ML100750331

Request for Additional Information Regarding Scoping and Screening Results for the Hope Creek Generating Station (Tac ME1832)

ML100750331
Person / Time
Site:	Hope Creek
Issue date:	04/15/2010
From:	Ashley D License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group, Public Service Enterprise Group
Ashley D, NRR/ADRO/DLR, 415-3191
References
TAC ME1832
Download: ML100750331 (14)

Text

April 15, 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 SCOPING AND SCREENING RESULTS FOR THE HOPE CREEK GENERATING STATION (TAC NO ME1832)

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 NPF-57 for the Hope Creek Generating Station (HCGS). 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 by Bennett Brady for/

Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

As stated cc w/encl: See next page

April 15, 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 SCOPING AND SCREENING RESULTS FOR THE HOPE CREEK GENERATING STATION (TAC NO ME1832)

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 NPF-57 for the Hope Creek Generating Station (HCGS). 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 by Bennett Brady for/

Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION: See next page ADAMS Accession Number: ML100750331 OFFICE LA:DLR PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1 NAME YEdmonds DAshley BPham DAshley (BBennett for) (BBennett for)

DATE 04/13/10 04/15/10 04/15/10 04/15/10 OFFICIAL RECORD COPY

Letter to PSEG Nuclear from D. Ashley, dated April 15, 2010 DISTRIBUTION:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING AND SCREENING RESULTS FOR THE HOPE CREEK GENERATING STATION (TAC NO ME1832)

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsOgcMailCenter Resource BPham DAshley REnnis MModes, RI ABurritt, RI RConte, RI

Hope Creek Generating Station cc:

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

Hope Creek Generating Station cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079

REQUEST FOR ADDITIONAL INFORMATION BALANCE OF PLANT SYSTEMS BRANCH DIVISION OF SAFETY SYSTEMS FOR THE HOPE CREEK NUCLEAR GENERATING STATION LRA (TAC NO. ME1832) 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 Chilled Water LR-M-87-1(SH5) at C-4, Section of (a)(2) piping is continued to drawing System C-6, and D-5 LR-M-61-1(SH1). The continuation could not be located.

LR-M-87-1(SH2) at E-6 Section of (a)(2) piping is continued from drawing LR-M-43-1(SH1). The continuation could not be located.

Closed Cycle LR-M-13-1(SH1) at D-3 Section of 1 (a)(1) piping ends without a Cooling Water and D-4 continuation note.

Standby Diesel LR-M-30-1(SH4) at C-4 Section of (a)(1) piping continues to to control Generators and air supply transmitters without a drawing Auxiliary location identified.

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 verifying that there are no 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.

ENCLOSURE

2.3.3.2 Closed Cycle Cooling Water System The following RAI was generated as part of the scoping and screening review for the Closed Cycle Cooling Water System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.2-01

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:

Drawing LR-M-13-1 (SH1), locations D-3 and D-5, show 10 CFR 54(a)(1) lines 4-HBB-024 and 4-HBB-023 connected to 10 CFR 54(a)(2) lines 6-HBD-003 and 4-HBD-018. The anchors on the 6-HBD-003 and 4-HBD-018 lines could not be located.

Request:

Provide additional information to locate the anchors for the 6-HBD-003 and 4-HBD-018 lines between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

2.3.3.5 Control Area Chilled Water System The following RAI was generated as part of the scoping and screening review for the Control Area Chilled Water System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.5-01

Background:

LRA Section 2.1.5.1 states, Systems and structures that are identified as safety-related in the UFSAR or in design basis documents have been classified as satisfying criteria of 10 CFR 54.4(a)(1) and have been included within the scope of license renewal. 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 the 10 CFR 54.4(a)(1) criterion.

Issue:

License renewal drawing LR-M-90-1 (SH3), locations C-5 and H-5, shows a portion of piping in scope for 10 CFR 54.4(a)(1) up to valves V9990 and V9982. The drawing indicates that downstream of the valves the piping is within scope for 10 CFR 54.4(a)(2) but is still Q-listed

and seismic Category 1. This appears to be safety-related piping in scope for (a)(2), which would conflict with the scoping procedure described in the application.

Request:

Provide additional information to clarify the scoping classification on the above drawing.

2.3.3.14 Fuel Pool Cooling and Cleanup System The following RAIs were generated as part of the scoping and screening review for the Fuel Pool Cooling and Cleanup System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.14-01

Background:

LRA Section 2.3.3.14, Fuel Pool Cooling and Cleanup System, states that components are within the scope of license renewal for 10 CFR 54.4(a)(1), 10 CFR 54.4(a)(2) and 10 CFR 54.4(a)(3) and have intended functions of providing mechanical closure, direct flow, pressure boundary, leakage boundary, spray, and throttle.

Issue:

Drawing LR-M-53-1 (SH1), locations B-7 and B-8, show starter strainers (TS 182 and TS 181) in 10 CFR 54.4(a)(1) lines 8-HBC-042 and 8-HBC-047, respectively, that are not included as a component type in LRA Table 2.3.3-14.

Request:

Provide additional information to explain why these within scope strainers are not included as a component type with their intended function in LRA Table 2.3.3-14.

RAI 2.3.3.14-02

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:

LR-M-53-1 (SH1), at the locations listed below, show 10 CFR 54.4(a)(2) pipelines that transfer clean radwaste (CRW) to equipment drain sumps connected to 10 CFR 54.4(a)(1) pipelines:

- Location A-3, pipeline 4-HBD-036

- Location A-5, pipeline 1-HBD-144

- Location A-7, pipeline 1-HBD-055

- Location A-8, pipeline 1-HBD-046

- Location B-4, pipeline 1-HBD-143

- Location B-5, pipeline from PSV4674B

- Location B-7, pipeline from V037

- Location B-8, pipeline 1-HBD-044

- Location C-5, pipeline 1-HBD-070

- Location D-2, pipeline 1-HBD-025

- Location E-5, pipeline 2-HBD-032

- Location E-8, pipeline 4-HBD-083

- Location B-2, pipeline 10-HCD-073 to and from the Condensate Storage Tank.

