ML031470077

American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection (ISI) Program - Relief Requests

ML031470077
Person / Time
Site:	Sequoyah
Issue date:	05/13/2003
From:	Salas P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
-nr
Download: ML031470077 (70)

Text

{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 May 13, 2003 10 CFR 50.50a(g) (5) (iii) U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentleman: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSERVICE INSPECTION (ISI) PROGRAM - RELIEF REQUESTS Pursuant to 10 CFR 50.55aig) (5) iii), TVA is submitting i%ve requests for relief from ASME Code requirements. The eli.ef requests are associated with ISI activities performed curing SQN's first and second periods of the second ISI inter;Tal. Three relief requests are for Unit 1 and two relief requests are for Unit 2. The relief requests are based on limitations that preclude full code examination of ASME Class 1 and 3 welds. Code examination of the welds is limited due to design configurations. The relief requests are submitted in accordance with 10 CFR 50.55a(g)(5)(iii). TVA requests that NRC provide approval in accordance with 10 CFR 50.55a(g)(6)(i). The SQN ISI Program is currently in the second 10-year ISI interval. TVA is in the process of planning inspection activities for the end of the second 10-year interval (i.e., Cycle 13 refueling outages for both units). NRC response is requested by June 2004 to support scheduling of ISI activities during the cycle 13 refueling outages. P,,ted on recyded paper

U.S. Nuclear Regulatory Commission Page 2 May 13, 2003 provides the Unit 1 specific request for relief. provides the requests for relief common to both units. provides examination data reports for each relief request. provides ISI drawings. provides a limitation drawing typical of Unit 1 and Unit 2 for Essential Raw Cooling Water strainer. provides pipe support drawing 1-SIH-801. provides TVA' s procedure for calculation of the ASME code coverage for Section XI nondestructive examinations. There are no commitments contained in this letter. This letter is being sent in accordance with NRC RIS 2001-05. If you have any questions about this change, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672. Sincerely G e o ~~~~~46 Pedro Salas -Licensing and Industry Affairs Manager Enclosures cc (Enclosures): Mr. Michael L. Marshall, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0-8G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT (SQN) AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) REQUEST FOR RELIEF FOR UNIT 1 1-ISI-23 El-I

Request for Relief 1-ISI-23 Executive Summary: TVA is requesting relief from the ASME code to address the circumferential pressure retaining piping weld RHRF-107 in the residual heat removal (RHR) system. The design configuration of the subject piping precludes a 100% ultrasonic examination of the required weld volume. These physical examination limitations occur when the 1989 Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the issue date of SQN's Unit 1 construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10 CFR 50.55a(g)(4). An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject weld. The design configuration used limits the best effort ultrasonic examination to approximately 72%. Performance of an ultrasonic examination of essentially 100% of the subject circumferential pressure retaining weld, would be impractical. The maximum extent practical ultrasonic examination of the subject weld provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the welds. Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval. Unit: 1 System: RHR - System 74 Component: One Piping Circumferential Pressure Retaining Weld. ASME Code Class: ASME Code Class 1 (Equivalent) El-2

Reauest for Relief 1-131-23 (continued) Section XI Edition: Code Table: 1989 Edition; 1995 Edition with 1996 Addenda; 10 CFR 50.55a(b) (2) (xv) (A); WCAP-14572, Revision 1-NP-A; and WCAP-14572, Revision 1-NP-A, Supplement 1 WCAP-14572, Table 4.1-1 Examination Category: Examination Item No: Code Requirement: Code Requirement From Which Relief is Requested: List of Items Associated With the Relief Request: R-A, Risk - Informed Piping Examinations R1.11, Elements Subject to Thermal Fatigue R1.16, Elements Subject to Intergranular Stress Corrosion Cracking (IGSCC) WCAP-14572, Table 4.1-1, Examination Category R-A, Item Nos. R1.11 and R1.16, requires Volumetric Examination Volumetric Examination Coverage of Essentially 100 Percent RHRF-107, Piping Circumferential Weld Basis for Relief: The design configuration of the RHR piping and piping support location precludes an ultrasonic examination of the required volume of the subject weld RFRF-107 because of interference of a permanent piping support. The design configuration limits ultrasonic examination to approximately 72% of weld RHRF-107 for the required examination areas as calculated in accordance with TVA Procedure N-GP-28. E1-3 Reauest for Relief 1-ISI-23 (continued)

Request for Relief 1-ISI-23 (continued) Alternative Examinations: In lieu of the code required 100% volumetric examination, a best effort ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject weld. Refer to attached examination data report. Justification for the Granting of Relief: The design configuration used in the fabrication of the subject piping in conjunction with the permanent rigid pipe support (1-SIH-801) precludes ultrasonic examination of essentially 100% of the required examination volume. In order to examine the welds in accordance with the code requirements, the RHR system pipe support would require extensive modification. RHRF-107 is limited at two locations due to a permanent rigid support (1-SIH-801) plate which limits the access from the elbow side for a total of 8 inches. One plate is located on the inside radius of the elbow and is approximately 5 inches in length. The other plate is located on the outside radius of the elbow and is approximately 3 inches in length. The design configuration limits the best effort ultrasonic examination to approximately 72% for weld RHRF-107. The subject weld was examined using application of the best available ultrasonic technology. Radiographic examination as an alternate volumetric examination method was determined to be impractical because the same plates that limit ultrasonic examination also obstruct film placement. Examination of similar components provides reasonable assurance that significant degradation, if present, would have been detected. Performance of an ultrasonic volumetric examination of essentially 100% of the required volume of pressure retaining circumferential welds RHRF-107 (pipe to elbow) in the RHR piping is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The maximum extent practical ultrasonic examination of the weld and adjacent material and the code required VT-2 examination for leakage will provide reasonable assurance of an acceptable level of quality and E1-4

Request for Relief 1-ISI-23 (continued) safety. Significant degradation, if present, would be detected during the ultrasonic and VT-2 examinations that are performed on the subject weld. As a result, reasonable assurance of structural integrity for this weld is provided by the examinations that were performed. Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval. Implementation Schedule: This request for relief is applicable to SQN's second 10-year inspection interval for SQN Unit 1. Weld RHRF-107 for Unit 1 was examined in the second period.

References:

Examination Data Report: R7785 - ISI Program Drawings: CHM-2336-C-06 weld isometric CHM-2435-C-06 support isometric - Pipe Support Drawing: 1-1-H20-0801 for support 1-SIH-801 - Non Destructive Examination Procedure N-GP-28 "Calculation of ASME Code Coverage for Section XI NDE Examinations" E1-5

ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT (SQN) AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) REQUEST FOR RELIEF FOR UNITS 1 AND 2 1/2-ISI-24 1/2-ISI-25 E2-1

Request for Relief 1ISI-24 and 2-ISI-24 Executive Summary: TVA is requesting relief from the ASME code to address the Unit 1 and Unit 2 pressurizer support skirt integral attachment welds. The design configuration of the pressurizer support skirt precludes a 100% surface examination of the required area. These physical examination limitations occur when the 1989 Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the issue date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10 CFR 50.55a(g) (4). An inservice surface examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject welds. The design configuration limits the best effort surface examination to approximately 50% on both pressurizer welds. Performance of a surface examination of essentially 100% of the subject integral attachment welds, would be impractical. The maximum extent practical surface examination of the subject welds and a supplemental ultrasonic examination of the inaccessible area provide reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the area and volume examined provide sufficient information to judge the overall integrity of the welds. Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval. Unit: 1 and 2 System: Reactor Coolant System (System 68) Pressurizer Components: Integral Attachments for Vessels (Pressurizer Support Skirt) ASME Code Class: ASME Code Class 1 (Equivalent) Section XI Edition: 1989 Edition Code Table: IWB-2500-1 E2-2

Request for Relief 1-ISI-24 and 2-ISI-24 (continued) Examination Category: Examination Item No.: Code Requirement: Code Requirements From Which Relief is Requested: List of Items Associated With the Relief Request: B-H (ASME Code Case N-509, Category B-K) B8.20 (ASME Code Case N-509, Item No. B10.10) Code examination-figure IWB-2500-13 which requires a surface examination of areas A-B and C-D of the pressurizer support skirt to vessel weld. Requirement to perform a surface examination of the pressurizer support skirt weld examination area C-D, as illustrated in Figure IWB-2500-13 (inaccessible surface area). Pressurizer Support Skirt Weld No. RCW-23A (Unit 1) and RCW-23 (Unit 2) Basis For Relief: The design configuration of the pressurizer support skirt precludes a surface examination of the required area (examination area C-D illustrated in Figure IWB-2500-13). This area is not accessible for surface examination due to the location, configuration, and close proximity of the 78 immersion heaters extending from the bottom head. The design configuration limits surface examination to approximately 50% of weld RCW-23 for Unit 1 and 50% of weld RCW-23A for Unit 2 of the required examination areas as calculated in accordance with TVA Procedure N-GP-28. Alternative Examination: In lieu of the code required 100% surface examination on both sides of the pressurizer support skirt integral attachment welds, a 100% surface examination on surface A-B as illustrated in Figure IWB-2500-13 and a best effort ultrasonic volumetric examination for surface C-D as illustrated in Figure IWB-2500-13 was performed on both welds. Refer to attached examination reports. E2-3

Request for Relief 1-ISI-24 and 2-ISI-24 (continued) Justification for the Granting of Relief: The design configuration of the pressurizer support skirt precludes surface examination of essentially 100% of the required examination area. In order to examine the welds in accordance with the code requirements, the pressurizer would require extensive modification. The examination requirement is a surface based on the weld configuration. The weld configuration for SQN Unit 1 and 2 pressurizer support skirts is illustrated in code Figure IWB-2500-13, and requires a surface examination of areas A-B and C-D, (the outside and inside surfaces, respectively). This design configuration of the subject pressurizer support skirt to pressurizer integral attachment weld precludes surface examination of surface C-D as illustrated in Figure IWB-2500-13. The examination area C-D in Figure IWB-2500-13 is not accessible for surface examination due to the location, configuration and close proximity of the 78 immersion heaters extending from the bottom head. Physical access by the examiner is limited because of high radiation levels and obstructions due to the immersion heaters and the related wiring. The magnetic particle examination (yoke) cannot be used due to the space restrictions. The dye penetrant examination would require a very thorough cleaning of the weld and adjacent base material. The preparation of the weld would potentially require using techniques such as manual wire brushing since power tools may not fit into the limited space area. The design configuration limits surface examination to 50% (examination of areas A-B only) for both welds. Radiological dose rate in these areas (bottom head) may be approximately 40 to 45 mr/hour. It is conservatively estimated that approximately 32 man-hours would be required (2 people 8 hours to remove/assemble scaffolding, 2 people x 4 hours to remove/assemble insulation and 2 people x 4 hours to perform the examination, if it was accessible). A total of 1.28 roentgen equivalent-man (REM) could be received by all involved personnel. The ultrasonic volumetric examination of the inaccessible area was performed using a 45-and 60-degree shear wave examination resulting in 100% examination coverage of the E2-4

Request for Relief 1-ISI-24 and 2-ISI-24 (continued) pressurizer support skirt weld examination area C-D, as illustrated in Figure IWB-2500-13 (inaccessible surface area). Performance of a surface examination of essentially 100% of the required surface of the pressurizer support skirt weld is impractical. A surface examination on surface A-B as illustrated in Figure IWB-2500-13 and a ultrasonic volumetric examination for the inaccessible surface was performed on the subject weld. These examinations provide reasonable assurance of an acceptable level of quality and safety because the weld surface and the weld volume examined provides sufficient information to judge the overall integrity of the weld. The proposed alternative volumetric examination of the inaccessible area has been evaluated and judged technically acceptable by the NRC Staff for use at TVA' s Brown's Ferry Nuclear plant, Units 2 and 3, for the reactor pressure vessel support skirt weld. Therefore, an acceptable level of quality and safety will be achieved and public health and safety will not be endangered by utilizing the proposed alternative volumetric examination of the inaccessible areas in lieu of the prescribed surface examination requirements of the ASME Code. Compliance with the ASME Code, will result in unusual difficulty and radiation exposure to personnel without any compensating increase in the level of quality or safety. The proposed alternative will provide an acceptable level of quality and safety Therefore pursuant to 10CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval. Implementation Schedule: This request for relief is applicable to the second 10-year ISI Interval for SQN Unit 1 and Unit 2. Weld RCW-23A for Unit 1 and RCW-23 for Unit 2 were examined in the second period.

