JAFP-08-0038, Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout
| ML081290489 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/30/2008 |
| From: | Jim Costedio Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-08-0038 | |
| Download: ML081290489 (104) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP Enterigy P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 April 30, 2008 JAFP-08-0038 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 James A. FitzPatrick Nuclear Power Plant Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout
Dear Sir or Madam:
Entergy Nuclear Operations Inc., (Entergy) completed the Third Inservice Inspection, Interval. The attached report closes out the Third Ten-year Interval Relief Requests.
There are no commitments contained in this letter. If you have any questions, please contact Mr. Joe Pechacek at (315) 349-6766.
Very truly yours, d aJimnCostedio Manager, Licensing JC:ed Enclosure 1: James A. FitzPatrick Nuclear Power Plant Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout cc: next page f\)ýNk
JAFP-08-0038 Page 2 of 2 cc:
Mr. Samuel J. Collins Regional Administrator,. Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Adrian Muniz, Project Manager Plant Licensing Branch I-1 Division~of Operating Reactor Licensing N Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory. Commission Mail StopO*.8-G5: .
Washington, DC 20555-0001 NRC Resident Inspector U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear; Power Plant P.O.PBox136 Lycoming, NY 13093
JAFP-08-0038 ENCLOSURE 1 James A. FitzPatrick Nuclear Power Plant Inservice Inspection Program Relief requests 3 RD Ten-year Interval Closeout Relief Request RR-CRV-1
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM RELIEF REQUESTS 3 TEN-YEAR INTERVAL CLOSEOUT Relief Request RR-CRV-1
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Table of Contents INTRODUCTION ......................................................................................... 4 RELIEF REQUEST ........................................................ 5 CLASS 1 COMPONENTS - Table RR-CRV-1 .................................... 9 Code Category B-A: Pressure Retaining Welds in Reactor Vessel Item No. B1.21 Circumferential Weld Weld ID: VC-BH-2-3 ............................................. Attachment I Item No. B1.22 RPV Bottom head Meridional Weld Weld ID: VV-BH-2A -thru 2F ................................. Attachment 1 Code Category B-D: Full Penetration Welds of Nozzles in RPV Item No. B3.90 Reactor Vessel Head Nozzle-to-Vessel Welds Weld ID: N-TH-A .................................................. Attachment 2A Weld ID: N-TH-B . ................................................. Attachm ent 2B Weld ID: N-TH-C .................................................. Attachment 2C Item No. B3.90 Reactor Water Recirculation Nozzle-to-Vessel Welds Weld ID: N-1A ....................................................... Attachm ent 3A Weld ID: N-lB .................................. Attachment 3B Weld ID: N-2A, B, E, H, K. ......................... Attachment 4A Weld ID: N-2F ............... .......................... Attachment 4B Weld ID: N-2C, D, G, J ............................................. Attachment 4C Item No. B3.90 Main Steam Nozzle-to-Vessel Welds Weld ID: N-3A, B ................................................... Attachment 5A Weld ID: N-3C, D ................................ Attachment 5B Item No. B3.90 Feedwater Nozzle-to-Vessel Welds Weld ID: N-4A, C ................................................... Attachment 6A Weld ID: N-4B, D ................................................... Attachm ent 6B Item No. B3.90 Core Spray Nozzle-to-Vessel Welds Weld ID: N-5A .................................. Attachment 7A Weld ID: N-5B ........................................................ Attachm ent 7B Item No. B3.90 Jet Pump Instrumentation Assembly Nozzle-to-Vessel Welds Weld ID: N-8A .................................. Not Required Weld ID: N-8B ........................................................ Attachm ent 8 Item No. B3.90 Control Rod Drive Nozzle-to-Vessel Welds Weld ID: N -9 ........................................................... Attachm ent 9 Page i
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Table of Contents Code Category B-G-1: Pressure Retaining Bolting, >2"in. In Diameter Item No. B6.40 RPV Threads in Flange ............................... Attachment 10 Code Category B-K (B-H): Integrally Welded Attachments (Code Case N-509)
Item No. B10.10 RPV Integrally Welded Attachments ............... Attachment 11 CLASS 2 COMPONENTS - Table RR-CRV-2 .................................................... 15 Code Category C-A: Pressure Retaining Welds in Pressure Vessels Item No. C1.20 Shell Circumferential Weld ........................... Attachment 12 Code Category C-B: Pressure Retaining Nozzles Welds in Vessels Item No. C2.20 Nozzles w/o Reinforcing Plate ........................ Attachment 13 Code Category R-A (C-F-2) Circumferential Piping Weld (RI-ISI)
Item No. R1.20 RI-ISI (No Identified Damage Mechanism) ........ Attachment 14 Page ii
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 INTRODUCTION These Relief Requests are being submitted as part of the close-out for the 3 rd Ten-year Interval performed in accordance with the ASME Section XI Code Edition 1989, No Addenda. The requests for relief enclosed are submitted pursuant to 10CFR50.55a(g)(5)(iii) as stipulated in a Safety-Evaluation (SE by the Office of the Nuclear Reactor Regulation). The requests, along with their specific regulatory basis are described in detail along with supporting technical discussion, documentation and referenced SE, when applicable.
Included in the Tables and Attachments are welds examined during the 3 rd Ten-Year Interval (10/98 -. 2/08) whose inspections have not met the code required coverage as defined in Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, along with sketches, photographs and/or drawings depict the limiting condition(s) and coverage achieved.
Page 4 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Proposed Alternative In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticability-ASME Code Component(s) Affected Code Classes: 1 and 2
References:
[1] ASME Section XI 1989 Edition, No Addenda
[2] Sub-article IWB-2500, Table 2500-1
[3] Sub-article IWC-2500, Table 2500-1
[4] Code Case(s) N-509, N-578
[5] Relief Request RR-4 NRC SER JAFNPP, Third Interval ISI Program Relief Requests (TAC No. MA071 1) dated November 25, 1998
[6] Relief Request RR-17, NRC SER JAFNPP RPV Circumferential and Vertical Shell Welds (TAC No. MA6215)
[7] Relief Request RR-20 NRC SER JAFNPP, ASME Code -
Relief for Risk-Informed ISI of Piping (TAC No. MA6926
[8] Relief Request RR-30, NRC SER JAFNPP, Third Interval ISI (TAC No. MC0293) dated July 21, 2004 Examination Categories: B-A, B-D, B-G-1 B-K (B-H)
C-A, C-B%R-A (C-F-2)
Item Numbers: B 1.20, B 1.22, B3.90, B6.40, B 10.10 C1.20, C2.22, R1.20 (C5.51)
2. Applicable Code Edition and Addenda
ASME Section XI 1989 with no Addenda
- 3. Applicable Code Requirements IWB-2500, states in part, "Components shall be examined and tested as specified in Table IWB-2500-1. The method of examination for the components and parts of the pressure retaining boundaries shall comply with those tabulated in Table IWB-2500-1, except where alternate examination methods are used that meet the requirements of IWA-2240." Table IWB-2500-1 requires that a volumetric and/or surface examination be performed on specified components based Code Category and Item Number. The applicable examination area or volume and method required from Table IWB-2500-1are shown below in Table 1:
Page 5 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Table 1 Examination ItemItNmbe Number ASME Section XI Examination 1 euirements Figure Number Examination Method Category B...... ...................
? ........................ Z Z Z II~i B-A B1.20/11.22 . IWB-2500-3 Volumetric B-D B3 .90. ___ IWB-2500-(A) thrpyu.g...... Volumetric B-G-1 B6.40 I IWB-2500-12 Volumetric B-K (B-H 1 )) B3l0.1 IWB-2500-13, 14 and 15 Surface Note: (1).Category B-H & B-K are examined in accordance with Alternate Rules for Selection, and Examination of Class 1, 2, and 3 Integrally Welded Attachments CodeN-509 (Relief Request RR-4) [6]
IWC-2500, states in part, "Components shall be examined and tested as specified in Table IWC-2500-1.
The method of examination for the components and parts of the pressure retaining boundaries shall comply with those tabulated in. Table IWC-2500-1, except where alternate examination methods are used that meet the requirements of IWA-2240." Table IWC-2500-1 requires that a volumetric and/or surface examination be performed on specified components based on Code Category and Item Number. The applicable examination area or volume and method required from Table IWC-2500-are shown below in Table 2:
Table 2 Examination ASME Section Xi Examination Examination.Method Item Number 7 Categ~ory Requirements / Figure Number E C-A C1.20 IWC-2500-4 (a) or (b) Sraceanid Volume1tri-c
.................. o l me......................
