continuation drawing.

LR-205227(SH1) at H-4 Section of (a)(2) piping continues from drawing LR-206967, which was not submitted as part of the application.

LR-205327(SH1) at F-5 Section of (a)(2) piping continues from drawing and F-6 LR-247729(SH1), which was not submitted as part of the application.

LR-205339(SH1) at G-11 Section of (a)(2) piping continues from drawing LR-247729(SH1), which was not submitted as part of the application.

LR-205344(SH1) at D-3 Section of (a)(2) piping continues to drawing

LR-205327(SH1). The continuation could not be located.

LR-205234(SH1) at G-6 Section of (a)(2) piping continues from the Holdup Tank without a continuation drawing.

LR-205239(SH1) at G-10 Section of (a)(2) piping continues to drawing LR-205327(SH2). The continuation could not be located.

LR-205344(SH1) at D-4 Section of (a)(2) piping continues to drawing LR-205327(SH1). The continuation could not be located.

Radwaste LR-205230(SH1) at F-1 Section of (a)(2) piping continues to drawing System LR-205349(SH1), which was not submitted as part of the application.

LR-205330(SH1) at E-1, Sections of (a)(2) piping continue to drawing C-2, C-3, C-4, and D-4 LR-247729(SH1), which was not submitted as part of the application.

Main LR-205202(SH1) at D-2, Section of (a)(2) piping continues to drawing Condensate and D-5, and D-7 LR-205244(SH4), which was not submitted as Feedwater part of the application.

System LR-205202(SH1) at E-11 Section of (a)(2) piping continues to drawing LR-205223(SH1), which was not submitted as part of the application.

LR-205302(SH1) at D-2, Section of (a)(2) piping continues to drawing D-5, and D-7 LR-205344(SH4), which was not submitted as part of the application.

LR-205302(SH1) at E-11 Section of (a)(2) piping continues to drawing and F-11 LR-205323(SH1), which was not submitted as part of the application.

LR-205302(SH1) at G-11 Section of (a)(2) piping continues to drawing LR-205311(SH1), which was not submitted as part of the application.

Main Steam LR-205203(SH6) at H-7 Section of (a)(2) piping continues to drawing System LR-205245(SH3), which was not submitted as part of the application.

LR-205303(SH6) at H-7 Section of (a)(2) piping continues to drawing LR-205345(SH3), which was not submitted as part of the application.

Emergency LR-205241(SH1-6) at E-5 Section of (a)(1) piping continues to booster Diesel and E-7 rack without a continuation drawing provided.

Generators and Another section of (a)(1) piping ends without a Auxiliary continuation note.

Systems

Request:

Provide additional information to locate the license renewal boundary. If a section of pipe does not continue to a specific drawing number and location, then provide additional information describing the extent of the scoping boundary and any additional components between the continuation and the termination of the scoping boundary in that line. If the scoping classification of a section of piping changes over a continuation, provide additional information to clarify the change in scoping classification.

2.3.3.3 Chilled Water System The following RAIs were generated as part of the scoping and screening review for the Chilled Water System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.3-01

Background:

LRA section 2.1.5.1 states, Safety-related components in the SAP database were also reviewed and the system or structure associated with the safety-related component was included in scope under 10 CFR 54.4(a)(1) criteria.

Issue:

License renewal drawing LR-205216 (SH1), locations H-5, F-4 and F-7, shows a change of scope classification from 10 CFR 54.4 (a)(1) to 10 CFR 54.4 (a)(2) right after the 1/8 diameter orifices near valves 1CH28, 1CH6 and 1CH20. The piping class break is shown downstream of the 1/8 diameter orifices. The inclusion of safety-related piping in scope for (a)(2) would conflict with the scoping procedure described in LRA section 2.1.5.1.

Request:

Provide additional information to clarify the license renewal boundary for these locations.

RAI 2.3.3.3-02

Background:

LRA section 2.1.5.1 states, Safety-related components in the SAP database were also reviewed and the system or structure associated with the safety-related component was included in scope under 10 CFR 54.4(a)(1) criteria.