References:

Letter from Richard P. Correia, NRC to J.A. Scalice, TVA, dated June 19, 2000, "Brown's Ferry Nuclear Plant Units 2 and 3, Relief Request 2-ISI-10 and 3-ISI-9, Alternatives for Examination of Inaccessible Reactor Pressure Vessel Support Skirt Welds (TAC Nos. MA6408 and MA 8423)" (L44 020604 001) E2-5

Request for Relief 1-ISI-24 and 2-ISI-24 (continued) Examination Data Reports: R7811 and R7819 (Unit 1) R6432 and R6436 (Unit 2) ISI Program Drawings: ISI-0394-C-01 (Unit 1) ISI-0396-C-01 (Unit 2) - Non Destructive Examination Procedure N-GP-28, "Calculation of ASME Code Coverage for Section XI NDE Examinations" E2-6

Request for Relief 1-ISI-25 and 2-ISI-25 Executive Summary: TVA is requesting relief from the ASME code to address the Unit 1 and Unit 2 the essential raw cooling water (ERCW) system strainer support AlA-A Unit 1 and A2A-A Unit 2 integral attachment. The design configuration of the ERCW strainer to support interval attachment weld precludes a 100% visual VT-3 examination of the required area. These physical examination limitations occur when the 1989 Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10 CFR 50.55a(g) (4). An inservice visual examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject welds. The design configuration limits visual examination to approximately 75% on both welds. Performance of a visual examination of essentially 100% of the subject integral attachment welds, would be impractical. The maximum extent practical visual examination of the subject welds provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the area examined provides sufficient information to judge the overall integrity of the welds. Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval. Unit : 1 and 2 System: ERCW System (System 67) Components: ERCW Strainer Support Integral Attachment Weld ASME Code Class: ASME Code Class 3 (Equivalent) Section XI Edition: 1989 Edition Code Table: IWD-2500-1 Examination Category: D-A, Systems in Support of Reactor Shutdown Function (ASME Code Case N-509 Integral Attachments for E2-7

ReQuest for Relief 1-151-25 and 2-131-25 (continued) Class 3 Vessels, Piping, Pumps and Valves) Examination Item No.: Code Requirement: Code Requirement From Which Relief Is Requested: ASME Section XI Item Number D1.20, Integral Attachment - Component Supports and Restraints (ASME Code Case N-509, Item No. D1.10) ASME Section XI, Table IWD-2500-1, Examination Category D-A, Item Number D1.20, Requires VT-3 Examination (ASME Section XI Code Case N-509 Item No. D1.10 Requires VT-1 Examination) Visual VT-3 Examination Coverage of Essentially 100% of the ERCW Strainer Support Integral Attachment Weld List of Items Associated With the Relief Request: ERCWSH-05-IA, Integral Attachment Weld (Unit 1) ERCWSH-11-IA, Integral Attachment Weld (Unit 2) Basis for Relief: The design configuration of the ERCW strainer support precludes a complete visual VT-3 examination of the required area for the integral attachment weld ERCWSH-05-IA (Unit 1) and ERCWSH-11-IA (Unit 2). These areas are not accessible for visual examination due to the location and configuration between the strainer and the concrete floor. The design configuration and location limits visual examination to approximately 75% of weld ERCWSH-05-IA for Unit 1 and 75% of weld ERCWSH-11-IA for Unit 2 of the required examination areas as calculated in accordance with TVA Procedure N-GP-28. Alternative Examination: In lieu of the code required 100% VT-3 visual examination, a VT-1 visual examination of the ERCW strainer integral attachment weld was performed on accessible areas to the maximum extent practical given the physical limitations. Refer to attached examination reports. E2-8 Reauest for Relief 1-ISI-25 and 2-ISI-25 (continued)

Request for Relief 1-ISI-25 and 2-ISI-25 (continued) Justification for the Granting Of Relief: The design configuration of the subject weld (partial penetration), Item No.5 (base plate) to Item No.1 (strainer) precludes visual examination of essentially 100% of the required examination area. In order to visually examine the weld in accordance with the code requirement, the ERCW strainer would require extensive disassembly in order to access the inside surface of the strainer. In order to dissemble the subject strainer, a temporary monorail is required to be installed due to limited overhead clearance. The physical arrangement of the ERCW Strainer is composed of 16 integral lug (Item No.30) attachments that support the strainer body No.1 to a base plate connection (Item No.5). As part of the integral attachment, the base plate assembly (Item No.5) is attached to the strainer body (Item No.1) by a partial penetration weld from the inside surface for 360 degrees and a fillet weld 360 degrees around the outer circumference for 360 degrees. Each of the 16 attachment lugs and outer base plate to strainer body welds are accessible from the outside surface. The inside surface partial penetration weld does not allow access for visual examination. The amount of examination coverage when considered in total weld length examined was determined to be approximately 75%. Radiographic examination from the outside surface as an alternate volumetric examination method was determined to be impractical due to the support attachments affecting radiographic quality. Performing radiographic examination from the inside surface of the ERCW strainer would require placing a radiographic source near the center of the component. The ERCW strainer would require complete extensive disassembly and being taken out of service for an extended period of time. Radiographic quality would be compromised due to the support attachments and the subject contrast effects from conditions associated with a partial penetration weld (i.e., butt joint match lines would mask indication due to the partial penetration condition).

Thus, additional radiography from the inner surface, to gain any additional coverage, are also impractical.

Performance of an ultrasonic volumetric examination to supplement the required coverage was also deemed to be impractical. The design configuration of the partial penetration weld is not amenable for the detection of E2-9

Request for Relief 1-ISI-25 and 2-ISI-25 (continued) circumferential flaws due to the partial penetration condition (i.e., discrimination of weld flaws is masked due to the partial penetration weld geometry). In addition, the fillet weld impedes the search unit position from the outside surface such that the ultrasonic beam cannot be oriented for detection of radial oriented flaws. The support attachments are 1 inch thick welded lugs equally stationed at 16 positions around the strainer. The lug attachments, along with 5 equally spaced bolt holes, would in addition interfere with the sound beam from being directed to the inner-weld region. Performing a surface examination from the inside was determined to be impractical due to the same reasons as the visual examination. The more detailed VT-1 visual examination was performed in lieu of the VT-3 examination. The high percentage (75%) of the VT-1 visual examination of the subject weld areas and adjacent base metal was obtained. This examination coverage provides reasonable assurance of an acceptable level of quality and safety. The weld areas examined provide sufficient information to judge the overall integrity of the weld. Significant degradation, if present, would be detected during the VT-1 visual examination of the subject weld. As a result, assurance of structural integrity for these welds is provided by the examinations that were performed. Therefore pursuant to OCFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval. Implementation Schedule: This request for relief is applicable to the second 10-year ISI interval for SQN Unit 1 and Unit 2. Weld ERCWSH-05-IA for Unit 1 and ERCWSH-11-IA for Unit 2 were examined in the first period.

References:

Examination Data Reports: R7152 Unit 1 R5762 Unit 2 E2-10

Request for Relief 1-ISI-25 and 2-ISI-25 (continued) - ISI Program Drawing: ISI-0285-C-01 (Unit 1) ISI-0268-C-01 (Unit 2) - Examination Limitation Drawing Typical of Unit 1 and Unit 2 - Nondestructive Examination Procedure N-GP-28, "Calculation of ASME Code Coverage for Section XI NDE Examinations" E2-11

ENCLOSURE 3 EXAMINATION DATA REPORTS Request for Examination Data Relief Nos. Reports 1-ISI-23 R7785 1-ISI-24 R7811 R7819 2-ISI-24 R6432 R6436 1-ISI-25 R7152 2-ISI-25 R5762 E3-1

RECORD OF VT-1 EXAMINATION lJDATE AWING NC PROCEDURE N-VT-1. REV. 2 (O IREPORT NO. R 57 -2 DIRECT REMOTE Q COMPONENT IDENTIFICATION: SYSTEM: REMOTE VISUAL AID: PLANT I BFN 0 UNIT 1 CYCLE 0 SQN UNIT 2 0 INSERVICE WBN UNIT 3 0 PRESERVICE OBLN I EXAMINATION RESULTS fT B-M-21 B-N-2 ACC. REJ. ACC. REJ. ATTRIBUTE (~)ATTRIBUTE V CRACKS CRACKS ( EAR / WEAR CORROSION CORROSION A EROSION EROSIO PHYSICAL DAMAGE PHYSICAL DAMAGE EXPLANATION OF UNSATISFACTORY RESULTS: / /A REMARKS: EYA4/ito,477o0A L,1/17E-2)0JE 7?

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4-4!' (cP ZWA.1,J.SgA7A-i5 AAJb /6S /LOGSG 4"EAtH ) '/re-,j 2SA t -7/o <~~~K EXAMINED BY: LEVEL WED DY:C DATE B: ~~~~~~~~~~~~~~~~~~~ ANII REVIEWED B DATE / / TVA 7904F (NP 10/92) r 'T- -J; -, 57 1/ --;f-no e6q-A / 4 2,

.  TRA y\\7vrAL. 9 ?? /o I iv>RENCE DRA WINGS 37W206-7 CONTRACT NO. 76K36-d 1766/ 17771-I z AJb 3- ?.. 82006 (N2AI-4 99) ASME CC-J (EQUIVALENT) j?OA,o 5g&tJ JNLE7 7L,6I1 qO ,/ 24 W IA S, IA 'S, I " EACH4D BAS I EACHA CA-SC PLAIG 2 rft/Cl<) PLA7G 2 '7/HCI<) z51-cE D67A)L.4Al BOLTS (4) .STEEL - -TFFL- /11 11 11 Y 11 1 1 r CONCRETE;L-i r I~~ ~ ~~~~~~~~~~ I I 1-L- - J ERCWSH-I I - CORRESPONDS TO STRAINER A2A -A ERCWSH CORRESPONDS TO STRAINER. B2B-B 'II 2 lio. I I. NOTE: FOR CONFXGURA TION SEE ISI-0158-C SH./. f4 - L_. CORRECT NOM. OF IA 'SI & MOVE To CAAA 9EV. BY CHECKED SWUMITTED A PPROVED DA TE TENWVESEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNIT 2 ESSENTIAL RA W COOLING WA TER SYSTEM STRAINER SUPPORT DETAIL DRAWN, RP DATE. 10-/6-87 scALE, Nrs CAoA(/ISICIIP CHECKED:i *f?A I APPROVED, CLII ShTET / OI-I SWUITTED, CE IX&I-026 8-A K .4 BOLTS C 2 J -SPiCJ-;x~' 2 LXC _Lk -I DASII OUTINE O STRAIWR I _I RE I I IX,1 JS-i02 68-A 0-c SWMITTED CR

TENNESSEE VALLEY AUTHORITY RECORD OF 1 REPORT NUMBER MAGNETIC PARTICAL I E& PROJECT: SQN UNIT: 2 CYCLE: 11 EXAMINATION DATE: 04/25/2002 SYSTEM: PZR EXAM SURFACE: L1 ID I OD WELD/COMPONENT I.D.: RCW-23 PRESERVICE I CONFIG.:- VIWASK TO: ISRIE~ REFERENCE DWG NO: ISI-0396-C-01 PROCEDURE: N-MT-6 REV 24 TC N/A EXAMINATION CODE: 89E-02 ACCEPTANCE CRITERIA CODE CLASS 1 CATEGORY: B-K l OTHER NIHTHOD OF MAGNETIZATION EXAMINATION MEDIUM: Magnaflu,x COLOR: Red 8A BATCH NO.: N/A YOKE Y5 l Y6 i PRODS: AC l DC LI COILS: AC DC OTHER: N/A EQUIP TYPE: EQUIP TYPE: EQUIP S/N: 538069 EQUIP S/N: EQULIP SIN : CAL. DUE DATE N/A CAL. DUE D,vE CAL. DUEDTE POLE SPACING: 6 inches PROACING: inches COIL RNS: TEST WEIGHT SN: 901470 G. CURRENTamps G. CURRENT: amps THERMOMETER S/N: N/A CALIBRATION DUE DATE N/A BLACK LIGHT METER SN: N/A CALIBRATION DUE DATE N/A INTENSITYVERIFICATIONTIME lINIT.: N/A

1) N/A

2) N/A

3) N/A EXAMINATION RESULTS:

SATISFACTORY ] EXPLANATION OF EXAM RESULTS NT%T UNSATISFACTORY 3 NOI NO.: N/A COMMENTS I LIMITATIONS Nn imitntinnq werp P-nrinntprl I I Pre r Pmgt lhi,minzation rherk ok Ililmination enrr1 sin 012 KVD fltilkflio 4 D AD 6M6Xt-It-I W5e7l 1 X17 la .tAw4 b W I I I I I EXAMINER: Stephen Wi11iams LEVEL:II EXAMINER: Michae LEVEL: LI DATE: REVIEWER: AM -LEVEL: DATE: PAGE: V I ~~~~~~~1-OFLA I/ I t )
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K> TENNESSEE VALLEY EMATON SUARYl REPORT NUMBER: AUTHORITY RESOLUTION SHEET l R-o PROJECT: SQN UNIT: 2 CYCLE 11 COMPONENT ID: RCW-23 EXAMINATION METHOD SYSTEM: PZR ISI DWG NO: ISI-0396-C-01 MT Ol PT O UT i VT CONFIGURATION CATEGOR' PROCEDURE: N-UT-7 REV 13 TC: N/A VIWASK TO B-K EXAMINER: EXAMINER: EXAMINER: EX ER: Paul ypl4en Angela Tucker flavid t__ke____,_. LEVEL: H LEN VL: H LEVEL: 11 i-LEVEL: Total coverage calculated to be approximatelv 700 This report contains the data associated with weld RCW-23 a Pressurirer.support skirt attachment weld. xamination of this weld is in accordance with the A SM Section Y Code requirements. A 450 shear 1 1/4 V-path examination was performed in 2 directions perpendicular and 2 directions parallel to the weld. This examination is a supplemental examination erformed in lieu gf MT-for the rnl surface not accesvihle. A 60 shear wave examination was also Performed , --_ -r.77 -- A - ?-- . -7. t ussure Jun exaUinfnano voume coverage. Weld crown geomet!v was observed 360° at varvin ' amplitudes. No limitations were noted for this examination. MT K 1,12%ZTuDm~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ RES,%IIONBY REVIEWED BY ANII: DATE: LEVEL: DATE: 4zshZ. LEVEL. DATE: 4 4UV Page: -OF 6 ACCESS: FORMS DATABASE R-10/04/01