C-B C2.22 IWC-2500-4 (a) or (b) Volumetric RI.20 IWC-2500-7 Volumetric Note: (1). Code Categories R-A (C-F-2) are examined in accordance with JAF's Risk-Informed Inspection Program (RI-ISI) Code Case N-578 (NRC Approved Relief Request RR-20)
[5]
(2). In addition to the requirements in Code Cases N-578, JAF's Risk-Informed Inspection Program (RI-ISI),'has further defined segments and/or'elements into a subset of Items No(s) that captures and identifies individual and combinations of damage mechanisms based on the component.
Page 6 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1
- 4. Reason for Request - Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that the required "essentially 100%" coverage examination is impractical due to physical obstructions and limitations imposed by design, geometry and materials of construction of the component.
Relief is requested from performing a complete coverage examination of the entire volume or area required. Entire volume or area required is defined by ASME Section XI Code Case N-460 titled "Alternative Examination Coverage for Class and Class Welds,Section XI, Division 1." Code Case N-460 states in part, "...when the entire examination volume or area cannot be examined .. .a reduction in examination coverage.. .may be accepted provided the reduction in coverage for that weld is less than 10%."
The NRC through, Information Notice 98-42 titled "Implementation of 10CFR 50.55a(g)
Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be essentially 100 percent." Information Notice 98-42 states, in part, "The NRC has adopted and has further refined the definition of 'essentially 100% percent' to mean 'greater than 90 percent'... has been applied to all examinations of welds or other areas required by ASME Section XI."
Relief is requested from performing an examination of "essentially 100% of the required volume or area as applicable for components identified Table RR-CRV-1.
Note 1: Category B-A Reactor Pressure Vessel Shell Welds (Item Nos. B 1.11 and B 1.12) are not listed in Table RR-CRV-i. Relief was submitted and granted for coverage limitations for the augmented examination of the reactor pressure vessel shell welds in the following relief requests:
- JAFNPP relief request RR-17 to USNRC dated August 5, 1999/Supplemental Letter November 24, 1999, Augmented Inspection of RPV Circumferential Shell Welds
- NRC SER for RR-17 to JAFNPP dated February 22, 2000 (TAC No. MA6215)
Deferral of Inspections of RPV Axial Shell Welds & Projected Coverage
- NRC SER for RR-18 to JAFNPP dated February 29, 2000 (TAC No. MA6270)
- JAFNPP Relief Request RR-30 to USNRC dated August 4, 2003/Supplemental Letter December 30, 2003, Augmented RPV Vertical Shell Weld Examinations
- NRC SER for RR-30 to JAFNPP dated July 21, 2004 (TAC No. MC0293)
Note 2: Partial examinations performed on welds that are outside the previews of ASME Section XI i.e.; Intergranular Stress Corrosion Cracking (IGSCC), Augmented Core Spray, Feedwater/Main Steam High Stress Weld Inspection Program and/or other Augmented Inspection Programs that are not required to be examined in accordance with the Risk-Informed Inspection Program (RI-ISI), are not included in this relief request:
- JAFNPP relief request RR-5 to USNRC dated May 24, 2000, Letter No. JPN 016, Risk-Informed Inservice Inspection (RI-ISI) Program
- NRC SER for RR-5 to JAFNPP dated September 12, 2000, (TAC No. MA6926)
Page 7 of 101
Entergy Nuclear Operations, Inc.,
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1
- 5. Relief Request Basis - Burden Caused by Compliance At the time JAF was constructed, the ASME Boiler and Pressure Vessel Code only covered nuclear vessels and associated piping up to and including the first isolation or check valve.
Therefore, piping, pumps and valves were built primarily to the rules of USAS B31.1.0 - 1967 Edition. The Reactor Vessel Code of Construction is the ASME Boiler and Pressure Vessel Code,Section III, 1965 Edition including the 1966 Winter Addenda. Based on the lack of Code guidance regarding consideration for NDE examination, literal compliance was not always feasible or practical within the limits of the current plant design.
Physical obstructions imposed by design, geometry and materials of construction are typical of vessel appurtenances, biological shield wall, insulation support rings, structural and component support members, adjacent component weldments in close proximity, unique component configurations (valves and pumps), and dissimilar metal weldments.
Compliance with the examination coverage requirements of ASME XI would result in extensive engineering, modification, redesign, or replacement of components.
- 6. Proposed Alternative and Basis for Use As a minimum, all components received the required examination(s) tothe extent practical with regard to the limitation or lack of access available. The examinations conducted confirmed satisfactory results evidencing no unacceptable flaws present, even though "essentially 100%" coverage was not attained. James A. FitzPatrick has concluded that if any active degradation mechanisms were to exist in the subject welds, those degradations would have been identified in the examinations performed.
For surface examinations, James A. FitzPatrick calculated the coverage percentage based on the area examined within the required coverage area divided by the required surface area to be examined. For volumetric (ultrasonic) examinations, the transition to PDI examinations varied the means of coverage determination based on code requirements. Earlier Code examination coverage was determined by a simple average of the examination scans performed. Later examinations performed per PDI requirements identify coverage based on a simple average of the scans per the requirement of PDI and CFR. The attachments within identify the means of determining examination coverage and are based on the requirements at the time the examinations were performed.
- 1. No additional volumetric examinations will be performed.
- 2. A visual examination (VT-2) is performed in conjunction with the pressure testing conducted on these components every refuel outage (with no evidence of leakage detected) in accordance with IWA-5000 and IWB-5000, which provides reasonable assurance of component integrity.
Page 8 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 1 COMPONENTS Table RR-CRV-1 Class 1 Components with Less Than 100% Code Required Coverage
- S e c t io n ." Secton f+ .Percentage,
... Code Code Item Syste Component Component Limiting NDE
,XI Category No. IID S ystem Ii: Description Condition Method of Coverage i ev d Remrk R emarks Inaccessible RPV Bottom Head dueto Volumetric R B-A 1B1.21 RPV VC-BH-2-3 Cilrcumferentilat Ccfei .and In-core
. (UT) i 0% Attachment Monitoring 1 I_______*
- .w elds ]! Housings
.. Inaccessible RPV Bottom due to CRD Reference B-A B 1.22 RPV VB2F tr2F(UT)
Head Meridional and In-core t 00% Atcmn Attachment Welds Monitoring 1
...... . . .... ..H o u sin gs ...
BD RPV Head N-TH-A R9PV Top Head - .OD Blend Vol umetrc Reference Attachment to-Nozzle Weld Radius (UT)
.. 2A BD I RPV DB~d Hd VltrReference RPV Head N-TH-B RPV Top Head - OD Blend Volumeic 79% Attachment to-Nozzle...
........... Weld
.. Radius (UT) 2B 2
..........J Page 9 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 1 COMPONENTS Table RR-CRV-1 Components with Less Than 100% Code Required Coverage Percentage Section XI Code Item System Component Component Limiting NDE of Remarks ID Description Condition Method Coverage R Category
_ __ Achieved RPV Top Head - OD Blend Volumetric Reference B-D B3.90 RPV Head N-TH-C 57.3% Attachment to-Nozzle Weld Radius (UT) 2C RPV-to- Reactor Insulation Water Support Ring _ Reference Volumetric B-D N-lA Recirculation and Bracket 40.6% Attachment Outlet Nozzle & OD Blend ( I 3A Weld Radius -
RPV-to- Reactor Insulation Water Support Ring Volumetric* Reference B-D B3.90 N-1 B Recirculation and Bracket 23.9% Attachment Outlet Nozzle & OD Blend (UT) 3B Weld Radius Insulation RPV-to- Reactor Support Ring Water and Volumetric Reference Recire.
B-D B3.90 H &K Recirculation Permanent 66.1% Attachment System Inlet Nozzle Insulation & 4A Weld OD Blend Radius ........ .. .__
Page 10 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 1 COMPONENTS Table RR-CRV-1 Components with Less Than 100% Code Required Coverage Section Item SystemReak NE Percentage System Component Component Limiting NDE of XI Code No.
Description Condition Method Coverage Category
_ " ........... ...... . .. A chieved _
i Insulation RPV-to- Reactor Support Ring Recirc. Water and Volumetric 68 Reference B-D B3.90 System N-2F Recirculation Permanent (UT) i 68% Attachment.
Inlet Nozzle Insulation & 4B Weld OD Blend Radius _ _
Insulation RPV-to- Reactor Support Ring Water and Reference Recirc. N-2C, D, G RecirculationReirultinerann Volumetric .Ac 85.9% .Attachment B-D B3.90 System &J (UT)
Inlet Nozzle Insulation & (T 4C Weld OD Blend R a ius.
~Radius_
0......
Insulation B-D B3.90 I..!.....
.... . ..... ..Maini Sem N-3A & B
. .....i.........RV-to
..................MS.. . . .Support
.. ..and
.......Ring
.................Vlmti
........35.6%
.Reference............................
