ML18100A776
| ML18100A776 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/10/1993 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N93194, NUDOCS 9312280127 | |
| Download: ML18100A776 (19) | |
Text
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Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations DECl 0 1993 NLR-N93194 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM FIRST 10-YEAR INTERVAL, FINAL RELIEF REQUESTS SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 By letter dated September 28, 1992, Public Service Electric & Gas Company (PSE&G) submitted the Final Relief for the first 10-year interval for Salem Unit No. 2. By letter dated October 5, 1993, the NRC requested additional information to support PSE&G's submittal for Salem Unit No. 2 Inservice Inspection Program.
Attachment 1 contains PSE&G's response to the requests for additional information. Attachment 2 contains the revised relief request pages.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
- ')')001-8 t.. ..J .. ll}* .
Document Control Desk 2
- DEC 10 1993 NLR-N93194 C Mr. J. c. Stone Licensing Project Manager Mr. c. Marschall Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Manager IV New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
NLR-N93194 ATTACHMENT 1 SALEM UNIT NO. 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM FIRST 10-YEAR INTERVAL FINAL RELIEF REQUESTS The following is a response to the NRC request for additional information (RAI), dated October 5, 1993.
REQUEST A Final Relief Request #1 includes requests for relief due to limited volumetric examination coverage. In February, 1990, the licensee requested and received approval for the use of ASME Code Case N-460, which allows a reduction of examination coverage not to exceed 10 percent of the required volume.
The licensee has provided a table describing the examination areas for-which relief is requested. Under the table heading "LIMITATION", the licensee gives the percent of volumetric examination area that received volumetric coverage followed by the statement that coverage was obtained in at least one direction. Based on Code Case N-460, the licensee states that for some of the limited examinations listed in this table, relief would no longer be required.
From the information provided, the extent to which Code required volume coverage being obtained is unclear to the staff; therefore, the examination areas that would not require relief based on Code Case N-460 cannot be determined. Code examination coverage is satisfied when the ultrasonic beam passes through the cross-sectional volume of a specified examination area in two directions for the specified Code examination length. If coverage is obtained in at least one direction, as stated, but coverage in the second direction is not quantified, the Code required coverage obtained is not known, and the basis for the claim that relief may no longer be required is not clear.
The staff requests that the licenseer.provide the accumulative examination volume coverage based on; (1) the percent of ,volume coverage obtained by two directional, beam component coverage for scans perpendicular to the weld; (2) the percent of volume coverage obtained for scans performed with the beam component parallel to the weld; and (3) the percent of the total length scanned.
RESPONSE A See below
NLR-N93194
- 2 REQUEST B In the table for Final Relief Request #1, it.appears that examination areas 29-STG-1240-IRS and 6-SJ-1241-16 both have duplicate examination areas identified under a separate Sum #.
Please clarify the apparent duplication.
RESPONSES A AND B The attached final Relief Request #1 has been revised. These revisions include:
- 1. Only those welds requiring relief when applying Code Case N-460 are included. Welds receiving accumulative examination average of 90% or greater when incorporating the NRC guidance in paragraph 2A of the RAI have been deleted.
2~ The "Alternative Examination" section has been revised to present PSE&G's position on not performing alternate examinations.
- 3. The end of the "Basis for Relief" section has been revised to present the process on how PSE&G identified what belonged on the final relief request list.
- 4. The Relief Request Table was revised to include the following:
- a. Editor.:i,.al corrections were made on the table, including corrections to examination areas 29-STG-1240-IRS and 6-SJ-1241-16 as identified in the RAI.
- b. The remarks column and basis column have been removed with the pertinent information shown in a "Limitation" column.
- c. The Alternate Examination column has been removed.
There are no alternate examinations.proposed for any of the areas.
- d. A "% of Accum. Exam. Code Coverage" column is now included. These percentages have been calculated in accordance with the NRC staff request identified above.
NLR-N93194 3 REQUEST C Final Relief Request #2, Alternative Examination, states: "Public Service Electric and Gas examined at least one valve in a valve group (valves of similar design and function) where at least one valve in the group was disassembled for maintenance purposes during the inspection interval. If any valve was found to require corrective action, additional valves in that group would be disassembled and inspected as required by Section XI". It is further stated in the second paragraph under "Alternative Examination", that the aforementioned statement is a guideline.
It is unclear to the staff whether the guideline for the "Alternative Examination" is a statement of examinations performed or a statement of requirement (i.e. will examine at least one valve ..... ). Please clarify the extent of the Code required examinations that were completed during the first 10-year interval.
