ML20149G246
| ML20149G246 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/07/1997 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20149G227 | List: |
| References | |
| NUDOCS 9707230074 | |
| Download: ML20149G246 (112) | |
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New York Power Authority 1
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INSERVICE INSPECTION
SUMMARY
REPORT j O FOR l
REFUELING OUTAGE RO12 AT l
JAMES A. FITZPATR!CK NUCLEAR POWER PLANT e
l REVISION 1 i
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 O
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TEXT i
o INTRODUCTION.................................
..................... 2 II.
FORM NIS-1, OWNERS DATA REPORT for INSERVICE INSPECTION.....
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ISI EXAMINATION CHECKLIST...........................................
.2 IV.
EXAMINATION RESULTS....................................
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e indications.....
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Limited Examinations........................
3 CRD Housings (Bolts. Studs, and Nuts).............
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V.
CERTIFICATION I QUALIFICATIONS..................
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Personne!....
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Equipment
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Materials..............................
........... 5 VI.
PROC EDURES.......................
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IN-VESSEL INSERVICE INSPECTION 6
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SECTION XI REPAIR AND REPLACEMENTS.........
... 6 IX.
PRESSURE TESTING....................
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SNUBBERS..............................................
... 7 XI.
FEEDWATER NOZZLE LEAKAGE MONITORING SYSTEM 7
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FEEDWATER NOZZLE INSPECTIONS.
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O TABLE OF CONTENTS (Con't) 4 l
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ENCLOSURES 1.
Form NIS-1, Owners Data Report for Inservice Inspection i
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ISI Examination Summary
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ISI Examination Checklist
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ISI Examination Results & Disposition f
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Certifications / Qualifications Personnel Listing Equipment Listing Material Listing i
6.
NYPNOC Miscellaneous ISI Checklist NYPA ISI Miscellaneous Checklist 7.
Limited Examinations 8.
in-Vesselinservice Inspection In-Vessel Visual inspection Summary In-Vessel Visual inspection Checklist in-Vessel Visual inspection Results and Disposition (Reference Documentation Memo: PEP-PO-96-341) i ISIFTZ6. DOC
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INTRODUCHQH This summary $eport details the Inservice inspecbon Program conducted at the Jam 6s A.
FitzPatrick Nuclear Power Plant during RO12 Refueling Outage in the last quarter of 1996. The t
inservice Inspection F m;, ram requires performing examinations on Class 1,2,3 and augmented components. Tho NDE inspectons were performed by General Electric Nuclear Energy (GENE) and New York Power Authority personnel.'
This report is a summary of inspections performed during the RO12 Refueling Outage. The ISI j
inspectons performed during RO12 were in accordance with the following goveming documents:
Technical Specifications, ASME Boiler and Pressure Vessel Code,Section XI, " Rule for inservice Inspecton Nuclear Power Plant Components",1980 Edition up to and including Winter 1981 Addenda, approved NRC relief requests, and ISI Programmatic Commitments as approved by the NRC for the Second Ten-Year intental. In addition, other regulatory documents were used where applicable to develop sugmented inspection programs to meet mandatory requirements. These documents are referenced specifically in the following text, ie., NUREG-0313, Rev. 2 and Generic j_
Letter 88-01 were used for selection and performance of IGSCC examinations.
included in this report is a listing of partial and/or limited examination coverages along with j
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percentages complete for inspectons conducted during the RO12.
q The NDE methods utilized were visual (VT-1, VT-2, W-3, VT-4 and Enhanced Visual for Shroud i
inspection), magnetic particle, liquid penetrant, and ultrasonic testing (manual), and radiography.
These examinations were conducted using approved site / vendor procedures and personne!
j certified and qualified to an spproved QA NDE Program.
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FORM NIS-1, OWNERS DATA REPORT for INSERVICE INSPECTION
'i The NIS-1 Form as required by the goveming code secten will be supplemented with the ISI
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. Examination Checklist, Examination Results Listing, and Limited Examination Listing for 1
inspectons conducted by GENE and NYPA Personnel. These supplements are Enclosures 1,3,4 i
and 7.
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181 EXAMINATION CHECKLIST The ISI Checlmt was developed in accordance with the Second Ten-Year ISI Program Plan.
Totnical Specificabons, ASME Code Secten V and XI, NUREG 0313, Rev. 2, Generic Letter 88-01 including supplements, NUREG 0619 and NRC-approved relief requests as applicable to specific components and/or systems The ISI Checklist once,npeeeed all of the examination requirements of the above as well as delineating the following:
Component / Wold identificaton ASME Code Category ASME Code item Number NUREG -0313 Category Isometric Drawing Number NDE Method Utilized for Examination NDE Procedure Number Utilized j
UT Calibraton Block (if applicable)
Examination Completion Date NDE Report Number.
Additional Remarks (if applicable)
The ISI Examinston Checklest was used for both scheduling and tracking purposes. in this way, control was maintained over 131 activities.
g ExARENATION RESULTS The results of examinstons documented in this secten of the report are for inspectons performed by GENE and are included in the Examination Result Listing.' Examinatens performed by NYPA QC personnel are referenced in the NYPA Miscellaneous Examination Checklist secton and in-Vessel Visual inspechons performed by GENE are referenced in the in-Vessel inservice Inspection secten e
indications Compwmts and/or welds found to have recordable / rejectable indications were promptly called to the attention of the responsible engineer. Disposition of components and/or welds with unacceptable indications were addressed by repair, bounding evaluation, and/or reinspechon, to ensure any and all unacceptable results or conditions meet plant safety and continued operational critena.
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1 i-a RPV Head Wald VC-TH-1-2 i.
1 Examinations conducted on RrV Head Weld VC-TH-1-2 during RO12 were in
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accordance with Sechon XI requirements for reexaminaton of unacceptable indications i
under NRC Regulatory Guide 1.150 and ASME Section XI, lWB-3510. The exeminations j
conducted during RO12 have successfully met the reexamination requested by the NRC.
j The Authority will retum weld VC-TH-1-2 to a normalinspechon schedule based on ASME Section XI,
Reference:
NRC letter dated 12/27/g6, Evaluston of Reactor Vessel Head indicabon inspection and Evaluation Submittal for JAF N.P.P. (TAC No. M97443) c
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Components that have a limited exammaton can be accessed through the list which details Code Required Volume (CRV). Conditions that would result in a limited exam are F
component configuraton, vanous types of permanent obstructions, and limited access i
When a limitabon was identified that precluded 100% coverage, ca!culations were performed to determine the percentage actually examined. A listing of the RO12's partial jl exams with their percentages cow-C'd is a part of the Limited Examination Listing.
Apphcation for relief of components that do not meet the criteria in Code Case N-460, will be subrnetted in accordance with 10CFR50.55a(a)(3)(ii) under separate cover, l'
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CRD Housings fBolta. Studs. and Nuts) i ISI inspecton requirements of CRD Housings Bolts are incorporated into the maintenance achvibes associated with CRD Flange disassembly and botting replacement. Procedurally as part of these activtbes visual examination of bolting removed and/ or replaced has l'
been a requirement in accordance with ASME Section XI and GE SIL No. 483, CRD Cap Screw Crack Indications, Recommended schons, when bolting is reinstalled. This _
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l-included a visual and liquid penetrant examinaten of the heaa to shank region on bolting i
that exhibits cracking or that is reinstalled. The Authonty's policy on CRD Cap Screws is l
to replace all bolbng removed with the new style resistent material. Prior to RO12 a procedural change was premaad and the requirerrent to inspect bolting that is removed e
t was reworded and gave opton whether to inspect the removed bolting (if not reinstalled),
I but maintained the required insp&luun of any and all bolting installed. An extensive review of inspections conducted during RO12 revealed that no examinstons were performed on CRD Flange Cap Screws that were removed from service during CRD disassembly.
Consequently, the CRD Cap Screws were removed and shipped off site for disposal'
- -j; before this acacawsance was detected The Authority had a search performed by the Rad Waste disposal organization, identified the CRD Cap Screws and subsequently, i
performed the required inspechons. The inspecten revealed six (6) cap screws had j
recordable indications located the head-to-shank region. The evaluaton of indications j_
detected identified (2) cap screws with crack lengths of g/16", (2) with crack lengths of 7/16" and (1) with aligned rounded indicatens with a total length of 1/2".
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The Non-destructwe Examinaten Procedure used to perform the visual examination -
j invoked ASME Seebon XI 1989, IWB-3517 as a basis for reportable indications during the performance of visual examinations (VT-1) because the 1080 version of ASME Secton XI (Table IWB-2500-1) indicated that the acceptance criteria was under the course of J
preparaton p
In order to determine the character of the flaws identified, supplemental examinabons j
i (lWB-3200) were performed using destructive test techniques. The results of these l
examinstons were evaluated using supplemental acceptance standards which were i
j specifically developed for these examinatens. The results of these evaluations indicated that expanding the sample population of CRD cap screws (lWB-2430) examined was not i
required.
j All CRD Flange Cap Screws used as replacement bolting during RO12 have received a l
VT-1 (botting )inspecton.
I i-The Authority is re-instituting VT-1 inspecbon requirements for all CRD Flange Cap Screws when the CRD Flange is disassembled and continuing GE SIL No. 483, Recommended acbons on all reinstalled or cracked cap screws. A root cause analysis j
was conducted to identify and correct procedural defincsoneses and to prevent j
reoccurrence, i
The RPV Bottom Head and CRD Flanges were visually examined (VT-2) for leakage i p during the system leakage pressure tests (no leakage detected), which provides
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reasonable assurance of the continued inservice structural integrity.
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A copy of this position along with the plant specific analysis for JAF will be submitted to 1
the NRC by September 1,1997.
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CERTIFICATION IQUALIFICATIONS l
e' Personnel
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i-All personnel performing NDE examinatens were certified and qualified in accordance with their company's approved QA Manual and Certification Program which was reviewed and accepted for use. Additionally, all NYPA personnel were certified in accordance with j
the Authonty's Quality Assurance NDE Program. All personnel performing IGSCC-related i-exawdn.uuns (i.e.: detecton, sizing, and overlay repairs) have been qualified through the i
EPRI PDI Qualificaten Program and/or EPRI's lGSCC Qualification Program.
Certifications and qualifications are available for review upon request.
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'a Equipment j-Certifications and qualifications for NDE equipment utilized in the performance of 191 and IGSCC examinstons were reviewed and approved for use by NYPA and/or through the EPRI PDI qualification process. Certifications for equipment are available for review upon request o
Temperature Gaugea Magnetic Particle Equipment Ultrasonic instruments Ultrasonic Transducers Ultrasonic Calibration Blocks l
Beam spread plots for transducers used for Reactor Pressure Vessel examinations and for those employed in conjuncton with Reg. Guide 1.150 Rev.1 (RF Waveforms are available for review).
m Materials NDE materials utilized during ISI activities were reviewed and approved for use by the NYPA cognizant Level lli. The material certificeNns covered by this statement are:
Magnetic Particle Powder Liquid Penetrant Materials -
l-i Ultrasonic Couplant j
VI.
PROCEDURES Procedures'used for performing nondestructive examinations of welds and components were prepared in accordance with ASME Secten V and XI,1980 Edition up to and including Winter 1981 Addenda. When the above referencing codes did not apply, acceptable NRC and industry.
' standards were used (i.e.: IGSCC Exams, RPV Shroud Exams).
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IN-VESSEL INSERVICE INSPECTION in-Vessel Visylinspection in-Vessel visual examinations were conducted inside the RPV by GENE utilizing personnel certified and qualified to ASME Sechon V and XI, who also met the guidelines as outlined in BWRVIP 'Starxiards for Visual inspectons of Core Shroud, and of Core Spray Piping, Spargers, and Associated Components", (two separate documents). Per requirements of these documents, NYPA conducted specific training for all inspechon personnel addressing plant specific procedural requirements, core shroud and core spray configuration details, previous inspechon results, inspechon procedures, and any other pertinent informabon related to all inspechons on the checklist, acceptance criteria and contingency plans, with emphasis on core shroud and core spray enhanced visual inspechons. Enclosure 8 provides a summary report of examinaten results, the in-vessel visual inspechon checklist of work performed, and the summary report of a -
meeting with NRC Residents at the FitzPatrick Plant on November 14,1996, to review core shroud inspection results. All relevant indications recorded during the IWI examination were satisfactorily disposeboned in accordance with NYPA's intemal tracking system, and were found acceptable forcontinued operaton Vill.
SECTION XI REPplR AND REPLACEMENTS Seebon XI repairs and replacements were conducted in accordance with James A. FitzPatrick's Repair and Replacement Program, Administrative Procedure (AP-05.14). All activities were performed in accordance with this program and are controlled, tracked and retrieved through the 5.
plant's work control system. There were a total of eight-six (86) Sechon XI repairs and /or replacements conducted during the RO12, all of which were reviewed and signed off by the designated ISI Engineer and Authorized Nuclear Inservice inspector (ANil) as required.
IX.
PRESSURE TESTING ISI pressure testing is conducted in accordance with Plant Procedure PSO-31B and the ISI Pressure Test Program at James A. FitzPatrick as defined in Engineering Report JAF-RPT-MISC-00658, Rev. 3. Scheduling and actual testing is implemented through the Operations Department's Surveillance Test Schedule and Surveillance Test Procedures (ST).
ISI pressure testing required and completed for the Second Ten-Year Interval is tracked through the JAF ASME XI Pressure Test Performance Matrix which is maintained by the JAF Technical Services Department. The Authority has adopted Code Case N-498, as approved by the NRC Reg. Guide 1.147, at JAF in lieu of hydrostatic testing for C; ass 1 and 2 systems. There is also an NRC-approved relief request for the implementation of Code Case N-498-1 for Class 2 and 3 systems. Testing required based on the NRC-approved relief request for Code Case N-498-1 along with all required pressure testing, which closes out the Second Ten-Year Interval, has been completed.
