ML020590404
| ML020590404 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/11/2002 |
| From: | Salamon G Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LRN-02-0045, SC-RR-B06 | |
| Download: ML020590404 (6) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 FEB 1 1_2002 LRN-02-0045 0 PSEG Nuclear LLC United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Gentlemen:
INSERVICE INSPECTION PROGRAM RELIEF REQUEST SC-RR-B06 SALEM GENERATING STATION - UNIT I and 2 FACILITY OPERATING LICENSES DPR-70 and DPR-75 DOCKET NOS. 50-272 and 50-311 Pursuant to 10CFR50.55a(a)(3)(i), PSEG Nuclear is submitting Inservice Inspection (ISI) relief request SC-RR-B06 for NRC approval. The attached relief request proposes that a remote visual examination of the M-N surface [as shown in Figures IWB-2500-7 (a) through (d)] be performed on sixteen (16) Class 1 Reactor Pressure Vessel (RPV)
Nozzle Inside Radius Sections, in lieu of the volumetric examination requirements of ASME Section Xl, Table IWB-2500-1, Examination Category B-D, Item No. B3.100.
This relief request is applicable to the Salem Unit 1, 10-year second interval vessel examination scheduled for the spring of 2002. The performance of the enhanced visual examination of the M-N surface is expected to reduce vessel examination time, which translates into significantly reduced personnel radiation exposure and significant cost
- savings, The attachment to this letter includes the proposed alternative and supporting justification for the relief. Based on the evaluation contained in the attachment, PSEG Nuclear has concluded that the proposed alternative provides an acceptable level of quality and safety. Accordingly, this proposal satisfies the requirements of 10 CFR 50.55a(a)(3)(i).
Should you have any questions regarding this request, please contact Mr. Howard Berrick at 856-339-1862.
G. Salamon Manager - Nuclear Safety and Licensing
Attachment:
ISI Relief Request No. SC-RR-B06 A60I' 95-2168 REV. 7/99
Document Control Desk
-2 LRN-02-0045 FEB 1 1 200?
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. R. Fretz Licensing Project Manager - Salem Mail Stop 08B2 Washington, DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625
Attachment I PSEG NUCLEAR LLC SALEM GENERATING STATION ISI RELIEF REQUEST SC-RR-B06 Component Description LRN-02-0045 Alternative Requirements for Inner Radius Examinations of Class1 Reactor Vessel Nozzles ASME Section Xl Class: 1 Code Requirement Examine sixteen (16) Class 1 Reactor Pressure Vessel (RPV) Nozzle Inside Radius Sections in accordance with ASME Section Xl, Class 1 Examination Category B-D, Item B3.100 requirements at Salem Nuclear Generating Station Units 1 and 2.
Salem Unit 1 ASME Section Xl Class 1, ASME Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 1995 Edition up through and including 1996 Addenda; IWB-2500-1, Examination Category B D, Full Penetration Welded Nozzles In Vessels, Code Item B3.100, Figures IWB 2500-7 (a) through (d).
Summary Number Examination Area Configuration Identification 002900 29-RPV-1110-IRS Outlet Nozzle @ 202 degrees 003100 29-RPV-1 120-IRS Outlet Nozzle @ 338 degrees 003300 29-RPV-1 130-IRS Outlet Nozzle @ 158 degrees 003500 29-RPV-1 140-IRS Outlet Nozzle @ 22 degrees Salem Unit 1 RPV Inlet Nozzle Inner Radius Exams Summary Number Examination Area Configuration Identification 003000 27.5-RPV-1110-IRS Inlet Nozzle @ 247 degrees 003200 27.5-RPV-1 120-IRS Inlet Nozzle @ 293 degrees 003400 27.5-RPV-1 130-IRS Inlet Nozzle @ 113 degrees 003600 27.5-RPV-1 140-IRS Inlet Nozzle @ 67 degrees Salem Unit I RPV Outlet Nozzle Inner Radius Exams
PSEG NUCLEAR LLC SALEM GENERATING STATION ISI RELIEF REQUEST SC-RR-B06 Salem Unit 2 ASME Section XI Class 1, ASME Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 1986 Edition with no Addenda; IWB-2500-1, Examination Category B-D, Full Penetration Welds Of Nozzles In Vessels, Code Item B3.100, Figures IWB-2500-7 (a) through (d).