Attachment System Nozzle Weld I (UT)
Permanent 5A Insulation ________
Page 11 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 1 COMPONENTS Table RR-CRV-1 Components with Less Than 100% Code Required Coverage Percentage Section Item S Component Component Limiting NDE of XI Code No. System ID Description 1 Remarks Condition Method Coverage Category No.
Achieved Insulation Support Ring and *Reference Main Steam N-& RPV-to- MS Volumetric B-D B3.90 N-3C & DWl S Nozzle Weld Permanent 46.3% Attachment System (UT)
Insulation & 5B OD Blend Radius Nozzle Reference B-D i B3.9 ...ytm Feedwater N-4A & C. RPV-to- FW Obstruction Volumetric
- 42 %o Attachment
.D System Nozzle Weld & OD Blend (UT)
Radius - _ _ 6A
.......... ... ...... . ................... . . . . . . . . . .. . . . . . . . .. . . i Permanent Feedwater RPV-to- FW Reference Insulation & Volumetric
-S ystem N4 Nozzle Weld 53% Attachment OD Blend (UT) 6B Radius _ "
Page 12 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 1 COMPONENTS Table RR-CRV-1 Components with Less Than 100% Code Required Coverage Section SectionPercentage X1I C~ode Item SSID ystem Component t Component Limiting
_* NDE of Rmr R_ emarks Coe o. Description Condition Method Coverage Category _ _ _ _ _ Achieved
......... ~. F- OD'Bien'd BD B.0 Core Spray - I RPV-to- CS C Radius & Volumnetric Reference B-D B3.90 CoreNSprayN-5potyo 38.11% Attachment System Nozzle Weld proximity of (UT) thermocouple 7A
..............__...................................._pad
-.................en ........................................... ......... . . ...... .. ........ .
OD BlendH i .. .. ~Radius & . lReference
- Core Spray RPV-to- CS Volumetnc Reference BSDm5B B3Wd 1 proximity of (UT) 38.6% Attachment thermocouple 7B
.... [......... . .....p ad _.............
Jet Pump Permanent Instrumentati B-D B3.90 on (JPI) N-8A RPV-to- JPI Insulation & Volumetric iRelief Not Assembly Nozzle Weld OD Blend (UT) 93.4%
Required
- System Radius _ __
IiInstrumentati f RPV-to- JPI "Insulation & Volumetric Reeec B-D 11B3.90 on (JPI) N-8B Nozzle Weld OD Blend (UT) il 71"6% Attachment Assembly System R Radiusp__ 8 Page 13 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 1 COMPONENTS Table RR-CRV-i Components with Less Than 100% Code Required Coverage Percentage Section Item Component Component Limiting NDE of XI Code System Remarks No. ID Description Condition Method Coverage Category Achieved B.0" Control Rod Insulation RPV-to- CRD Support Ring Volumetric 66.2% Reference B-D B3.90 Drive System N-9 Nozzle Weld & OD Blend (UT) .2o Attachment 9 Radius Threads in Reference RPV Threads in Design and Volumetric B-G-1 ' i:B6.40 li! Flange Flange Flange 14- 79% Attachment Flange Configuration (UT)
- 17. . . . . . . . . . . .....
............ 52 10
...g.....
B-K ; ..... i6 6 ....
............. .. ... f 1Stabilizer-i, RPV Integra Desig n and Surface 7 34% Reference (B-H) Stabilizer 2, 3,and 4 Welded (MT) Attachment uration
.........Brackets Attachment Cni I1I Page 14 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 CLASS 2 COMPONENTS Table RR-CRV-2 Class 2 Components with Less Than' 100% Code Required Coverage ce nia g.e Section XI Code .CodeItem ,System *Component j.Percentage Mto Cveae Remarks Component Limiting NDE of No.gSystem.ID Description Condition Method Coverage Category Ahee i h Scram Tn -Tank Shell-to- Support Volmetic Reference CA 12 c3TK1A BH-1A Bottom Head Rings & (UT) 18% Attachment Weld Weld-0-lets ______ 12 Design/ Reeece C-B C22 Scram
.... Tank N--1-A-IRt 1 nera Radius Inner Configuration
. . . Volumetric
.. 85% Attchent Attachment 03TK-IA & OD Blend (UT) 1
. Radius
... . 1*.. . . . .o.
........i .. ....... i I ... ........................
J..
. . . . ...I[...
. -.- ].i..........
R-A Ri 20 HPCI 14-23-43.3 Pipe to - Valv -Design and Volumetric 87. 57* Reference (C-F-2) (C5.51) Configuration (UT) Attachment
____ ____ __ ____ ___14 Page 15 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 1 Reactor Pressure Vessel Bottom Head Welds Code Category: B-A Item No. B1.21 & B1.22 Weld ID: VC-BH-2-3 & VV-BH-2A thru 2F Basis: Inspection of the Code-required accessible length of one weld was conducted on the RPV Bottom head Circumferential Welds with limitation based on restricted access. Access to the area is limited to four 18" diameter manways 900 apart in the vessel support skirt. In addition, the one hundred and thirty-seven (137) control rod drives and forty-three (43) in-core monitor instrumentation penetrations present extensive interference. The positioning and spacing of these components prevent an inspector from physically being able to reach them and limits the surface distance required to perform the examination (reference attached photograph depicting configuration). This combined with the curvature of the bottom head and the Bio-shield wall narrowing in this area precludes access. Permanent vessel insulation and limited storage space for those insulation panels which require removal is extremely limited based on the size of the manways.
- Inaccessible due to the proximity of CRD Housings penetrations
- Physical access to the Bottom Head Dollar Plate Weld inaccessible Page 16 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 1 Reactor Pressure Vessel Bottom Head Welds Code Category: B-A Item No. B1.21 & B1.22 Weld ID: VC-BH-2-3 & VV-BH-2A thru 2F Plan View from Drawin2 MSK-3036 Page 17 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 1 Reactor Pressure Vessel Bottom Head Welds Code Category: B-A Item No. B1.21 & B1.22 Weld ID: VC-BH-2-3 & VV-BH-2A thru 2F RPV Bottom Head Drawin2 Showin2 CRD Penetrations 6-i Ci24V' n(d7ý)W a
'V,
ýýzr ý %Iv,.