J TENNESSEE VALLEY AUTHORITY j ,.vR)rFzjr SON)t YTJ19T/C'- DIGITAL ULTRASONIC CALIBRATION DATA SHEET V'CT,p 7/77 A "-VJ - -1 1 -A -A A IPROCEDURE: N-UT-7 REV: 13 TC: N/A I. TRANSDUCER, MANUFACTURER KBA MODEL: SWS SIN J15205 SIZE: 0.5xl.0" FREQ: 2.25 MHz SHAPERectandl # ELEMENTS: I

1. CONS: 0 CABLE TYPE RG-58 LENGTH- '

MODE: SHEAR O L01G LI RL 100 80 60 40 20 DAC 0 DISPLAY WIDTH REF. REFLECTOR N A AMPl.lTUDE 45A / n e A M p L I T U ..D E, 7.00 inches VSH/FSH GAIN: 34.0 dB MP-TAT. PATR-45"/1.05" REPORT NUMBER R-We CALIBRATION DATE: 4/25/02 CALIBRATION BLOCK NO.SQ-40 TEMP; 79 F SIMULATOR BLOCK:RomPas THERMOMETER SIN 573207 DUE DATE 10/1/02 COUPLANT: l7trazel II BATCH: 95-325 ANGLE VERIFICATION BLOCK TYPE: IIW SIN: 790609 NOMINAL ANGLE 45' ACTUAL ANGLE 45 INSTRUMENT MANUFACTURER Krautkramer DUE DATE 6/8/02 MODEL NO.: USN-52L SIN: 30216 INSTRUMENT SETINGS EFCI OR REFERENCE MENMORY SCAN DIRECT. NTC SDH SENSITIVITY NUMBER AXIAL n 1 34.0 dB 48 CIRC. NIA B NIA FREQ: 2.0 8. MHz REJECT: 0 %

• ANGLE 45 deg DAMPING:1000 ohms
• DELAY 0.000 msec PULSER: SINGLE ZERO:

12.918 msec VELOCITY .1277 msec PRR/PRF: HIGH RANGE: 7.00 inches TOF: PEAK DISP.MODE: FULLWAVE* POWER: BATTERY CALIBRATION TIMES INIlIAL TIMIE: 1312 FINAL TIME 1536 VERIFICATIONTIMES l1) 135012) N/A13) N/A 4) N/Al5) N/A6) N/A17) N/A 8) N/A) N/A

• PDI QUALIFEED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIMICATION IMPLEMENTATION PROCEDURE! LINEARITY CHECK VERTICAL SIGNAL 1 100 50 4016 30 20 SIGNAL2 50 45 401 35 301 25 20 15 10 GAIN SET -6 dB -12dB SET +12 SET +6 ATTENUATOR AMP 80% 32TO48 16 TO 24 20% 64 TO 96 40% 64 TO 96 40 20 80 80 CW-23 'I IIH dXAMINER: Tucker LVL.- Il/I IREVIEWER: /AA W& LVL.: DATE: A 0O 0 ACCESS: FORMS DATABASE 1027-01 ANT: 02c / DATE: 5 1M/.P PAGE I OF I I v I

2~~~~~~~ ) TENNESSEE VALLEY A T Tm I1V Tm5 T l DIGITAL ULTRASONIC I CALIBRATION SHEET I p f IIlUKIIY I DATA ROJECT SON UNIT/CYCLE 2/11 ROCEDURE: N-UT-7 REV: 13 TC: N/A TRANSDUCER MANUFACTURER EBA MODEL: SWS S/N J15204 SIZE: 0.5xl.0" FREQ: 2.25 MHz SHAPE:Rectanzl # ELEMENTS: I

1. CONS:

0 CABLE TYPE RG-58 LENGTH, 6' MODE: I SHEAR O LONG RL DAC 100 80 60 40 20 0 DISPLAY WIDTH A M p L I T U D E: '10.00 inches REPORT NUMBER Thto-fo l CALIBRATION DA.LE: 4/25/02 CALIBRATION BLOCK NO;S0-40 TEMP: 79°F SIMULATOR BLOCK-Rompas THERMOMETER SIN 573207 DUE DATE 10/1/02 COUPLANT: Ultrazel II BATCH: 95-325 ANGLE VERIFICATION BLOCK TYPE: W S/N: 790609 NOMiNAL ANGLE 60° ACTUAL ANGLE 60 INSTRUMENT MANUFACTURER Krautkramer DUE DATE 6/8/02 MODEL NO.: USN-52L S/N: E30216 INSTRUMENT SETFINGS REFLECIOR RE MEMORY SCAN DIECT. NTC SDH SENSITIVITY NUMBER AXIAL [ [1 40.0 dB 49 CIRC l l N/A dB N/A FREQ:

2.

MH8.0MHz REJECT: 0 %

• ANGLE:

60 deg DAMPING:1000 ohms

• DELAY 0.000 msec PULSER: SINGLE ZERO:

15.590 nisec VELOCITY .1222 msec PRR/PRF: HIGH RANGE: 10.00 inches TOF: PEAK DISP. MODE: FULL WAVE* POWER: BATTERY REF. REFLECTOR-NSH/FSH GAIN: 40.0 dB CALIBRATION TIMES AMPLITUDE: 35150 % METAL PAul:.65"!.45" INTIAL TIME: 1313 FINAL TIME 1535 VERIFICATION TIMES l1) 145512) N/Al3) N/A 4)N/A5) N/A 6) N/A 7) N/A 8) N/A ) - - N/A

• PDI QUALIFIED INSTRUMENT SE1TINGS:

VERIFY INSTRUMENT SETINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION RIPLEMENTATION PROCEDURE! LINEARITY CHECK VERTICAL SIGNAL 1 100 90 80 70 60 50 40 30 20 SIGNAL 2 50 45 40 35 30 25 20 15 10 GAIN SET -6 dB -12dB SET +12 SET +6 ATTENUATOR AMP 80% 32 TO 48 16 TO 24 20% 64 TO 96 40% 64T096 40 20 80 80 I_RCW-23 ' IXAMINER: P alden II OXAMINER: An e Tucker/David Tucker LVL._/Il IREVIEWER: Amft ud% p LVL.:# DATE: 4 ?2°o-OX ACCESS: FORMS DATABASE 10-27-01 q ANII: DATE: /6c9 PAGE 3 OF 6 I I =3 I_ = A" 4 S M_ =~~~- __vk _-~~N I _p

I 4 I TENNESSEE VALLEY VINUk. U. AUTHORITY PIPING E DATA ROJECT: SQN UNIT/CYCLE 2 111 SYSTEM PZR WELD I.D.: RCW-23 CONFIG.: VWASK TO FLOW PROCEDURE: N-UT-7 REV: 13 TC: N/A Wo

REFERENCE:

CL of Transition (See Attached DWR.) Lo

REFERENCE:

ZA77nith Pad 0.tamn U A r A TTT A T TT LTRASONIC AMINATION SHEET Y EXAMINATION DATE 4125 START TIME 35 EXAM SURFACE ID MATERIAL TYPE: R CS SURFACE TEMP. 80 REPORT NUMBER END TZE: 151 iOD EISS ECSCL CCSS _PYRO NO. 573207 EXAMINATION ANGLE 45 DEG. 60 DEG. AXIAL SCAN SENSITVITY 50.0 dB 64.0 dB CIRC SCAN SENSITrr I sn n Id c _,.."^,, vvs, IND L (in) FROM REF. AT MAXJAM P MAX EXAMI IND )____ -ROM R A r MAX AU P AMP NO. NOM. NRI INDICATION INFORMATION: NO. LI L Max L2 WMAX MPMAX :)MAX %DAC 3-14 ANG. YPE,DAMPING,Erc. N/A 3 45°s 1 204' 1.8' 2.4 1.7' 90 4 45's C 'See Note Below N/A 5 45's E N/A 6 45s E N/A 3 60Is 2 204'_ 2.7' 4.0' 20' 90 4 60's [ 'See Note Below AT/A d I REMARKS/LIMITATIONS

• Indications noted above can be observed 360° at varvineg amplitudes. Maintained a 5% to 20% ID roll throughout examination.

IEXAMINER: 1,2ul/Valden --- LF,3. EL: [ ( tNMTER: Au' e ,vv. EVEL: II VIEWED BY: '1A) LEVEL:L DATE: t ?.ov I ACCESS: FORMS DATABASE 118/01 DATE: 5/ / PAGE OF f; -I s I A -H,.~, I /w, 4 -1.II

V Y - TVA Ofrice of Nuclear Power PROJECT:. Unit: 11ll SYSTEM: PZPZ WELD NO.: 7--W-2z I. I i I-A.4 1 T' 0 ut d1 % I,, i -P I I I I I I I. I i w i:: i&t 0 IItoo Il tii _ 1 . 9 REPORT NO.: I i i j, i il, !, j

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I iI BY:_ ____ LEVEL: DATE 4q,0z PAGE 5 OF 5 TVA 19669 (ONP-6-88) j w / 7 NWAOP'- i 4:

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i I.'"'

TENNSEE VALLEY AUTHORI!-~ AM DATE: lRECORD OF VISUAL EXAMINATION AM DATE:-25_ PROCEDURE: N-VT-, REVL2 TC: q 7-Z 5 REPORT rLANT: 6C2IVP UNIT: / CYCLE: INSERVICE s PRESERVICE El COItPONENT ID: E2CWS,/ -C5- /F MODFED PORTION ONLY: YES El NO 0 DRAWINGNO: /./- Oz8 5.- / SYSTEM: eC WS CODE CATEGORY: D - COMaONENT TYPE: SuPPORT El BOLTING El PUIVALVE El INTEGRAL ATTACH (IA) X TYPE OF VISUAL EXAM: VT-11 VT-3 El DECT REMOTE El VISUAL AID(S):fARSLl,I4tcie ATRIBUTE ACCEPT REJECT NJA SUPPORT TYPE: DEFORMED OR SHEARED El RIGID SUPPORT E CONSTANT FORC BOLTS/STUDSfrHRFEDS (Vr-1) El E1 El VARIABLE SPRNG E SNUBBER CORROSION (VT-1) O O DUAL SPRING/ SNUBBER LOOSE BOLTING (VT-I) Y E YES NO THREAD ENGAGEMENT (VT-I) El l is 29fg. / COOLANT LEAKAGE (VT-I) [l Type: CRACKS/FRACTURES (Vr-L3) E O E Model: STRUCTURAL DISTORTION/ Size: DEGRADATION (VT-1,3) 1 El I Range: (1) J/ PHYS. DAMAGE Setting: (1) A DISPLACEMENT (VT-i,3) El O Range: (2) LOOSE/MSSING PARTS (VT-I;) j El O SettinE. (2) A3RI/CORROSION OF x ;CHINED SURFACES (vr-3) n Temp: Pvro. No.: /1 WEARJEROSION/CORROSION El I ER (Vr-3) ._/ FUNC1IONAL ADEQUACY (-3) El E BOLTING: FREEDOM OF MOTION (VT-3) El El _LACE: El REMOVED:E] VERIICATION OF SETTING(VT-3) E El 1 _/ DISASSEMBLED: El LOSS OF TIIEGRITY (VT-3) El El /_ CLEARANCE VERIFICATION (Vr-3) EJ El 71 REMARKS! / ASc ,4 /-v4 e-Exs-LF jgl Ar xcsX LA1h11 I Ur;,4'- 95sS eZjb f.s44Qsz NOI NUMBER WORK DOCUMENT: EAMINER EXAMINER: ).%IvrEwER.: ANUIREVIEW: 40,3/4' C1, T OAL LEVEL: LEVEIi' O LEVEL: r DATE: _ a DATE: _P-2-f _) DATE:________ i DATE: 9 2498 L.' TVAISO REV1 04/01/1998

• RmE7s TJ t

wTmoovEr7XSov -~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ -.::s F'1X N`11 ...:-g t1 11' -b_ X f I 'll-

I REFERENCE DRAVINGS cOtIftACr No. 76XJ6-82006l fN2M-499) 777t t-I, -2 ANO -3 24t INLEr AND 24 OUTLEr eo6 APARr gOt rs (8) STEEL ERCwSlI-05-IA IA'S, t' EAC ANO ASt PLArt 2 THlClK) ERcFSN-IO-IA (7 IA'S t' EAf ANO ASE PLATE 2' THICJ) NOTES: I. Fr CWfict,iRAmlo SEE ISI-023-C-Ot & -02

2.