Salem Unit 2 RPV Outlet Nozzle Inner Radius Exams Summary Number Examination Area Configuration Identification 003700 29-RCN-1230-IRS Outlet Nozzle @ 22 degrees 004000 29-RCN-1240-IRS Outlet Nozzle @ 158 degrees 004100 29-RCN-1220-IRS Outlet Nozzle @ 203 degrees 004400 29-RCN-1210-IRS Outlet Nozzle @ 338 degrees Salem Unit 2 RPV Inlet Nozzle Inner Radius Exams Summary Number Examination Area Configuration Identification 003800 27.5-RCN-1230-IRS Inlet Nozzle @ 67 degrees 003900 27.5-RCN-1240-IRS Inlet Nozzle @ 113 degrees 004200 27.5-RCN-1242-IRS Inlet Nozzle @ 247 degrees 004300 27.5-RCN-1210-IRS Inlet Nozzle @ 293 degrees Basis for Relief Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative examination provides an acceptable level of quality and safety and the granting of relief should not jeopardize the health and safety of the public.
As an alternative to ASME Section Xl Table IWB-2500-1, Examination Category B-D, Item B3.100, which requires volumetric examination (Ultrasonic - UT) for Inner Radius of Class 1 Reactor Vessel Nozzles at Salem Units 1 & 2, PSEG Nuclear LLC proposes to perform a VT-1, Visual Examination of the surface M-N shown in Figures IWB-2500-7 (a) through (d) for those components previously identified above.
LRN-02-0045
PSEG NUCLEAR LLC SALEM GENERATING STATION ISI RELIEF REQUEST SC-RR-B06 PSEG Nuclear Salem Units 1 and 2 are currently required to perform inservice examinations of these selected areas in accordance with the requirements of 1 OCFR50.55a, and ASME Section Xl (Code Editions and Addenda are previously listed above). According to a NRC memorandum (Reference No. 1), the NRC staff indicated that an ultrasonic examination could be replaced by a VT-I visual examination for the proposed nozzle inspections on the basis surveillance is maintained and VT-1 visual examination is performed.
The implementation of this relief is also expected to reduce vessel examination time by approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which translates to significantly reduced personnel radiation exposure and cost savings.
In NRC memorandum (Reference No. 1), the NRC staff indicated that an ultrasonic examination could be replaced by VT-1 visual examination for the proposed RPV nozzle inspection on the basis surveillance is maintained and VT 1 visual examination is performed.
Alternate Requirements PSEG Nuclear, LLC proposes to perform a remote visual examination of the M-N surface as shown in Figures IWB-2500-7 (a) through (d) in lieu of the volumetric examination requirements of ASME Section Xl, Table IWB-2500-1, Examination Category B-D, Item No. B3.100.
PSEG Nuclear proposes to perform an enhanced VT-1 (EVT) visual examination with essentially 100-percent coverage upon examination surface M-N. The enhanced aspect of the examination is to use 8x magnification video equipment to examine the inner radii. The resolution sensitivity for this remote examination will be established using a 1-mil diameter wire.
Crack-like surface flaws exceeding the acceptance criteria of Table IWB-3512-1 are unacceptable for continued service unless the reactor vessel meets the requirements of IWB-3142.2, IWB-3142.3 or IWB-3142.4.
Applicability This Relief Request is applicable to the following:
Salem Unit 1-Third Ten-Year Inservice Inspection Interval.
Salem Unit 2-Second Ten-Year Inservice Inspection Interval.
LRN-02-0045 Attachment I
Attachment I LRN-02-0045 PSEG NUCLEAR LLC SALEM GENERATING STATION ISI RELIEF REQUEST SC-RR-B06 References
- 1. NRC Internal memorandum from K.R. Wichman (NRC) to W.H. Bateman (NRC) dated May 25, 2000; Subject The Third Meeting with the Industry to discuss the elimination of RPV Inner Radius Inspection (ML003718630).
- 2. Code Case N-648, Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel NozzlesSection XI, Division 1.