, I; Page 18 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 1 Reactor Pressure Vessel Bottom Head Welds Code Category: B-A Item No. B1.21 & B1.22 Weld ID: VC-BH-2-3 & VV-BH-2A thru 2F 18" Man way (Typical)
Page 19 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 1 Reactor Pressure Vessel Bottom Head Welds Code Category: B-A Item No. B1.21 & B1.22 Weld ID: VC-BH-2-3 & VV-BH-2A thru 2F Depicts Proximity to Weld Page 20 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 1 Reactor Pressure Vessel Bottom Head Welds Code Category: B-A Item No. B1.21 & B1.22 Weld ID: VC-BH-2-3 & VV-BH-2A thru 2F Depicts Proximity to Weld Page 21 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2A Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-A Total Volume Calculation (NDE Report R014-UT-041)
Basqe Metal Nozzle Area= a+ h -c Area = a
- c + d +c Area = at (c + 360') *Area - bxh Area ý 3:141x095"' (44- 360.) Area 0,95" x 2.75" Area = 2,84"- (0.122) Area = 2.61 Area= 0.35"'1 weld Mectal Total Weld Metal
- 1 Area =a I i j Area 1 - 2 + 3 + 4 +5 Area - V (b x h) Area = 0.023-2 Area = (0.l5" x0.30") 0 075"'
Area =V (f.45:fl) 0.026"1 Area = 0.023"I 1.050"1
- 2 Area = i + k + h - in
- 1.23"'2 Area = b x h Area = 0,15" x 0.50" Area ý 007512" k3 Area - k +1+ rn Total Examination AMre Area I/, (b i h)
Area - (0. 1Y' x 0.35) Shell Base MetIl - 2.63-'9 Area - (0.05251') Nozzle Base Metal ý 2.96"'
Area - 0,026"' Weld Metal,= 1.237"'
6.827"'
- 4 Aran g, hi in + n Area = b x h Area = 0.50" x 2. 10" Area = 1.05A"
- 5 Area - f + g + n Arca = '/ (b x h),
Area = '/2 (0.25" x 0.50")
Area1/4= / (0A 25"9 Arca = 0.063"
Page 22 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2A Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-A Coverage Calculation Axial and Total (NDE Report R014-UT-041)
Base Metal Coverage Area =-a+ b+ c Area - Base Metal Shell - (a + b + c) = Scanned Area Area = Vz(b x h) Area = 2.63"' - 0 14"' = 2.49"' scanned Area = '/ (0.40" x 0.70")
Area - '6 (0.28"3)
Area - 0.14'n Area = d + e +-f Total Base Metal Scanned Area Vi (b x h)
Area = Vi(0.25" x 0.45") 2,49"1 + 0.06"1 - 2.55"1 scanned Area = (0.1 125'-) 2.55"1 + 5-59"' Total Base Metal = 0.4562.or 45.62% scanned Area = 0.06"1 Scanned Weld Metal Coverage Base Metal % Weld Metal %
- ]Area c4-d+g 0' = 15.70% 0' = 0%
Area"= K (b x h) 450 Ax. 600 Ax - 45.62% 450 Ax 600 Ax = 16.53%
Area=' '(0.50" x 0.93") 45' Cire, = 15370% 45' Circ. = 0%
Area = 14 (0.465"') 60 Cite. = 15.70% 60' Citc. = 0%
Area = 0233" scanned in one direction 92.74% 16.53%
- 2 Area= d+i+ h + g 92,74% --, 4 :' 23.18%
Area= b x h 4 26.5% 1/ Co4,rag 27.31%"~t-q+/--166% Total Coverage Area = 0,50" x 0.35" ITP4-goo Area = 0.175"' scanned in one direction Area - #I + #2 = scanned in one direction Area = 0.233"' + 0. 175"' = 0.409"' scanned in one direction Area = 0.409"' e 1.237"' Total Weld Metal = 03306 or 33.06%
Area = 33.06% + 2 " 16.53%
Page 23 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2A Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-A Circumferential Coverage Calculation (NDE Report R014-UT-041)
Area covered by 0°, 47, 610 Area = (b x h) Base Metal Coverage Area = V (0.90" x 1.95")
Area = 1/2/2(1.755"2) Area = 0.8782 - 5.592 Total Base Metal = 0.1570 or 15.70%
Area = 0.878"'
Page 24 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2A Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D item No. B3.90 Weld ID:' N-TH-A Nozzle Configuration for N-TH-A (NDE Report R014-UT-041)
N-TH-A 41 Page 25 of 101
- Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV-I Attachment 2A Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category:. B-D Item No. B3.90 Weld ID: N-TH-A Axial Coverage Plot (NDE Report R014-UT-041)
N-TH-A
&'rP Page 26 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2A Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-A Circumferential Coverage Plot (NDE Report R014-UT-041)
N-TH-A Page 27 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2B Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-B Coverage Calculation (NDE Report 06UT117)
CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume P 32,2 Area Sq. In. Manual Manual Manual Manual 60'NS T-Scan A 9.8 4.3 13.4% 360' 687%
60' S6 T-Scan A 22.4 22.3 69,3% 360 34C6%
60' S4 T-Scan A 00 0.0 0.0% 360 0.0%
_0 NS P-Scan _ A 9.8 3.1 9_6% 360 4.6%
60" S6 P-Scan A 22.4 21.2 1 65.8% 1 _3_ 0 32.9%
60' S4/1RS Scan A 0.0 0;0 1 0.0% 1 360 0.0%
6B" NS T-Scan 60 S6 T-Scan
.60 34 T-Scan ... '
60°_NS P-Scan 60 SO P-Scan,. ...
60*S411RS Scan
% Total Composite Coverage = 79.0%
Page 28 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2B Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-B Axial Coverage Plot (NDE Report 06UT117) 600 NS Exam Volume = 9, 8 Sq, In.
60' FV Exam Volume = 22.4 Sq. In.
0'"(Inner 15% T) ExamVolume = N/A non-clad 60' NS Coverage .achieved i" 4.3 Sq. In.
60' FV Coverage achieved = 22.3 Sq. In, 9- 600 (inner 15% T) Coverage achieved = N/A non-dad
./
S carns 60 0T 0
- _____________________ 60 T
-F Page 29 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2B Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-B Circumferential Coverage Plot (NDE Report 06UT117) 60° NS Exam Volume = 9.8 Sq. In.
600 FV Exam Volume = 22.4 Sq. In.
60" (Inner 15% T) Exam Volume = N/A non-clad 60* NS Coverage achieved = 3.1 Sq. In.
600 FV Coverage achieved = 21.2 Sq. In.
600 (Inner 15% T) Coverage achieved = N/A non-clad P-Scans 60TP 60 0P Page 30 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2C Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category:, B-D Item No. B3.90 Weld ID: N-TH-C Coverage Calculation (NDE Report 06UT 118)
CODE CRO$-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume - 37,5 Area Sq. In. Manual Manual ,Manual. Manual 6A. NS T-Scan 123 2.4 64% 360 3.2%
60* S6 T-Scan 60° S4 T-Scan 4I A A
252 0.0 23.0 0.0
,1.3%
0.0%
360 0
30.7%
0.0%
60" NS P'Sm A 123 1.7 4.5% 360 2.30 60* S6 P-Scan A 25.2 15.9 42.4% 360 212%
60AS4IRS Scan 0.0 [ .0 0.0% 0 0 60' NS T-Scan ______ ______ _____
60' $6 T-Scan 60' S4 T-Scan 60_ NS P-Scan 60' S6 P-Scan 760S411RS Scan
%Total Composite Co~verage = 57.3%
Page 31 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2C Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-C Axial Coverage Plot (NDE Report 06UT118) 60° NS Exam Volume = 12.3 Sq. In.
60C FV Exam Volume = 25.2 Sq. In.
600 (Inner 15% T) Exam Volume =.N/A non-clad 60 NS Coverage achieved 2.4 Sq. In.
" - 60° FV Coverage achieved = 23.0 Sq. In.
/ 60' (Inner 15% T) Coverage achieved = NIA non-dad
.oo600T T- cas
-Scan 600T Page 32 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 2C Reactor Pressure Vessel Top Head - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-TH-C Circumferential Coverage Plot (NDE Report 06UT118) 6ifl NSS Exam Volume = 12.3 Sq. ln.,
600 600 FV(inner 15%Volume Exam T) Exam= 25.2 Volume Sq. In.
= N/A non-dad 60" NS Coverage achieved = 1.7 Sq, In.
60°FV Coverage achieved =15.9 Sq. In.
/ 60' (Inner 15% T) Coverage aohieved = N/A non-clad
/
lo P-Scans 60P 601 I
60°P Page 33 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No, B3.90 Weld ID: 'N-1A Coverage Calculation (NDE Report 06UT121)
CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Per ent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume= 69.4 Area $q. In, Manual Manual Manual Manual 60' NS T-Scan A 20.5 0,8 1.2% 306 0.5%
60' S4 T-Scan [A l 8 3 8.3 12.0"/% 306 5.1%
50' NS P-Scan- A 20,5 r 04 0.6%. 360 03%
607S P-Scan A 40.6 14.6 21.0% 360 10.5%
6C' S441RS Scan A 8.3 5.8 .84% - 360 4.2%
80' WS T-Scan B 20.5 0.8 1.2% 54 0.1%
60' 86 T-Scan 1 40.6 24.7 35 6% 54 2.7%
60' S4 T-Sc-an 1B 8.3 4.2 6.1% 54 0.5%
S0' NS P-Scan I 60' 66 P-Scan 60*S4,RS Scan
% Total Composite Coverage = 40.6%
Page 34 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1A Drawiilg of Nozzle and Limiting Confliuration (NDE Report 06UT121)
Insulation support ring Scan was restricted due to the proximity of the insulation support ring and bracket.
Page 35 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-IA Axial Coverage Plot (250 to 3350)
(NDE Report 06UT121) 60' NS Exam Volume = 20.5 Sq. In.
60' FV EMam Volume 40.6 Sq. In.
60, ,*Ilrer 16% T) Exam Vdume = 8.3 Sq. In.
60* NS Coverage achieved = 08 Sq. In.
/
'-K 60* FV Coversge achieved = 27.5 Sq, In.
60* (inner 15% T) Coverege achieved = 8.3 Sq. In.
1*_1or T-Scans r ....
I---- -
I
-'-~ +/- .
Page36 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1A Axial Coverage Plot (3350 to 250 limited by insulation support bracket)
(NDE Report 06UT121)
EVONS Exam Voiunme 20.5 Sq, In.
E0* FV Exam Volume = 40.6 Sq. In.
60° (inner 15% T) Exam Volume = 813 Sq. In.
60' NS Coverago achieved 0.8 Sq. 'In, eOa R' Coverago aohlovd 24.7 Sq. In, EO< (Inner 15% T) Coverage achieved = 4.2 Sq, In.
/
I T-Scans 60'r 60T i I I I "r=
-I-Page 37 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1A Circumferential Coverage Plot (NDE Report 06UT121)
M1 NS Exrmm Vokimo -20.5 Sq. In.
601 PV Exwi 1.o~i-mD 40.6 Sq. In.
6C'~ (luar 16% T) Exam Vcgume =8,3 Sq. In.