HIS OVI StlPERCEDES SI-0285-A-01. ( FOL rs (5) BtOLTS (4 /Pi4L .j ,i ERcrSt-0 STEEL j jII ERC SH-t0 I, .i ISI I CONCRETE I_ I---- ERCrsH COY?RESPcWOS TO STRAINER AIA-A ERCIStl CDRESPOHOS TO StRAINER B 18-B -Z V /

1g7,

-r ( REV[ or IW*CXfI SUeItttEO I ArreOVto DArt YEAISSEr Atrr AU7rIWIr SEOUOYAH NUCLEAR PLANr UNIT I ESSENrIAL RAW COOLING wArEr SYsTEtM STRAINER S,FPOfr DETAIL SCAZE, Not to SCAt ~ Ntg M O [.9^ M4AitIO CRAA I. c; 1/2 aD" DETAIL A N.- P\\rl ASUE CC-J (COUt/VALENr) 15W.1 1 1 9 0, ) kl.:";
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TENNESSEE VALLEY lEXAMINATION

SUMMARY

REPORT NMBER: AUTHORITYRESOLUTION SHEET %55 PROJECT: SQN UNIT: 1 CYCLE 11 COMPONENT ID: RHRF-107 EXAMINATION METHOD SYSTEM: RHRS ISI DWG NO: CHAM-2336-C-06 MT PT UT j VT CONFIGURATION CATEGOR' PROCEDURE:N-UT-64 REV 4 TC:ee-/ PC,PIPE TO PE,EL R-A EXAMNER: rA MFS M. RTI.T.FN LE'VEL: II EXAMINER: TOMMY F. A crKsqo LEVEL: II EXAMINER: .1I LEVEL: EXAMDNER: I LEVEL: Total coverage calculated to be approimatelv 639 THIzS RFPORT CONTAIN TTE DATA ASOCTATFtYRITTH Rr-IRF-707 A PP TO F1310W CONFGURA TION IN A CCORDA NYC WTHU R7C KINFORMED REQUIRFMFNTS., A 45 DEGREE SHEAR WAVE. FULL V-PATH EXAMINATION WAS PERFORMED FROM 2 DIRECTIONS PERPENDICULAR AND 2 DIRECTIONS PARALLEL TO THE WELD. THEPRE Wk'RE NO RECORDAR TF INDICA TIONS. THE EXAMINA TION WAS LIMITED DUE TO PROXIMITY OF LUGS WELDED ON THE WHIP RESTRAINT. ~Cow..-ds~. JD= g co.-e +ie, gs5oc544d

72. ?o 1

7 o d/ s{kD RES LUON V R EDBY ANn-I D E S t ri g /; -- MEM.B 1JLEVEL:4DATE:W I_ A II A_ _P._'AI LEVEL II DATE: 10-26-01 LEVEL:TCd DATE:IQ 9t Page: L OF ACCESS: FORMS DATABASE R-10104/01 ( I r5,)

TENNESSEE VA AUTHORI1 DIGITAL ULTRASONIC CALIBRATION PROJECT SQN UNIT/CYCLE 1111 oa-/6' PROCEDURE: N-UT REV: 4 TC: _ TRANSDUCER MANUFACTURER KBA MODEL: COMP-G SIN O0D8KK SIZE: .375" FREQ: 1.S -MHz SHAPE:Round

1. ELEMENTS: I
2. CONS: 0 CABLE TYPE RG-174 LENGTH, 7 "

MODE: SHEAR l LONG l RL DAC DISPLAY WIDTH REF. REFLECTOR: AMPLITUDE: N/A % A r 57 L II T D D

• E 3.0 inches N/A GAIN:

N/A dB METAL PAT H:N/A I CALIBRATION DATE: 10-26-01 CALIBRATION BLOCK NO. SO-7 TEMP: 73.4°F SIMULATORBLOCKN/A T.HERMOMETER S/N E27489 DUE DATE 6-15-02 COUPLANT: Ultrarel H BATCH: 95325 ANGLE IERIFICATION BLOCK TYPE: Rompas SIN: 93-5719 NOMINAL ANGLE 45° ACTUAL ANGLE 45 INSTRUMENT MANUFACTURER Krautkzramer DUE DATE 6-15-02 MODEL NO.: USN-52L SIN: E30219 INSTRUMENT SETTINGS REFLECTOR REFERENCE MEMORY SCAN DIRECT. NTC SDH SENSITIVITY NUMBER AXIAL 0I O 25 dB 8 CIRC. 0 O 33 dB 8 FREQ: 2 MHz REJECT: O % ANGLE-45 deg DAMPING:1000 ohms DELAY 0.000 rnsec PULSER: SNGLE ZERO: 6.164 msec VELOCITY .1249 nsec PRR/PRF: HIGH RANGE: 3.000 inches TOF: PEAK DISP. MODE: FULL WAVE POWER: BA7TERY CALIBRATION TIMES INrTIAL TIME: 1244 FINAL TIME 1727 VERIFICATIONTWIES l1) N/A12) N/A13) NA 14) N/AIS) NA16) N/AA7) N/

8)

N/A 9) N/A

• PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF TLE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE! LINEARITY CHECK VERTICAL SIGNAL I 100 90 80 70 60 50 40 30 20 SIGNAL 2 50 45 40 35 30 25 20 1 10 GAIN SET -6 dB -12dB SET +12 SET +6 ATTENUATOR AMP 80% 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 r 8.2 v U 40 20 80 980 rd) {N RE~~~~RF-107 ...........-~ ~ ~ ~~~~. t... .EXAMINER: YAMESM i ft4EMINE R: TOM SE.JACKSON RE ER: 1\\1 LVL.: II LVL.: L L DATE: ID QM0 ACCESS: FORMS DATABASE 10-18-01 ANI: A I 7 DATE: i [/o( PA GE I2-F I I I ,,^

TENNESSEE VALLEY &A MANUAL ULTRASONIC RPORT NUMBER AUTHORITY PIPING EXATXINATION j W1e5 l ~~DATA HEET ,AOJECT: SQN 'YSTEM RHRS 'ELD I.D.: RHRF-107 CONFIG.: PC,PIPE UNIT/CYCLE I /11 TO PE,EL FLOW PROCEDURE: N-U-64 REV: 4 Wo

REFERENCE:

WELD CENTER LlNE T-l.n R F.FF VrF.(. Dt i Tnil nfF. TC: ad-Z/ EXAMINATION DATF, 10-26-01 START TIME,- 1610 END IME17Z5 EXAM SURFACE MID 0OD MATERIAL TYPE: []CS ISS [DCSCL O3CCSS SURFACE TEMP. 780 PYRO NO. E27489 EXAMINATION ANGLE l 45 DEG. N/A DEG. AXIAL SCAN SENSITIVITY 37 d N/A dB rTrt crAlUgovaNcyTT--r-7 I nn al xrIA R AJ flt A t.4 tfuljl-J tlill ql £,lJ _t.JAnt. ota1J¶ I A VAA. I IND L(in) FROM REF. AT MAX AMP MAX EXAM NOM. NRI INDICATION INFORMATION: NO. Li ~AMP NO. AG YE APN,EC NO.1 L Max L2 W MAX MP IAX MAX % DAC 3-14 ANG. TYPE, DAMPING, ETC. 3 45 4 45 5 45 0 .~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 6' REMARKS/LIMITATIONS NO EXAM AT 90 DEG. AND 270 DEG. DUE TO PROXMITY OF 5"X5" LUGS WELDED ON IMPRESRAINT. VATAATDF) 5 T)n TT PfOT7. WTE PFRFf)PMTNG FYAM7NAT70VN lEXAMIl'4ER:AMES~ e ) XAM`NER: TOM E ACKSON REVIEWED BY: 'W?* Lk& LEVEL: rL LEVEL: II LEVEL: 1L DATE: lOV) D ACCESS: FORMS DATABASE 101101 ANTI: A NM DATE: II /0( PAGE 3 OF

QJ WALL THICKNESS~~~~~~1~ REPORT NO: TVA WAL HCKESO PROFILE SHEET PROJECT: N WELDONO: H IC 1 UNIT: A-SYSTEM: P R Record Thickness Measurements As Weld

• Weld Edge Indicated, Including Weld Width, Centerline Edge-To-Edge At 0 2525' Position O.

90' 10' 270.F5 Flow_ CROWN, HEIGHT: FL L, 6 H DIAMETER:__ CROWN WIDTH:

• l WELD LENGTH:

22 7 7 C6vCRA&,E 9 F Lo J 7:7-- ~ ~ .. ~£L,~ TtF-77. ZI.171 EXAMAINER REVIEWED B:II LEEVE L _DA__ _T )Ofl D DATEt: j'r~ DATE: I E E :..... AE PAGE OF. AVOP'l-16 e- %-' "I

-' 'IF I 0) 1.109-999-44 TVA MU NT-5-89)

TVA Office of Nuclear Power 0 PROJECT: .1 Unit: I I - _ SYSTEIVI: u\\,: WELD NO.: cREk 0i~1 I o i - -1 / REPORT NO.: R ?155' I i ! .I'; II Rf 101 9 ir 0,300" 5150gfD .50 " 11-V x 110 L VIN = kb~ I 17. O 03 i., 105 -19 PtJfkloD lO-19-01 (I TVA 19669 (ONP-6-88) s~~~~~~~~~~~ 1

l

-i 7 J Z-4 i Z I I I r> -7,z/z7ZrT=;~ J BY: t___/ LEVEL:__ DATE: ID. f9 D I PAGE 5 OF 5 I I 0 C--=0~~~~

!i I

I !i I ' i I I i t II 1. ;. I , !- II . 'i. 1-. t ..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ // ~~~~ =S~~

TENNESSEE VALLY RECORD OF REPORT NUNBER AUTHORITY MAGNETIC PARTICAL 11 PROJECT: SN UNIT: I CYCLE 11 EXAMINATION DATE: 11/02/2001 SYSTEM: PZR EXAM SURFACE: [ ID 2 OD WELD/COMPONENT I.D. RCW-23A PRESERVICE O INSERVICE PI CONFIG.: VI WIASK TO:_ VISUAL CARD S/N: 085 PROCEDURE: N-MT-6 RE_24 TC_n/a REFERENCEDWG NO: ISI-0394C-01 EXAMINATION CODE: 89E-02 ACCEPTANCE CRITERIA CODE CLASS:OI CATEGORY---~ E APPDX. A 0 APPDX. B CODE CLASS: I CATEGORY B-K C1 OTHER n/a METHOD OF MAGNETIZATION EXAMINATION MEDM: Dry Powder COLOR: Gray BATCH NO.: 94H077 YOKE Y5 E Y6 R PRODS: AC El DC COILS: AC El DC E OTHER: n/a EQUIP TYPE: n/a EQUIP TYPE: n/a EQUIP SIN: US-TVA538069 EQUIP S/N: n/a EQUIP S/N: n/a CAL. DUE DATE n/a CAL. DUE DATE n/a CAL. DUE DATE n/a POLE SPACING: 6 inches PROD SPACING: n/a inches COIL TURNS n/a TEST WEIGHT S/N USTVA901470 MAG. CURRENT: n/a amps MAG. CURRENT n/aamps THERMOMETER SIN na CALIBRATION DUE DATE nla BLACK LIGHT OR LIGHT METER SIN: nla CALIBRATION DUE DATE na. NESIYVERFICATION TEnE INIT.:<0,,),,SV

2) nia{3)na EXAMINATION RESU1LTS:- SATISFACTORY EZ UNSATISFACTORY O NOINO.:r/

EXPLANATION OF EXAM RESULTS No Recordable Indications / LIMITATIONS 4M P2041 I

s.

s I, :M gl -A .7D Zg -6al art.g,L4 Jffl //- ( r 9lq luQ SP6tz ILLUMINATION CHECK ADEQUATE: Rl MT POWDER CHECK ADEQUATE: EXAMINER: Jason Polisensk3j/rnAJ LEVEL: H EXAMINER: MichealGagniern7> LEVEL: DATE REVMEWER: 1J/j LEVEL: A DATE: 1lZO1 PAGE: ACCESS: FORMS DATABASE 10-22-01 W Q)