Issue:

License renewal drawing LR-205216 (SH2), locations H-7, G-4 and F-8, shows a change of scope classification from 10 CFR 54.4 (a)(1) to 10 CFR 54.4 (a)(2) right after the 1/8 diameter orifices near valves 2CH28, 2CH20 and 2CH6. The piping class break is shown downstream of the 1/8 diameter orifices. The inclusion of safety-related piping in scope for (a)(2) would conflict with the scoping procedure described in LRA section 2.1.5.1.

Request:

Provide additional information to clarify the license renewal boundary for these locations.

RAI 2.3.3.3-03

Background:

License renewal rule 10 CFR 54.21(a)(1) requires applicants to list all components subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.

Issue:

License renewal drawing LR-205216 (SH1), location D/E-6 shows several lines (2"-1CH1143 and 2"-1CH1142) out of the No. 1 expansion tank (1CHE1) as in scope for license renewal for 10 CFR 54.4 (a)(1) whereas similar lines (2"-2CH1105 and 2"-2CH110) out of the No. 2 expansion tank (2CHE8) on license renewal drawing LR-205216 (SH2), location D/E-3 are shown within scope for 10 CFR 54.4(a)(2)

Request:

Provide additional information explaining why there is a difference in scope classification in similar lines.

2.3.3.5 Component Cooling System The following RAIs were generated as part of the scoping and screening review for the Component Cooling System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.5-01

Background

LRA Section 2.1.5.2 Nonsafety-Related Affecting Safety-Related - 10 CFR 54.4(a)(2) states in part For a nonsafety-related piping system that is connected and provides structural support to a safety-related piping system, the nonsafety-related piping and supports should be included within the scope of license renewal up to and including the first anchor point past the safety-nonsafety interface.

Issue Anchors for nonsafety-related piping connected to safety-related piping on the following drawings and locations could not be located.

Drawing and Sheet Number Pipe Number and Location LR-205231 (SH1) 3-1075/(C-1) 3-1076/(D-1)

LR-205331 (SH1) 3-1083/(C-1) 3-1082/(D-1)

LR-205231 (SH3) 4-1312/(E-2) 4-1411/(E-3) 1-1361/(C-7) 1-1362/(F-7) 1-1376/(C-10) 1-1394/(F-10)

LR-205331 (SH3) 4-1346/(E-2) 4-1340/(E-3) 1-1344/(C-7) 1-1342/(F-7) 11345/(C-10) 1-1343/(F-10)

Request:

Provide additional information to locate the anchors for the pipelines listed above.

RAI 2.3.3.5-02

Background:

License renewal rule 10 CFR 54.21(a)(1) requires applicants to list all components subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.

Issue:

Drawing LR-205229 (SH1), location F-1, shows a section of pneumatic piping (1063 B-N) in scope for 10 CFR 54.4 (a)(2) that continues to drawing LR-205231(SH2) and LR-205315 (SH1.

The continuation on drawing LR-205231 (SH2), location G-4, is not within scope.

Request:

Provide additional information to clarify the scoping classification of the pneumatic piping sections associated with the Component Cooling System.

2.3.3.20 Radioactive Drain System The following RAIs were generated as part of the scoping and screening review for the Radioactive Drain System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.20-01

Background:

LRA Section 2.3.3.20 states in part The scoping boundary also includes the reactor coolant pump oil lift pump oil and water separators and associated piping and components.

Issue Drawing LR-205227 (SH3) shows the RCP lift pumps within scope for 10 CFR 54.4(a)(1) or (a)(3). However, the connected water separators and piping to trench 1WDE17 are not within scope. Drawing LR-205327 (SH3) does not show the RCP oil collection system, water separators and associated piping and components within scope Request:

Provide additional information to clarify why these nonsafety-related piping and components that contain water/oil, and are located inside structures that contain safety-related SSCs, are not included within scope for potential spatial interaction under criterion 10 CFR 54.4(a)(2).

RAI 2.3.3.20-02

Background:

License renewal rule 10 CFR 54.21(a) requires applicants to list all component types subject to an AMR. The staff confirms inclusion of all component types subject to an AMR by reviewing components within the license renewal boundary.

Issue Drawing LR-205330 (SH1), location A-4, shows a 10 CFR 54.4(a)(2) continuation from the No 21 and 22 primary water make-up pumps to LR-205327 (SH1), (C-2). The continuation on LR-205327 (SH1), (C-2) is shown as not within scope for license renewal.