N 60' K'S Coverage achieved 0.4 Sq. In.
OC' FV Coverage achieed =14.6 Sq, In.
60* (liveor 15% T) Coverago achieved = .8 Sq. In.
/ 00"P P-Scanls 60'F I-- II I Page 38 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1
(
Attachment 3B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No, B3.90 Weld ID: N-1B Coverage Calculation (NDE Report # 98-JAF-UT5-012)
TV?--rL CýNLC~uL-A=rCN ~~VL 01-0'/0 -1 f 0/0 Io 5.9-/0 At.- c~
o' 00/ ~
-IŽ' w/o
- -Tc7 - ; Coz k*SCAýAr, EXAM. CbMACAE ýAt;ý
-10 "614Z Ekt'=\.'S CC,>TAF--rVL'Y I A-41 S%.AtTzj Lur- A,-4t L=MM-Mb CmvEm^L-- tvc-ro rTXUw1.
Page 39 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1B Drawing of Nozzle and Limiting Confl2uration (NDE Report # 98-JAF-UT5-012) t-1,Rorj 1:J5ULATi0&/
Page 40 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3B Reactor Pressure Vessel Shell- to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1B Axial Coverage Plot (Typical confi2uration limitation)
(NDE Report # 98-JAF-UT5-012)
L4ZY~ GL. ZU (~ Aa-r
~LN-T~r -r\t L NG Page 41 of 101
Entergy Nuclear Operations,. Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1B Axial Coverage Plot (Insulation ring!limited coverage)
(NDE Renort # 98-JAF-UT5-012l
'~. sI~
Page 42 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1B Axial Coverage Plot (Mirror insulation limited coverage)
(NDE Report # 98-JAF-UT5-012)
AuN No- CcAAj~ratýa Page 43 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 3B Reactor Pressure Vessel Shell - to- Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-1B 00 and Circumferential Coverage Plot INDE Report # 98-JAF-UT5-012)
UT -- 12 epr 9-A
-fD At;-R Ner Cwuaavcý Eye pw 1h eOCIZ?- 1LCAS 7
,1~
I P
- I
.....-- f Page 44 of 101
Entergy Nuclear Operations, Inc.
James'A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2A, N-2B, N-2E, N-2H and N-2K Note: Nozzles N-2A N-2B, N-2E, N-2H and N-2K were examined during the same outage, have typical configurations and limiting conditions.
Covera2e Calculation (NDE Report #'s 98-JAF-UT5-001, 98-JAF-UT5-002, 98-JAF-UT5-003.
98-JAF-UT5-004 and 98-JAF-UT5-005)
TY jr- tx CqLcu-ý C.u Toii -Fog, COZ& REQU=P&th Vo Lu KE S-Jý-,wN- G.,\)P-UC-G- C~E ~
E~m. ~
MZ7 P'Cv\ME.VeZ O VL~l ~ 3~7o
'45"' ý0 2~ ~ lo I- - t AIL - 5c-MW
!S7o 11- '1o (zz.C.
U,, k-i, =. 7.7 AL F ER.L--E ýZ. k(ý& OF 60ý)C Z EQQX r-eD Page 45 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2A, N-2B, N-2E, N-2H and N-2K Drawing' of Nozzle and Limiting Configuration (NDE Report #'s 98-JAF-UT5-001. 98-JAF-UT5-002. 98-JAF-UT5-003, 98-JAF-UT5-004 and 98-JAF-UT5-005)
.flJZLLLATIC zkhsUatbrI@ I A.'fli IV S~ppyeor Page 46 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2A, N-2B, N-2E, N-2H and N-2K Axial Coverage Plot (Typical configuration limitation)
(NDE Report #'s 98-JAF-UT5-001. 98-JAF-UT5-002. 98-JAF-UT5-003.
98-JAF-UT5-004 and 98-JAF-UT5-005)
C t,^LF- T TW [- -- -- -
HAZ Page 47 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2A, N-2B, N-2E, N-211 and N-2K Axial Coverage Plot (Insulation support ring limited coverage)
(NDE Report #'s 98-JAF-UT5-001. 98-JAF-UT5-002. 98-JAF-UT5-003, 98-JAF-UT5-004 and 98-JAF-UT5-005) 4 T Y~z~ Co Cc3C6VELc ~T2"i
)
III
~~L'~S LVIo Page 48 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2A, N-2B, N-2E, N-2H and N-2K 00 and Circumferential Coverage Plot (NDEReport #'s 98-JAF-UT5-001. 98-JAF-UT5-002. 98-JAF-UT5-003, 98-JAF-UT5-004 and 98-JAF-UT5-005)
'Tyý.hCAt. Cýt~ COQEZR~a..
tM.ZCUL.PT:=wu =ýxLs~ NAILE-S QE0--, E 7 L Kký.NO Qr2.Y1ý 615' cm S C;6 r--ýe HAZ Page 49 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2F Total Volume Calculation (NDE Report # 02UT017)
BMETALVOLE Area I Area 2 Area 3 Area - A, B, C Area' B, C, D, E . Area = F, G, H, I Area - Vi(b x h) Area *bxh Area - b x It Area = V/(0.901 x 1.7')C Area = 1.75" x 3.50" Area = 1.7Y x 3.50" Area = (V.58") Area - 6.13"1 Area - 6.13"'
Area - 0.79"'
TOTAL BASE METAL CODE REOUIRED VOLUME Area I +2+3 Area - 0.79"1 4 6.13'9 + 6.13"Y Area - 13.05",
WELD METAL VOLUME TOTAL WELD REQUIRED VOLUME Area 4 Area= I + 2+3 + 4 Arco = D, E, F, 0 Area = 0.79" + 6,13", + 6. 13"14 2.6312 Area Ih Area- 15"68"I Area - 0.75" x 3,50" Area = 2.6311 Page 50 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2F Axial Coverage Calculation (NDE Report # 02UT017)
BASE METAL COVERAGE 2 ANGLES ONE DIRECTION Area 5 Area 6 Area = J,K, 1, Area = K, L, M, N Area - '/ (b x h) Area=bxh Arica = 1/2K (1.75" x 1.60Y') Area= 1.75" x 1.90" Ares - 'A(2.80"1) Area - 3.331 Area - 1,40"1 TOTALBASLMETAL gOVER.GE Area-3+5+6 Area 6.13111+1.40"1z + 3.33"2 Area -I 0.8Y'1
% BASE METAL COVERAGE Pcrcentage - Base Metal Coverage + Total Base Metal Volume fercentage - 10.85" "-13,05"*
Percentage = 0.3314 or 83.14% Scanned TOTAL WELD METAL COVERAGE Area 4 Area =2.63"1 x 2 Diteciions Area = 526"0 Total weld metal volumv Area = 2.63"2 One direction - 5.26"2 Ara - 0.50 or 50% Scanned Page 51 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2F 01, Circumferential and Total Coverage Calculation (NDE Report # 02UT017)
W° BASE METAL COVERAGE 0" WElLD METAL COVERAGE fAu = 3 - Total Base Metal Volume Area = 4 - Total Weld Metal Volane Area = 6013",
- 13.05" Area 5.26""
. - 5.26"9 Arm -=0.4097 or 46.17%/Scanncd Area m 1,0 or 100% Scajued 450& 600 TASV NMETAAL COVERAGE CW 450& 600 BASE METAL COVERAGE CCW Area = 3 + Total Base Metal Volume Area - 4 '- Total Base Metal Volume "Area - 6.13 "1+ 13,05",
Area - 6.1". 13.05'"
Area - 0.4697 or 46,97% Scanned Area - 0.4697 or 46S97% *SaoSwed 450& 6,0 WELD METAL COVERAGE CW 450& 600 WELD METAL COVERAGE CCW Area Total Welt Mctal Voluwlri Arca 4 + Tqtal Weld Metal Volume Arma 5,26"'
- 5.260` Area 5.7262 + 5.260' Agea = 1.0 or IU% Scnne d Area 1.0 or 100% Scarmid TOTAL WELD RE*Q*RED VOLUME SCAND 0' 100.00% 400.1 0% +- 5 Scm = 80.00% Towal Weld KFwtuirod Valuore Sceannd 45'&-60°CW= 100.00%
450 & 600 CCW 100.00%
2 ANGLUS FORWARD- 100.0w.0 400.000 TOTAL BASE METAL REQUIRED VOLUME SCANNED)
- 0. = 46.97% 224.05% 4 4 S*ans, 56.01% Total Weld Required Volume Scia*cd 45" & 60' CW 46.97%
45 & 601 CCW - 46.97%
ZAN"1~QP~AD ~ .