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SNUBBERS h
Snubbers arc inspected in accordance with the JAF Technical Specifications. Control and
. implementabon of the Snubber inspection Program is conducted through the JAF Maintenance Department as discussed in the ISI Prograrn Relief Request (R8). The listing of individual components and examinations conducted during RO12 are in the NYPA Miscellaneous Checklist.
4 XI.
FEEDWATER NOZZLE LEAKAGE MONITORING SYSTEM i
F The'Authonty, per NYPA letter, JPN-94-031, dated July 19,1994, is submitting the operating status of the Leakage Monitoring System (LMS) and the measured leakage for the Feedwater Nozzles at James A. FitzPatrick.
Laakage Monitonng System A Leakage Monitoring System (LMS), that monitors for feedwater leakage past the sparger thermal sleeve seals, was installed on all four nozzles at FitzPatrick in the spring of 1992.
Maintaining bypass leakage levels less than about 0.5 gpm assures that fatigue usage is minimized. Measured leakage rates in excess of 0.5 gpm is evaluated to determine its impact on the fatigue usage factors in order to cahbrate the leakage monitoring system for the actual conditions in the annulus between the thermal sleeve and the feedwater nozzle, a finite element analysis of the nozzle
'O configurabon was performed. The analysis used the FitzPatrick feedwater nozzle and safe-end geometry. In the annulus region, the heat transfer coefficient was varied to reflect varying leakage rates. In this manner, resistance temperature detector (RTD) indications are correlated to thermal and leakage conditions in the annular region.
Currently, the LMS RTD data from the past operating cycle confirms acceptable bypass leakage levels for all four feedwater nozzles. The RTD data from the A, B, and D nozzles confirms the readings are still consistent with zero or very small leakage. For Nozzle C the previously estimated leakage of 0.75 gpm has decreased to approximately 0.5 gpm.
The predicted 40-year cumulative fatigue usage is unchanged from the previous studies for Nozzles A, B, & D. For Nozzle C, with the previously assumed leakage of 0.75 gpm, the resulting contribution to 40-year cumulative fatigue usage still remains at about 0.28. This is based on '
Figure 4-131 of GE-NEDE-21821-02.
j CONCLUSION J
The recent data does not indicate a trend of increasing leakage at any nozzle. The predicted 40-year cumulative fatigue usage remains the same.
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FEEDWATER l(OZZLE INSPECTIONS INUREG 06191 Inspechons conducted on Feedwater Nozzles to satisfy NURFG 0019 during RO12 were conducted by performing inspechons on Zones 1, 2; & 3: These inspechons are in accordance with NYPA Letter JPN-94-031, dated 7/19/94, which details the extent of exarninabon coverage performed during the 1990 Refuel Outage.
The Authonty will continue to follow our present commtments:
- 1. UTinspection of Zones 1,2, & 3
- 2. Visualinspechon of the spargers and nozzles every forth refuel outage
- 3. Delebon of the PT exam on the inner nozzle bore. This is an approvert attemative based on the NRC Letter, TAC No. M89950, dated 10/21/94.
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4-NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
DOCKET NO. 50-333
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ENCLOSURE 1 2'
i FORM NIS-1 OWNERS DATA REPORT FOR INSERVICE INSPECTIONS i:..
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. FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules (3
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- 1. Owner New York Power Authority, 123 Main St., White Plains, NY 10601 (Name and Address of Owner)
- 2. Plant James A. FitzPatrick N.P.P., Box 41, Lycoming, NY ~13093 (Name and Address of Plant) 3, Plant Unit 1
- 4. Owner Certificate of Authorization (if required)
N/A
- 5. Commercial Service Date 7/28/75
- 6. National Board Number for Unit 20764
- 7. Components inspected See Enclosure for Specific Components Inspected Manufacturer Component or Manufacturer or installer State or National Appurtenance or installer Serial No.
Province No.
Board No.
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Reactor Pressure Vesse l GE/CE CE-66108 N/A N/A Piping Systems N/A N/A N/A i
Kellogg / RCI / GE JFI GE N/A N/A N/A RPV Internals CE N/A N/A N/A RHR Ht. Exch.
Perfex N/A N/A N/A l
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Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,
(2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
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This form (E00029) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y. 10017 i
FORM NIS 1 (back)
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- 8. Examination Dates 8/27/96 to 12/15/96 9. Inspection interval from 7/85 to 9/97
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. Status of current interval and work are included in Summary Report
- 11. Abstract of Conditions Noted See Summary
- 12. Abstract of Corrective Measures Recommended and Taken
( See Summary)
We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken confor to the rules of the ASME Code,Section XI.
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Date 19 Signed By u
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p v g Owzer NA VM Expiration Date Certificate of Authorization No. (if applicabic)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of M YBAE and employed by /ft144/gF47 h'df 7718 G of d a y/A v) M A have inspected the components described in this Owners' Data Report during the, :riod
//-4 ff to /2-2/- 84
. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.
Date MMZ 19 N
(,fs Commissions NE Y$bb }D'AfAf Al I.
" Inspector's Signature National Board, Sta'te, Province and No.
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ISI REPAIR / REPLACEMENT
SUMMARY
ISI COMPONENT REMARKS CONTROL ROD DRIVES
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d CRD 02-23' COMPONENT REPLACEMENT INC. BOLTING CRD 02 COMPONENT REPLACEMENT INC. BOLTING CRD 1047 COMPONENT REPLACEMENT INC. BOLTING CRD 18-47 COMPONENT REPLACEMENT INC. BOLTING CRD 22-39 COMPONENT REPLACEMENT INC. BOLTING CRD 22-43 COMPONENT REPLACEMENTINC. BOLTING CRD 30 COMPONENT REPLACEMENT INC. BOLTING CRD 30-47' COMPONENT REPLACEMENT INC. BOLTING CRD 34 COMPCNENT REPLACEMENT INC. BOLTING CRD 38-27 COMPONENT REPLACEMENT INC. BOLTING CRD 46-31 COMPONENT REPLACEMENT INC. BOLTING CRD 18-03 COMPONENT REPLACEMENT INC. BOLTING CRD 26-31 COMPONENT REPLACEMENT INC. BOLTING CRD 10 COMPONENT REPLACEMENT INC. BOLTING CRD 22-35 COMPONENT REPLACEMENT INC. BOLTING CRD 26 COMPONENT REPLACEMENT INC. BOLTING CRD 30-23 COMPONENT REPLACEMENT INC. BOLTING V
CRD 38-19 COMPONENT REPLACEMENT INC. BOLTING CRD 06-19
- COMPONENT REPLACEMENT INC. BOLTING CRD 14 COMPONENT REPLACEMENT INC. BOLTING CRD 30-27' COMPONENT REPLACEMENT INC. BOLTING CRD 06 COMPONENT REPLACEMENT INC. BOLTING CRD 02-19.
BOLTING REPLACED CRD 14-11 BOLTING REPLACED CRD 18-07 BOLTING REPLACED CRD 18-15 BOLTING REPLACED CRD 18-39 BOLTING REPLACED CRD 22-03 BOLTING REPLACED CRD 22-07 BOLTING REPLACED CRD 22 27 BOLTING REPLACED CRD 22-31 BOLTING REPLACED CRD 26-03 BOLTING REPLACED CRD 26-39 BOLTING REPLACED CRD 38-23 BOLTING REPLACED CRD 42-23 BOLTING REPLACED CRD 42-31 BOLTING REPLACED CRD 46-11 BOLTING REPLACED CRD 46 BOLTING REPLACED Page 1
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Vt.LVES AND VALVE BOLTING 7
29AOV-800 VALV~ OVERHAUL FAOV-80A VALVE vVERHAUL 13MOV-16 VALVE OVERHAUL
- 4V-111B VALVE OVERHAUL 1~ 6.OV-18 VALVE OVERHAUL 4
29AOV-80B VALVE OVERHAUL 29AOV-86D VALVE OVERHAUL 29AOV-86A VALVE OVERHAUL 12MOV-15 VALVE OVERHAUL 02RV-71J VALVE OVERHAUL 02RV-71C VALVE OVERHAUL 02RV-71D VALVE OVERHAUL 02RV-71A VALVE OVERHAUL 02RV-71K VALVE OVERHAUL 02RV-71H VALVE OVERHAUL 02RV-71L VALVE OVERHAUL 02RV-71B VALVE OVERHAUL 02RV-71F VALVE OVERHAUL 02RV-71E VALVE OVERHAUL 02RV-71G VALVE OVERHAUL O,.
COMPONENT REPLACEMENT
.m o 10RV-41B '
VALVE REPLACEMENT 46RV-112A VALVE REPLACEMENT 46SWS-120K VALVE REPLACEMENT 46SWS-127B VALVE REPLACEMENT 46SWS-708 VALVE REPLACEMENT 46SWS-71B VALVE REPLACEMENT 46ESW-10B VALVE REPLACEMENT 46ESW-28B VALVE REPLACEMENT 46ESW-121B VALVE REPLACEMENT 13MOV-131 VALVE REPLACEMENT 23MOV-16 BOLTING REPLACED PIPE SUPPORT REPAIRS PFSK-8953 RHR SUPPORT PFSK-1875 MAIN STEAM SUPPORT PFSK-4858 MAIN STEAM SUPPORT PFSK-3334 HPCISUPPORT PFSK-2156 RHR SUPPORT BFSK-893 RB SERVICE WATER SUPPORT PFSK-3260 CRD SUPPORT H46-165 SERVICE WATER SUPPORT Page 2
PIPINGNALVE REPLACEMENTS 10-16"-WS-151-208 RHR SERVICE WATER SYSTEM 46-8"-WES-151-1168 EMERGENCY SERVICE WATER SYS. -
13-4"-W22-902-4 RCIC SYSTEM UNIT COOLER 66UC-22B RB SERVICE WATER SYSTEM INLET PIPING BONNET RELIEF LINE HPCI SYSTEM FOR 23MOV-19 BONNET RELIEF LINE RCIC SYSTEM FOR 13MOV-21 10MOV-898 REPLACE RHR SYSTEM VALVE 10MOV-89A REPLACE RHR SYSTEM VALVE 46-2"-WES-151-118 SERVICE WATER SYSTEM
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NEW YORK POWEL AUTHORIfY JAMES A. FITZPATPJCK NUCLEAR POWER PLANT DOCKET NO. 50-333 I
ENCLOSURE 2 1
ISI EXAMINATION
SUMMARY
O O
r GE INSPECTION SERVICES
SUMMARY
OF.
0 INSERVICE INSPECTION EXAMINATIONS.
a PERFORMED FOR NEW YORK POWER AUTHORITY-
-JAMES A. FITZPATRICK NUCLEAR POWER PLANT INTRODUCTION During the last quarter of 1996, General Electric Nuclear Energy Inspection Services performed inservice Inspection (ISI) and Erosion Corrosion (EC) of specific ASME Class 1,2 and 3 vessel and piping components at the New York Power Authority (NYPA)
James A. Fitzpatrick (JAF) Nuclear Power Plant. These exan ~ nations were conducted in accordance with Purchase Order No.C95 20083 and were performed to the applicable O'
plant Technical Specifications and the ASME Boiler and Pressure Vessel Code, Section' XI, " Rules for Inservice Inspection of Nuclear Power Plant Components",1980 Edition up to and including the Winter 1981 Addenda.
j Alll Inservice: Inspection activities were performed in accordance with controlled Checklists developed by NYPA ISI Engineering.
The inspection checklists were generated in accordance with JAF's Second Interval,10 Year ISI Program Plan, and reflected the examination requirements within applicable sections of the 80/W81 ASME Section XI requirements, as well as, Regulatory Augmented requirements, incorporated by the plant's adoption of NUREG 0313 (IGSCC examinations), NUREG 1.150, Appendix-'A, as modified by the Ad Hoc Committee (reactor pressure' vessel examinations) and Regulatory Guide 0619 (Examination of BWR Feedwater Nozzle and CRD Return line Nozzle Cracking).
The nondestructive examination (NDE) methods utilized were conducted in conformance with ASME Sections V and XI methodology, for visual (VT), magnetic particle (MT), -
liquid penetrant (PT) and ultrasonics (UT) examinations, during volumetric examinations and thickness measurements in support of flow accelerated corrosion detection.
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i GE INSPECTION SERVICES
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!' V The organization of the JAF's RFO 12 ISI/EC Final Report, is as follows:
- 1. Summary of the ISI and E/C activities l
Owners's Reports for Inservice Inspections, Form NIS-1 i
- 2. Final revision ofcontrolled ISI Checklist
- 3. NDE personnel qualification records
- 4. NDE equipment and materials records
- 5. Final revision of approved NDE Procedures l
- 6. ISI examination Data Reports
- 7. NYPA generated Miscellaneous Examination reports
- 8. E/C Examination Summary
- 9. Final revision of controlled E/C Checklist
- 10. E/C examination Data Reports Section 1
SUMMARY
OF ISI and E/C ACTIVITIES The Summary report section provides a general overview of the workscope and examination results. Additionally, each sections provides a description for each of the subsections covered, together with the supporting documentation and/or
)
applicable referenced report (s).
As required by the provisions of ASME Section XI, Appendix II, section 1.2 contains copies of completed Form NIS-1 " Owners Report For Inservice Inspecticn".
Section 2 ISI CHECKLIST The los Checklist was developed in accordance with the Plant's Second 10 Year ISI Program Plan, Plant Technical Specifications, ASME Section V and XI, and NUREO 0313, revision 2 for UT IGSCC and weld Overlay examinations.
The checklists identified the component scheduled for examination by referencing the plant system, applicable ASME XI exam category and item number, NUREG 0313 augmented category, system's ISI isometric, NDE examination method, required procedure and the applicable UT calibration standards.
The ISI Checklist provided space for the identification of the exam's Data Report number, date of exam, site work request (WR) and for remarks.
