ML031280135

Response to Request for Additional Information Regarding Reactor Pressure Vessel Nozzle Weld Inspection

ML031280135
Person / Time
Site:	Hope Creek  (NPF-057)
Issue date:	05/01/2003
From:	Salamon G Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LRN-03-0200, TAC MB7839
Download: ML031280135 (18)

Text

PSEG Nuclear LLC P.O Box 236, Hancocks Bndge, New Jersey 08038-0236 MAM 1-2003 -'

LRN-03-0200 United States Nuclear Regulatory Commission 0 PSEG Document Control Desk Nuclear LLC Washington, DC 20555 Gentlemen:

REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354

SUBJECT:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL NOZZLE WELD INSPECTION (TAC NO. MB7839)

HOPE CREEK GENERATING STATION By letter dated February 20, 2003, PSEG Nuclear LLC (PSEG) requested relief (HC-RR-B08) from the requirements of sub paragraph Figures IWB-2500-7 (a) and (b) of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xi, 1989 Edition, in order to implement the alternative reduced volume of one-half (1/2) from the weld per ASME Code Case N-613-1. This request for relief is applicable to the second 10-year inservice inspection (ISI) interval The Nuclear Regulatory Commission staff discussed the subject relief request with PSEG staff on April 9, April 16, and April 21, 2003 and requested additional information and clarification be provided. Pursuant to that request, PSEG is submitting the enclosed response to the request for additional information.

Should you have any questions regarding this request, please contact Mr. Howard Berrick at 856-339-1862.

Manager - Nuclear Safety and Licensing Enclosure - Response to Request for Additional Information for Relief Request HC-RR-B08 - ASME Boiler and Pressure Vessel Code Case N-613-1 - Hope Creek Affected Components - Hope Creek Reactor Vessel Nozzle Design Configuration Drawings - Hope Creek Reactor Vessel Nozzle Repair Weld Drawings 95-2168 REV 7/99

Document Control Desk LRN- 03-0200 MAY 0 1 2003 C

Mr. H. Miller Regional Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission ATTN: Mr. G. Wunder Licensing Project Manager - Hope Creek Mail Stop 08B1 Washington DC 20555-001 USNRC Senior Resident Inspector - Hope Creek (X24)

(w/o enclosure)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 (w/o enclosure) 2

Document Control Desk ENCLOSURE LRN- 03-0200 REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION By letter dated February 20, 2003, PSEG Nuclear LLC (PSEG) requested relief (HC-RR-B08) from the requirements of sub paragraph Figures IWB-2500-7 (a) and (b) of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, in order to implement the alternative reduced volume of one-half inch (1/2") from the weld per ASME Code Case N-613-1, at the Hope Creek Generating Station.

The Nuclear Regulatory Commission staff discussed the subject relief request with PSEG staff on April 9, April 16, and April 21, 2003. The Nuclear Regulatory Commission staff has requested answers to the following questions regarding the previously submitted relief request:

Question 1:

You are proposing to reduce the examination volume currently described in Figure IWB-2500-7 of Section Xl of the ASME Boiler and Pressure Vessel Code (Code) to a volume that would encompass the weld and base metal one-half inch on either side of the weld.

The basis for relief describes the examination volume as one-half inch base metal on either side of the weld at the widest part of the weld, for reactor pressure vessel (RPV) nozzles. Provide a sketch showing the configuration [IWB-2500 (a), or (b)] and examination volume. Please list all nozzle-to-vessel welds included within the scope of this request.

Response

PSEG Nuclear proposes to utilize Code Case N-613-1 Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D Item No.'s B3.10 and B3.90, Reactor Nozzle to Vessel welds, Figs. IWB-2500-7 (a), (b), and (c), Section Xl Division 1. Code Case N-613-1, Figure 2, Nozzle in Shell or Head (Examination Zones in Flange Type Nozzles Joined by Full Penetration Butt Welds) as the basis for examination volume. [Attachment 1] The examination volume depicted, as A-B-C-D-E-F-G-H within Figure 2 will be applied. Dose rates of Hope Creek's reactor vessel nozzle to vessel welds range from approximately 0.80 - 10.0 R on contact. Reduction of the examination volume in accordance with this request for relief would lessen examination time and reduce personnel exposure by approximately 75%. lists all nozzle-to-vessel welds included within the scope of this request and its configuration design.