224.05%
TOTAL REQUIRED VOLUMF SCANNED) ALL ANGLES Total Weld Requirad Volume Scatncd + Total Base Metal Volume S&anrd 80.00% 56.G 1% 136,01% 68.00% Total Required Volumc Scanried All Angles Page 52 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2F Coverage Plot (Total Volume)
(NDE Report # 02UT017)
A I -~
B - - ~
I I
I I
0 J
Cl V. 1~
Page 53 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2F Axial Coverage Plot (NDE Report # 02UT017)
II it I
I I
I 1
I Page 54 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2F 0'. Circumferential Coverage Plot (NDE Report # 02UT017) i II I
K!
Page 55 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4C Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2C, N-2D, N-2G, and N-2J Note: Nozzles N-2C, N-2D, N-2G and N-2J were examined during the same outage, have typical configurations and limiting conditions.
Coverage Calculation (NDE Report 06UT123. 06UT125, 06UT127 and 06UT129)
CODE CROSS-SECTIONAL AREA I TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume - 69.3 Area Sq. In. Manual Manual Manual Manual 60° NS T-Scan A 10.1 5.8 1 9.8% 350 4,9_%
60° S6 T-Scan A 40.6 39.8 67.1% 350 32.6%
60Y S4 T-Scen A &S 8.5 14.5% 350 7,0%
600 NS P-Scan A 101 5.2 8.8% 380 47,1.
600 S6 P-Scan AP 40.6 34A1 57.5% 1 3-0 28.8%
600 S4JIRS Scan A 8.6 8.6 14.5% 360 7.3%
60' NS T-Scan 60' S6 T-Scan 21 40.6 32.2 54.3% 10 0.8%
60' S4 T-Scen B 8.6 6,2 10,5% 1 10 0.1%
60' NS P-Scan 60' S6 P-Scan 60°S411RS Scan
% Total Composite Coverage = 15.9%
Page 56 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4C Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2C, N-2D, N-2G, and N-2J Axial Coverage Plot A( 51 to 3550 (NDE Report 06UT123. 06UT125. 06UT127 and 06UT129) 60W NS Exam\ Iolurne = 10.1 Sq. In.
601FV Exam 'olume = 40.6 Sq. In.
60' (Inner 15% T) Exam Volume*= 8.6 Sq. In.
600 NS Govera ge achieved = 5.8 Sq. In.
60W FV Covera ge achieved = 39.8 Sq. In.
600 (Inner 15% T) Coverage achieved =8.6 Sq. In.
T-Scan 601T 600T 71 I
Page 57 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4C Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2C, N-2D, N-2G, and N-2J Axial Coverage Plot (f 3550 to 50 (Limited by insulation support bracket)
(NDE Report 06UT123. 06UT125. 06UT127 and 06UT129) 60 NS Exam Volume = 10.1 Sq. In.
60 FV Exam Volume = 40.6 Sq. In.
60, (Inner 15% 1) Exam Volume = 8.6 Sq. In.
60~
60; NS Coverage achieved = 5.8 Sq. In FV Coverage achieved = 32.2 Sq. In.
60'ý(Inner 15% T) Coverage achieved = 6.2 Sq. In.
60 60" T-Scan4 Burl- 60"T1 I I Page 58 of 101
C-Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 4C Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-2C, N-2D, N-2G, and N-2J Circumferential Coverage Plot (NDE Report 06UT123. 06UT125. 06UT127 and 06UT129)
NS Exam Volume!= 10.1 Sq. In.
FV Exam Volume 40.6 Sq. In.
600 (Inner 15% T) Exam Volume 8.6 Sq, In.
600° NS Coverage achieved = 5.2 Sq. In.
6001 FV Coverage achieved 34.1 Sq, In, 600! (inner 15% T) Coverage achieved = 8.6 Sq. In.
P-Scans 606P 609P II 1
/
.1
~~~~1~
Page 59 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 5A Reactor Pressure Vessel Shell - to- Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-3A & N-3B Coverage Calculation (NDE Report 06UT135 and 06UT137)
CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume w 53.7 Area Sq. In, Manual Manual Manual Manual 60* NS T-Scan A 17.7 .0.6 1.1% 360 0.6%
60' S6 T-Scan A 29.5 19.7 36-7% 360 18.3%
60' S4 T-Scan A 38.5 6.5 12.1% 360 6.1%
60° NS P-Scan A 1 177 0.2 0.4% 360 0,2%
600 $6 P-Scan d A 1 29.5 1 8.0 14.9% 360 7.4%
60° S4AIRS Scan IA Aj 6.5 3.2 6.0% 380 3.0%
601 NS T-Scan I .I I 60'S6 T-Scan I I 60 S4 T-Scan 60' NS P-Scan 60* S6 P-Scan 6QXS4I1RS Scan
_ _ _ _ _ _ _ C_ _ _ _
% Total composite Cowerage = 35.6%
Page 60 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 5A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-3A & N-3B Axial Covera2e Plot (NDE Report 06UT135 and 06UT137) 60° NS Exam Volume " 17.7 Sq. In.
60° FV Exam Volurme = 29.5 Sq. In.
600 (Inner 15% T) Exam Volume = 6.5 Sq. In.
60° NS Coverage achieved = 0.6 Sq. In.
60' FV Coverage achieved 19.7 Sq. In,
. * , 600 (Inner 15% T) Coverage achieved = 6.5 Sq. In,
/ / TScans 60°"T 607T I6",6C7,,
1 n
..T-
- ~
Page 61 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 5A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-3A & N-3B Circumferential Coverage Plot (NDE Report 06UT135 and 06UT137) 600 NS Exam Volume 17.7 Sq. In, 600 FV Exam Volume 29.5 Sq. In.
60" (inner I5%T) Exam Volume = 6.5 Sq. In.
,I 600 NS Coverage achieved =0.2 Sq. In.
] 600 FV Coverage achieved =8.0 Sq. In.
- 1 60' (inner 15% T) Coverage achieved =3.2 Sq. In,
' / / P-Scans .
/ " 60P 60"P
/!
Page 62 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 5B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-3C & N-3D Coverage Calculation (NDE Report #'s 98-JAF-UT5-013, 98-JAF-UT5-014)
T~ ~0 u~ YN C? rOL, EZ V e I3.0Yo0 I -.ý *o Lts~ ~ .~Io
\ /'\7
~L. SC~.Ns MS04 (.j I3. '(°/ft) I q.-H 7' ~
Cz~c...
9 '3/C
. Page 63 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 5B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-3C & N-3D Axial Coverage Plot (NDE Report #'s 98-JAF-UT5-013. 98-JAF-UT5-014) r(&s Ct&D By kTEST Twio Kmz-: IVV/-
Page 64 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 5B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-3C & N-3D Circumferential Covera2e Plot (NDE Report #'s 98-JAF-UT5-013. 98-JAF-UT5-014)
Lmn.=*itz L.CCzatNr.
ht mz O
No.r-
~ ~ci LA Mst bTC'~~ y s..i cz- cm Page 65 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 6A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-4A and N-4C - Feedwater Nozzles Coverage Calculation (Tvnical for N-4A and N-4C0 (Reference NDE Reports 02UT059 to 02UT070)
BEAM DIRECTION_ 0 45 Shear 60 Shear "_--
. WELD ,VOLUME WELD W VOLUME ELD OLUME 0 Degree 62 55 N/A N/A ,N/A INIA N/A N/A Perp. Toward N/A N/A 68 73 73 , 83 Perp. Away N/A N/A 0 NR 0- NR CW N/A N/A 50 54 50 54 CCW N/A NIA 50 54 50 54 AVERAGE 59 50 52 Combined Average 53 Comments ,NR= Heat Afferted Zone nee', only be scanned by two angle beams-in any direction.
Break downs above are calculated by areas calculated In autocad (see plot sheet>
An addliional limitation was encountered frorn the NI 1A nozzle limiting the scan by 17" or 21% of the weld. This brings the total combined average of 53 (53 X .79) to 42% Code Coverage.
TOTAL AVERAGE 42 Page 66 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 6A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-4A and N-4C - Feedwater Nozzles Drawing of Nozzle and Limiting Configuration (Typical for N-4A and N-4C)
(Reference NDE Reports 02UT059 to 02UT070) 17" (Area of Interest)
Page 67 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 6A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-4A and N-4C - Feedwater Nozzles Coverace'Plot (Typical for N-4A and N-4C)
(Reference NDE Reports 02UT059 .to 02UT070)
Areas used Par CaLcuta-Ions Totul o? Welohi 20.98 TotoaL of HAZs 42.57 Weld Diu. (at C.L.)
26,06' Clrc, 81,83.