The checklist was used for controlling the workscope, scheduling purpons, as well as l
tracking of exams' progress.
l p/
The final revision of the controlled ISI Checklists are located within Section 2 "lSI
-C Checklist", of this report.
2
GE INSPECTION SERVICES im Section 3 ISI NDE PERSONNEL 1
This section contains the RFO 012 ISI NYPA/GE Organization, as well as, a matrix of Nondestructive examination (NDE) personnel, and copies of the supporting Qualification and Certification records.
The GE NDE personnel were qualified and certified in accordance with General Electric Procedure 386HA480 " Procedure for the Examination and Certification of Nondestructive Examination Personnel".
i-Personnel qualifications satisfied SNT-TC-1 A 1975, as well as, special qualifications such as, NRC Generic Letter 88-01, implemented by the Electric Power Research Institute (EPRI), NDE Center for UT Operator Training for the Detection and Sizing of Intergranular Stress Corrosion Cracking (IGSCC), Weld Overlay, as well as, Performance Demonstration Initiative Program (PDI), in accordance with Section XI, Appendix VIII.
ISI and E/C NDE Personnel which have participated in the exams at JAF's RFO 12, together with all applicable supporting records of certification, (PDI, IGSCC etc.) are listed in alpha numeric order within Section 3 " Personnel Certifications", of this report.
1 O Section 4 NDE EQUIPMENT / MATERIALS U
Certification records pertaining to the nondestructive examination (NDE) equipment, such as ultrasonic instruments, transducers, surface thermometers, and reference calibration standards, such as IlW Blocks, Step Wedges and magnetic Yoke Lift Bar, as well as, conmaable such as UT couplant, and Liquid Penetrants employed during the
. performance of the required examinations are indexed within Section 4 i
" Equipment / Material", of this report.
In the case of the ultrasonic instruments employed in support of the E/C Exams, the i
required initial and final instrument linearity's are located with the annual electronic calibration data for each instrument.
Section 5 NDE PROCEDURES The required examinations were performed utilizing approved procedures encompassing various NDE methods including visual (VT), liquid penetrant (PT), magnetic particle (MT) and ultrasonic examination (UT). The examination procedures were reviewed and approved prior to use by General Electric Level III, NYPA Quality Assurance p
representative personnel and the Authorized Nuclear Inservice Inspector (ANII).
All examinations were performed in accordance with approved procedures.
3
GE INSPECTION SERVICES e o '
" A complete index together with copies of the approved procedures are contained within l
L Section 5 " Examination Procedures", of this report.
s j
j-Section 6 ISI EXAMINATION DATA
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l' The ultrasonic examinations are summarized in an " Examination Summary Sheet".
j.
The Summary sheets identify:
i Weld's system, unique weld number, weld type and configuration Examiner's ID, ASNT Level and exam's NDE Procedure l
Reference (s) to applicable; UT Instrument Linearity-
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Supporting UT Calibration Sheet (s)
A detailed report on the observations regarding the examination's Coverage Surface conditions
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Previous exams
[
Supplemental scans Examination results-Disposition of recorded indications f
J.
The Examination Summaries were used to compile the entire record of the examination, and a unique summary number was entered in the ISI Checklist for tracking.
Examination Summary Sheets were reviewed by GE's Level III, NYPA NDE representatives and the ANII.
Section 6.1 EXAMINATION RESULTS As a result of the examinations performed to support Refueling Outage 12 at the J.A.
Fitzpatrick Nuclear Power Plant, in accordance with the ISI Checklist, five examinations with recordable indications were reported to the NYPA ISI Engineer.
e' RCIC Weld no. FW-74: The original Magnetic Particle examination of this weld resulted in the recording of a 2.20" long linear indication. This condition was documented on DER %-1448. The indication was removed by surface preparation and reexamined. The results were no recordable indications.
' RCIC Weld no FW-74A: During the ultrasonic examination of this weld 10 e
recordable indications were noted. The indications were evaluated as slag and lack of fusion (construction defects) and documented on DER 96-1472. As a result of further evaluation the weld was cut out and replaced.
4
t GE INSPECTION SERVICES
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NYPA performed radiography on the new replacement weld.
Recire Weld no.12-02-2-66: Initial examination results from the ultrasonic examination of this weld were reported as recordable indications. The indications.
were further evaluated and classified as root geometry. Reexamination of this weld is schedule for next refuel outage.
'.. Recirc Weld no. 12-02-2-13: Indications present in this weld were initially reported as root geometry as a result of the ultrasonic examination. Further evaluation concluded that the nature of the indications was inconclusive but did not exhibit any measurable
- through wall dimension. The weld is' scheduled for reexamination next refuel outage.
.- Weld no. VC-TH-1-2 : As a part of the origina' examination scope two areas of the top head dollar plate weld where previously recorded rejectable indications were present, were examined for comparison with previous data. Document No., JAF-
- RPT-MISC-02633,"Evahiation of Ultrasonic Indications in RPV Closure Head Weld VC-TH-1-2 " contains copies of the completed < valuation. The re-examination and subsequent evaluation results were evaluated r s no significant change in the size or location of the reflectors was noted.
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.1 Section 6.2 ' ~ LIMITED EXAMINATIONS During the examination sequence areas oflimited examination coverage were reported on three occasions:
These welds are support lugs on the RHR "A" heat exchanger and the bottom edge q
of these lugs was restricted for full examination coverage by a whip restraint.
The areas in question received a supplemental dye penetrant and visual examination.
u The calculated examination coverage achieved is 70%,83%,81%,'and 80% of the
- attachments, respectively.
RHR Wed nos. 24-10-142,24-10-143 and 24-10-144: The required ultrasonic examination of these welds was severely limited due to component geometry (valve to tee etc.). The examination was performed and documented as a "best effort".
Jet Pump Instrument Weld no. N8A-SE3: The ultrasonic examination of this weld was restricted by a welded code plate on the end cap side of the weld. After performing supplemental scans to achieve maximum coverage, the reported coverage
. was calculated at 96.45%.
5
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GE INSPECTION SERVICES The extent of ultrasonic examination of the four RPV N 4 Feedwater Nozzles inner radii, Zones 1,2 and 3, were performed in accordance with US NRC, transmittal letter No.,
TAC #M89950, dated October 21,1994, which adressed NYPA's Inquire letter No.,
JPN 94-031, dated July 19,1994 " NUREG 0619, Inspection Program for Feedwater Nozzles at the J A Fitzpatrick NPP".
~
Additionally, an In-Vessel Visual inspections (IVVI), of the accessible in-vessel inside radius of the RPV Feedwater nozzles located at 45 and 135 were also conducted, with no reportable indications noted.
Section 6.3 NON-CONFORMING CONDITIONS As a result of the examination activities undertaken at J. A. Fitzpatrick NYPA site Quality Assurance personnel initiated 3 DERs addressing procedural non-compliance in j
relation to ultrasonic examinations. General Electric personnel in tum initiated 5 separate Non-conformance Reports to document corrective action and root cause of these
- incidents.
Copies of the NCRs and supporting close-out documentation can be located within Volume 3. Section 6.3 of this report.
Section 7 NYPA MISCELLANEOUS REPORTS 1
In addition to the GE workscope, several examinations were performed by NYPA QA/QC representative personnel.
NYPA. generated data reports are located within Volume 3, Section 7 " NYPA Miscellaneous Data", of this report.
Section 8 E/C EXAMINATION
SUMMARY
The Erosion / Corrosion examinations were performed in accordance with applicable E/C
' Examination Checklist. The information used to develop the E/C Checklist was provided by NYPA. The JAF E/C Program follows NRC I.E.Bulletin 87-01, Generic Letter 89-13, EPRI's CHEC and CHECMATE computer program, as well as, knowledge of previous problem areas and plant operating conditions.
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GE INSPECTION SERVICES
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G E/C EXAMINATION RESULTS As a result of the E/C examination conducted during RO-12, there were twenty-six (26)
Indi. cation Notification Report Numbers (INRs). NYPA's E/C Engineer representative generated site Deficiency Engineering Repons (DERs) for further evaluation ~ of the i
reported conditions.
A tabulation of all DERs, INRs, with applicable site Work Requests (WR), and affected components, compliled by system and line number are contained within "RO-12 Refuel Outage E/C DER Summary Table", in Volume 4, Section 8 " Summary of E/C Examinations Performed for NYPA JAF", of this report.
Section 9 E/C CHECKLIST The contiolled E/C Checklists identified component's system, exam location ID, system drawing and/or line number, manual or automated examination technique, and provided for the identification of exam's Data Report, Indication Report, Deficiency Engineering 7(V Reports DERs, site work request (WR) and Remarks, as well as, component's Nominal and Minimum thickness.
The E/C Checklist was used for controlling the workscope, scheduling purposes, as well as, the tracking of exams' progress.
The final revision of the controlled E/C Checklists are contained within Volume 4, Section 9 "E/C Controlled Checklist", of this report.
Section 10 E/C EXAMINATION DATA The report identification, such as Report # JAF-FAC-EDS/CDS-046, is representative of GE's E/C exams unique identification, i.e., plant site (JAF), type of exam, i.e.,; flow accelerated corrosion (FAC), unique numerical Examination Data Sheet (EDS), and the supporting UT instrument's Calibration Data Sheet.
The E/C repon number were entered within the E/C Checklists. Copies of the completed exams are filed by systems, as reflected by the controlled E/C Checklist, and are contained within Volume 4, Sections 10 "E/C Examination Data", of this report.
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NEW YORK POWER AUTHORITY l
JA.W!S A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i
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ISI CHECKLIST Date:
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SYSTEM:
Reactor Pressure Vessel Head (02) Area of Existing Indication Only RO12 NDE METHOD iso CALIBRATION DATA i
tion Cat 313 U
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RPV HEAD VC-TH-1-2 B-A B121 N/A MSK-3036 A45*S OT-FPK-300Vo 38 11/12//96 R-022 WR896-02164-00 C-45's UT-FPK-300Vo 11/12/96 R-022 A-e0*S UT-FPK-300Vo 11/12/96 R-022-C40's UT-FPK-300VO 11/12/96 R-022 A
UTfPK-300Vo 11/12/96 R-022 Thickness Only
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NOTES: Examinations are to be conducted in the area of the existing Indication.
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Reactor k ' 1-M System (02-2) Circ. & Long Seem WeMs RO12
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11/11/96 R406 NOTES:
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SYSTEM:
l Reactor Rec.ird.ation System (02-2) Cire. & Long Seam Welds RO12 l
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11/14/96 R-010 GE-PORH JPK-12-02-2-5m1 B-J 89.12 A-1 MSK-3002 A45'S 2VO 8
11/14/96 R-010 N
c45*S 11/14/96 R-010 GE-PDMIT-FPK-1242-2-59-1.S2 B-J 89.12 A-1 MSK-3002 A45's 2VO 6
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NYPA PROGRAM ENGINEERING ISI CHECKLIST Dete:
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Propet J.A. FitzPatrick N.P.P.
SYSTEM:
l Reactor Recirculation System (02-2) Overlay Weids i
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SYSTEM:
. Reactor Recwculation System (02-2) Oveday Welds RO12 '
NDE METHOD i
Iso CALIBRATION DATA Weld or item Exam item NUREG NDE DATE Drawing SURF.
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SYSTEM:
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MSK-3002 AetfL NDEP-9 4-25(4 47 1119/96 R408 WR895-08596-00 C8tfL 11MW96 R-006 NOTES:
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SYSTEM:
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Project J.A. FitzPatnck N.P.P.
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Control Rod Drive (CRD) 03 Nozzle Cap' Weld RO12 NDE METHOD DATA Weld or item Exam item NUEG NDE DATE ident4caton Cat.
No.
0313 PROCEDURE COMPLETED Number UT REQUIRED NUMBER PT MT 1
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Rev.3 Page 12
_. -. -.~
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NYPA PROGRAM ENGINEERING i
ISI CHECKLIST Dese:
i Project J.A. FitzPatnck N.P.P.
SYSTEM Residual Heat Removal Heat Exchanger (RHR)'10 RO12 i
NDE METHOD
[
l leo CALIBRATK)N DATA Wold or item Exam
. Item '
gg ROCKS T
RE N Idenbecation Cat.
No.
0313 PROCEDURE COMPLETED UT RE N R
2 3
i i-Sup-1A C-C C3.10 MSK-3037 X
MT-FN100vt 11/18#98 R-031 WR996-01844-00 l
X NDEP-9.5-1(J) 11/18/96 R-031 I
X PTTPK-100V1 11/18/96 R-031 Sup-2A C-C C3.10 MSK-3037 X
MT-FN100vt 11/18t96 R-031 WR99641844-00 j
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NDEP-9.5-1(J) 11/18196 R-031 l
t X
PT-FPK-100V1 11/18t96 R-031 Sup-3A CC C3.10 MSK-3037 X
MT-FN100vt 11/18/96 R-031 WRf96-01844-00 f
X NDCR* 5-1(J) 11/18#98 R-031 f
I X
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POEP-9.5-1(J) 11/18196 R-031 i
X PT-FPK-100V1 11/18/96 R-031 k
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NOTES:
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Page 13
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SYSTEM:
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O NYPA PROGRAM ENGINEERING ISI CHECKLIST Does:
Pro,ect
.A. FitzPatnck N.P.P.
SYSTEM:
Reactor Core Isolation Coohng (RCIC)- 13 Cire. Welds RO12 NDE METHOD iso CAllBRATION DATA Wald or item Identificebon Code Case Dramng SURF.
VISUAL g
PROCEDURE COMPLETED Number VOL REQUIRED NUMBER PT MT 1
2 3
Pump Diecharge unos 4*-W22-002-4 SpoolPece A45*St FW Wold 74A (4" de )
N4961 Dwg.13-26 C45*S NDEP-9 44(J) 12 11/20/96 R-025 WR896-02165-00 Dwg. 6.27-17A MMfS NDEP-9 44(J) 11/20/96 R425 di UTEPK-10?VD 11/20/96 R-025 A45%
C45*S NDEP-9.44(J) 11/20/96 R-025 (fL UT4PK-102v0 11/2G96 R-025 X
MTJPK-100V1 11/20/96 R-025 Spool Pece A-es"St Field Wald 74 (6" dia.)