Copies of Hope Creek's reactor vessel nozzles design configuration drawings are contained within for purposes of further clarification and information.

3

Document Control Desk ENCLOSURE LRN- 03-0200 Question 2:

You state that the current Code requirements for base material adjacent to these welds (Code-required volume extends to one-half the vessel wall thickness) contain volumes not prone to inservice cracking, and you further state that creation of flaws during plant service is unlikely due to the low stresses in the base metal away from the weld.

(a) Please provide a technical basis to conclude that portions of the base metal over the entire regions currently specified by the Code are not susceptible to service-induced degradation.

(b) Please provide analyses to indicate the extent and magnitude of stresses associated with RPV nozzle-to-vessel welds at Hope Creek in support of the contention that creation of flaws during plant service is unlikely due to the low stresses in the base metal away from the weld.

Response

(a)

As previously stated in response to Quest-on No. 1, PSEG Nuclear proposes to utilize Code Case N-613-1 [Attachment 1] as the basis for examination volume which requires Category B-D nozzle-to-vessel welds to be previously examined ultrasonically using the examination volumes of Figures IWB-2500-7 (a), (b), and (c). The applicable examination volume depicted as A-B-C-D-E-F-G-H within these figures will be applied for all nozzle-to-vessel welds listed in Attachment 2.

The procedures used have been satisfactorily demonstrated in accordance with the requirements of the ASME Section Xl, Appendix Vill, Supplements 4, 6 and 7 (for the inner 15%) of the 1995 Edition with Editions and Addenda through 2000, as modified by the Performance Demonstration Initiative (PDI) program description. This demonstration was also conducted in accordance with the requirements of the Federal Register, Part II, Nuclear Regulatory Commission, 10CFR Part 50, Industry Codes and Standards; Amended Requirements; Final Rule dated September 26, 2002.

PSEG Nuclear has previously completed full volume examinations of the welds listed in during preservice and inservice examinations. Preservice examinations were conducted in accordance with ASME Xl 1977 Edition up through and including Summer 1978 Addenda as amended by 1 OCFR50.55a(b)(2)(IV)(a). The first Inservice Inspection (ISI) ten-year inspection interval exams were conducted in accordance with the 1983 Edition of ASME Xl. In addition, the following Reactor Pressure Vessel (RPV) nozzle-to-vessel welds ultrasonic exams have been completed during the current second ten-year ISI interval, 15 period (May 2000):

RPV1-NlA, N2A, N2B, N2C, N2J, N2K, N5A, N5B, and N9A. There have been no indications observed as a result of these examinations that required evaluation in accordance with the requirements of ASME IWB-3512.

(b)

The technical basis for this approach proposed is derived from EPRI Technical Report 1003557 BWRVIP-108: BWR Vessel and Internals Project-Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii and GE Nuclear Energy: Hope Creek Feedwater Nozzle Fracture Mechanics Analysis Report NDEC-32480P Rev. 1, September 2001.

PSEG Nuclear will continue to perform ultrasonic examinations in accordance NUREG-0619 requirements and earlier regulatory commitments.

4

Document Control Desk ENCLOSURE LRN- 03-0200 Question 3:

A significant issue is related to as-built weld configurations that may exist at Hope Creek, the interpretation of ultrasonic signals, and assurance of volumetric coverage. Because the examination of the subject nozzles is primarily by remote (automated ultrasonic methods that are implemented from the inner clad surface of the RPV), it is unclear how you will be able to locate the extremities (widest sections) of the nozzle-to-vessel welds precisely. It is not clear how repaired areas (fabrication or inservice) extending beyond the ideal weld cross-sectional area are identified and how these areas will be examined.

(a) Please discuss the documentation available of the actual cross-sectional dimensions and precise locations of repaired areas for all RPV nozzle-to-vessel welds at Hope Creek.

Please discuss the process for defining new examination volumes that encompass these repair weld areas.