Anchor points on the above lines could not be located.

Request:

Provide additional information to locate the anchors for the pipelines listed above between the end of the (a)(2) scoping boundary and the safety-nonsafety interfaces.

2.3.3.18 Makeup Demineralizer System The following RAIs were generated as part of the scoping and screening review for the Makeup Demineralizer System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.18-01

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:

Drawing LR-M-11-1 (SH1), locations H-5 and E-5, show 10 CFR 54(a)(1) lines 2-HCC-111 and 2-HCC-112 continued to 10 CFR 54 (a)(2) lines AN-2-HCD-001.

The anchor for the two AN-2-HCD-001 lines could not be located.

Request:

Provide additional information to locate the anchor for the two AN-2-HCD-001 lines between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

RAI 2.3.3.18-02

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:

LR-M-90-1 (SH3), location D-6 and E-6, shows 10 CFR 54(a)(1) lines 18-HCC-187, 18-HCC-188 and 18-HCC-189 continued to 10 CFR 54(a)(2) lines 2-HCD-022, 2-HBD-133 and 2-HBD-132.

Drawing LR-M-90-1 (SH2), location D-6, shows 10 CFR 54(a)(1) Head Tank BT 410 connected to 10 CFR 54(a)(2) line 2-HCD-024.

The anchor for lines 2-HCD-022, 2-HBD-133, 2-HBD-132 and 2-HCD-024 could not be located.

Request:

Provide additional information to locate the anchors for lines 2-HCD-022, 2-HBD-133, 2-HBD-132 and 2-HCD-024 between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

RAI 2.3.3.18-03

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:

Drawing LR-30-1 (SH2), locations G-2, G-3, G-5 and G-7, show 10 CFR 54(a)(1) lines 1-HBC-098, 1-HBC-096, 1-HBC-097 and 1-HBC-095 continued to 10 CFR 54(a)(2) lines 1-HCD-232, 1-HCD-230, 1-HCD-231 and 1-HCD-229.

The anchor points for lines 21-HCD-232, 1-HCD-230, 1-HCD-231 and 1-HCD-229 could not be located.

Request:

Provide additional information to locate the anchors for lines 1-HCD-232, 1-HCD-230, 1-HCD-231 and 1-HCD-229 between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

2.3.3.21 Process and Post-Accident Sampling Systems The following RAI was generated as part of the scoping and screening review for the Process and Post-Accident Sampling Systems for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.21-01

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:

Drawing LR-M-38-0 (SH1), location B-7, shows line 1-DBB-006 within scope of license renewal for 10 CFR 54.4(a)(1) attached to tubing that is not in scope. The anchor for line 1-DBB-006 could not be located.

Request:

Provide additional information to clarify the scoping classification of this line. Provide additional information to locate the anchor for the line 1-DBB-006 after the safety-nonsafety interface.

2.3.3.22 Radwaste System The following RAIs were generated as part of the scoping and screening review for the Radwaste System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.22-01

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:

License renewal drawing LR-M-61-1 (SH1), locations G-6 and G-7, show a 3 10 CFR 54.4 (a)(1) line (3-HBB-014) connected to 10 CFR 54.4 (a)(2) lines (3-HBD+-013 and 3-HBD+-

017).

The seismic anchor or anchored component for the 10 CFR 54.4 (a)(2) lines (3-HBD+-013 and 3-HBD+-017) could not be located.

Request:

Provide additional information to locate the seismic anchors or anchored components for the 3-HBD+-013 and 3-HBD+-017 lines between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

RAI 2.3.3.22-02

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:

License renewal drawing LR-M-61-1 (SH 2), locations G-6 and G-7, show a 3 10 CFR 54.4(a)(1) line (3-HBB-023) connected to a 10 CFR 54.4 (a)(2) lines (3-HBD+-022 and 3-HBD+-019).

The seismic anchor or anchored component for the 10 CFR 54.4 (a)(2) lines (3-HBD+-022 and 3-HBD+-019) could not be located.

Request:

Provide additional information to locate the seismic anchors or anchored components for the 3-HBD+-022 and 3-HBD+-019 lines between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

2.3.3.31 Torus Water Cleanup System The following RAI was generated as part of the scoping and screening review for the Torus Water Cleanup System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.3.31-01

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 affecting safety-related piping at the following locations could not be located.

• LR-M-53-1 SH 2, location D-5, 6 inch line (EE-6-HCD-009)

• LR-M-53-1 SH 1, locations C-3 and C-4, 8 inch lines (8-HBD-002 and 8-HCD-001)

Request:

Provide additional information to locate the anchors for the EE-6-HCD-009, 8-HBD-002 and 8-HCD-001 lines between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.

2.3.4.1 Condensate Storage and Transfer System The following RAI was generated as part of the scoping and screening review for the Condensate Storage and Transfer System for the Hope Creek Nuclear Generating Station LRA.

RAI 2.3.4.1-01

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:

Drawing LR-M-51-1 (SH1), location H-6, shows 10 CFR 54.(a)(2) line AP-4-HCD-022 connected to 10 CFR 54.(a)(1) line AP-4GBB-030.

The anchors for AP-4-HCD-022 could not be located.

Request:

Provide additional information to locate the anchors for this line between the end of the (a)(2) scoping boundary and the safety-nonsafety interface.