N-496-1 Dwg.13-26 C45*S NDEP-9 44(J) 13 11/11/96 ft-026 WR99642165-00 01 UTJPK-102VD 11/11/96 R-026 Dwg. 6.27-17A X
MTTPK-100V1 11111/96 R-026 DERW96-1448 X
11/11/96 R-026 NRI NOTES:
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Page 16
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Pmject J.A. FitZPatnck N.P.P.
SYSTEM:
Feedwater System NOZZies per RG 0619-Zones 1,2,3 4
RO12 NOE RAETHOD leo CAU9 RATION DATA Exam Cat seem No.
Draudng SURF.
VISUAL.
BLOCKS REPORT REMARKS IdentoceInn 0819 PROCEDURE COhrt ETED RE N PT MT 1
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
~-
DOCKET NO. 50-333
~~
ENCLOSURE 4 ISI EXAMINATION RESULTS & DISPOSITION O
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GE INSPECTION SERVICES l
w r
Section 6.1 EXAMINATION RESULTS As a result of the examinations performed to support Refueling Outage 12 at the J.A.
Fitzpatrick Nuclear Power Plant, in accordance with the ISI Checklist, five examinations
~~
l with recordable indications were reported to the NYPA ISI Engineer.
RCIC Weld no. FW-74: The original Magnetic Particle examination of this weld i
e resulted in the recording of a 2.20" long linear indication. This condition was documented on DER 96-1448. The indication was removed by surface preparation an'd reexamined. The results were no recordable indications.
RCIC Weld no. FW-74A: During the ultrasonic examination of this weld 10 recordable indications were noted. The indications were evaluated as slag and lack of fusion (construction defects) and documented on DER 96-1472. As a result of further evaluation the weld was cut out and replaced.
NYPA performed radiography on the new replacement weld.
Recire Weld no. 12-02-2-66: Initial examination results from the ultrasonic examination of this weld were reported as recordable indications. The indications were further evaluated and classified as root geometry. Reexamination of this weld is q
scheduled for next refuel outage.
'V Recire Weld no.12-02-2-13: Indications present in this weld were initially reported as e
root geometry as a result of the ultrasonic examination. Further evaluation concluded that the nature of the indications was inconclusive but did not exhibit any measurable through wall dimension. The weld is scheduled for reexamination next refuel outage.
Weld no. VC-TH-1-2 : As a part of the original examination scope two areas of the top head dollar plate weld where previously recorded rejectable indications were present, were examined for comparison with previous data. Document No., JAF-RPT-MISC-02633, " Evaluation of Ultrasonic Indications in RPV Closure Head Weld VC-TH-1-2 " contains copies of the completed evaluation. The re-examination and subsequent evaluation results were evaluated and no significant change in the size or location of the reflectors was noted.
l i
GE INSPECTION SERVICES r
l.
Section 6.3 NON-CONFORMING CONDITIONS l
As a result of the examination activities undertaken at J. A. Fitzpatrick NYPA site l
Quality Assurance personnelinifiated 3 DERs addressing procedural non-compliance in j
relation to ultrasonic examinations. General Electric personnel in turn initiated 5 separate l
Non-confonnance Reports to document corrective action and root cause of these
)
l incidents.
l Copies of the NCRs and supporting close-out documentation can be located within this I
section.
1 O
l 1
i
h h oE Nuclear EnergyNon Conformance Report
-t NCR No.
NCR-IFRAA-001 Project:
J. A. Fitzpatrick Project No.
IFRAA l
Reference Documents:
G. E. Procedure GE-ADM-1001 V0 l
Description of Non Conformance: (State Ccuse)
NCR. Code: 043 Cause Code:
F01 l
Pre examination Linearities were not performed prior'to the beginnin~g~ of a period of extended use as required by the referenced NDE procedure.on the following Panametric 26 DL ultrasonic instruments:s/n 92052503, s/n 93127706, s/n 93128006, and s/n 96355909 l
Initiated By:
Date: /2214,QC Supervisor: A, hDate. zg ft-9c 10CFR21 Re[ view:
/
Is, @ Is Not Reportable Signature: A. J J - -
_Date: /s-e, r c Proposed Disposition and Technical Justification:- (Attach Extra Sheets, Sketches, Etc. as Necessary)
)
Accept-As-Is @
Repair Rework Reject Other IfNot Matl. Or Items A final calibration was performed and all affected instruments were found within acceptable calibration parameters. The examinations performed were acceptable and no re-examinations are required J
Project Manger:
Date: /t./z.SQC Supervisor: A, ]& y-Date: /,i,/s. rc i
Final Dispositio'n Accept as is. Examinations were acceptable and no re-exams were required l
Date: th *ANI Review Date:/
- Client:
s Y
Date: //a-st,QC Supervisor: A, ).. A _
Date: /J-t4-M Project Manger:.
- If Required [
/
l Preventative Action:
Emphasize procedure adherence and proper equipment pre and post examination status during procedure training i
QC Approval: A,].A.
_ Date: im-fc r
l l
Disposition Completed And Non Conformance report Closed QC Supervisor: A.
Date: /*u-n t
N q
b GE Nuclear Energy -
Non Conformance Report i
\\
Project:
J. A. Fitzpatrick Project No.
IFRAA NCR No. NCR-IFlMA-002 l
Reference Documents:
GE-PDI-FPK-2VO REV.1 and GE-PDI-FPK-3VO REV. 0,,
Description of Non Conformance: (State Cause)
NCR Code: 045 Cause Code:
F01 During ultrasonic examinations utilizing the referenced procedures the searchidits.u:cd were not included on the EPRI PDI Table 1 as required (see attached Table) l l
Initiated By:
4 Date: en 9. QC Supervisor: A, IA x Date: <a4 7/r6
{
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\\
10CFR21 Review: O Is E Is Not Reportable Signature: A.1/
Date: f a /a/n
)
Proposed Disposition and Technical Justification: (Attach Extra Sheets, Sketches, Etc. as Necessary)
(
Accept-As-Is ED Repair C Rework C Reject O Other IfNot Matl. Or items EU l
Each search unit listed on the attached Table will be qualified at EPRI and included on Table 1 provided the PDI standards are met.
Project Manger)f._
e Date: aweQC Supervisor: A. 2 A -- - Date: u/e urc
/
/
/. _
Final Disposition Accept as is pending qualification results and Table 1 inclusion
- Client: M Date:/2bd%*ANI Review:
Date:/2//P/fle Project Manger:
Date: /N# SQC Supervisor: A. h = _ Date:
i u-so -pc I
- If Required f "'
Preventative Action:
Perfom PDI specific pre-job breifing for all ar>plicable technicians, evaluation personnel and custmer representative (s) prior to the start of examination activities.
QC Approval: A, h Date:
/-J-P 7 Disposition Completed And Non Conformance report Closed QC Supervisor: A. dr/# -
Date: /-J-97 e
GE Nuclear Energy Non Crnformance R: port
. NCR-1FRAA 002 12 SCC EXAMINATIONS 4
.OOCEDURE CONFIG SCOPE SEARCH UNIT T
DIA.
6
- .,LUT-3 P-E SONIC 136 RTD TRL2 AUST 60*L 2(6X14)mm
.76 17
]
PDkUT 3 P-E SONIC 136 MEGA CGD 2.25 Mhz 70*L 2(.25 X>50")
.76 12' s._
1
~'
PDLUT-2 NOZ SE SONIC-136 KBA C/ GAMMA 2.25mhz 45*S.25-
.90 5.3* OD FOLUT 2 NOZ SE SONIC 136 KBA C/ GAMMA 1.5 Mhz 39'S.50"
.90 Si'lD i
PDi-UT 2 NOZ SE SONIC-136 MEGA CGD 2.25mhz 40*L 2(.25"X50-)
.90 5.3* OD PDLUT 2.
NOZSE SONIC-136 RTD TRL2 AUST 60*L 2(8X14)mm
.90 5.3* OD PDLUT-2 LNG SM USK 7D KBA MSWS 1.5mhz 45*S.25-
.76 17 PDI UT 2 P-E SONIC 136 KBA C/ GAMMA 2.25mhz 70*S.375'
.76 12' c PDi UT 2 P-E SONIC-136 KSA C/ GAMMA 2.25mhz 60*S.375*
.76 17 PDLUT-2 PE SONIC-136 KBA C/ GAMMA 1.5rahz 45*S. 50"
.59/1.1 -
10/14 NOZ-SE 1.5/1.9 28*
PDLUT 2 ~
P-E USK70 KBA C/ GAMMA 1.5mhz 45'S.50
.76 17 PDI-UT-2 PE SONIC-136 KBA C/ GAMMA 1.5mhz 70*S.375"
.76 17 j
PDI-UT-2 P-CAP SONIC 136 KSA C/ GAMMA *.5mhz 45'S.375*
.68/1.1 5.3* OD j
P-REDUC
.70/.52 8/12/14' NOZ-SE A;
4 E: Dunng the course of exammatuns Megasonics 70 L and 40* L search uruts were used with pulser settags outside of those required by PDLUT-2 Rev. A, m 2. The settag used was 250ns. Table 2 requires a settog of 222ns. These search urwts will be qualified with a puteer settmg of 250ns and 222ns for inclusion m
. PDI Table 1.
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i 1
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Electne Power Research Institute Noncestructive Evaluation Center Leadership in Technology Transfer
- c January 2,1997
~
Mr. Richard Keck General Electric 12200 Herbert Wayne Court Hunterville, NC 28078
SUBJECT:
Generic Procedure Equipment Qualification
Dear Richard:
Per your request, NDE Center staff have performed equipment qualifications on the following search unit instrument combinations. The following combinations have been successfully
)
qualified for Depth Sizing of IGSCC flaws in austenitic piping welds utilizing Generic
(
Procedure PDI-UT-3 Rev. A.
Search Units
, Searth W. Mig. _
t Model r.
. Aape.-
" Made ~
v7Stae aW
- Pimen.t
- Shape
..'t off-lesenument ' Access JUmitf[M
((p *
- -. f ;d' TUT %Y 6.Q3h]t[' ipsog'f$ $%13)eceive[.) #K
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me
. a,. m i
MEGA CGD 70 LONG 2(.25 X 2.25 RECT 2
I I
.50) 2 RTD 1RL 60 LONG 2(B X 14) 2.0 RECT 2
I I
MM Instrument 1 7 ay. Race R
. Senech; Mig.
Model.-
. Pulser Demeping Frogmsmey",.sg,, W
. g,gg (,)
- paus.U. -
I Stavely Sonic 136 222ns 500 ohms 2.25 Off 4K 1, 2 Stavely Sonic 136 250 ns 500 ohms 2.25 Off 4K i
I I
i!m i'
Teieonone (704) 547 6100 Cnanotte North Ca'ohna 28262 1300 Ha'ris Bou6evard
+
fax i 04: 547 6168 iPo Bos 20097 Cnanone Nortn Catoma 28221:
"f*'&
+
l' L V..
' Abbreviations:
k Megasonics MEGA Longitudinal LONG RND Round Access "1" Dual Single Access "2" i
If I can be of further assistance please contact me at (704) 547-6140
}
Sincerely '
I /)
// [/
L J-f}
Il s:
j-Carl Latiolais Project Manager LevelIII Piping and Bolting Performance Demonstration ce;
. Carl Osman Gary Lofthus
. F.L. Becker -
PDI Correspondence file JAF2 Doc. DOC l
'l
' S l
O 1
1
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EPRI NDE CENTER Electnc Power Research Institute Noncestructeve Evaluatnon center Leadership sn Technology Transfe' v
1 January 2,1997 4
Mr. Richard Keck General Electric
^
12200 Herbert Wayne Coun Hunterville, NC 28078
SUBJECT:
Generic Procedure Equipment Qualification
Dear Richard:
Per your request, NDE Center staff have performed equipment qualifications on the following search unit instmment combinations. The following combinations have been successfully qualified for the detection of IGSCC flaws in austenitic piping welds utilizing Generic Procedure PDI UT-2 Rev. A.
i L)
Search Units pW'e@2 Seassei.*
N; ~ Medaly;
..Mede n smer(in
+
_[
]JAasesaw Assess g'
f1Jait#M fiV
.h 5:s c% n QQ v
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.a *.,
3a;;g
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l KBA MSWCG 45 SHEAR
.25" 2.25 RND I
2
- 1. 2 3
KBA MSWCG 39 SHEAR
.50" 1.5 RND I
2
- 1. 2 3
MEGA CGD 40 LONG 2(.25" X.50")
2.25 RECT 2
2 1
4 RTD TRL 60 ADNG 2(8 X t4)MM 2.0 RECT 2
2
- 1. 2 5
KBA MSWS 45 SHEAR
.25" 1.5 RND 1
I
- l. 2 -
6 KBA MSWCG 70 SHEAR
.375" 2.25 RND I
2
- l. 2 7
KBA MSWCG 60 SHEAR
.375" 2.25 RND I
2
- 1. 2 8
KSA MSWCG 45 SHEAR
.50" 1.5 RND I
2
- 1. 2 9
KBA MSWCG 45 SHEAR
.50" 1.5 RND l
i
- 1. 2 10 KBA MSWCG 70 SHEAR
.375" 1.5 RND I
2
- l. 2 Il KBA MSWCG 45 SHEAR
.375" i.5 RND I
2
- 1. 2 G
1300 Marns Bowievard Cmartotte Nortn Carchna 28262
- Teleonone a?O4i 547 6100 4P O Bos 217097 Charlotte North Carohna 28220 F AX 1704 547 6168
_..~
_ ~
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1 l
NEW YORK POWER AUTHORITY JAMES A, FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 l
ENCLOSURE 5 CERTIFICATIONS / QUALIFICATIONS Personnel Listing Equipment Listing O
Material Listing O
6 i.