TotaL cireos cover-ed by 4lncAe 3Bw' HAZ Veld CW/CCV CV/CCW Foword Z Void L" 2943,3 4.2 - 2*6IA N/
- 2-16 Wa NA N/
Coverage Plats N4A, N4B, ?N4C, N4D N~zte "x'Shedtt WtLni cw/ccw
'45*
Page 68 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 6B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-4B and N-4D - Feedwater Nozzles Coverage Calculation (Tvnical for N-4B and N-4D1 (Reference NDE Revorts 02UT059 to 02UT070)
BEAM DIRECTION 0 45 Shear 60 Shear WELD VOLUNE WELD VOLUME WELD VOLUME WELD VOLUME 0 Degree 62 55 NiA NIA NIA N/A N(A NA Perp. Toward N/A N/A 68 73 73 83 Perp. Away N/A NfA 0 NR 0 NR CW N/A N/A 50 54 50 54 CCW N/A NIA 50 54 50 54 1 1 AVERAGE 1 59 50 52 Combined Average 93 Comments: NR= Heat Affected Zone need Dnly be scanned by two angle beams in any direction.
Break downs above are calculaled by areas calculated in aulocad (see plot sheet).
TOTAL AVERAGE 5~3 Page 69 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 6B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-4B and N-4D - Feedwater Nozzles Covera2e Plot (Typical for N-4B and N-4D)
(Reference NDE Reports 02UT059 to 02UT070)
Areaos used for CaLLcuLations TotoA of Weli 20,98 TotaLI of HAZ' 42.57 Vetd Dia, (at CL,)
26,06' Circ, 81,83' ToTIt areos covered by--- ortge
- 1A i veld kWICCV CIV/CCW W
roword HAZ WOW 4:*r3094f 14.2 1 23,03 1O 23 IZ9jI N/A N/A Coveroge Plats Nz, Nn :-N4C. 4UD No~zzle 70 Shell welcks cw/ccw F45&
Page 70 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle Total Volume Calculation (NDE Report R014-UT-023)
Area = A+B+C Area = D+B+C Area = %A(b x h) Area= 1A(b x h)
Area = 1A 0.20" x 0.60") Area - ' (0.20" x 0.60" Area -A( .12"') Area -A ( .12"1)
Area = 0.06"' Area - 0.06' Area = A+E+D Area - A+E+F Area - ' (bx h Area-'A(bxh)
Area 4 ( 0.60" x 1.20") Area 'A( 0.90" x L.20")
Area= A2 0.72"') Area = Y ( 1.08"')
Area = 0.36"' Area -0.135"'
Area = D+F+H+I Area = H+I+S+T Area = b x h Area -b x h Area -1.50" x0.50" Area - 1,50" i 3.00" Area = 0.750"1 Area *4.50"'
Area- F+O-tJ Area -=+KN Area 'A (bxh,)
Ame - Y, b x h)
Area: ' (0,40" x 0.75") Area - V ( 0. 15" x0. 75")
Area- 'A ( O.11252%3)
Arta - 0.15"' Area.- 0;05625!
Area - G+H+J+K Area - H+K+R+S Area=bxh Area" bxh Area - 0.75" x 0. 15" Area - 0.75" x 3.00" Area - 0. 1125"' Area - 2.25"2 Area - K.L+N Area =,L+M+N Area- 'A, b~.h )
A*e=A (0.15" I. 0.75")
Area (A ,Ib25r Area - (0. 1 1,71 )
Arena 0 5625' Area ,-&.5625"'
Area - L-4+Q"*R At- N+O+P+Q Arft - bXft Aream bib Area - 0.75" x 2.85" Area- 13" x -3.00" Are* 4.50rý Vessel Base Metal = 4.50"' + 2.1375"; +.0.05625"' = 6.69"'
Weld Metal- 0.05625"' + 0.05625", + 2.25"' + 0.1125'; + 0-1.5" =2.625"'
Nozzle Base Metal - 4.50"' r+ 0.750"' + 0.36" 1 + 0.135"' + 0.06"' + 0,06"* 5.8651' Page 71 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle Coverage Calculation (NDE Report R014-UT-023)
Vessel Base Metal Area a + C + d Area = a + c + e Area - 0.2625"'* - 0.05625"1 Areao - (b x h) Area=-V( b x h) Area - 0.21 "' for a + d + e Area- _V ( 0.15" x 0.75" Area = 'A (0.70" x,0.75")
Area=1/2V(0.1125"1) Area = Ya 0.525"1 Area = 6.69'" Total vessel base metal - 021" = 6,48"1 scanned Area = 0.05625' Arca = 0.2625'" Area.- 6.48"'
- 6,69!'Z = 0.968 or 96.8%
Weld Metal Area-c +f+g Area - f+g+h + i Arcoa 0.2625" +1,20'; = 1.46"1 Area - v(b x h) Area b x h Area = 1.46"1 + 2,625" r'otal weld Metal - 0.56 or Area - Y (0.75" x 0.70"') Arca=,0.75" x, 1.60" Area = 56.0%
Area = Y (0.525"') Area = 1.20"ý scanned Area - 0,2625"1 scanned Nozzle 'Base Metal Area - g + i + I Area " 1.40"' + 5.865"' Nozzle Base Metal = 024 or 24 %
Arma -A ( bx )
Area AV .76"KxL6.5")
At" - A~ 2.,Q~'
AmewIV, 4 al"semita keg.4( ir k IxO0'dw Amea - 43" Weased
&06O6'A 011 Wwvtm al 56Q% In. cQ4wAt cIr#' CCW owwrkts 'r nJA%
Page 72 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle Drawing of Nozzle and Limiting Configuration (NDE Report R014-UT-023)
/
'ý&) 01 1'.
I Page 73 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle Coverage Plot (Calculation Drawing)
(NDE Report RO14-UT-023)
I I, /
Ip Ir I
I I
I Page 74 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle Coverage Plot (Calculation Drawing)
NDE Report R014-UT-023)
Page 75 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle 450 Axial Coverage Plot (NDE Report R014-UT-023)
Page 76 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle 600 Axial Covera2e Plot (NDE Report R014-UT-023)
Page 77 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7A Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5A Core Spray Nozzle 0° and Circumferential Coverage Plot (NDE Report R014-UT-023)
(6 Page 78 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5B Core Spray Nozzle Coverage Calculation (NDE Report 06UT133)
CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = '360. Required Exam AreaScanned of Area Weld Length Percent Exam Voluma
- 5. Area Sq,, In. Manual Manual Manual Manual 6D' NS T-Scan A 16.9 1..1 2.0% 350 1.0%
60" 55 T-Scan A 31.6 22.1 40.2% 350 19.5ya 60° 54 T-Scan A 6.5 6.5. 11.8% 350 5.7%
603 NS P-Scan 1.. 1A 0,6 1.1% 350 0.5%
60' 88 P-Scan A J 31.6 915 17.3% 350 .8.4%
60' S4WIRS Scan A 6.5 319 7.1% 350 3.4%
60' NS T-Scan 60' S5 T-Scan 00* 54 T-Scan 60' NS P-Scan 60' S6SP-Scan 60'°4/IRS Scan
% Total Composite Coverage 38.6%
Page 79 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5B Core Spray Nozzle Axial Coverage Plot
"(NDE Report 06UT133) 60= NS Exam Volume 16.9 Sq. In.-
6o0 FV Exarn Volume = 31.6 Sq. In.
6O0 (Inner 15% T) Exam Vilurne = 6-5 Sq. 1n.
- V Rin' NS Coverage achieved 1.1 Sq:. Ih.
60' FV Coveruae,a.chieved = 22.1 Sq. In, 60' (Inner 15% T) Coverage achieved = 6,5 9q. In,
/
T-UaTIriS 60-T 60-T I
Page 80 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 7B Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-5B Core Spray Nozzle Circumferential Covera2e Plot (NDE Report 06UT133) 60 NS Exam Volume = 1e.g9lSq. In.
60" FV Exam Volume -31.3 Sq. In.
60 (Inner 15% T) Exam Volume = e4 S*q. I_
600 NS Coverage achievedz 0,QB Sq. Ii.
60' FV Coverage achieved = 0,5 Sq. VI.
60' (Inner 15% T) GCvve*ru achieved a 3.9 Sq, In.
/ P-Scans 60-p 60Bp I
/
I I I 7/
H---
K L
N Page 81 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 8 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-8B Coverage Calculation (NDE Report # 98-JAF-UT5-011)
I-A.. N& EýAm. (u T 5& Cc a2a.a % Io.- 6 ISO° -k ý.D 151°10
'ýi.-S_*k a7.2ao Lj5' - (7': Io. b 70ý C=Zr.SCtz
-7 ~ ~ ~
Vowm=r F AjE*M-V-w- MOre'. CL-L-.4 7. kA kam E~.m- 0.xta NOT kur4.-ICLm&c..