RESPONSE C In order to more clearly state PSE&G's position, the "Alternative Examination" section of Relief Request #2 has been revised. The revision includes a description of the use of 19S9 Edition of Section XI, Table IWB-2500,.Category B-M-2, item B12.50.
REQUEST D Included in Final Relief ReqUes( #3*is a referenc~ to Examination Category B-A, Item Number B1.1, for examination of reactor vessel welds in the beltline region. It appears that the licensee is requesting credit for examination area coverage of Category B-A welds that exceeded the Code requirements, as an alternative examination for relief associated with Examination Category B-B and B-D. The licensee states that for vessel welds in the beltline region, 100 percent examination of all required welds was attempted.
Although the licensee maximized coverage on the category B-A examination volume, this does not constitute an alternative examination for other examination categories. The licensee should include alternative examinations that are applicable to the examination category and examination areas for which Code required coverage is not obtained. Please provide a revised relief request that addresses any alternative examinations for limitations associated with Examination Categories B-B and B-D.
NLR-N93194
- 4 RESPONSE D See below REQUEST E Final Relief Request #3 has a table that lists percents of coverage for "Beam Directions," cw, ccw, Up, Down, and Toward RX.
Refer to "A" above and provide the percent of examination area coverage obtained.
RESPONSES D AND E In order to more clearly state PSE&G's position, Relief Request
- 3 has been revised. The revision includes a re-write of the "Basis for Relief" section and the "Alternative Examination" section, also revisions to the table listing welds requiring relief were made, which include:
- a. Adding a "% of Accum. Exam. Code Coverage" column with percent coverage as described previously.
- b. Deleting the "Remarks" column and including pertinent information in a " Limitations" column.
As an additional point of clarification, PSE&G has not, or proposed to take credit for excess examination coverage obtained in category B-A as an alternative to a relief request for examinations in category B-B , B-D or any other examination category.
ATTACHMENT 2 REVISED FINAL RELIEF REQUESTS
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1 COMPONENT DESCRIPTION:
Pressure vessels, components, and piping welds and integrally welded attachments subject to surface and/or volumetric examination listed on the attached table.
ASME CODE CLASS:
ASME Section XI Class 1, 2 welds.
ASME EXAMINATION REQUIREMENTS:
In accordance with the examination requirements of Subsection IWB, Table IWB-2500 of examination categories: B-C, B-D, B-F, B-J and Subsection IWC, Table IWC-2520 examination categories: C-A, c-c, C-E-1, c-F and C-G when an examination (surface or volumetric) is performed, essentially 100% of the weld length is required to be inspected.
BASIS FOR RELIEF:
The ASME Code requires surface and volumetric examination of various Class 1 vessel and piping welds as defined in Paragraph IWB~2500 and various Class 2 vessel and piping welds as defined in Paragraph IWC-2500.
During the inservice examinations performed at SALEM. NUCLEAR GENERATING STATION UNIT 2 it has been the position of PUBLIC SERVICE ELECTRIC AND GAS COMPANY that examinations which could not be performed completely, (i.e., performed from two (2) directions because of component configuration or restrictions from permanent structures) the examination would be performed to the greatest extent possible and whatever limitation that existed be documented.
It has also been PUBLIC SERVICE ELECTRIC AND GAS COMPANY'S position that when there was a "removable" structure, (i.e., hanger, support) these items were removed, when practical, providing greater access to the component being examined. The basis for this position. is as follows:*
The Code of Federal Regulations, 10CFR50, "Domestic Licensing of Production and Utilization Facilities" defines those requirements which must be adhered to by the utility in order to be issued and maintain an operating license. This document states in Paragraph 55a(g) that inservice inspections shall meet the requirements of the ASME Boiler & Pressure Vessel Code.
Throughout 10CFR50 numerous references are made allowing performance of these inspections "to the extent practical".
PAGE 1 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1 Some of the specific paragraphs are:
Paragraph 50.55a(g)4 states that throughout the service life of a nuclear power facility components which are classified as ASME Code Class 1, 2 and 3 shall meet the requirements of Section XI of the ASME B&PV Code, "to the extent practical within the limitations of design, geometry and materials of construction of the components".
Paragraph 50.55a(2)i of this document states that inspection of systems and components is performed "to the maximum extent practical, in accordance with generally recognized codes and standards" i.e., ASME Boiler & Pressure Code.
Paragraph 50.55g(l) states that components (including supports) shall meet the requirements of (ASME Code) "to the extent practical".