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GE INSPECTION SERVICES i
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Section 3.4 NDE Personnel Qualification and Certification 4
Nondestructive examination (NDE) personnel were qualified and certified in accordance with General Electric Procedure 3'86HA480 " Procedure for the Examination and Certification of Nondestructive Examination Personnel".
Personnel qualifications satisfied SNT-TC-1 A 1975, as well as, special qualifications such as, NRC Generic Letter 88-01, implemented by the Electric Power Research Institute (EPRI), NDE Center for UT Operator Training for the Detection and Sizing of Intergranular Stress Corrosion Cracking (IGSCC), Weld Overlay, as well as, Performance Demonstration Initiative Program (PDI), in accordance with Section XI, Appendix VIII.
I I
Im 3
h rtTZPATRICK I
PM Rv PROJECT NO: R012 r----
TEL8
~~
(315)T494219 GENE FAXS
!315) 349,-6205 SITE NAME: James A.Fitzpatrick 268 Lake Road ISI/NDE OUTAGE PERSONNEL Oswego,NY 13126 Sec*rty Merita Hart l
l TEL8 (315) 349-6219 INSPECTION SERVICES JOB LEVEL LEVEL LEVEL LEVEL EPRIIGSCC PD1 PERSONNEL CATEGORY MT PT VT UT DET SIZ OVER DET LENG SIZ SS #
Anderson, Paul LevelIIM 11 If X
X 477-64-9663 Barrett. Chuck LeveillM 11 11 11 X
252-334854 Beck. Tim E/C Lead il ill 28646-7695 Brannin. Mike LevelllM 18 Il 11 X*
X 141 4 0-0508 Breza. Jason Leveli I
il 1-T 470 9N612 Briley, Bob Level 11 ASME 18 11 11 X.*
X 437-04-2551 si Clay. Sean LeveillM 11 11 VT-1 Il X*
X 574-88-0896 Crane. Martin Level 11 1-T I
11 X
366-72-9831 Cnbbe. Olen Level!!M 11 Il 11 + IR X
X X
250-80-2095 Curley. Ed LevelI i
11 1
061-56-4778 lie Halley Jimmy SMART DA lit lit VT1.2.3.4 Ill X
X X
461-35-2781 Harry, AJ LevelII ASME 11 II Il 11 544-64-4637 Hart. Merita Doc Specialist 513-46-2159 til Heath, Mike IVVI Leveilli Ill Ill VT1.2.3.4 Ill X
X X
185-36-6465 11 Hebert. Donna Levellt il 11 VT-1 Il X Ext.
435-72-8917 11 Hendrix. Gerald LevelllM ll Il VT1.2.3.4 X
X 450-19-5520 Jenniges. Mike LevelI i-T 1-T I
502-98-1958 Johnson. Chris ET 530-68-3965 Ill Keck Richard IVVI Levelill VT1.2.3.4 Ill 201-42-7868 -
Khan. Yousuf Projed Level 111 Ill til X
099-64-9683 Knott. Brian
, Level 11 Il 11 11 - L 477-74-2320 Pagel
- WITHOUT IGSCC 4
^
j PROJEC.
ATR9CK PM Rodolfo radlemen
~
PROJECT NO: R012 TELO (315) 349-6219 g
GENE-FAX 8 (315)349-6205 SITE NAME. James A.FitapeaH:k 2es take Road ISI/NDE OUTAGE PERSONNEL Oswe90.NY 13126 Sec~ny hk l
-l TELS (315) 349-6219 INSPECTION SERVICES JOB LEVEL LEVEL LEVEL LEVEL EPRIIGSCC PDI PERSONNEL CATEGORY MT PT VT UT DET SIZ OVER DET LENG SIZ SS #
11 Ligget. Randy LevelllM ll 11 VT1.2.3.4 II X_
521-86-7653 til Paillaman, Rudy Project Manager VT-1.3 III 077-42-0053 Paszkowski, Bob Opr il Il X
X 464-43-8496 i
PhiNips, Nathan levelI l-T 372-98 0139 Serth, Joe Levell 1
066-48-8453 il Sistek, Bob Leve!Il 11 11 VT1.2.3,4 11 197-38-9693 Taylor, Mike levelIl II ll ll N 7040 Tucker. Dave LevelI l-T l-T l-T 530 84-2298 Van Hecke, Chuck Opr il II il X Ext.
472-84-7467 Waker, Angela LevelI l-T LT l-T 2554 5-0268 Weams, Steve LevelIIM 11 Il il X
169-52-4922
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Fufferton, w,g Engineer 006-72-6469 e
V Page2 WITHOUT IGSCC
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("H GE INSPECTION SERVICES t.
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Section 3.3 NDE Personnel Signature Log l
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GE INSPECTION SERVICES l
O s
io. 4 nottocir ture=Arcarios 1
~ Certification records pertaining to the nondestructive examination (NDE) equipment, f
such as ultrasonic instruments, transducers, surface thermometers, and reference, calibration standards, such as IIW Blocks, Step Wedges and magnetic Yoke Lift Bar. as i
well as, consumable such as UT couplant, and Liquid Penetrants employed during the performance of the required examinations are indexed within Section 4 l
" Equipment / Material", of this report.
In the case of the ultrasonic instruments employed in support of the E/C Exams, the required initial and final instrument linearity's are located with the annual electronic calibration data for each instrument.
i O
5 t
GE INSPECTION SERVICES Section 4 NDE EQUIPMENT / MATERIALS j
Section 4.1 Index
-~
l 1
l Section 4.2 UT Instruments i
Section 4.3 UT Transducers i
Section 4.4 MT Lifting Standard l
Section 4.5 Thermometers i
i Section 4.6 Calibration Blocks -
Section 4.7 PT Material Certifications Section 4.8 MT Material Certification Section 4.9 Ultrasonic Couplant Section 4.10 E/C Markers O
l
,4 l
()
FITZPATRICK EQUIPMENT CERTIFICATION l
12/11/96
. ULTRASONIC SCOPES MANUFACTURER MQQEL SERIAL NUMBER DUE DATE l
STAVELEY SONIC 136P 136P1106B091353 9/18/97 STAVELEY SONIC 136P 136P991A071181 8/7/97 STAVELEY SONIC 136P-019 136P991A091220 8/7/97 i
STAVELEY SONIC 136 -
677H 12/9/96 STAVELEY SONIC 136 717 H 2/11/97 PANAMETRIC 26DLP 92052503 10/13/97 PANAMETRIC 26DLP 93127706 8/27/97 PANAMETRIC 26DLP 93128006 8/27/97 PANAMETRIC 26DLP 95236703 1/28/97 PANAMETRIC 26DLP 96346108 10/13/97 PANAMETRIC 26DLP 96355209 10/13/97 i
PANAMETRIC 26DLP 96355909 10/13/97 KRAUTKRAMER USK7D KBA-USK7-025 8/11/97 32810-2021 KRAUTKRAMER USK7D KBA-USK7-028 10/09/97 32810-2043 i
KRAUTKRAMER USK-7D KBA-USK7-032 1/17/97 32810-1823 IDILQSCAN MANUFACTURER MODEL SERIAL NUMBER D_UE DATE TERCRAD TOMOSCAN TTP10094108 6/18/97 i
i O
Page 1 of 6
~4) ym TRANSDUCERS MANUFACTURER FREQUENCY SIZE SERIAL NUMBER -
KBA-2.25 Mhz
.5" x 1.0" A14200
- KBA 2.25 Mhz
.5" x 1.0" B16153' KBA-2.25 Mhz 1.0 diameter C11862 KBA 2.25 Mhz
.50" x 1.0" F11323 KBA 1.5 Mhz'
.250" diameter F16735 KBA 2.25 Mhz
.25" diameter KB10071 KBA 5.0 Mhz
.25" diameter KB11414
-KBA-2.25 Mhz
.5" x 1.0" K29909 KBA 2.25 Mhz
.5" x 1.0" LO3129 KBA 2.25 Mhz
.50" x 1.0" L10622 KBA 2.25 Mhz
.5" x 1.0" M31148 KBA 2.25 Mhz
.5" x 1.0" M31149 KBA 1.5 Mhz
.375" diameter 00359N KBA 1.5 Mhz
.375" diameter -
0022WV -
KBA 4.0 Mhz 2(3.5 x 10)mm 04091 KBA 1.5 Mhz
.50" diameter 0 04247 KBA 2.0 Mhz 2(3.5 x 10)mm 00885 KBA 2.0 Mhz 10mm 00896 l
KBA 4.0 Mhz 2(3,5 x 10)mm 00984
- KBA, 1.5 Mhz
.50" diameter 0041RW KBA.
5.0 Mhz
.25" diameter 003RFB KBA 2.25 Mhz
.25" diameter 003PBP KBA 2.25 Mhz
.25" diameter 003YMC l
KBA 2.25 Mhz
.375" diameter 003YMJ KBA 2.25 Mhz
.375" diameter 003YMR KBA 2.25 Mhz
.375" diameter 003V8F i
1 KBA 10.0 Mhz
.375" diameter 003V8T KBA 3.5 Mhz
.5" diameter 003V8N
.KBA 2.25 Mhz
.25" diameter 003V86
[
KBA 2.25 Mhz '
.5" diameter 003W50 KBA-2.25 Mhz
.5" diameter 003WCR I
KBA' 2.25 Mhz
.25" diameter 003X5F I-i u
Page 2 of 6 a.,
8
---w-
~
-c
- :i i
l TRANSDUCERS (Cont'd) noununur L
MANUFACTURER FREQUENCY SEE SERIAL NUMBER MEGA 2.25 Mhz 2(.25" x.50") ~ ~
-80953 MEGA 2.25 Mhz 2(.25" x.50")
80954 MEGA 2.25 Mhz 2(.25" x.50")
80955 l
MEGA 2.25 Mhz 2(.25 x.50) 90968 MEGA 2.25 Mhz 2(.25" x.50")
91266 MEGA 1.5 Mhz.
.375" diameter E0357 MEGA 2.25 Mhz
.375" diameter CO272 i
MEGA 1.50 Mhz
.375" diameter CO273 PAN METRICS 5.0 Mhz
.312" diameter 19501 PANAMETRICS 5.0 Mhz
.312" diameter 19502
(
PANAMETRICS 5.0 Mhz
.2" diameter 19511 l
PANAMETRICS 7.5 Mhz
.2" diameter 29526 l-PANAMETRICS 5.0 Mhz
.312" diameter 39606 O
PANAMETRICS 5.0 Mhz
.312" diameter 59602 L/
PANAMETRICS 5.0 Mhz
.312" diameter 59604 l
' PANAMETRICS 5.0 Mhz
.312" diameter 59605 PANAMETRICS 5.0 Mhz
.312" diameter 59606 PANAMETRICS 5.0 Mhz
.2" diameter 59636 PANAMETRICS 5.0 Mhz
.2" diameter 59638 PANAMETRICS 5.0 Mhz
.2" diameter 201569 PANAMETRICS 5.0 Mhz
.2" diameter 201573 i
PANAMETRICS 5.0 Mhz
.2" diameter 201581
'?ANAMETRICS 5.0 Mhz
.2" diameter 201582 l
RTD 2.0 Mhz 2(10 x 18)mm 92-895 RTD-TRL2 AUST 2.0 Mhz 2 (10 x 18)mm 91-28 RTD-TRL2 AUST -
2.0 Mhz 2 (10 x 18) mm 88-264 RTD-TRL2 AUST 2.0 Mhz 2 (8 x 14) mm 92-332
' RTD-TRL2 AUST 2.0 Mhz 2 (10 x 18) mm 92-887 RTD-TRL2 AUST 2.0 Mhz 2(8x14) mm 94-340 RTD-TRL2 AUST 2.0 Mhz 2(8x14) mm 94-344 RTD-TRL2 AUST 2.0 Mhz 2(8 x 14) mm 94-705 lb RTD-TRL2 AUST 2.0 Mhz 2(8 x 14) mm 94-706 RTD-TRL2 AUST 2.0 Mhz 2(8 x 14) mm 94-714 l
r Page 3 of 6 I
M' d-3 ().
EQUIPAAENT j.
MTLfFTBLOCK SERIAL NUMBER l
10 LB MT LIFT PLATE CAL-10MT-002 i
THERMOMETERS CALIBRATION MANUFACTURER DUE DATE SERIAL NUMBER PTC 8/19/97 162887 PTC 8/19/97 164135 PTC
' 8/19/97 164203 PTC 8/19/97 167185 PTC 8/19/97 167282 PTC 8/19/97 167303 PTC 8/19/97 167305
(
PTC 8/19/97 167335 PTC 8/19/97 169199 Page 4 of 6
?A h
CALIBRATION BLOCKS NAME SIEEL RANGE OF S.W.