J) TENNESSEE VALLEY EXAMRETION SUMMNARY EPORT NUMBER: AUTHORITYRESOLUTION SHEET 1 PROJECT: SQN UNIT: I CYCLE 1 COMPONENT ID: RCW-23A EXAMINATION METHOD SYSTEM: PZR ISI DWG NO: ISI-0394-C-01 MT E l PT UT b3 CONFIGURATION CATEGORY PROCEDURE: N-UT-7 REV 13 TC: N/A VI WA SK TO B-K EXAMINER: CarelaSo~zvar LEVrEL: II EXAMINER: tnenn Pnlivpnsli LEVEL: II EXAMINER: LEVEL: EXAMINER: LEVEL: This report contains the data associated with weld RCV-23A a Presuri7er support skirt attachment weld. Examination of this weld is in accordance with the ASME Section XI7 Code requirements. A 45 degree shear wave 1 14 V-path examination was performed in 2 directions erpendicular and in 2 directions parallel to the weld. This examination is a supplemental examination performed in lieu gf MT-for the surface not accesvqhle. A 60 deree shear wave eramination was also erformed to assure fll examination volume coverate. Weld crown eometrv was observed 360 deerees around. at aring amplitudes with both the 45 and the 60 degree examinationi No limitations were nofed for this examination. -~~~~~~~~~ I_ I - - r u D A TE: D / LEVEL \\T DAE: (I-3-> W tEj f t Pe 2 OFLS RESOLUTION BY,. REVIIE'ED BY ANII: .LEVEL :r DATE: X l-3-af LEVEL:2 DATE: ll St Page: lOF ACCESS: FORMS DATABASE R-1W04/01 QK) Total eoverane calculated to he annroximatelv 100, ,0

TENNESSEE VALLEY DIGITAL ULTRASONIC AUTHORITY l CALIBRATION ~ I DATA SHEET PROJECT SQN UNIT/CYCLE 1/11 PROCEDURE: N-UT-7 REV: 13 TC: N/A TRANSDUCER MANUFACTURER KBA MODEL: MSIIS SIN J15205 SIZE: 0.5xl.0" FREQ: 2.25 MHz SHAPE:Rectanzl # ELEMENTS: I

1. CONS: 0 CABLE TYPE RG-174 LENGTH 10" MODE:

SHEAR El LONG RL DAC 100 80 60 40 20 0 1 III I I I 1 1 - I-I L 1 =-== I-I I I DISPLAY WIDTH REF. REFLECTOR:_ A lrPT TTTW F-4- A M p L I T U D ~-E 7.0 inches GAIN: dB r MFTAT PATTT-L REPORT NUMBER CALIBRATION DATF, 7L42/1Z1071 t-W CALIBRATION BLOCK OS -40 TEMP: 73 °F SIMULATOR BLOCK N/A THERMOMETER SIN E27489 DUE DATE 615/02 COUPLANT: Ultrael 1I BATCH: 95325 ANGLE VERIFICATION BLOCK TYPE: 11W S/N: 7 9 7 g NOMINAL ANGLE 450 ACTUAL ANGLE 44 INSTRUMENT MANUFACTURER Krautkramer DUE DATE 6/14/02 MODEL NO.: USN-52L SIN: E30217 INSTRUMENT SETTINGS REFLECTOR REFERENCE MEMORY SCAN DIREC. NTC. SDH SENSITIVITY NUMBER AXIAL E 32.8 dB 10 CIRC. l l NI/A dB N/A FREQ: 2.1.8.MHz REJECT: 0 % ANGLE-44 deg DAMPING:1000 ohms DELAY 0 isec PULSER: SINGLE ZERO: 11.534 msec VELOCITY .1261 msec PRRIPRF: HIGH RANGE: 7.0 inches TOF: PEAK DISP. MODE: FULL WAVE POWER: BATTERY CALIBRATION TIMES INITlAL TIME: 08:20 FINAL TIME 15:35 VRIFICATION TIES 1

2)

).

6) 7 8

I YERIFICATION TIMES I 1) l 2) 1 3)

14) l 5) 1 6) 1 7)

18) l9)

• PDI QUALIFIED INSTRUMENT SETTINGS:

VERIIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WArITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE! LINEARITY CHECK VERTICAL SIGNAL 1 100 90 80 70 60 1 50 40 2 30 20 SIGNAL2 5i0 45 0 5 301 25 201 1 10 GAIN SET -6 dB -12dB SET +12 SET +6 ATTENUATOR AMP 80% 32 TO 48 16 TO 24 20% 64 TO 96 40% 4644T996 40 20 80 80 _8 Supplemental Examination. RCW.23A .1~ ~ ~~~~~~,I ,, - t:XAMINER: Carey LSoya e z a~) XAM M R: Jason PolisenskJ REVEWER: LVL.: II LDL.:_ _11 LVI,.-li1 DATE: 'DI ACCESS: FORMS DATABASE 10-27-01 ANH: DATE: (/h / / 4 PAGE

f.

OF 3 I r

TENNESSEE VALLEY-j' DIGITAL ULTRASONIC jD REPORT NUMIBER AUTHORITY CALIBRATION DATA SHEET PROJECT SQN UNIT/CYCLE 111 PROCEDURE: N-UT-7 REV: 13 TC: N/A TRANSDUCER MANUFACTURER KBA MODEL: MSWS S/N J15204' SIZE: O.5x1.0" FREQ: 2.25 MHz SHAPE:Roand-

1. ELEMENTS: I
2. CONS: 0 CAL T

R2-0 G-CABLE TYPE RG-174 LENGTH, 7'0" MODE: E3 SHEAR El LONG El RL DAC 1tA I I I k 1 t ILkr I u Is r I 1 1 1~~~ 1 kH I I I I T T l I DISPLAY WIDTH 10.0 inches A M P L I T D E 4 REF. REFLECTOR:- AMPLITUDE: iler % I /4 GAIN: pJil dB METAL PATH: I I CALIBRATION DAThLIIL1L:0 CALIBRATION BLOCK NO.S0-40 TEMP: 73 F SIMULATOR BLOCKN/A THERMOMETER SIN E27489 DUE DATE 615/02 COUPLANT: Ultra zel II BATCH: 95325 ANGLE VERIFICATION BLOCKTYPE: IW SIN: 7 7 71f NOMIN'AL ANGLE 60° ACTUAL ANGLE 59e INSTRUMENT MANUFACTURER Krautk-ramer DUE DATE 6/14/02 MODEL NO.: USN-52L SIN: E:30217 INSTRUMEN'T SETTINGS N REFLECTOR REFERENCE MEMORY SCAN DIRECT. NTC SDH SENSITIITY NUMBER AXIA4,L [E 40dB 11 CIRC. l E N/A dB N/A FREQ: 2.0 8,OMHz REJECT: 0 % ANGLE-5Q deg DAMPING:OOO ohms DELAY 0 msec PULSER: SINGLE ZERO: 15.319 msec VELOCITY .1266isec PRRIPRF: HIGH RANGE: 10.0 inches TOF: PEAK DISP. MODE: FULL WAVE POWER: BATTERY CALIBRATION TIMES INrIAL TIME: 08:15 FINAL TIME 15.30 VERIFICATION TIMES

1)

12) A

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8) 9)

• PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE! LINEARITY CHECK VERTICAL SIGNAL 1 100 90 80 70 60 50 40 30 20 SIGNAL2 0 50 25 20 15 10 GAIN SET -6 dB -12dB SET +12 SET +6 ATTENUATOR AMP 80% 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 40 20 80 80 C0N-ME f ITS E Supplementl Examination RCW.-23A r __________________________________________________________________~ XAMINER: Carey LaSova g A -$ 4 Jason Polisensk IN LVL.: n LVL.: II LVL. 4' DATE: A °-AP I. ACCESS: FORMS DATABASE 1O-27.0O ANH: DATE: //i// ( PAGE A OF+/- 100 80 60 40 20 0 I

TENNESSEE VALLEY M NIANUAL ULTRASONIC AUTHORITY PIPING EXAMINATION l DATA SHEET '. ROJECT: SQN UNIT/CYCLE 1/1

-SYSTEM PR WN'ELD I.D.: RCW-23A CONFIG.:

VIWASK TO _ FLOW PROCEDURE: N-UT-7 REV: 13 TC: N/A Wiro

REFERENCE:

CIL of Transition (see attached dr. Lo

REFERENCE:

ZAzmith Pad 0 stamp IND L(in)FROM REF. NO. Li L Max L2 AT MAX AMP W MAX MP AX k MAX EXAMINATION DATEI. START TIMF: 09:05 END TIM: I0:30 EXAM SURFACE []ID ROD MATERIAL TYPE: CS ESS ECSCL []CCSS SURFACE TEMP. 78 PYRO NO. E27489 EXAMINATION ANGLE 45 DEG. 60 DEG. AXIAL SCAN SENSITIVITY 44.8 dB 52 dB CIRC. SCAN SENSITIVIY I p 1 p MAX I AMP % DAC EXAM NO. 3-14 NOM. ANG. NRI 44.8 dBI N/A dB INDICATION INFORMATION: TYPE, DAMPING, ETC. 1 45 2 45 D weld crown geometry 3 45 4 45 w 2 60 [ weld crown geometry ) REMARKSILIM1TATIONS

• Indications noted above can be observed 360 degrees around at varving amplitudes. Scanning Derformed with an ID roll maintained at 5 to 20 % FSH.

EXAMINER: Carev LaSova X4 oa LEVEL: LL. XAMINER: Jason PolisenskV LEVEL: II W [REVIEED BY: nAN LEVEL: DATE:ILQ k LD ACCESS: FORMS DATABASE t0/18./0t 1 y _ / /7 ANU: zf ( DATE: i/,i/o ( PAGE A OF 1 a l T I

TENNESSEE VALLEY AUTHORtTY BEAM SPREAD AND RESOLUTION DATA SHEET REPORT NO. R-lb[9 , PROJECT: UNIT: I SEARCH UNIT MANUFACTURER _ SIZE: . 5 /. S/N: z 1 5 MEASURED ANGLE: BEAM SPREAD: FREQ.:

2. 25 MhZ 2 oS NOM. ANGLE Y5 ij DEG.

9' 6 '514-{ ffA DEG. BEAM SPREAD DATE: It/ / o/ PROCEDURE: N-UT-7 REV. 1 3 TC N2/A CAU8 RATION SHEET NO. C-. I A UT INSTRUMENT MANUFACTURER: MODEL NUMBER: SERIAL NUMBER K / t ,RSn he USAl L TRAILING RAY (WI) W MAX LEADING RAY (W2) HOLE POSrLoN 20% DAC 50% DAC 100% DAC 5D% DAC 20% DAC W MP W MP W MP W MP W MP 1/4-t 65

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3.' 2.s-3.5 ~~LEADING RAY NV2 / A-JI >< TR~~~IFAILING RAY fW18 R.G. 1.150 RESOLUTION VERFICATION-- NEAR SURFACE REFLECTOR: 1 /9r SibE bF %LL HEF DEPTH: 31 IN. SIZE: 3//f FARSURFACEREFLECTOR: /Y.r 5 biILL HoLE DEPTH: /IN. SIZE: 3/,C' SCANNING (REFLECTORS PROVIDE 50% DAC SIGNALS AT SCANNING SPEED: lgES O NO REMARKS: EXAMINER: TAsoA) P L VAE5Sx_ MINER: CAREY t Soy ye EED BY: 17 II LEVEL: .LL7 LEVEU LEVEL: f DATE: I j, k l I L TVA 1 9670A (NP 7/92) DATE: /,/i ( PAGE-iOF l 5 0 ti

TENNESSEE VALLEY AUTHORITY BEAM SPREAD AND RESOLUTION DATA SHEET REPORT NO. R-1g 9 ! PROJECT: MANUFACTURER A SIZE: ' /. 0 S/N: 5 oq MEASURED ANGLE: BEAM SPREAD: (%, 6 - UNIT: I FREO.: 2. Z 5 MhZ NOM. ANGLE 6 0 5-r DEG.

4{, U9 DEG.