(b) Please describe the process for accurately determining the location of ultrasonic reflectors with respect to the proposed new examination volumes.

Response

(a) Hope Creek reactor vessel weld repairs to the reactor vessel base material areas are identified within PSEG Nuclear drawings PNI-Bll-AOOI-0151 sheets 1 and 2. Review of the drawings determined that the repairs completed are encapsulated within the existing nozzle-to-vessel weld. (Reference Attachment 4)

(b) The examination of the subject nozzles is primarily conducted by manual ultrasonic methods as accessed from the exterior surface of the RPV. These exams will be conducted using techniques designed for detection and sizing of surface and subsurface flaws within the examination volume (A-B-C-D-E-F-G-H) oriented in a plane normal to the vessel inside surface and both transverse and parallel to the weld identified in Attachment 1 (Code Case N-613-1),

Figure 2, Nozzle in Shell or Head (Examination Zones in Flange Type Nozzles Joined by Full Penetration Buff Welds). Exam personnel are fully capable of visually identifying the extremities (widest sections) of the nozzle-to-vessel weld.

As previously stated in the response to Question 2, the procedures used have been satisfactorily demonstrated in accordance with the requirements of the ASME Section Xl, Appendix Vill, Supplements 4, 6 and 7 (for the inner 15%) of the 1995 Edition with Editions and Addenda through 2000, as modified by the Performance Demonstration Initiative (PDI) program description and 10CFR50.55a.

References:

1. GE Nuclear Energy: Hope Creek Feedwater Nozzle Fracture Mechanics Analysis Report NDEC-32480P Rev. 1, September 2001. (PSEG Vendor Document # 325179)

2. EPRI Technical Report 1003557 BWRVIP-108: BWR Vessel and Internals Project-Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii

3. ASME Xl Code Case N-613-1 5

Document Control Desk LRN- 03-0200 ATTACHMENT I ASME Boiler and Pressure Vessel Code Case N-613-1 Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D, Item No's. B3. 10 and B3.90, Reactor Nozzle-To-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c)

Section Xl, Division 1.

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, M-N-O-P NOTES:

11) Examination glons are Identliled for the lwriose of differaoifating the acptane atdasrds In MB4512.

12) Examination volumes may be determined either by direct messuramontf on the componen or by measurements based on design drawings' 5 n FI163 NOZZLE IN SHELL OR-HEAD (Examination Zones In Set-On Type Nomles Joined by Full Penetration Corner Wekis) 5

Document Control Desk LRN- 03-0200 ATTACHMENT 2 Hope Creek Nozzle-to-Vessel Welds Within Scope of Request 1

ATTACHMENT 2 Document Control Desk LRN- 03-0200 Hope Creek Nozzle-to-Vessei Welds Within Scope of Request Full Nozzle Coverage Summary No Component ID Description Configuration Exam Previously Completed 100185 RPVI-NIA Loop A Recirculation System Outlet Code Case N-613-1 Yes 100195 RPV1-NA RAt 0 Deg Nozzle to Vessel Weld Figure 2 Loo0 R Recirculation System Outlet Code Case N-613-1 1001905 RPVI-NIB Loopclaio B

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Figure 2 Yes 100210 RPV1 -N 1 B At 180 Deg Nozzle to Vessel Weld Figure 2 Yes Recirculation System Inlet At 30 Deg Code Case N-613-1 100195 RPV1-N2A Nozzle to Vessel Weld Figure 2 Yes 100200 RPV1-N2B Recirculation System Inlet At 60 Deg CodeCase N13-1es 1002300

[ RPVI-N2B Deg Nozzle to Vessel Weld Figure 2 Yes Recirculation System Inlet At 90 Deg Code Case N-613-1 100205 RPV1-N2C Nozzle to Vessel Weld Figure 2 Yes Recirculation System Inlet At 120 Code Case N-613-1 100210 RPV1-N2D Deg Nozzle to Vessel Weld Figure 2 Yes 101 RPINE Recirculation System Inlet At 150 FigurCae 2