SERIAL NUMBER DEPTH HT. #470715 CAL-DPTH-037 IlW2 304 SS CAL-llW2-018 96-5542
- IlW2 304 SS CAL-llW2-020 965544 IlW2 1018 CS CAL-llW2-026 96-5532 IlW2 1018 CS CAL-llW2-027 96-5533 STEP WEDGE SS
.25-1.00 CAL-STEP-013 792395 STEP WEDGE CS
.100.500 CAL-STEP-015 STEP WEDGE CS
.100-2.00 CAL-STEP-022 STEP WEDGE 1018 CS
.050.500 CAL-STEP-024 STEP WEDGE 1018
.25-2.00 CAL-STEP-031 STEP WEDGE 4340 CS
.100.500 CAL-STEP-042 STEP WEDGE 4340 CS
.100.500 CAL-STEP-045
\\]
/
STEP WEDGE 304 SS
.100.500 CAL-STEP-057 v
STEP WEDGE 4340 CS
.25-2.00 CAL-STEP-065 STEP WEDGE 1018 CS
.050.500 CAL-STEP-071 STEP WEDGE 4340 CS
.25-2.00 CAL-STEP-079 STEP WEDGE 4340 CS
.25-2.00 CAL-STEP-080 STEP WEDGE 1018 CS
.050-2.5 CAL-STEP-082 STEP WEDGE 1018 CS
.050-2.5 CAL-STEP-083 STEP WEDGE 1018 CS
.050-2.5 CAL-STEP-088 STEP WEDGE 1018 CS
.050-2.5 CAL-STEP-093 STEP WEDGE 1018 CS
.050-2.5 CAL-STEP-095 l
WILLY 304 SS CAL-WILLY-017 m
ROMPUS CAL-RHOM-036 ss 95-5947 ROMPUS CAL-RHOM-050 cs 96-5534 ROMPUS CAL-RHOM-051 cs 96-5535 ROMPUS CAL-RHOM-044 ss 96-5539 ROMPUS CAL-RHOM-045 ss 96-5540 ROMPUS CAL-RHOM-056 cs 96-5702 Page 5 of 6
- p PTMATERIALS BATCH Ti MANUFACTURER CODE 94LO7K SPOTCHECK MAGNAFLUX--
-SKC-S CLEANER / REMOVER 94L12K SPOTCHECK MAGNAFLUX SKD-S2 DEVELOPER 94M05K SPOTCHECK MAGNAFL'UX SKL-SP PENETRANT 92A03K SPOTCHECK MAGNAFLUX SKC-S CLEANER / REMOVER 94K01K SPOTCHECK MAGNAFLUX SKC-S CLEANER / REMOVER l
94J03K SPOTCHECK MAGNAFLUX SKD-S2 DEVELOPER I
1 94F13K SPOTCHECK MAGNAFLUX SKL-SP PENETRANT MTMATERIALS BATCH TYPE MANUFACTURER 92LO34
- 1 GRAY MAGNAFLUX 93A045
- 8A RED MAGNAFLUX 94H063
- 8A RED MAGNAFLUX UT COUPLANTMATERIAL BATCH TYPE MANUFACTURER 19565A COUPLANT HUMEX O
Page 6 of 6
.--.~.. -...-
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s i
E/C MARKERS Q
CERTIFICATION LISTING
' t : T/18'9 Mark-Tex #33 Black ink Lot #187 m-=.,
Acbon Makers #44 Black ink Lot #187 Gu, i
1 9
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_. - _.... ~ _
93 :
i I
- O NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i
l i
ENCLOSURE 6 i
NYPA/QC MISCELLANEOUS ISI CHECKLIST i
l O
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NYPA PROGRAM ENGINEERING
-i 4/s /et NvP-Sce-OUS o ex-muon cN clust 1
JA FnzF. a N.P.P.
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Wald or flom idenssicamon Emen Cat.
Item Na Drameig 3
- SURF, } i/15UAL ICE PROCEDURE DATE COtrLETED DATA REPORT NURSER Number Q UT 1
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- i
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PT -MT *1B2 4
h f
M-261 (142C445-te7)
X M3EP 9.5-2 10f23fBBSWTOO7
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r M-314 (1417418-55)
X M3EP 9.5-44 11JelWSOSVTO22
[
s i
t M-418 (10-195445-122)
X NDEP 9.5-2(4 11 -
s um
't 1
M-231/310(10 RA4tS-252)
X ISEP 9.5-2 10r25ftS SWVTOM i
M-seo(2e-10-H5 39)
X NDEP S 5-44 10f3vesesVm11 M-551 (29-18446-13A)
X M3EP 9.5-2(J) 10f31Jg800VT011 M444 (02-2-1844S-17)
X EP. 5-2(4 10,3 J VT011 t
M-L501 (SPANE)
X
,OEP 9.5-2(J) 11/1JOSSOVT012 3
L M-220 (SPARE)
X NDEP 9.5-2(4 tuttee eeVT012 M-200 (SPARE)
X NDEP 9.5-2(4 11/1 JUS 00Vf012 I
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RO12 NDE METHOD leo M or M N Exem Cat item No.
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VtSUAL NDE PROCEDURE DATE COMPLETED DATA REPORT NUMBER Number UT PT MT 1
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JAF-136 (23-1SHS-15)
X POEP 952fJ) 11J82698VT025 b
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X NDEP 9 52(J) 11JtdB698VT031 M-81s (1N)
X NDEP 9 5-2(J) 11let9e 98VTO31 JAF-182 (149A44S-14)
X IOEP 952(J) 11AW96 96VTQ31 W-814 (10-W X
NDEP 952(J) 11/8#9696VT031 JAF-803 (01SE-HS-8)
X NDEP 952(J) 11AWB6 98VT031 JAF-175 MSE-HS-9)
X NDEP 952(J) 11JGd9698VTO31 JA"-174 (10-10844S-18)
X POEP 952(J) 1110/9696VT031 JAF-143 (10-10B+tS-17)
X POEP 9 5-2(J) 1110/9698VfD31 JAF-178 (10-3SNS-196A)
X NDEP 9 5-2(4 11J8tB8 98VT031 i
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X f0EP 952(J) t tJ879696VT031 JAF-117 (23-2tJLHS-102)
X NDEP 9 5-2(J) 12/3/9698VTD98 NOTES:
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NYPA PROGRAM ENGINEERING j f 7/ 7 U i NYPA/QC MISCELLANEOUS ISI EXAMINATION CHECKUST Dese: / w JA FitrPatrxA N.P.P. SYsIt:M: CRD (Cap Screws I CRD Flange Bolling) CRD(Cap Screw RO12 ICE hAETHOD j les Wold or llem leenluicotton Enem Cat. Ilom No. Droung SURF. VtSUAL NDE PROCEDURE DATA REPORT NUteER Number UT PT BfT 1 2 3 CR0 (Cap Sasus) 195 BG2 X POEP 951 10rbg898VTUO4 CRD Flange Scelhe-45 Bons 842 X POEP 9.5-1(J) 11/13fg898VTD51 CRD Flange SonMg-192 Seas 842 X NOEP 9 5-1(J) 11/14/9698VT054 CRO Flange Soning (Removed) 842 X NDEP-9.5(J) 4/23f9797SC34 i CRD Flange Bommg ptemoved) 842 X NDEP 9 5-1(J) - 4/23/97 97VTD04 ,i ? h l a I e i l l s' !N I NOTES: POssee82623 HT Code Q4X -90 Solte iPnenamaasan HT Code 13221 96 Delts; POs89484308 -46; 'M1531-162; f r A l 's _.V< WM i
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.I Page 23 h
k NYPA PROGRAM ENGINEERING ff-NYPAlQC MISCELLANEOUS ISI EXAMINATION CHECKLIST oene-7f ffU Propea: J.A. FitzPatnd N.P.P. SYSTEM: Vart0us (Repew/ Replacement) RO12 NDE METHOD ho Welt!oritem klantecellert Exam. Cat. Item No. Dramme SURF. VISUAL TOE PROCEDLAtE DATE COneLETED DATA REPORT PEJISER Number UT E MT 1 2 3 Vefue 40SWS-1218 X NDEP 954(J) 11/2MSSOVTORS value 40ESW-288 X seep 958(J) 51/1775888VT079 veme 40ESW-105 X NDEP SM(J) 11/249808VTUS2 vesse asSust27s X NDEP S 5 4(J) 11/2728 00VTOS4 Vetue 48SWS-120K X fOEP 9.54(J) 11/1995 BBVTUS2 the s 4HnAES-tst-11es X NDEP 958(J) 12NASOSVfDB7 une s 40-2"-WES-151-118 X NDEP 95e(A 12Nm3O9VTOBS une # 13 4*-W224024 X NDEP 954(A 12H148SSVT112 une 8 00-21/2"-WES-151-1 X peep 958(J) 11/2770600VTOB5 Lhe # 10-16"-WS-151-308 X NDEP S 54(J) 11/22f08SSVTOB1 vesse 10ns0V-ta4 X NDEP 958(J) 1tf222598VTO90 Support PFSK4058 X EP 952(J) i t, 0.vTOs4 Support PFSK-3200 X NDEP 952(J) 11/12fts00VT041 Support H46-185 X NDEP 952(J) 11/W8800VTO63 Support H46-195 X NDEP 95t(J) 11/14f5808VTO52 the s t3rSee-902-17 (Velme 13nsoV-13t) X poEP 9 5-1(J) 11f5fte98VT018 seOTES: / REVIEWED SY: r l e Page 24
-m..___._ ._m--._.__.--. ....m .- _. - ~. -m l - x S. / i 1 . NYPA PROGRAM ENGINEERING. 7_!T_!T7 l NYPA/QC MISCELLANEOUS ISI EXAMINATION CHECKLIST Does: Project J.A. FftrPetsi N P.P. SYSTEM: VariDus (Repair & PW) I i RO12 f 10ERETHOD leo - DATA l D M E 1 2 3 Velve 10hSOV-80A X ICEPS.RJ) 11/1848 OSS100 ' i Value10tAOV-8SA X IEEP 9_gJ) 11/17198 985100 i Volvo 10hAOV405 X feEP S 2(J) 11/12fSS maamma '5 Volvo 10tAOV408 X NDEP 9.MJ) 11113fBS 98S007 uno S 1M-W22-9024 X NDEP 3.RJ) 11/22f98 985121 b Une 813-4"-W22-902-4 X NDEP 9.1(J) 11,*22f98 988120 Unos 1W-W22-002-4 X NDEP 9.1(J) 11/23fBS 98S122 2 Vefwe 10RAOV-SSA X BWEP 95J) 11/14f98 98S100 f f Velve 1LAOV-808 X NDEP 9.RJ) 11/1348 985007 Vefue 100AOV-OSS X NDEP 9.2(J) it/ farts 988008 I value 13040V-131 X NDEP 9.1(J) 11/5/08 meenes Pdmary Contamment (Ped Eye .1 eene se uner was) X NDEP 9.2(J) 11/10fBS 985094 Unos 23-10"-SHP-902-19A T NDEP 9.5-8(J) 12f10fBS 98VT100 i Vefwe 23tAOV-18 X NDEP 9.5-1(J) 12M48 98VT100 Velve 230AOV-14 X NDEP 9.5-RJ) 12M48 SeVT101 I t h i 1 i ISDTES: 1 / l stEvanuED ev: Jean I } s -- Page 25 [ Ji i >4 i
.-.--_....-~....~.--..--.-..-.--..-.-..-.----....-...--.-..~...-.3 4 i d 4 i O I } NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT i. DOCKET NO. 50-333 - i 4 i 1 i i 4 1 1 i 2 ENCLOSURE 7 LIMITED EXAMINATIONS O O
-s [ \\ i l ( GE INSPECTION SERVICES N pg iV Section 6.2 LIMITED EXAMINATIONS During the examination sequence areas oflimited examination coverage were reported on three occasions: RHR "A" Heat Exchanger - weld nos. SUP-1 A, SUP-2 A, SUP-3 A and SUP-4A: e These welds are support lugs on the RHR "A" heat exchanger and the bottom edge. - of these lugs was restricted for full examination coverage by a whip restraint. The areas in question received a supplemental dye penetrant and visual examination. The calculated examination coverage achieved is 70%,83%,81%, and 80% of the attachm~ nts, respectively. e l RHR Wed nos. 24-10-142,24-10-143 and 24-10-144: The required ultrasonic e examination of these welds was severely limited due to component geometry (valve to tee etc.). The examination was performed and documented as a "best effort". Jet Pump Instrument Weld no. N8A-SE3: The ultrasonic examination of this weld was restricted by a welded code plate on the end cap side of the weld. After performing supplemen*.al scans to achieve maximum coverage, the reported coverage was calculated at 96.45%. O O
... ~. -... 'M NEW YORK PO'WER AUTilORITY JAMES A. FITZPATRICK NUCI F.AR POWER PLANT DOCKET NO 50-333 4 i i i sNCLOSURES IN-VESSEL INSERVICE INSPECTION in-Vessel Visual Inapection Summary -O' - In-Vessel Visual laspection Checklist. i In-Vessel Visual inspection Results & Disposition O
[ -,,g l lO h GE INSPECTION SERVICES l l J. A. FITZPATRICK RFO - l REACTOR PRESSURE VESSEL INVESSEL VISUAL INSPECTION
SUMMARY
l EXECUTIVE
SUMMARY
Invessel Visual Inspections of the J. A. Fitzpatrick Nuclear Power Plant were conducted during the twelfth refueling outage by personnel from General Electric Nuclear Energy in accordance with the provisions of New York Power Authority contract C-91-20038. The examinations were conducted in accordance with approved procedures and were completed within the allotted time schedule. All relevant indications recorded as a result of these examinations were dispositioned in accordance with site specific requirements A and were found acceptable for continued use. U Applicable contingency plans were in place for critical examinations including: Ultrasonic examination for the Core Spray Piping and the Core Shroud; a repair contingency per Mod F1-96-063 for susceptible areas of the Core Spray piping; and a contingency for returquing or replacement of the Tie Rod nuts of the repaired Core Shroud. During the performance of the IVVI examinations no Safety or ALARA violations were recorded. It should be noted that no Foreign Material Exclusion (FME) incidents occurred during the examinations. A detailed summary including all pertinent supporting documentation follows. 1 1 0000 24.s 2:70
e.q-INTRODUCTION Remote visual examinations of the James A. Fitzpatrick Nuclear Power Plant reactor pressure vessel interior and its internal components were conducted from Octob_er 30,1996 through November 14,1996 per the requirements of New York Power Authority - (NYPA) contract number C-91-20038. These examinations were conducted in accordance with ASME Section XI,1980 Edition, Winter 1981 Addenda, the J. A. Fitzpatrick RFO 12 Controlled IVVI Checklist, Revision 3, and various Augmen.ted . Inspection Commitments. 4 SCOPE OF EXAMINATIONS The scope of examinations included ASME Section XI Code Category B-N-1 Interior of Reactor Vessel, Code Category B-N-2 Integrally Welded Core Support Stmetures and Interior Attachments to Reactor Vessels, Code Category BN-3 Removable Core Support l Structures and numerous Augmented Inspections. Reference the attached Table for l specific examination component listings and examination summary details. PROCEDURES O.- All visual examinations were conducted in accordance with General Electric Procedure VT-FPK-202VI, Revision 1," Procedure for Invessel Visual Inspection (IVVI) of BWR '4 Reactor Pressure Vessel Internals" dated October 25,1996. Examination personnel t were qualified and certified in accordance with General Electric Procedure 386HA480 " Procedure for the Examination and Certification of Nondestructive Examination l Personnel". The performance of the GERIS Beltline Accessibility study was conducted in accordance with General Electric Procedure ADM-FPK-2019V0, Revision 1. l All procedures were reviewed and approved prar to use by the applicable NYPA personnel in accordance with J. A. Fitzpatrick APO-19-06, Revision 2. RECORDING AND EVALUATION The Remote Visual Examinations of the Feedwater Spargers and associated Brackets l were conducted using a Remotely Operated Underwater Vehicle (ROV) utiising a RGB l color camera. In addition the color camera fonnat was used in the hand held mode for / other examinations.