The ASME Code itself provides allowance for "limited" examinations.
The 1986 Edition,Section V, Article 4, Paragraph T-441.3.2.4 states:
"Whenever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where configuration of adjacent parts of the component are such that the scanning from both sides is not feasible, this fact shall be included in the report of the examination".
PUBLIC SERVICE ELECTRIC AND GAS COMPANY has utilized approved technical procedures written in accordance with the applicable Section/Paragraph of the ASME Code in regard to the area/volume to be examined and the specified requirements of the examination for the 1st inspection interval. Recognizing that because of component design, construction, etc. there are cases when examinations can only be performed "to the greatest extent possible". PUBLIC SERVICE ELECTRIC
& GAS has previously submitted a list of those identified limitations after performing the preservice examination. Subsequently Weld selection for this interval was made to minimize known limitations identified during preservice examination (PSI). For limitations found during the 1st inservice inspection interval, additional, components were scheduled and examined, when possible, to meet the allocation table requirements of ASME Section XI 1974 Edition, Summer 75 Addenda.
PSE&G requested and received approval for use of ASME Code Case N-460 in February, 1990 allowing a reduction of examination coverage not to exceed 10% of the required volume. Utilizing that criteria and the additional guidance found in 2.A of the NRC RAI, dated October 5, 1993 on accumulative examination volume coverage, PSE&G has been able to minimize those components requiring relief.
PAGE, 2 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1 ALTERNATE EXAMINATION:
No alternate examinations were performed on the components listed in the attached table for the following reasons:
- 1. Where appropriate,Section XI had already required surface examinations in addition to volumetric examinations.
- 2. Performing surface examinations on areas with limitations were not justified when considering the following:
a) all examination areas received coverage greater than 50% of the required volume.
b) The Code has identified the examination area, to be the lower 1/3 of the weld.
- performing a surface examination on the outside surface gives no information on the condition of the lower 1/3 of the weld.
c) Additional radiation exposure to personnel.
PAGE* 3 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1
SUMMARY
COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
002700 2-RPV-7442 B-C/ VOL. 60% DUE TO THE FLANGE VESSEL TO FLG Bl. 3 CONFIGURATION.
CIRC. WELD 020600 31-STG-1240- B-D/ VOL. 86% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT OUTLET NOZZLE INSULATION SUPPORT.
IRS 020700 31-STG-1230- B-D/ VOL. 81% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT OUTLET NOZZLE INSULATION SUPPORT.
IRS 020800 31-STG-1220- B-D VOL. 75% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT OUTLET NOZZLE INSULATION SUPPORT.
IRS 020900 31-STG-1210- B-D/ VOL. 80% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT OUTLET NOZZLE INSULATION SUPPORT.
IRS 021000 29-STG-1240- B-D/ VOL. 84% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT INLET NOZZLE INSULATION SUPPORT.
IRS 021100 29-STG-1230- B-D/ VOL. 75% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT INLET NOZZLE **INSULATION SUPPORT.
IRS PAGE 4 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1
SUMMARY
COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
021200 29-STG-1220- B-D/ VOL. 66% DUE TO THE LOCATION IRS B3.2 OF A PERMANENT INLET NOZZLE INSULATION SUPPORT.
IRS 02i300 29-STG-1210- B-D/ VOL. 86% DUE TO THE LOCATION IRS '
B3.2 OF A PERMANENT INLET NOZZLE INSULATION SUPPORT.
IRS 050000 6-PR-1205-1 B-F/ VOL. 50% DUE TO THE NOZZLE NOZZLE TO B4.1 & AND SAFE-END SAFE-END SUR. CONFIGURATION.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
051200 6-PR-1204-1 B-F/ VOL. 50% DUE TO THE NOZZLE NOZZLE TO B4.1 & AND SAFE-END SAFE-END SUR. CONFIGURATION.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
052400 6-PR-1203-1 B-F/ VOL. 64% DUE TO THE NOZZLE NOZZLE TO B4.1 & AND SAFE-END SAFE-END SUR. CONFIGURATION.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
070000 31-RC-1240-1 B-F/ VOL. 50% DUE TO THE NOZZLE NOZZLE TO B4.1 & CONFIGURATION AND ELBOW SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
PAGE 5 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1
SUMMARY
COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
070500 31-RC-1240-3 B-J/ VOL. 79% DUE TO THE ACOUSTIC PIPE TO ELBOW B4.~ PROPERTIES OF THE ELBOW.