CoZ~S'hiLNT Due To&I> RolL t~r TOAo3 Gc-k % Cwc 5-&
Page 82 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 8 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-8B Drawin2 of Nozzle and Limiting Configuration (NDE Report # 98-JAF-UT5-011)
$ " t_ F,r , * -3 N.$s
.t= o.**
o~ VES$EL Page 83 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 8 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-8B Axial Coverage Plot (Configuration Limitation)
(NDE Report # 98-JAF-UT5-011)
I-N tkcOtN Nte- (.oq Ck3by (\7'~
See~j wx" -CAwtPA Page 84 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick.NPP Third Interval Relief Request RR-CRV- 1 Attachment 8 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-8B Axial Coverage Plot (Configuration Limitation)
(NDE Report #'s 98-JAF-UT5-011)
TYPIMLAA C-OZG~ 4AE Z r F-49 !4d SN o- LLE ma. co~ja'Z.lG~'by AnLE -1 Ae&
e~L~u~4~M LCZ S
7-Page 85 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV-1 Attachment 8 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-8B Axial Coverage Plot (Configuration Limitation)
(NDE Report #'s 98-JAF-UT5-011)
T'01CAL- CNI-CqLIKIMON Pez cozig-Fqg, I
~-
Thcn ttCct Page 86 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 8 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-8B O0 and Circumferential Coverage Plot (Configuration Limitation)
(NDE Renort #'s 98-JAF-UTS-01 )
CwNe\kC4; Rso7ý=LZD5k L~~~t~ANC Lo*
~I (2 LZIX.. SLMS: (O.~/O I
I!
Page 87 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 9 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-9 Control Drive Nozzle Coverage Calculation (NDE Report 06UT140)
CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE re Percent Weld Length a 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume w 55.6 Area Sq. In, Manuel Manuel Manual Manual 60' NST-Scan A 153 41 7.4% 315 3.2%
601 S6 T-Scan t A 32.2 28.8 51,8% 3115 22.7%
80' S4 T-Scan A 8.1 8.1 14.6% 315 6.4%
60D NS P-Scan A 15.3 38 6.8% 315 3.0%
601 S6 P-Scan A 32.2 " 24.8 44.6% L 315 j 19H5%
60° S41IRS Scan _A 8,1 8.1 14.6% 315 6.4%
60' NS T-Scan . 1 B 15.3 4.1 7.4% 45 0.5%
60' 36 T-Scan I B 32.2 15.6 1 28.1% 45 !.8%
601 S4 T-Scan .... 8.1 . 11.6%
0.9 45 0.1%
60' NS P-Scan 8 15.3 3.8 6.8% 45 0,4%
60' S6&P-Scan a 32,2 17.4 31.3% 45 2.0%
60°$4/IRS Scan a . 8.1 29 5.2% 45. 0.3%
%Total Composite Coverage 66.2%
Page 88 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 9 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-9 Control Drive Nozzle Drawing of Nozzle and LimitinE Condition 600 RL T-Scan restricted due to insulation support ring (NDE Report 06UT140)
OD Blend Radius Insulation support rii 1250 a.
170° az.
Page 89 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 9 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-9 Control Drive Nozzle Axial Coverage Plot (NDE Report 06UT140) 600 NS Exam Volume 17.8 Sq. In.
60 FV Exam Volume - 27.7 Sq. In.
606 (Inner 15% T) Exam Volume;-- 8.1 Sq. In.
A 60" NS Coverage achieved = 4.1 Sq' In, 60' FV Coverage achieved = 28.8 Sq. In.
60' (inner 15% T) Coverage achieved = 8.1 Sq. In.
,//
/.
/ 607T 6O-T BOOT
/
F--
N
-I Page 90 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 9 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-9 Control Drive Nozzle Axial Coverage Plot 125 to 175 Degrees (NDE Report 06UT140)
L\ 00" NS Exam Volume = 17.8 Sq. In.
100 FV Exam Volume = 27.7 Sq. In.
60U (Inner 15% T) Exam Vohame = 81 Sq. In.
60 0 NS Coverage achieved = 4.1 Sq. In.
603 FV Coverage achieved,- 15.6 Sq. In.
50a (Inner 15% T) Coverage achieved = 0.9 Sq. In.
I 5QUT Il 60' T-Scan restricted due to insulalion support ring Page 91 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 9 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. B3.90 Weld ID: N-9 Control Drive Nozzle Circumferential Coverage Plot 11 (NDE Report 06UT140)
I 60* NS Exam Volume 15.3 Sq. In 60* FV Exam Volume = 32,2 Sq. In.
600 (Inner 15% T) Exam Volume: 8.1 Sq. In.
60 N$ Coverego achkicd = 3,8 Sq. In.
60' FV Coverage. achieved --24.8 Sq. In.
60" (inner 15% T) Coverage achieved = 8.1 Sq. In.
/
I 60"~P 601P II I
1 I.
- *1
1 Page 92 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 9 Reactor Pressure Vessel Shell - to - Nozzle Weld Code Category: B-D Item No. . B190 Weld ID: N-9 Control Drive Nozzle Circumferential Coverage Plot 125 to 175 Degrees (NDE Report 06UT140) 60* NS Exam Volume'= 163 Sq. In.
60" FV Exam Volume = 32.2 Sq. In.
60° (Inner 1S%T) Exam Volume - 8.1 Sq'. In.
- 60. NS Coverage achieved = 3.8 Sq. In.
600 FV Coverage achieved = 17.4 Sq. In.
600 (Inner 15%T) Coverage achieved 2.9 Sq. In.
/
// \
>1 SWP
~
0OP IIt Page 93 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 10 Reactor Pressure Vessel Ligaments Code Category: B-G-I Item No. B6.40 Weld ID: RPV Threads in Flange (Ligaments)
Drawing Depicting Limiting Conditions and Volume Examined (NDE Report # 98-JAF-UT7-001)
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Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 11 Reactor Pressure Vessel Integrally Welded Attachments Code Category: B-K (B-K-i)
Item No. B10.10 Weld ID: Stabilizer-i, 2, 3 and 4 Drawing Depicting Limitin2 Conditions (Typical for all Stabilizers) 13 of 38 inches examined -34% complete Page 95 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 11 Reactor Pressure Vessel Integrally Welded Attachments Code Category: B-K (B-K-i)
Item No. B10.10 Weld ID: Stabilizer-i, 2, 3 and 4 Drawing Depicting Limitin2 Conditions (Typical for all Stabilizers) 13 of 38 inches examined - 34% complete F:R oNT ViEW.
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Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 12 Control Rod Drive System (Scram Tank 03TK-IA)
Code Category: C-A Item No. C1.20 Weld ID: BH-1A (Scram Tank Shell-to-Bottom Head)
Axial / Circumferential Covera2e Plot (NDE Report # 04UT069)
I_
76" Weld Length Obstructions : 4 Supports 9" Wide = 36" 4 Weld-o-lets 3" Wide = 12" Total Weld Obstructed 48" 76" - 48" = 28" Inspected 18 % Total Weld Coverage Page 97 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 12 Control Rod Drive System (Scram Tank 03TK-IA)
Code Category: C-A Item No. C1.20 Weld ID: BH-1A (Scram Tank Shell-to-Bottom Head)
Coverage Plot (Obstructions/Limitin2 conditions)
(NDE Report # 04UT069)
Shell 9.
q, 13, KU-Is,'
V H W.M W.dd Boltom Head
-I Page 98 of 101
Entergy Nuclear Operations, Inc.
James A. FitzPatrickNPP Third Interval Relief Request RR-CRV- 1 Attachment 13 Control Rod Drive System (Scram Tank 03TK-1A)
Code Category: C-B Item No. C2.20 Weld ID: N-1-A-IR (Nozzle Inner Radius) 00 and 1800 Coverage Plot (NDE Report # 04UT071) 5 J'.0z 2[.O
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Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 13 Control Rod Drive System (Scram Tank 03TK-1A)
Code Category: C-B Item No. C2.20 Weld ID: N-1-A-IR (Nozzle Inner Radius) 900 and 270 Coverage Plot (NDE Report # 04UT071) 1.5*
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Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP Third Interval Relief Request RR-CRV- 1 Attachment 14 High Pressure Cooling Injection (HPCI)
Code Category: R-A Item No. R1.20 Weld ID: 14-23-433 Axial / Circumferential Coverage Plot (NDE Report # 06UT052)
Flow ,.
Valve AXIAL EXAM
- Coverage = 100%ý CIRC EXAM
- Exam width = (0.5- US 4 Weld f 0.5" D06)- 2.0"
, Examined (Weld + 0.5" DS) i15 1.S/2=75%
CALC
- (lOD%+ 75%)12 =87.5%rcojjergew Page 101 of 101