- The remainder of the required examinations were completed using ITS 1250 black and white underwater camera system equipped with twin 50 lighting. Supplemental lighting was provided for Enhanced Visual VT-1 erinations by use of a 500 watt auxiliary light. All examinations were recorded m Super VHS format video tape and
- data review and analysis was conducted either on-line in real time or post-examination by.
l 0000 .e 4 2 s 2371 2
29 ) n GE Level III and NYPA Quality Assurance Level III personnel. The results of all '_ V examinations were recorded on the applicable procedure attachments included as part of - the examination procedure. ] l^ L EXAMINATION RESULTS Access Hole Cover l The Shroud Support Access Hole Cover at 0 was examined and no recordable indications were reported. Core Spray Spargers e Examinations.were conducted on all Core Spray Spargers using the multiple pass technique. In addition all applicable Sparger support brackets and the T-Boxes were also L exam ne.d As a result of these examinations an indication characterized as weld profile i deficiency was recorded on spray nozzle D-28. The indication was documented on DER l 96-1484. The historical IVVI data was reviewed (Tape no. 94-15) and the indication was previously noted and dispositioned as acceptable for continued use. . Core Spray Piping l The Loop A and Loop B Core Spray Piping Internal to the vessel was examined in two L separate steps. The initial examination was performed to satisfy BWR VIP recommendations and entailed en Enhanced VT-1 of all piping welds after power bmshing. During the course of this examination an initial indication was reported on weld # A 21. The area in question was rebrushed and reexamined and the indication was evaluated as a surface tool mark. No other recordable ind! tions were noted. The second - portion of the examination was an MVT-1 to.001 mil resolution performed on all piping and components including the Inner Radius section of the Core Spray Nozzles @ 90 and 270. As a result of this examination no recordable indications were found. Feedwater Spargers The Feedwater Spargers and associated support brackets located at 45' and 135" were - examined using the GE Phantom remote,1y operated vehicle equipped with an RGB color camera. No recordable or reportable indications were noted during the course of the examination. The area of examination was extended to include the nozzle inner radius section.
- Guide Rod and Bracket
- The Steam Dryer Guide Rod and the Guide Rod Bracket @ 0 was examined and no recordable indications were noted, Repaired Shroud e The J. A'. Fitzpatrick Shroud was repaired during a the 1994/1995 refueling outage and L as part of the IVVI scope of examinations various areas and components of the repair i. were examined. These included Tie Rods at 15,135 and 255. In addition the Gusset welds at those locations as well as 12" of the Shroud Support to Vessel weld SH9 each i 3 0000 y4pe e372 l 1
w l i side of the Gusset were examined. No recordable indications were noted as a result of L1 ? these examinations. j i e - Shroud Vertical Welds A representative sample of the Shroud Venical and Ring Segment. welds were examined using the Enhanced VT-1 technique after power bmshing. The required examinations of L. welds SVlB, SVIE, SV2B, SV3B, SV3E, SV6A, SV7B, SV8A and SV9C resulted in no recordable indications.- During the initial examination of the ID surface of weld SV4A linear indications were reported. The weld was reexamined using multiple camera angles and enhanced supplemental lighting and the indications were evaluated as small welding l anomalies. The examination of the ID surface of weld SV5A resulted in the recording of one crack like indication which was documented on DER 96-1490. During the OD examination of weld SVSA five (5) crack-like linear indications were recorded and I documented on DER 96-1512. These crack like linear indications were assessed by NYPA with corresponding allowable criteria presented in EPRI document TR-105747, " Guidelines for Reinspection of BWR Core Shrouds" (BWRVIP -07) and with site'- specific acceptance criteria by MPR (9/96). The assessment concluded that the cumulative effect of these indications, treated as cracks, was bounded by the allowable criteria (s). The indications were measured and mapped for comparison during l subsequent examinations. I e Shroud Circumfrential Weld Shroud circumferential weld SH2 was required to be examined in two_ specific areas correlated to previously mapped ultrasonic examination data. The weld was examined from 80* to 130" and from 320' to 350 using the Enhanced VT-1 method after power brushing. The examination was performed using the RGB color camera in the hand held configuration. The results of the examination recorded two areas of crack like indications which were mapped and measured for comparison during subsequent examinations. The cracking present in this weldment is being mitigated by the Shroud Repair. e : Control Rod Drive Nozzle The nozzle inner indius section of the Control Rod Drive nozzle at 135 was examined and no recordable indications were noted. e' RPV Beltline Weld Survey As a pan of scheduled IVVI activities a survey of in-vessel clearances and positions of - various in-vessel components was conducted. This survey will be used to provide information needed to assess the ability to ultrasonically examine the Reactor Pressure Vessel horizontal'and vertical welds during a future outage. A detailed compilation of u this data will be provided under a separate report. L 1 4 o o o a.
- d. : e
? *. 7 3
a L-f Fuel Support Casting 34-07 l During the movement of Control Blades within the reactor vessel an incident occurred that resulted in the dislodging of Fuel Suppon Casting 34-07. The incident was documented on DER 96-1540 and the condition was corrected in accordance with NYPA Temporary Operating Procedure TOP-241 Rev. O. As part of the wnrective action an examination of the Fuel Support Casting was performed (not p'an of the original IVVI ~ ~ workscope). No recordable indications were noted. In addition Control Blades and IRMs - and LPRMs in the cells adjacent to location 34-07 were examined and no recordable indications were reported. Fuel Support Castings - e ' General Electric refueling personnel performed the scheduled Control Rod Blade shuffle utilizing the Remtek II tool. The use of this tool made the Fuel Support Castings in those core areas where the Control Blade was moved accessible for examination. This in process examination was performed at cell locations 18-11,'14-11, 10-27, 06-23, 10-35, 06-27, 18-27, 06-31, 18-43, 14-43, 18-35,26-47,26-43,22-47, 10-19,22-27, 18-19, 26-07,26-11,22-07,34-11,38-11,42-19,30-27,26-27,30-07,26-35,30-47,34-43, 38-43,42-27,46-23,34-35,26-31,34-19,26-23,42-35,46-27,38-27, and 46-31. As a result of these examinations no recordable indications were noted. One small piece of-foreign material was identified during tape review, located at cell location 26-43 on the core plate. The appropriate NYPA personnel were notified, the condition was documented on DER 96-1640 and the material was subsequently removed by vacuuming. 4 O 5 0 i:: O O e el. 2 8 2 6 7 el-
h P.O. Seu 41 Lycoming, NewYo,k 13083 M2morandum 1
=
- ># Authority New York Power
(_) 4 November 26, 1996 PEP-PO-96-355 i To
- Distribution From
- P. Okas Subject
- James A.
FitzPatrick Nuclear Power Plant IVVI checklist Used for RO12; Rev. 4 Attached for record purposes is a copy of the updated IVVI Checklist (Rev. 4) used during RO12. The signed-off copy of the . checklist is included in the Final IVVI Report, dated November, 1996. If th re are any questions on this, please call me at JAF x-6624. i P. Okas Sr. Project Engineer Engineering Programs ' D r )i ' ( cc: T. Dougherty, J. Flaherty, G. Hanselmann, W.
- Josiger, D. Lindsey, V. Mabry, P.
Morris, W. Rheaume, R.
- Penny, D. Ruddy, Records Sta-WPO; J. Hartigan (GE);2 (all w/ attachment) t l
~~ INSPECTION CHECKLIST GENudeerEnergy ~ James A. Fitzpatrick Station Page 1 of 4 - 19% RFl2 October 18.1996 INSPECTION STATUS - - D VVIC CKLIST REVISIONJ ,y coy i gfPROVED FOR NYPA BY: g/ M2. ~/ff (CHECK COMPLEE) (, APPROVED FOR GE B,Y:.{,_ _ m / m J .A r n u v ,,y - TYPE AUG EXAM ' PROCEDURE S CH ID REPORT NOTES GE NYPA [ [ WR COMPONENT e REQ'D No. r EXAM REVIEW s I I Access Hole Cover @ 0* 95-09419 00 W-1 SIL 462 VT-FPK-202VI Anschment I6 g Core Spray (CS) Upper C Spargers 95-09416-00 MVT-l NUREGCR-VT-FPK-202VI Attachment Il 100% of accusaible . MM f b EVT-1 (T Box) 4523 A REF.2 ,,gg, g,fg g g (Inlet T-Box 170*) OO. T' I Core Srray(CS) tower D Spargers 95-09416 00 MVT-1 NUREOCR-VT-FPK-202VI Anacluned iI 100% of.~=.='Me N EVT-I (T Box) 4323 A REF. 2 ,,gga
- ggagf, g
(Inlet T-Bom 190*) [pg$ g Core Spray (CS) NIR @ 270* 9549416-00 VT-I REF. 2 VT-FPK-202VI Anachment 10 l Core Spray (CS)NIR @ 90* 95 09416-00 ' VT-I REF. 2 VF-rPK-202VI Anachment to y[g M h { i I Core Spray (CS) Piping loop A @ 93-09416-00 MVT-1 Piping A S11239 RI S2 A VT-FPK-202VI Anschment 9 A 10 100%of itile D/pgf'(, TS.483/99 9(r* (28 welik) Components (Eltiows) RIT. 2 A 3
- weg, EVT 1 Piping welds i
and brackets to RPV t b #'" i Core spray (CS) Piping leap B @ 93-094 t MW3 MVT-1 Piping & SIL239 RI S2 A VT-rPk-202VI Anadwnent 9 A 10 100% of accessMe 270* (22 welds) Congonents(Elbows) REF 2 A 3 welds M f-#iD TS NP48 i EvT-1 Piping welds and brackets to RPV NE M I Core Spray (CS) Upper A Spargers 95-09416-00 MVT1 NUREGCR-VT-FPK-202VI Attacionent il 100%efech EVT-1 (T Box) 4323 A REF. 2 weMs pgg ] { (Inlet T-Box IO*) Core spray (CS)Lawr B Sparge's 934941640 MVT-l NUREOTR-VT-FPK-202VI Attachnwnt il 100%eface ma. g I EVT-1 (T Box) 4523 A REF.2 ,,gj, f g (Inlet T-Bos 350*) Feedwater Sparger @ 043* 95494I740 VT-3 F1-78-036 VT-FPK 202VI Attadenent ? DER 95 0957NRC 8 I P *""'"8 asuuudeness can met be irJ % (( I I j NURE006tt dage,,,d rY Feedwater Sparger @ 135' 95-09417 40 VT-3 F1-78436 VT-FPK-202VI DER 95 0937NRC ' p'>M ~ .a ,d ,e t b. NURE0 0619 dahrved y teo?H_,fsurpM : s Seeh st v + 2/ I W* ~ crlital as Ma Nb M n-BR $L na-e&g t 'h h t
i b O A Q %/ Q) INSPECTION CHECKLIST GE NudearEnergy ^ James A. Fitzpatrick Station Page 2 of 4 1996 RF12 (ktober 18,1996 CONTROLLED IVVI CHECKLIST REVISION 2 INSPEGON STATUS, (CIECK t6.,) COMPONEffr WR EXAM TYPE AUG EXAM PROCEDURE SKETCH ID REPORT NOTES GE NYPA REQ'D No. EXAM REVIEW
- I'%M Guide Rod O' Bracket Welds 95-09421-00 VT-3 VT-FPK-202VI Anac!vners 2 g/ car -<e, pg g k