Drawing LR-205327 (SH1), location C-2, shows a 10 CFR 54.4(a)(2) continuation from the No 21 & 22 waste monitor tanks to LR-205339 (SH1), (E-11). The continuation on LR-205339 (SH1), (E-11) is shown as not within scope for license renewal.

Drawing LR-205327 (SH1), location C-2, shows a 10 CFR 54.4(a)(2) continuation from 205330 (SH1), (A-4). The continuation on drawing LR-205327 (SH1) is shown as not within scope for license renewal.

Drawing LR-205327 (SH1), location C-2, shows a 10 CFR 54.4(a)(2) continuation from 205339 (SH1), (E-11). The continuation on drawing LR-205327 (SH1) is shown as not within scope for license renewal.

Request:

Provide additional information to clarify the scoping classification for this pipe section.

RAI 2.3.3.20-03

Background:

License renewal rule 10 CFR 54.21(a) requires applicants to list all component types subject to an AMR. The staff confirms inclusion of all component types subject to an AMR by reviewing components within the license renewal boundary.

Issue Drawing LR-205339 (SH2), location F-7, shows 2-1204 from the P.W.S.T. as within scope for 10 CFR 54.4(a)(1) or (a)(3). This line is continued from drawing LR-205330 (SH1), (A-7). The continuation on drawing LR-205330 (SH1), (A-7) is within scope for 10 CFR 54.4(a)(2).

Drawing LR-205330 (SH1), location A-7, shows line 2WL1192 as within scope for 10 CFR 54.4(a)(2). When continued on LR-205330 (SH2), (F-7) this line is within scope for 10 CFR 54.4(a)(1) or (a)(3).

Request:

Provide additional information to clarify the scoping classification for this pipe section.

2.3.3.21 Radwaste System The following RAI was generated as part of the scoping and screening review for the Radwaste System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.21-01

Background:

License renewal rule 10 CFR 54.21(a) requires applicants to list all component types subject to an AMR. The staff confirms inclusion of all component types subject to an AMR by reviewing components within the license renewal boundary.

Issue:

Drawing LR-205229 (SH1), location D-8, shows a pneumatic line (1065A-N) within scope for 10 CFR 54.4 (a)(2) that continues to Drawing LR-205315 (SH1). This line is not within scope on the continuation drawing LR-205315 (SH1), location H-11.

Drawing LR-205229 (SH1), location G-8, shows a pneumatic line (1078 A-N) within scope for 10 CFR 54.4 (a)(2) that continues to Drawing 205230 (SH1). This line is not within scope on the continuation drawing LR-205230 (SH1), location H-3.

Request:

Provide additional information to clarify the scoping classification for this pipe section.

2.3.3.22 Sampling System The following RAI was generated as part of the scoping and screening review for the Sampling System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.22-01

Background:

License renewal rule 10 CFR 54.21(a)(1) requires applicants to list all components subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.

Issue:

Unit 1 drawing LR-205244 (SH1), location F-5, shows 3/8-1042 H-N as within scope for 10 CFR 54.4(a)(2). Connected at three-way valve 1SS204 is a 1/2 O.D. tubing, 6714 Y-N, which is shown as not in scope for license renewal.

Unit 2 drawing LR-205344 (SH1), location F-5, shows 3/8-1042 H-N as within scope for 10 CFR 54.4(a)(2). Connected at three-way valve 2SS204 is a 1/2 O.D. tubing, 6714 Y-N, which is shown as not within scope for license renewal.

In both of these cases, two lines exiting the three way valve are in scope for 10 CFR 54.4(a)(2) while the third is not.

Request:

Provide additional information to clarify the scoping classification of this pipe section.

2.3.3.23 Service Water System The following RAIs were generated as part of the scoping and screening review for the Service Water System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.23-01

Background:

License renewal rule 10 CFR 54.21(a)(1) requires applicants to list all components subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.

Issue:

License renewal drawing LR-205212 (SH1), location A-7, shows a section 10 CFR 54.4 (a)(1) 6 service water line continuing to drawing LR-205309 (SH3), location E-9, where the same line continuation is not in scope.