BEAM SPREAD DATE: I PROCEDURE: N-UT-7 CAUBRATION SHEET NO. C-I / / o REV. 3 TC W4/A g1h UT INSTRUMENT MANUFACTURER: MODEL NUMBER SERIAL NUMBER: KPZA UtK(g,A1E& vS' 2L 2& 1,61 TRAIUNG RAY (WI) W MAX LEADING RAY (W2) HOLE POSITION 20% DAC 50% DAC 100% DAC 0% DAC 20% DAC W MP W MP W MP W MP W MP

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3-75 LI3 3os Y3 S3 C/ E,7 LEADING RAY W2) l / TRAILING RAY rWli R.G. 1.150 RESOLUTION VERFICATION-- NEAR SURFACE REFLECTOR: I/yr Y,F b L LF7 DEPTH: 3/4 IN. SIZE 3//4 FAR SURFACE REFLECTOR: 3/Y St bR,LL 14oLf DEPTH: IN. SIZE: 3// SCANNING (REFLECTORS PROVIDE 50% DAC SIGNALS AT SCANNING SPEED [ES O NO REMARKS: I EXAMINER: TA5OA1FvltstSE5kvge § LXAMINER: c-4eEy ZqSege, i ^ tREVIEWED BY: / A 'I LEVEL: LEVEU tC LEVEL: 5 DATE: rI-4'-( TVA 1 9670A (NP 72) a ANII / I DATE: f/)( PAGE _@ OF 5cQAl SEARCH UNtr B A I 7 "t,,

INDIcATiON PLor 5EEi wELb ACw-13A TPA,JS Ir1q 6 95 60r,r .~~~~~~~~ c BY: T/5 4 ^LtS4Pt ,, 3 fmc< q 8 I 1 eMP--19 toi.'y

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ENCLOSURE 4 ISI PROGRAM DRAWINGS Request for ISI Program Relief Nos. Drawings 1-ISI-23 CHM-2336-C-06 CHM-2435-C-06 1-ISI-24 ISI-0394-C-01 2-ISI-24 ISI-0396-C-01 1-ISI-25 ISI-0285-C-01 2-ISI-25 ISI-0268-C-01 E4-1

REFERENCE DRA WINGS \\4 A7201, A7202, 1-51-508-JW. -S1-509-JW REACTOR BUILDING MATERIAL SPECIFICATIONS LOWER CONTAINMENT A376 TP-3J6 STNL. STL. SEAML. PIPE ell ARHRS-185 A.- RHRS-J4 A403 WP-316 STNL. STL. FTGS. RHRS-t84 fN8" SCH. 40 RHR6-0 \\ 6" SCH. 760 RHRF-109A\\r>. 63644-SC -RHRF-107 2At82 3t6 STNL N._ RHRF-t7O8 H SA479 TP3t6 ORIFICE t' Cl />( - RHRS-t86 SA376 TP304 PIPE RF- -07A ASME CC-1 (EQUIVALENT) 1 8X6' RED.\\ i R-HRSB191 7 rRHRF-IO -RHRS-t83 IH HHHH,l RHRF-1O9BJJ / RHRS-t83C RHRF-t09C / J-\\ SI-t990 - RHRF-t09D / / -1 RHRF-tO9F 2 RHRF-t09E I4O J 9 RHRW-2 -o< s-t988 Slt9 0 7 \\963-6 ACC. RM. NO. SI-1987C - RHRF-106-- 63-643-SC 63-641 63-640 's 4' e. t-OR-63-544 A 63-641-BC 63-640BC -MATCH LINE B RHRF-tZ412 / RHRS-205B\\ -RHRF-122 SI-197B-SHEET 4. CC-2 RHRS-2 IO RHRF-123 .W Sl-7I4 SI-987 SJI 4RHRF-t24A -4 SI-79B2- ~ -I7'6RHRF-1248-RHRS-206 63-545 - S-1986 RHRS-212 -RHRS-207 S 9 4; RHRS l RR-2821t92 SI-? 985~~~~~~~~~~~~~~~~SI1 RHRS-2/3 REACTOR BUILDING RHRS-209 LOWER CONTAINMENT SI-1948_--5 -OR-63-54 RHRF-125 - 8X6' RED. ELB. -SJ-t948C RHRW-1 AD dTLSPECS. ADD ORIFICE AND WELDS 2PLACES PER PCDT 2000-0J REP: DCH 20J49A WD# 99-006732-002 & -003 EPG i -a+/- I I L!~ .ADMATCH LIEH PER ECOT 94.19. AD A TON LINE A.CORRECT CONIC. L LRPG i _ DC _ 1 _S-L. -_ 1 2-9.91 A 0 TED CNECTIAIS CHANE DN. TLE REV RE CHECKED SUBMIT7TED APPROVED DT TENNESSEE VALLEY AUTHO)TY SEQUOYAH NUCLEAR PLANT UNI T E RESIDUAL HEAT REMO0VAL SYSTEM HOT LEG LOOPS #1 & 3 WELD LOCATIONS DRAWN: RPG DATE: -JO-91 SCALE, NOT TO SCALE CHECKED, PHB APPROVED RE ICAD MAINTAINED DRA WINGREV SUBMITTED: EDO I (i9-IM-2.3.ib-U-Qb 1(14 tSUBMITTED: EDC CH -6 Q41

RtHRENCE DRAWINGS CHU-2336-C SH.4 CONTRACT NO. TV-42499A DWU NO. 0600 02-O9-11 LEGEND RIGID SUPPORT (FUNCTION A) RIGID SUPPORT (FUNCTION E) RIGID STRUT (FUNCTION A) ASME CC-1 (EOUIVALENT) 1-SIH-399 c ACCUMULATOR ROOM NO. 1 I -SIH-805 t-SIH-806 543 S"X6" RED. ELB. C 4 L RPC I - - I - l- - I - L-°° REAMOVE 1-SIH-803 & -9 PER CDT 2000-05. REF: DCN J8J. L PG i_cG -r_ n-w_ N i - I--:97 CORRECT CONFVRATION & ADD ELEVATIONS PR fCDT 6-28

• 2 L RP i -

DC FRS _Lw - I 2-L6-95 ADD ATCH LINES A & PER CDT 4-18, ADD SUPPORT

FUNCTION, CORRECT CONFICURATION.

L .I __c_1 ics - _ _-7 DELETE 1-SIH-810, OD. TITLE 9EV LY CHECKED SuIT TED APPROVED DATE TENNEsSEE VALLEY AUTHORJTY SEQUOYAH NUCLEAR PLANT UNIT I RESIDUAL HEAT REMOVAL SYSTEM SUPPORT LOCATIONS DRAWN: PC DAtE: 9-4-91 l SCALE: NOT TO SCALE CMECKED PM APPROVED: GLD CAD AAINTAINED DRAtINC REV rr nl .L AS ZC: -n, .1.--.-I------- I -SIH-80 63-641 SUc-UJ IIED: tDC r~~~~~~~.H .5tC-lh......

24' INLET AND 24' OUTLET 180' APAI BOLTS (8) \\ STEEL X_ BOL TS ( STEEL l -I C z REFERENCE DRAWINCS 371206-7 CONrRACT NO. 76KJ6-820061 (N2-499) 17661 17771-1. -2 AND -J A ASE t3 (EOUIVALENT) NOTES:

1. FOR CONFICIRATION SEE ISJ-0158-C-01

2. THIS DIG SUPERCEDES ISI-0268-A-01.

3J. INACCESSBLE PARTIAL. PENETRATION WELD.>\\ I I ~ ~ I I I ) I \\ )/ I SEE DErAIL A rmI A A A A I O TS ,g1 R R R R R R RdW kc DMTS (5) it I;..I I 11 -U- //'I ii ii I I Ii I I1 .' 'I I l! l l l l l - ERCWSH-1 II ERCWSH-12 \\ \\ -- / ' II II II " l CONCRETE I i i 'i ERCSH-l - CORRESPONDS TO STRAINER A2A-A ERCWSH-12 CORRESPONDS TO STRAINER B2B-B U IU IA WELDS SEE NOTE 3 LLL1qI-.E-I-4-02 CHANGE NOr J PER CDr 2002-04 .LRFL C_1 I I l_7Z99 ADD REFEREAVXS AND NOTE PER FCDT 9-21 REV I CHECKED I SUarTrD I APPROVED DATE TrNNESS!E VALLEr AUTHORIY SEQUOYAH NUCLEAR PLANT UNIT 2 ESSENTIAL RAW COOLING WArER SYSTEM STRAINER SUPPORT OETAIL DRANS RPO DATE 3.-S5 I SCALEt NOr TO SCALE CHECKED: JCC APPROVED, CN CAD mAINTAINED DRAYIIN REv LSUWilEu KM I J-2-Ud-C-o1 P ERCISH-11-IA (16 IA'S. 1' EACH AND BASE PLATE 2' THICK) ERCtSH-12-IA (17 IA'S. I' EACH AND BASE PLATE 2' THICK) c l I

• m l

I I ~~~~~~~I PR I

24 INLET AND 24' OUTLET 180' APAI DOLTS (8) SrEEL T\\7 BOLTS (4) M I STEEL 41] CH -Ur-I I I 11 n I I I REFERENCE DRAWINGS 37W206-7 CONrACr NO. 76K36-820061 (N2M-499) 77661 17771-1. -2 AND -J =n A ERCUSH-OS-IA (17 IA'S. EACH AND BASE PLATE 2 rHICK) ERCVSH-10-IA (7 IA'S, I EACH AND BASE PLATE 2 THICK) ~~~~~~~~~~SEE Di TA I A p1 1 11 n nn n n n\\q BOL TS (5) . ll I I1 l rr l ASUE CC-3 (EOWIVALENT) NOTES:

1. FOR CONFICURATION SEE ISI-0123-C-01 t -02

2. THIS DWG SUPERCEDES ISI-0285-A-O.

. INACCESSIBLE PARTIAL PENETRATION WELD. A Hu1 JIl 11 I 1 ERCWSH-05 \\i ERCWSH-IO CONCRErTE r -J--------------------------------___ I ERCrSH--CORRESPONDS TO STRAINER AA-A ERCWSH-t 0-CORRSPONDS TO STRANER OEB- .2 LPBAL C CP 1 CSJ -O-EL- ,HANGC NOrT J PER CoT 200Z-04 ALLL -c. .LN__lBJL-AA -Z?- ADD RErERENCES AND NOTE 3 PER FCOT 8-2? ?EVI HY I CCRED I SUBIrTTED I APPROVED I DATE TENNESSEE VALLEY AUTHORITY SEOUOYAH NUCLEAR PLANT UNIT ESSENTIAL RAW COOL INC WA TER SYSTEM STRAINER SUPPORT DETAIL DRAIN,: PC DAtE: 88 SCALE: Nor ro SCALE CHECKED, JCC APPROVED, C9 CAD MAINTAINED RAINS RIEP C U IU C SEE NOTE 3 l I t ,I - _-s_V{ .u.JrE. I Is_7snn )Pr

_ EFERENCE DRAWINGS 1-47W465-SERIES s.so A ~~~~~~~~~-CONTRACT NO. 68CS0-9 h--I SEISMIC LUG PRESSURIZER MANUAL (i (TYP. 4 PLACES) MATERIAL SPECIFICA ALL vESSEL SHELL AND HE, ~~~~~~~~~~~~~~~~~ARE FABRICATED OF SA-5.3' iT ~ ~~~~~~~~~~~~~~~~~MANGANESE-A Sl { \\ 4.00 ,-~~~~~~^^~~~-- CLAD WITH AUSTENITIC ST THE NOZZLES ARE FABRICAI INSTRU ENT NOZZLES CLASS 2

• UNANESE-WOLYI (4

IN LINE AROUND SAFE END CONNECTION. (_P42Z Ar TAEEEV)- CR. F-316L, FORGINGS sEcrioN fi-B \\ X TH~~~~~~15 INCHESTHICK AND Is PZRH-2 SEE NOTE 4) SA-S 16. R.70. CARBON Si FSS (TYrCA (SESUC LU ASME (CC-1) E / ~~TRUNNION \\ 6 p P-S / F ~(TYP. 2 PLACES) >\\ /r2.5 NWINAL a sv HEAD THICKNESS ^ R / / ~~~~TYP 4 NOZZLES EIl WP-a RCW-1 S CLADDZNC WP-7 \\.190' NOMINAL Np_g C9 R \\ 1 {SEE NOTE 6) RCW-24-SE Ir .44 l -/RCWI-2 9-SE / / WP-iL z t WP-3 / 6

6.

\\ X THIS VIEW IS NOT A TRUE ORIENTATION FOR TRUE ORIENTATION SEE ToP VIEW 3.0' NOUINAL INSTRUMENT NOZZLES HEAD THICKNESS (5 IN LINE AROUND PZR AT A> x SAEE ELEVATZON) A SAFEtY NZZL E -- .4 1934 'NII-2--6) ']lCS,S-S-71 TIONS 'D SECTIONS I CLASS 2 IEL AND ARkt AINLESS STEEL. IED r SA-S0. 3OENUA STEEL. S ARE SA-1J2. 'ROXIMATELY FABRICATED 0 fEEL PLATE. QUIVALENT RCW A ( EXCLDE ELD A NOTES:

1.

THIS OWC SUPERCEDES BOTH CHIU-2362-A AND CHM-2363-A.

2.

FOR UNIT 2 DIC SEE SZ-0398-C

3. O IS t r MANWAY AND MEASURED CLOCKWISE IN THE TOP VIEW

4. SUPPORT CLASSIfIED AS PZR RIGID SUPPORr AT THIS LOCATION SEE DRAWINC 48N428 FOR CONFIGURATION.

5.