Ozide Rod @ 0' 934947140 VT-3 VT-FPK-202VI Anachmera 2 fig,j,g. ec; Stroud - Gusset Plate Welds @ 015' 9640022-00 EVT-l JPN-96430 A VT-FPK-202VI Anschment 14 100%ofwelds at SOH RFFIA4 A ROV (both sides) and 12"ofweld at / each side on H9 (notal ///2ff Ng/ 24") @g M stroud - Omset Plate Welds @ 133' % 0002240 EVT-1 JPN-96-030 A VF-FPK-202VI Anacivnent i4 & 100% ofwelds at SOH REF I A 4 Drawing FW-26B A ROV (beeh sides) and 11" of weld at fh/,g gal l[( cg( I L e.ch.ide en H9 (==.I 24-) [ Stroud - Omset Plate Welds @ 253' 96-000224X) EVTl JPN-96-030 A VF-FPK-202VI Anativness 14 A 100% efwelds at SOH REF.IA4 Drawing FW-26B & ROV (both sides) and l2** ef weld et //-896 ff each side en H9(tonal 24") i strend < Ring Segmeet Weld SV3B 96-00021-00 EVT1 JPN-96-030 A VT-FPK-202VI Anschmers IS & 100%ofwelds(33%of NA gi gh I g,MyT C, REF. I A 4 Drawing FW-26B knal areas) e 3 stra u!. Ring Segreent Weld SV3E 96-00021-00 EVT 1 JPN-96-030 A VT-FPK-202VI Ana.:hmers 13 A 100%efwelds(33%er // ell' g Uh; i REF.IA4 Drawing FW-26B total areas) siiroud - Tie Rod @ 013* deg, 96400l9-00 VT-3 JPN-96430 A VF-FPK-202VI Anschmers 31 Tiereds, Aaa ma. MF / EVT-l (For Nut REF. I A 4 ADWO FV-26B loclung devices, j p,c74 h engagement only) Reference 4 critical contest seems. f stroud Tie Rod @ l35'deg, 96-00019 00 VF-3 JPN-96-030 A VT-FPK-202VI Anschmere 31 Tiereds Accountie 88 i EVT-1 (For Nut REF.IA4 ADWO FV-26B lacking devices, N 'A /ffpjy eng menienly) Rererence 4 ainic.i or ci.,s. 1 musn wc A {
O O! x 4 INSPECTION CHECKLIST GE NudserEfMfyy James A. Fitzpatrick Stationi Page 3 of 4 1996 RFl2 Ocember 18,1996 CONTROLLED IVVI CHECKLIST REVISION J INSPIKMONSTATUS ! ~ N CM, COMPONENT WR-EXAM TYPE AUG EXAM PROCEDURE ~SKETCHID REPORT NOTES GE NYPA', REQ'D ' No. j i k stvend-Tse Rodw? 255'. 964001940 YT-3 JPN-96-030 A VT-FPK-202VI ~ Anaciunent 31 & Tiereds. AcommeBit gg f EVf-l (For Nut REF.1 - DWO FV-268 lesetsne dessess, Reference 4 amiticalconnais areer g[g $-] engagesnent only) As meesd formeldM g~ b [ shroud - WeW H2 azienutts 80
- to 964002140 EVT-l JPN-96430 A VT-FPK 202VI Anacionens 15
.} REF.I ADWO FY 26B. enly. WeWtobe ~ i. 130' and 320* to 350* Wis 'p g gf M l i ,108" m Isas. stu m f w ew s Vin 964002040 EVT-1 JPN-96-030 A VT-FPK-202VI - Anacionent 15 A ' 100% weed (OD) Mb MI" '[ Ilh(g. l REF. I A 4 DWO FV26B g )pg 14 [h _ E s;m d weu sVII: 964no20m irr-1 JPN-96430 A VF-1 PK-202VI Anaclunem IS A 100% wcW (OD) [ hn REF. I A 4 DWG FV26B ggg MM .[ sim d wes sv2n % 00020 40 EVT l JPN-96-030 A VT FPK-202VI Anaciunem 15 A 100% weW(OD) l( ld[o ' Oki % { REF,1A4 DWO FV 268 - { simed weldsV4A 964002040-EVT-3 JPN-96-030 A - VT-FPK-202VI Anacionem I$ A 100% weW(ID.OD) M tQtN%( REF. I A 4 DWO FY26B / p-//% --{ shroeid weldsV5A 964002040 EVT-3 JPN-96430 A VT-FPK-202VI Anacienne 15 A 100% weW(ID.OD) i [" REFI&4 DWO FV 268 -
- 92%
g fg[y. j N# M.. simed WeldsV6A 96 40020-00 EVT-l JPN-%030 A VT-FPK-202VI Anaciunem l5 A 100% weW(ID. OD) REF l A 4 DWO FV 268 g/r/),7(,, Qgdef l i stroid weMsvm 964002040 EVT-1 JPN-964M A VT-FPK-202VI Anacionem 15 A 100% weW(OD) ^4W REF.t&4 DWO FV 268 - jgr//@(, oMSj sim.d weldsysA 964002040 EVT.1 JPN-96430 A VT-FPK-202VI Astactensnil5 A 100%==W(OD) N M REF.1&4 DWO FV268 g;./ t % ghk j l sivoud weWSV9C 964002040 EVT-1 JPN-96430 A ' VT-FPK-202VI Anaciense 15 A ' 100% weld (ODeidy) [J i g REF. I A 4 DWO FV268 pg4 g j gQkle ; s m mooc - j 1 f + 1
%). GENudearEnemy m INSPECTION CHECKLIST Page 4 of 4 James A. Fitzpatrick Station Ocsober 18,1996 19% RF12 INSPECTIONSTATUS, CONTROLLED IVVI CHECKLIST REVISION 2 (CHECK COMPfETE) COMPONENT WR EXAM TYPE AUG EXAM PROCEDURE SKETCHID REPORT NOTES GE NYPA No. REQ'D EXAM REVIEW M" b, CRD Noi71c NIR 93 49418-00 VT-I NURI.G a619 VT-FPK-202VI Attas:.._.; t9 4 VT-FPK-202VI Attactwnent I g kPY Behline Weld Survey 954942040 N/A 4 b Fuel Support Castings e/A VT-3 VT-FPK-202V1 4 MIME Sect. XI (BN-3) Note 2 IlWRVir - Giridefene for Reimpecteen of nWR Core Strouds REFERENCEI [PRI TR-105747 ( DWRVIP47). Sectim 4 (1996) REFERENCE 2 IlWRVIP Standards for " heal Inape(thm of Care Spray Piping. Spargers, and Associated Congoncrds-(1996) RFFERENCE 3 flWRVIP - BWR Core Spray Internals Impectam and risw Evaluation Guidelines (DWRVIP - 18) l TR - 106740. Revised Priect D301. DraR Regwwt. June.1996. REFERENCF. 4 Inspection and Acceptance Criteria for the Repaired Shroud, Revision 1; by ILIPR, July,1996. Will have Ultrasonic availibility for Core Shrotal and Core Spray piping NOTE 1: and NYPA Ievel III The following Fuel Support Castings were visually examined by G.E. NOTE 2: examiners; as they became accessible during Control Blade replacement: 18-11, 14-11, 10-27, 06-23, 10-35, 06-27, 18-27, 06-31, 18-43, 14-43, 18-35, 26-47, 25-43, 22-47, 10-19, 22-27, 18-19, 26-07, 26-11, 22-07, 34-11, 38-11, 42-19, 30-S, 26-27, 30-07, 26-35, 30-47, 34-43, 38-43, 42-27, 46-23, 34-35, 26-31, 34-19, 26-23, 42 46-27, 38-27 and 46-31. ,m u Ei
mmm P,4 Som 41 - , Lyoomin0. New Yodt 13003 ats 342.se40
- > New York Power mU W Authority November 14, 1996
-. PE P - PO-9 6 - 3 41. . To' R. Plasse From P. Okas Subject
- James A.
FitzPatrick Nuclear Power Plant IVVI-Core Shroud Inspection Results-RO12 Meetina with NRC Residents at JAF-11/14/96 This is to inform you that today with Bob Penny, we met with NRC Resident Inspectors R. Fernandez and G. Hunegs. The intent of the meeting was to-appraise NRC Residents of Core Shroud inspection results, and in particular,.of weld SVSA. I have attached for your information and use a copy of the summary report discussed with the Residents. ,m If you have any questions on the attached material, please call me -(] at JAF x-6624. . Okas Sr. Project Engineer Engineering Programs cc: M. Colomb, T. Dougherty, W.
- Josiger, D.
Lindsey, R. Penny, D. Ruddy, A. Zaremba, Records Sta-WPO; (all w/ attach) l l r V r
3 JAMES A. FITZPATRICK NUCLEAR POWER PLANT ~ ~ CORE SHROUD INSPECTION AND RESULTS-RO12
SUMMARY
REPORT FOR HASTING WITH NRC AT JAF-11/14/96 G(_/
- 1. COMMITLENT IN LETTER TO NRC JFN-96-030-01 FOR R12/C13 RFO Implement augmented ISI plan for the core shroud tie rod w
assemblies and core shroud welds per EPRI-TR-105747.
- 2. INDUSTRY GUIDELINES AND ACCEPTANCE CRITERIA
- EPRI Document TR-105747, Guidelines for Reinspection of BWR Core Shroud (BWRVIP-07), Section 4.4.1 (B)
(2/96). Inspection Considerations for Vertical Welds in BWR Core Shrouds, by S. Ranganath of GE-NE (Undated) ; and Suggested . Inspection of Shroud Vertical Welds S. Ranganath to P. Okas (11/11/96). JAF Inspection and Acceptance Criteria for tiie Repaired Shroud by MPR (9/96). l
- 3. INSPEC. TION REQUIREMENTS, RESULTS AND CONCLUSIONS a) Inspect 25% of all vertical welds not structurally replaced by the shroud repair (EPRI). Inspect 50% of vertical welds in Belt Line Region (H3 to H6) (GE-NE).
Criteria Met: Inspected 50% on Belt Line Region and over -] 25% of welds in other shroud areas. b) Inspections may be performed ID or OD by EVT-1 per guidelines in BWRVIP-03, EPRI TR-105692 (10/95), RPV and Examination Guidelines. Criteria Met: Inspected ID/CD for Belt Line welds; ID or OD on other areas. Performed EVT-1 Examination. c) If any cracking is detected in a weld, inspect all accessible portions of that entire weld, ID/OD. Criteria Met: Inspected 100% of accessible welds ID/OD where crack like indications were detected, (SV5A weld). d) If cracking at individual weld is less than or equal to 10 percent of weld, then inspection is complete. Otherwise, expand inspection to 50 percent of all vertical welds. Criteria Met: Crack like indication at SVSA weld adds up to 6-3/4", or 6.9 % of its vertical weld lenght. MPR's criteria allows an 88.8% crack if any single crack is no more than 22" in lenght. l
4 REACTOR PRESSURE VESSEL INTERNAL VISUAL EXAMINATION DATA SMEET \\ -). FE NuclearEnergy Procedure No. Vr-FPK-202V1,hvisioni Paga of j ,p ' 5 - Shroud - WELD SV5A .Q l Page 1 of 2 4 PLANT: UNIT: OUTAGE: IDENTIFICATION CF COMPONENT (S) EXAMINED: f ~ ~ 1 James A. 1 RFC 12 Shroud-Weld No. SV5A Fitzpatrick EVT-1 For welds & Tie Rod Nut Engagement Station VT-3 For Tie Rod Assembly f TECHNIQUE EQUIPMENT LIGHVING TOOLS RESOLUTION sICEMOTE REMOTE SM VIDEO a H11NTEN$rrY O FLOAT 80x a VT 1. 4/32* uNE O DIRECT o REMOTECOLORvtDEO O FLASHLGHT C StNOCULARS X 0.001* WWE l O MIRROR c AMBIENT - 0 OTHER X 0.00r5'W1RE { E O MAONIFIER c CNER NrA a VT 3 o oTHER y 3 o oTutR l i I Reference (s)/ Cross Reference (s)<.g.veeoTm u/Coum.t orviDS..teS TAPE NOS. 96-13,96-18, 96-17,AND 96-18 EXAMINATION CHECKLIST EXAMINATION RESULTS / REMARKS DESCRIPTION Gen.r.1 conobon of m. shroud mciudmg sn,oudts.o.r.tw Raf.p rn.tmgo o NRI ^ q) Condman of m. msce sur c..cc.sset. pcrison of me o,cumfer.nh.i w.id(s) O Q NRI MA 3 c.t.d m m. m.m cyimd.r secuan of m. snroud. The w.id(s)is loc.t.d b.nn.e.n th. c,)r. pl.i. i .. ud.. n cond..s...non.d dunno m n..on.s,.au,,.d m,.,sor. no o NRi N,A g ef n/# / ] .a2..
- n. in. us d..,, a w.. m.i coni
- m. sus ci
.ons. o 4.R, NoiCATeN NeTEo Am To mE WEtc Ae,Rox. iin iNCs iN LENcTN C non, = =<. se.c. =c.. - a m. I w.ms iocmd x Approx. 60 INCHES FROM CWtOuMFRENTW.WCLO SH4 l e } efy44 m m. m evia., s.cuon e = sn,oud. m.s. w. ids.,. ioc.i.o.s, n in. sc,. ini..nd m tooave. n eo, s.,. n. d dunn m..-s m.s,., ,.d.n -.on x af.m mE REtEvEut NoiCATON: NoTEo RErERENCE ATTACueo oRAWiNo,eR - OiMENS4NS AND APPROXIMATE LOCATON 8.22.5..x.mn. m. outad..r of m. w.id (s) tn.t cont.ms = suso.ct mec.tkms. ii i n uons.,. m d dunno m, n n.s, d m r, no o Nm =A e n2. saa. or sas..d..on, snroud w. ids,n., r ,.or = -io.. n.d. I R. cord m. s.cbon.nd/or w.ide of m. snroud m.i w.r..m.mn.d. X o Nm WEl.D NO SVSAVERTICAL WELD G 50' i Conmuon of Ti. Rod Ass.r ely O O NRI N/A REFERENCE ATTACHMENT 31 FOR TIE RotJ EXAMiNATON I i NYPAISI D.t. f u//.7/f6 en.,n..,in. R.=w NYP v w D.t. Examiner's Signature Independent Review Signature 1 f / M M 9[ b K. RO,BI ~~ EU 'A N "l"' 't/39(o ' 0 8 R.L.KECK VT Level 11 Date 11/11/96 VT Level 11 Date 11/12/96 1 / Sketches are provided for convenience purposes only and may not represe><t actualplant configuration ent* ere not to scale. K0CKY.00C
+-%f ~ n.= _ _ REACTOR PRESSURE VESSEL N VISlJAL EXAMINATION DATA SHEET * ' ? ~.. ' GENmdearPsyy r===dwo No.VTM4EV1, Ret Page of J Attachment 15-Shroud-ACPE .j o'ennea *"W2%- Page 2 of 2 ^ O N'X}If 4.as4/3Cd e AJ $ Mead C.D, 1 k & J/g
- Ath44. J.de.473C0 44 MUD M n
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