Yes-100215 RPV1-N2E Deg Nozzle to Vessel Weld Fgr e

Recirculation System Inlet At 21 0 Code Case N-613-1 100220 RPV1 -N2F Deg Nozzle to Vessel Weld Figure 2 Yes 1025 RV NG Recirculation System Inlet At 240 FigurCae 2

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Recirculation System Inlet At 270 Code Case N-613-1 100230 RPV1-N2H DgNzltoVseWldFigure 2

Yes Recirculation System Inlet At 300 Code Case N-613-1 100235 RPVI-N2J Deg Nozzle to Vessel Weld Figure 2 Yes Recirculation System Inlet At 330 Code Case N-613-1 100240 RPV1-N2K Deg Nozzle to Vessel Weld Figure 2 Yes Main Steam Outlet Nozzle to Vessel Code Case N-613-1 100245 RPV1-N3A Weld Figure 2 Yes IMain Steam Outlet Nozzle to Vessel Code Case N-6i13-1 100250 RPV1IN3B Weld Figure 2 Yes 2

Document Control Desk LRN- 03-0200 ATTACHMENT 2 Hope Creek Nozzle-to-Vessel Welds Within Scope of Request Full Summary Nozzle Coverage No Component ID Description Conigurion Exam Confguraion Previously Completed Main Steam Outlet Code Case N-613-1 100255 RPV1-N3C Nozzle to Vessel Weld Figure 2 Yes Main Steam Outlet Code Case N-613-1 100260 RPV1-N3D Nozzle to Vessel Weld Figure 2 Yes 100265 RPVI-N4A Feedwater Inlet Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100270 RPVI-N4B Feedwater Inlet Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100275 RPVI-N4C Feedwater Inlet Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100280 RPVI-N4D Feedwater Inlet Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100285 RPVI-N4E Feedwater Inlet Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100290 RPV-N4F Feedwater Inlet Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100295 RPVI-N5A Core Spray Inlet At 120 Deg Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100 RP-5B Core Spray Inlet At 240 Deg Code Case N-613-1 100300 RPV1-N5BNozzle to Vessel Weld Figure 2 Yes 100404 RPV1-N6A Head Spray Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 100405 RPVI-N6B Spare Head Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes 6Head Vent Code Case N-613-1 Nozzle to Vessel Weld Figure 2 Yes Jet Instrumentation Code Case N-613-1 100320 RPVI-N8A Nozzle to Vessel Weld Figure 2 Yes Jet Instrumentation Code Case N-613-1 100325 RPV1-N8B Nozzle to Vessel Weld Figure 2 Yes 100330 RPV1-N9A Control Rod Drive (CRD) Hydraulic Code Case N-613-1 Return Nozzle to Vessel Weld Figure 2 Yes 3

Document Control Desk ATTACHMENT 2 LRN- 03-0200 Hope Creek Nozzle-to-Vessel Welds Within Scope of Request Full Summry Nzzle Coverage Summary Component ID Description Configuration PEiul Completed 1040 RV-IA Low Pressure Core Injection (LPCI)

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Yes-100400 RPV1-N17A Nozzle to Vessel Weld At45 Deg Figure_2_Yes 100401 RPVI-NI7B Low Pressure Core Injection (LPCI)

Code Case N-613-1 Yes 10041 RV1-17B Nozzle to Vessel Weld At 135 Deg Figure__2_Yes 1042 P1-IC Low Pressure Core Injection (LPCI)

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100403 Low PressureCeoirwe In Ati ICode Case N-61 3-1 100403 RPV1-N17D Lo rsueCr Ineto LC)

Figure 2 Yes Nozzle to Vessel Weld At 315 Deg

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Document Control Desk ATTACHMENT 3 LRN- 03-0200 Hope Creek Reactor Vessel Nozzle Design Configuration Drawings 1

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Document Control Desk LRN- 03-0200 ATTACHMENT 4 Hope Creek Reactor Pressure Vessel Nozzle RPV Repair Weld Drawings Hard copy of following General Electric I Babcock-Hitachi K.K. Drawings attached:

PN1-B11-AO01-0151, shts.1&2 PN1-BI1-AOO1-0152, shts.1& 2