Request:

Provide additional information to clarify the scoping classification of this pipe section.

RAI 2.3.3.23-02

Background:

LRA Section 2.1.5.2 Nonsafety-Related Affecting Safety-Related - 10 CFR 54.4(a)(2) states in part For a nonsafety-related piping system that is connected and provides structural support to a safety-related piping system, the nonsafety-related piping and supports should be included within the scope of license renewal up to and including the first anchor point past the safety-nonsafety interface.

Issue Unit 1 drawing LR-205239 (SH1), location H-2, shows 2-1SW1460 as within scope for 10 CFR 54.4(a)(1). Connected to 2-1SW1460 are 10 CFR 54.4(a)(2) 2-1295, 2-1292, 2-1293 and 3/4-1291 lines.

Unit 2 drawing LR-205339 (SH1), location H-2, shows 2-1053 as within scope for 10 CFR 54.4(a)(1). Connected to 2-1053 are 10 CFR 54.4(a)(2) 2-1WL1295, 2-1074, 3/4-1318 lines.

The (a)(2) scoping boundary ends before these lines reach the waste monitor tanks or pumps.

No anchor point was identified between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

Request:

Provide additional information to locate the seismic anchors or anchored components between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

RAI 2.3.3.23-03

Background:

LRA Section 2.1.5.2 Nonsafety-Related Affecting Safety-Related - 10 CFR 54.4(a)(2) states in part For a nonsafety-related piping system that is connected and provides structural support to a safety-related piping system, the nonsafety-related piping and supports should be included within the scope of license renewal up to and including the first anchor point past the safety-nonsafety interface.

Issue:

Unit 1 drawing LR-205242 (SH1), location E-6, shows a continuation (1 S.L.) from LR-205209 (SH4), (H-1) as within the scope for 10 CFR 54.4 (a)(2). This line is connected to a 3 service water line within scope for 10 CFR 54.4 (a)(1). The seismic anchor or anchored component for the 1 (a)(2) line could not be located.

Unit 2 drawing LR-205342 (SH1), location C-8, shows a continuation (1 S.L.) from LR-205209 (SH4), (H-1) as within the scope for 10 CFR 54.4 (a)(2). This line is connected to a 1 service water line within scope for 10 CFR 54.4 (a)(1). The seismic anchor or anchored component for the 1 (a)(2) line could not be located.

Request:

Provide additional information to locate the seismic anchor or anchored component between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

RAI 2.3.3.23-04

Background:

LRA Section 2.1.5.2 Nonsafety-Related Affecting Safety-Related - 10 CFR 54.4(a)(2) states in part For a nonsafety-related piping system that is connected and provides structural support to a safety-related piping system, the nonsafety-related piping and supports should be included within the scope of license renewal up to and including the first anchor point past the safety-nonsafety interface.

Issue License renewal drawing LR-205242 (SH3), location B-4, shows a 3/4 10 CFR 54.4 (a)(1) line connected to a 10 CFR 54.4 (a)(2) line (7003 Y-N). The seismic anchor or anchored component for the (a)(2) line could not be located.

Request:

Provide additional information to locate the seismic anchors or anchored components between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

2.3.3.25 Spent Fuel Cooling System The following RAI was generated as part of the scoping and screening review for the Spent Fuel Cooling System for the Salem Nuclear Generating Station LRA.

RAI 2.3.3.25-01

Background:

LRA Section 2.1.5.2 Nonsafety-Related Affecting Safety-Related - 10 CFR 54.4(a)(2) states in part For a nonsafety-related piping system that is connected and provides structural support to a safety-related piping system, the nonsafety-related piping and supports should be included within the scope of license renewal up to and including the first anchor point past the safety-nonsafety interface.

Issue:

Anchors for nonsafety-related piping connected to safety-related piping on the following drawings and locations could not be located.

Drawing and Sheet Number Pipe Number and Location LR-205233(SH1) 3-1074/(H-2) 3-1031/(E-2) 2-1043/(A-3)

LR-205333(SH1) 3-1013/(H-2) 3-1140/(E-2) 2-1097/(A-3)

Request:

For the above lines, provide additional information to locate the seismic anchors or anchored components between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.