VESSEL INSIDE SURFACE CLAD O. 190 NOV

6. SEE TABLE BELOW:

AS DUILT D. ENSIONS WELD NO. A1 W P-9 S' . L RRC I - CiC -i - Sut -I -_~ CN _T #} 1D0 BOrTo VIEW, LUC NO.S. INSTRUKMT NDZZLES WOrE. AND REF. DWOS PER Fr 2O62-61 ADO OiMUfSlo CORRCr NOrf 4. ADD REF. TO NOTE 4 'ER CD 2II-05 CORRECr NorE TOLsU NODZE ETAIL RfV Y CACtOl wrTD APFOVfD DATE TrENhESE VALLEY AUTHWAITY UNIT 1 PRESSURIZER DRAN, RPG DATE 8-27-SI 9 SCALE: NOT TO SCALE aCOfD! $11f APPROVED, RI lCAD AINTrAINED DRAUJUC Rfl SUaWirTO: EDC I 1-394-C-O1 07 (I / PZRH-1 (SEE NOTE 4) SUPPORT SKIRT WELD RCW-23A / U ZE R DETAIL A RCW-21 RW21-ZR 3.75' THICKA SEE DETAIL A I SEE DETAIL E SHEET 5 A -(E No=TE 6) /~~~~~~ /- i

PZRH-I (SEE NOTE 5) rEtURIZER RCW 23 DETAIL A SEISMIC LUG (TYP. 4 PLACES) SECTION -B PZRH SEIS1 PZRH AL (TYP B INSTRUMENT NOZZL ES (4 IN LINE AROUND PZR AT SAME ELF V.) A (TYP 4 PLACES, UfIC LUCS) -2 (SEE NOTE 5) . 4 PLACES) TRUNNION f (TYP. 2 PLACES) 6" iAn L WP-3 \\ WP-s NOT A TRUE ORIENTATION RIENrATION SEE TOP VEW PR SURIZER Ia Z SUPPORT BRACKET7-' Z. LLUC NO.4 PZR ID -klCG-NOT IN THE SCOPEOF O THE SUPPORT BOUNDARY 0 -MANWAY UNIT -AJCj (TYPICAL 4 PLACES) BOLTINfG (0-156) BOTTOM VIEW TOP VIEW (LOOKING UP) (LOOKING DOWN) DETAIL REFERENCE DRAWINGS 2-47W465-SERIES CONTRACT NO. 68C60-91934 N2M-2-6) PRESSURIZER MANUAL (FICS.5-1. 5-7) MATERIAL SPECIFICA TIONS ALL VSSEL SHELL AND HEAD SECTIONS ARE FABRICATED Of SA-53J. CLASS 2, MANGANESE-MOL YBDENU& SrEEL AND ARE CLAD WrTH AUSTENITIC STAINLESS STEEL. rHE NOZZLES ARE ABRICArED OF SA-SO. CLASS 2, ANANESE-MOL YBDENUM STEEL. SAFE END CONNECTIONS ARE SA-182. CR. F-3t6L FORGINGS THE SUPPORT SKIRT IS APPROXMA TEL Y 1.5 INCHES THICK AND IS FABRICATED OF SA-516. CR.70. CARBON STEEL PLATE. ASME (CC-1) EQUIVALENT WP-5 ,_^,- TYP. 4 NOZZLES RCW-15 CRCW-I5-IR -RCW-24-SE ~~ 2.5' "NOMINAL HEAD THICKNESS

1.

THIS DWG SUPERCEDES ISI-O3O8-A. ISI-0323-A. AND ISI-0299-B.

2. FOR UNIT I DWG SEE S1-0394-C.

3.

0' 15 t OF MANWAY AND MEASURED CLOCKWISE IN THE TOP VIEW.

4.

VESSEL INSIDE sURFACE CLAD - O.190' NOMINAL.

5. SUPPORT CLASSIFIED AS PZR RGID SUPPORT AT THIS LOCATION SEE DRAWING 4N428 FOR CONFIGURATION.

6.

SEE TABLE BELOW: AS BUILT DENSIONS WELD NO. A' WP-6 L WP-9 L L I - JCC SL.R1 - CH L0-4-02 ,ORRECT SAFTY T R IEF NOZZLE LOCArION PER FCoT 2002-02 LL ~ J... i C_LI__Lti _c CH _ 4 02 oDD TTr VIEW. LuG NO.S. ISrlNNTNr NOZZLES vOTE S. AD REr. DRCS PER FrDr 2002-01 REVl oy I cHEcKiED I SUA EED APPROVED DATE TENNESSEE' VALLEY AUTM"ITY SEOUOYAHf NUCLEAR PLANT UNIT 2 PRESSURrZER DRAWN, RPG DATE, 12-9-S l SCALE NOT TO SCALE CHECKED: PHD APPROVED, G CAD AINTAIEfD bRA IAO RE SEE DETAIL SHEET 3 RCW-2 9-SE . O' NOMINAL HEAD THICKNESS (SEE NOTE 3) WP-1 t6">\\_~ WP-2 6 ~~~ K - ~~TH IS V IEW 1, FOR TRUE rNSTRUMENT NOZZLES (5 IN LINE AROUND PZR AT SAME ELEVATION) SAFETY NOZZLE -- C C'1 =-

ENCLOSURE 5 Examination Limitation Drawing Typical of Unit 1 and Unit 2_ Request for Relief 1/2-ISI-25 1 inch typical 6 inches / I'tem 30 Typical Front View with Cross Section L]hes Ztem I Side View with Cross Section 1Item 30 /2 in. I" X 45 deg Chamfer lI ] -'t mj E5-1 6 inches / %/ in. II i I I i0 lItem 5 l1

ENCLOSURE 6 PIPE SUPPORT DRAWING 1-SIH-801 FOR REQUEST FOR RELIEF 1-ISI-23 E6-1

900-LOCATION PLAN FLOOR EL 679'-9-3/8' SUPPORT NO: 1I-SIH-801 PLAN DET 81 ITEM QTY MATERIAL DESCRIPTION §6. 1 W6 X 25 X 2'-6 ,cc, 2 1 W6 X 25 X 1-0-7/8' 2:c 3 2 C4 X 5.4 X LG AS REOD oB z 4 2 F6 X 25 X 1/2 ID la 2 3/4' DIA SSD 40_ I PL 3/4 X 14 X 1'-2' Al -Al ITEMS 3 & 4 cl-cl CALCULATION BRANCH/PROJECT IDENTIFIERS: SIHO8O1 0600104-09-11 BASIC ENGINEERS CONTRACT NO: 71-92615 I i oVLLi A. NOTES:

1. FOR GENERAL NOTES SEE 47A050-SERIES.

REFERENCE DRAWINGS: 47W432-SERIES................... PIPING 0600102-09-11 CONTR TV-42499A. ISO 1-H2O-O8OO CONTR 71-92615.... SEC SPRT D l MU0555A N2A I SEE IIILE LULK INC, OCA MOOSSSA-12 R1 -13 P WALKDOEN DATA RIMS

• Bz 551011 837. DCA M0SS5A-13 RO PSTED CHANCE O CCD lIlH20-08I002 RE TO RE INCORPORATED ON CCD I-1-H20-08I-Oi RO. RENANE DCA M00555A-1 R

POSTED CHANCE TO CCD -- H20-0501-01 O. erkl snrbl rts 0 rDwvl l-U.- S.AL: Nl

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,l REACTOR BUILDING CATEODY UNIT MECHANICAL SAFETY INJECTION SYSTEU PIPE SUPPORTS SEQJOYAH NUCLEAR PLANT TENNESSEE VALLEY AUTHORITQ NUCLEAR ENGINEERING DESIGN INITIAL ISSUE ENGINEERING GRAFIER CHECKER RO ISSUE PER:D*G UADE APPROVAL K. NELSON A CCO FROM I-H20-0801 I N/A )ESIGNER REVIEWER - AC-RA & AD-R907. 2 N/A N/A

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ENCLOSURE 7 TVA' S PROCEDURE FOR CALCULATION OF THE ASME CODE COVERAGE FOR THE SECTION XI E7-1

/ NONDESTRUCTIVE EXAMINATION PROCEDURE TVA Nuclear Power I _) Procedure No. N-GP-28 Revision 3 Page 1 of 8 W47 010524 006 QA RECORD CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NDE EXAMINATIONS "QUALITY RELATED" Prepared By: Oria. signed by, Joel W. Whitaker Date: 5/24/01 Technical Review: Orig. signed by, N. Roger Bentley NDE Level III, Date: 5/24/01 ISO Approval: Orig. signed by, Frank C. Leonard Date: 5/24/01 I:Shared\\N-GP-28 Rev 3 (5-01).doc

NONDESTRUCTIVE EXAMINATION PROCEDURE TVA Nuclear Power fln+$ 4/3/96 8/15197 10/18/00 5/24101 b Procedure No. N-GP-28 Revision 3 Page 2 of 8 floe,rinflnn Initial issue. Incorporate TC 97-09. General revision to incorporate 10CFR50.55a ruling change which implements Appendix VIII Revised to upgrade procedure to ASME Section Xi 1995 Edition with Addenda through 1996 I:Shared\\N-GP-28 Rev 3 (5-01).doc D-, Kln 0 1 2 3 INUV. IMU. "aL
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} NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 3 Page 3 of 8 1.0 Scope The scope of this procedure is to provide generic guidelines for calculating the ASME Section Xi code coverage and augmented examination coverage obtained during volumetric and surface examinations. This procedure incorporates the requirements of Code Case N-460 and NRC Information Notice 98-42. This procedure is not applicable for calculating the examination coverage for RPV examinations performed in accordance with Appendix VIII. 2.0 Purpose This procedure applies to the calculation of ASME Section Xl Code coverage for vessel welds (excluding the RPV welds performed in accordance with Appendix VIII) piping welds, and integral attachments. This procedure applies when performing surface or volumetric examinations and may be used as a guide when calculating the examination coverage for preservice and inservice examinations. Coverage limitations may be due to an obstruction, interference, geometric configuration or other applicable reason. 3.0 References 3.1 ASME Code Case N-460 3.2 1 OCFR 50.55a, as amended by the Federal Register Notice, Vol. 64, No. 183, dated September 22, 1999 (Final Rule)- Implementation of Appendix Vill as executed by the Performance Demonstration Initiative (PDI) Program Description Document, Rev. 1, Change 1. 3.3 Guideline for the Implementation of Appendix Vil and 1 OCFR 50.55a, Rev. D, April 18, 2000 3.4 NRC Information Notice 98-42 4.0 Definitions 4.1 Examination Coverage-The percentage of the examination surface or volume obtained during the performance of the examination. 4.2 Examination Surface-The surface of the weld and base material required to be examined by ASME Section Xi or other requirement using a surface examination method. 4.3 Examination Volume-The volume of weld and base material required to be examined by ASME Section XI or other requirement using a volumetric examination method. 4.4 Scan Limitation-the inability to scan the surface(s) as required by procedure due to interferences. 4.5 Surface Limitation-the inability to perform a surface examination of the required surface(s) because of an interference. I:Shared\\N-GP-28 Rev 3 (5-01).doc

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 3 Page 4 of 8 4.6 Volumetric Limitation-the inability to examine the required volume because of the geometric configuration, a physical interference, or a metallurgical condition of the material being examined. 5.0 General 5.1 During the performance of inservice inspections, ASME Section Xl requires examination coverage to be essentially 100% of the weld area or volume. For examination coverage less than 100%, TVA has implemented ASME Code Case N-460 which states that when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage for Class 1 or Class 2 welds may be accepted provided the reduction in coverage for that weld is less than 10%. (NRC Information Notice 98-42 further defines the >90% rule to include all welds and other areas required by ASME Section Xi. 5.2 Surface examinations are typically conducted on the weld area plus a defined amount of base material on each side of the weld. Volumetric examinations specify a particular volume to be examined. The Section Xl required examination volume or surface examination area for each type of weld is depicted in figures of IWB-2500 or IWC-2500 as applicable. As depicted for piping welds, volume width generally constitutes the weld plus 1/4t on each side while volume thickness generally constitutes the lower 1/3 of the piping thickness for the length of the weld. The exception normally includes code category B-O which includes the weld plus 1/2 inch and full volume for the length of the weld. As depicted, for vessel welds, the volume width generally constitutes the weld plus 1/2t on each side of the weld while volume thickness generally constitutes the entire component thickness (i.e. full volume). The volume changes with variations in weld configuration (e.g. transition between different pipe thickness or vessel weld configurations). Note: Risk-Informed (RI) programs require larger volumes in certain areas. 5.3 The required examination volume or area shall be verified prior to calculation of the limitation. 6.0 Documenting and Calculating Examination Coverage 6.1 While performing a surface or ultrasonic examination, the NDE Examiner shall make every attempt to examine 100 percent of the examination area or volume. 6.2 When practical, the two beam path directions for ultrasonic examinations should be performed from two sides of the weld or additional angles employed in order to maximize coverage. 6.3 If 100% percent of the examination surface or volume cannot be examined, the NDE Examiner should perform the following under the direction of the inspection coordinator or the NDE Level IlIl: 6.3.1 Perform additional examinations with higher angles in order to maximize cover for ultrasonic exams. 6.3.2 Perform another surface method (i.e., PT in lieu of MT) in order to maximize coverage. I:Shared\\N-GP-28 Rev 3 (5-01).doc

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 3 Page 5 of 8 6.3.3 Perform alternative NDE methods if applicable. 6.4 The examiner shall accurately document all limitations, obstructions, interferences, geometric configurations or other applicable reasons for not obtaining the required code coverage. 6.5 The examiner shall document the limitation on a sketch. Examination coverage estimates may be performed by the examiner or the reviewer. 7.0 Calculation Basis 7.1 Volumetric Examinations-Piping Welds and Vessels 2 inches and less in thickness a) Examination volume coverage may be increased as previously discussed or by use of refracted longitudinal wave techniques on stainless steel or dissimilar metal welds. Use of refracted longitudinal waves to penetrate stainless steel weld material will increase the examination volume coverage by the amount depicted on the examination coverage drawing. b) Estimates shall be derived by estimating coverage based on two-beam path direction coverage of the complete examination. Each scan direction equals 25% (downstream, up-steam, clockwise, counterclockwise.) (Reference Figure 1) c) The effects of adjacent component interferences (e.g. welded lug attachments) along the weld length are also taken into account with the reduction in coverage identified as a percentage of reduced volume. 8.0 Surface Examinations - Piping Welds And Integral Attachments 8.1 Examination area coverage calculations are based upon one of the following suppositions: a) The total examination area is calculated, typically length x width, then the total area of limitation or interference is subtracted from the total examination area. b) The area of achieved coverage is divided by the total examination area for percentage of examination achieved. I:Shared\\N-GP-28 Rev 3 (5-01).doc r i i