072300 31-RC-1230-1 B-F/ VOL. 50% DUE TO THE NOZZLE NOZZLE TO B4.1 & CONFIGURATION AND ELBOW SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
074600 3*1-RC-1220-1 B-F/ VOL. 50% DUE TO THE NOZZLE NOZZLE TO B4.1 & CONFIGURATION AND ELBOW SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
075100 31-RC-1220-3 B-J/ VOL. 80% DUE TO THE ACOUSTIC PIPE TO ELBOW B4.5 PROPERTIES OF THE ELBOW.
076800 31-RC-1210-1 B-F/ VOL. 50% DUE TO THE NOZZLE NOZZLE TO B4/1 & CONFIGURATION AND ELBOW SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
078200 31-RC-1210-4 B-J/ VOL. 77% DUE TO THE LOCATION ELBOW TO B4.5 OF THE BRANCH PIPE CONNECTION AND ACOUSTIC PROPERTIES OF THE ELBOW.
PAGE 6 OF 9
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SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1
SUMMARY
. COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
080000 29-RC-1240-5 B-F/ VOL. 50% DUE TO THE NOZZLE ELBOW TO B4.1 & CONFIGURATION AND NOZZLE SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
081200 29-RC-1230-5 B-F/ VOL. 50% DUE TO THE NOZZLE ELBOW TO B4 .1 & CONFIGURATION AND NOZZLE SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
082200 29-RC-1220-5 B-F/ VOL. 50% DUE TO THE NOZZLE ELBOW TO B4.1 & CONFIGURATION AND NOZZLE SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
083200 29-RC-1210-4 B-J/ VOL. 75% DUE TO THE ACOUSTIC PIPE TO ELBOW B4.5 PROPERTIES OF THE ELBOW.
083300 29-RC-1210-5 B-F/ VOL. 50% DUE TO THE NOZZLE ELBOW TO B4.1 & CONFIGURATION AND NOZZLE SUR. ACOUSTIC PROPERTIES OF THE ELBOW.
NOTE: 100% OF THE SURFACE EXAM WAS PERFORMED.
PAGE 7 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1
SUMMARY
COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
083400 27.5-RC-1240- B-J/ VOL. 74% DUE TO THE PUMP 1 B4.5 CONFIGURATION AND PUMP TO PIPE THE PROXIMITY OF A BRANCH CONNECTION.
160750 10-SJ-1241-8 B-J/ VOL. 50% DUE TO THE EXISTING ELBOW TO PIPE B4. 5 . PERMANENT PENETRATION SLEEVE.
172400 6-SJ-1241-16 B-J/ VOL. 77% DUE TO THE VALVE VALVE TO PIPE B4.5 CONFIGURATION.
174550 6*-sJ-1222-1 B-J/ VOL. 50% DUE TO THE REDUCER REDUCER TO B4.5 AND VALVE VALVE CONFIGURATION.
179000 4-SJ-1282-10 B-J/ VOL. 83% DUE TO A PERMANENT PIPE TO ELBOW B4.5 STRUCTURAL I-BEAM MEMBER.
275040 2-CVCT-2VS-1&2 C-C/ SUR. 89% DUE TO A PERMANENT VESSEL SUPPORT Cl. 3 I-BEAM VESSEL SUPPORT.
275230 2-RCF-1 C-A/ VOL. 50% DUE TO THE WELD AND UPPER HEAD Cl.1 . FLANGE TO FLANGE CONFIGURATION.
360010 8-CV-2201-1 C~F/ VOL. 85% DUE TO THE PROXIMITY VALVE TO PIPE C2.1 OF A PERMANENT PIPE RESTRAINT AND THE VALVE CONFIGURATION.
360110 8-cv-2210-11 C-F/ VOL. 82% DUE TO THE PROXIMITY PIPE TO TEE C2.1 OF A PERMANENT PIPE RESTRAINT.
PAGE 8 OF 9
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 1
SUMMARY
COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
380050 34-MS-2241- C-E-1/ SUR. 25% DUE TO THE PROXIMITY 2PS-1&2 C2.5 OF THE PERMANENTLY INSTALLED PIPE SUPPORT.
384630 6-MS-2231-4 C-G/ VOL. 89% DUE TO THE VALVE PIPE TO VALVE C2.1 CONFIGURATION.
500810 6-PR-2203-2 C-F/ VOL. 60% DUE TO THE PROXIMITY ELBOW TO PIPE C2.1 OF A PERMANENTLY INSTALLED PIPE SUPPORT.
502410 8*-RH-2273-1 C-F/ VOL. 50% DUE TO THE VALVE TEE TO VALVE C2.1 AND TEE CONFIGURATION.