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 3 Page 6 of 8 9.0 Ultrasonic Examinations - Vessel Welds NOTE: THIS IS NOT APPLICABLE FOR APPENDIX Vill EXAMINATIONS OF THE RPV WELDS. 9.1 Examination volume coverage calculations are based upon the following suppositions: a) To achieve full examination coverage nine different scans are required for a typical vessel weld or nozzle examination. The following may be used for other vessel configurations:

1) 0 degree (weld metal scan)

2) 45 degree Transverse-scan from vessel side of the weld

3) 45 degree Transverse-scan from nozzle side of the weld

4) 60 degree Transverse-scan from vessel side of the weld

5) 60 degree Transverse-scan from nozzle side of the weld

6) 45 degree Parallel-scan CW direction

7) 45 degree Parallel-scan CCW direction

8) 60 degree Parallel-scan CWdirection

9) 60 degree Parallel-scan CCW direction 9.2 The examination volume achieved for each above examination scan shall be obtained and documented on a percentage basis. This calculation considers the required examination volume required perthe ASME Section Xl Code.

a) The total examination coverage may be calculated by averaging the exam volume coverage for all nine scans. 10.0 PDI Implementation for Piping Welds 10.1 Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds provided the examiner is qualified for single sided examination. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications. Therefore, examination of austenitic material welds shall be performed from both sides or a scan limitation shall be documented. 10.2 The NDE Level IlIl shall make an evaluation in the Weld Resolution document regarding total examination coverage (best effort) as calculated above in Section 7.0. In addition, a coverage evaluation which considers the PDI Implementation Guideline shall also be indicated in the Weld Resolution sheet. These two coverage evaluations shall be reported to the ISI Programs Engineer for incorporation into the Relief Request. 10.3 Typically a one-sided austenitic weld examination with no circumferential restrictions would be indicated as 75% examination coverage or 50% if circumferential scans were limited to one side. NOTE: These requirements do not apply to augmented examinations of piping welds. I:Shared\\N-GP-28 Rev 3 (5-01).doc

J' NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 3 Page 7 of 8 1 1.0 Responsibilities 11.1 The examiner or designee shall document the amount of code coverage obtained after all necessary steps to perform additional examinations has been completed in order to maximize coverage. The documentation shall become part of the examination weld data package. 11.2 The documentation may be reviewed by another individual with the same or higher NDE certification. 11.3 The NDE Level IlIl or data reviewer may review the calculations in order to verify that the information is accurate and correct. 11.4 The NDE Level IlIl may recalculate the examination coverage to obtain a more accurate value of the examination surface or volume examined. The calculation shall be documented on the exam report. 11.5 The NDE Level IlIl may require an altemate examination technique or method, or request that the interference be removed. For nozzle examinations, supplemental scans from the nozzle bore or flange face may provide complete coverage of the weld. 11.6 If the examination coverage indicates less than 90 percent of the required examination volume or surface, the site ISI Program Engineer shall be notified. 11.7 The site ISI supervisor shall ensure that examination results are accurately documented and incorporate results into a Request for Relief if necessary. I:Shared\\N-GP-28 Rev 3 (5-01).doc I

i i NONDESTRUCTIVE EXAMINATION PROCEDURE TVA Nuclear Power Procedure No. N-GP-28 Revision 3 Page 8 of 8 Em 3230 APPENDIX mII-MANDATORY . m-3310 Interference between shoe and wd 1 I l-Exam. ol. C-D- E - F GENERAL NOTE: For this example of interference with a $/AV examination applied from both sides, only the E-F-G-H portion of the examination volume receives two direction coverage, while volumes C-G-F and H-D-E receive one direction coverage. In this case, ihe examination beam path shall be increased to %V (O. to ID. and back towards OD. for '%t) to provide the required two direction coverage over the examination volume. Use of %V examination beam path O.D. to LD. to %t) provides additional beam path (past 'At) to help in obtaining required coverage when examination part thickness t increases. FIG. 111-3230-1 EXAMPLE OF PHYSICAL RESTRICTIONS TO THE WELD EXAMINATION Figure 1 I:Shared\\N-GP-28 Rev 3 (5-01).doc

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-0 st D UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205550001 Jane 19, 2000 Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3, RELIEF REQUESTS 2-ISI-10 AND 3-ISI-9, ALTERNATIVES FOR EXAMINATION OF INACCESSIBLE REACTOR PRESSURE VESSEL SUPPORT SKIRT WELDS (TAC NOS. MA6408 AND MA8423)

Dear Mr. Scalice:

By letter dated March 24, 2000, the Tennessee Valley Authority requested relief from certain surface examination requirements of the 1986 Edition of Section Xi of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Code) for the second 10-year inservice inspection interval at Browns Ferry Nuclear Power Plant, Units 2 and 3. The surface examination requirements pertain to the reactor vessel support skirt welds. Instead of the required surface examination from both sides of the skirt welds, the licensee proposed an alternative. The alternative is a surface examination of reactor pressure vessel support skirt welds and a best-effort ultrasonic testing examination of the opposite weld surfaces. The U.S. Nuclear Regulatory Commission staff has reviewed the request for relief. Based on its evaluation, the staff concludes that the proposed alternative will provide an acceptable level of quality and safety. Pursuant to Title 10, Code of Federal Regulations, Part 50, Section 55a(a)(3)(i), the staff authorizes the proposed alternative. The staff's safety evaluation is enclosed. This completes the staff's activities related to your relief reauest of March 24, 2000. If you have any questions, please contact the Browns Ferry project manager at 301-415-3026. Sincerely, 12A#P C Richard P. Correia, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-296

Enclosure:

Safety Evaluation cc w/encl: See next page p..flZ*hVi:Lt I -.f1 4 0' I 4V14 .1 1.-* ^ "~lili~ .w~~~~~~*, yuzz '
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION USE OF ALTERNATIVE TO CERTAIN SURFACE INSPECTION REQUIREMENTS TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR POWER PLANT. UNITS 2 AND 3 DOCKET NOS. 50-260 AND 50-296

1.0 INTRODUCTION

The inservice inspection of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components shall be performed in accordance with Section Xi of the ASME Boiler and Pressure Vessel Code (Code) and applicable addenda as required by Title 10, Code of Federal Regulations (10 CFR), Section 50.55a(g), except where alternatives have been authorized by the Commission pursuant to 10 CFR 50.55a(a)(3). t is stated, in part, in 10 CFR 50.55a(a)(3), that alternatives to the Code requirements may be used providing the licensee demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Pursuant to 10 CFR 50-55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the second 1 0-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval. By letter dated March 24, 2000, the Tennessee Valley Authority, the licensee, requested relief from certain surface examination requirements of the 1986 Edition of Section Xl of the ASME Code for the second 1 0-year inservice inspection interval at Browns Ferry Nuclear Power Plant (BFN), Units 2 and 3. The surface examination requirements pertain to the reactor vessel support skirt welds. Instead of the required surface examination from both sides of the skirt welds, the licensee proposed an alternative. The alternative is a surface examination of the ENCLOSURE reactor pressure vessel (RPV) support skirt welds and a best-effort ultrasonic testing (UT) examination of the surface of the welds.' 2.0 CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED The licensee requested relief from the requirements of the 1986 Edition with no addenda of Section Xl of the ASME Code, Table IWB-2500-1, Examination Category B-H, Item B8.10 for the surface or volumetric examination as applicable based on the configuration of the support skirt to vessel welds: RPV-SUPP-2-1-lA and RPV-SUPP-3-1-IA. The weld configuration and examination area are illustrated in the ASME Code, Section Xi, Figure IWB-2500-13. This corresponds to Figure 1 of Code Case N-323-1, and is depicted in this safety evaluation as Figure 1 (attached). 2.1 Licensee's Basis for Relief The reactor pressure vessels (RPVs) at BFN are supported on cylindrical skirts that are welded to the bottom RPV heads as shown In Figure 1. The Code requires that both surfaces of the weld be examined. An examination of the outside weld surface is readily accomplished with minimal, if any, hindrance. However, examination of the inside weld surface is difficult. The only access Into the skirt is through an 18-inch opening. Inside the skirt, the weld and bottom RPV head are covered by insulation. The tasks of removiny this Insulation, preparing the weld surface for examination, and performing the examination are hindered by limited maneuverability in the confined space within the skirt. The confined space also houses the control rod drive mechanisms (CRDMs) that are attached to the bottom RPV head. The CRDMs further contribute to the limited maneuverability. Because of these limitations, the time needed to complete an examination of the weld surface would expose inspection personnel to high radiation dosages. The licensee estimated that the total radiation to personnel involved with preparing and examining the weld surface would total 11.2 rem. The licensee proposes to perform a best-effort ultrasonic (UT) examination from the outside (accessible) weld surface to detect service related flaws on the inside weld surface. The best-effort UT examination would replace the required inside surface examination. The licensee believes that this alternative would provide an acceptable level of quality and safety. Furthermore, the licensee's request Indicates that there are no known failures of support skirt welds. Based on the limited access and absence of bulletins or reported failures of the inside surface on the support skirt weld, the licensee believes that the benefits derived from this examination do not warrant exposing examiners to the associated high-radiation doses. 'The licensee proposed use of ASME Code Case N-323-1 and a best-effort UT examination from the accessible side of the RPV support skirt welds. The staff has not endorsed Code Case N-323-1 in Regulatory Guide 1.147. Instead of citing Code Case N-323-1, the staff has restated the proposed alternative in autonomous terminology, so as not to connote endorsement of the code case.

K-K 2.2 Licensee's Proposed Alternative to Code Reguirements The licensee's proposed alternative is to perform a surface examination of the outside surface (considered the accessible surface) and a best-effort UT examination of the inside surface of the support skirt welds identified as: RPV-SUPP-2-1-lA (BFN Unit 2), and RPV-SUPP-3-1-IA (BFN Unit 3). 3.0 EVALUATION The licensee has requested approval of altemative examinations for its skirt welds. The altemative is necessitated by the narrow access through the skirt and the obstruction in the confined area inside the skirt under the bottom head. The working area inside the skirt under the bottom head limits maneuverability and exposes examiners to high radiation levels. The ASME Code specifies different examination requirements for the skirt weld configurations depicted in Figures 1 and 2. The Code requires surface examinations of both the outside and inside welded surfaces for the Figure 1 configuration. The inside examination requires personnel entry to the area inside the skirt. For the Figure 2 configuration, the Code allows (1) a surface examination for the accessible side, and (2) a volumetric examination from the accessible side of the inaccessible side. This does not necessitate personnel entry to the area inside the skirt. The skirt weld configuration at BFN is shown in Figure 3. This configuration is a hybrid of Figures 1 and 2. Instead of performing surface examinations from both sides of the welds in accordance with the Code requirements applicable to the Figure 1 configuration, the licensee proposes to perform (a) a surface examination on the outside surface (accessible) of the welds and, (b) a best-effort UT examination of the inside surface of the welds, from the outside surface. This licensee's proposed alternative for its Figure 3 skirt welds is similar to the Code requirements applicable to the Figure 2 configuration. The Figure 3 configuration can, to a significant extent, be volumetrically examined from the outside surface, as is the case for the Figure 2 configuration. The weld volume capable of being examined Is through wall and at or near the inside weld surface. Therefore, any crack propagating from the inside weld surface would be detectable. The staff believes that a best-effort examination, in combination with the outside surface examination of the skirt weld will provide reasonable assurance of structural integrity and an acceptable level of quality and safety.

4.0 CONCLUSION

The staff concludes that the proposed alternative described above will provide an acceptable level of quality and safety. Pursuant to 10 CFR 50.55a(a)(3)(i), the staff hereby authorizes the proposed alternative as described in Section 3.0 above. The proposed altemative is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. Principle Contributor: D. Naujock, NRR Date: June 19, 2000

Attachment:

Figures 1, 2 and 3 ' /

FIGURE 1 (ASME Code, Section Xi, Figure IWB-2500-13) in. K in

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K> Mr. J. A. Scalice Tennessee Valley Authority cc: Mr. Karl W. Singer, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. John T. Herron, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority ET 1 OH 400 West Summit Hill Drive Knoxville, TN 37902 Mr. N. C. Kazanas, General Manager Nuclear Assurance Tennessee Valley Authority 5M Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 y)j BROWNS FERRY NUCLEAR PLANT Mr. Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy E. Abney, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Mr. Robert G. Jones, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609}}