503340 8-RH-2216-4 C-F/ VOL. 50% DUE TO THE FLANGE FLANGE TO C2.1 CONFIGURATION.
VALVE 573383 12-SJ-2252-38 C-E-1/ SUR. 71% DUE TO T~E PROXIMITY PIPE SUPPORT C2.5 OF A PERMANENTLY INSTALLED PIPE SUPPORT.
PAGE 9 OF 9
s9EM UNIT 2 - lST INSPECTIO.NTERVAL FINAL RELIEF REQUEST - # 2 COMPONENT DESCRIPTION:
Pressure Retaining Valves listed below ASME CODE CLASS:
ASME Section XI, Class 1 Valves ASME EXAMINATION REQUIREMENTS:
Relief is being requested from the visual (VT) examination requirements of Table IWB-2500 Examination category B-M-2 Item No.
B6.7.
BASIS FOR RELIEF:
The disassembly of functional valves during the first ten year inspection interval for the sole purpose of performing a visual examination of the internals would have increased the likelihood for component failure in the future and was contrary to good maintenance practices. Considering the uncertainty of the benefit involved with this examination, it is difficult to justify the additional radiation exposure that would be incurred as a result of the disassembly, examination and reassembly these valves. For example, estimates from radiation surveys performed on and around valve 2RH1 indicate that the total job dose that would be received in disassembling, examining and reassembling this valve be in excess of 4 man-rem. Public Service Electric & Gas feels implementation of this examination is impractical for valves not scheduled for disassembly because of preventive or corrective maintenance. In the 1989 and later editions of Section XI, this examination is only required to be performed on valves scheduled for disassembly for maintenance purposes.
ALTERNATIVE EXAMINATION:
As required by the 1989 edition of Section XI, table IWB-2500 Category B-M-2, Item Bl2.50 examinations were performed when the valve was disassembled for maintenance, repair, or volumetric examination.
Also in accordance with the 1989 Edition IWB-2430 (a) when examinations reveal flaws or relevant conditions that exceed the acceptance standards, examinations were extended to include additional valves.
Utilizing the above requirements, the following valves, listed by group were .never disassembled during the first inspection interval and therefore, the internals were not visually examined.
Valve Valve Valve Valve Group Group Group Group 2RH1 2RH26 21SJ49 21SJ54 2RH2 22SJ49 22SJ54 23SJ54 24SJ54 PAGE 1 OF 1
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 3 COMPONENT DESCRIPTION:
Reactor Pressure Vessel and Nozzles listed on the attached list ASME CODE CLASS:
ASME Section XI, Class 1 Vessel ASME EXAMINATION REQUIREMENTS:
Relief is being requested from the ultrasonic (UT) examination requirements of Table IWB-2500 Examination Category B-D, Item Bl.4.
BASIS FOR RELIEF:
Due to the geometry of the reactor vessel, 100% of the Code required coverage of all the applicable welds cannot be obtained.
These examinations are performed from the inside diameter utilizing automated UT equipment. No examinations can be performed from the outside diameter surface, Due to the design of the building structure surrounding the reactor vessel making access impossible.
ALTERNATIVE EXAMINATION:
There are no alternative examinations proposed for these examinations ..
PAGE 1 OF 2
SALEM UNIT 2 - lST INSPECTION INTERVAL FINAL RELIEF REQUEST - # 3
SUMMARY
COMPONENT ID CODE CODE % OF LIMITATIONS
- W/DESCRIPTION CAT/ REQ. ACCUM.
ITEM EXAM EXAM
- CODE cov.
002900 29-RCN-1240 B-D/ VOL. 50% DUE TO THE INTEGRAL OUTLET NOZZLE Bl.4 EXTENSION AND
@ 22-DEG. GEOMETRIC SHADOWING.
003200 29-RCN-1230 B-D/ VOL. 50% DUE TO THE INTEGRAL OUTLET NOZZLE Bl.4 EXTENSION AND
@ 158-DEG. GEOMETRIC SHADOWING.
003300 20-RCN-1230 B-D/ VOL. 50% DUE TO THE INTEGRAL OUTLET NOZZLE Bl.4 EXTENSION AND
@ 203-DEG. GEOMETRIC SHADOWING.
003600 29-RCN-1230 B-D VOL. 50% DUE TO THE INTEGRAL OUTLET NOZZLE Bl.4 EXTENSION AND
@ 338-DEG. GEOMETRIC SHADOWING.
PAGE 2 OF 2