Text

Inservice Insp Summary Rept for Refueling Outage R012 at Jafnpp
	ML20136B705
Person / Time
Site:	FitzPatrick
Issue date:	03/04/1997
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20136B700	List: JPN-97-009, Forwards ISI Summary Rept for JAFNPP Which Provides Summary of ISI Exams Conducted During 1996 Refuel Outage & Info Re Operating Status of Feedwater Nozzle Leakage Monitoring Sys & Measured Leakage for Feedwater Nozzles; ML20136B705;
References
	NUDOCS 9703110094
	Download: ML20136B705 (115)
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l INSERVICE INSPECTION

SUMMARY

REPORT

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i REFUELING OUTAGE RO12 i

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l JAMES A. FITZPATRICK NUCLEAR POWER PLANT i

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT j

DOCKET NO. 50 333 4

9703110094 970304 DR ADOCK 0500 3

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O TABLE OF CONTENTS TEXT l

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INTRODUCTION.

.1 II.

FORM NIS-1, OWNERS DATA REPORT for INSERVICE INSPECTION 1

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ISI EXAMINATION CHECKLIST.,,

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EXAMINATION RESULTS 2

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Indications....

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RPV Head Weld VC-TH-1-2....

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Limited Examinations 3

V.

CERTIFICATION I QUALIFICATIONS.

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Personnel 3

m Equipment.

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Materials....

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PROCEDURES 4

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IN-VESSEL INSERVICE INSPECTION 5

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SECTION XI REPAIR AND REPLACEMENTS 5

IX.

PRESSURE TESTING 5

X.

SNUBBERS 6

XI.

FEEDWATER NOZZLE LEAKAGE MONITORING SYSTEM 6

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FEEDWATER NOZZLE INSPECTIONS..

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TABLE OF CONTENTS (Con't) 1 l

l ENCLt??uRES 1.

Form NIS-1, Owners Data Report for Inservice inspection 2.

ISI Examination Summary 3.

ISI Examination Checklist 4.

ISI Examination Results & Disposition

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CertificationsI Qualifications Personnei Listing f]

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Equipment Listing (j

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Material Listing 6.

NYPA/QC Miscellaneous ISI Checklist NYPA ISI Misce ineous Checklist 7.

Limited Examinations 8.

In-Vessel inservice 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)

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INTRODUCTION o

This summary report details the Inservice Inspection Program conducted at the James A.

FitzPatrick Nuclear Power Plant during RO12 Refueling OL,+ age in the last quarter of 1996. The Inservice inspection Program requires performing examinations on Class 1,2,3 and augmented components. The NDE inspections 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 and completes all inspection requirements in their entirety for the Second Ten-Year Interval. The ISI inspections performed during RO12 were in accordance with the following goveming documents:

Technical Specifications, ASME Boiler and Pressure Vessel Code,Section XI, " Rule for inservice inspection 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 Interval. In addition, other regulatory documents were used where applicable to develop augmented inspection programs to meet mandatory requirements. These documents are referenced specifically in the following text, ie., NUREG-0313, Rev. 2 and Generic Letter 88-01 were used for selection and performance of IGSCC examinations.

0 included in this report is a listing of partial and/or limited examination coverages along with percentages complete for inspections conducted during the RO12.

The NDE methods utilized were visual (VT-1, VT-2, VT-3, VT-4 and Enhanced Visual for Shroud Inspection), magnetic particle, liquid penetrant, and ultrasonic testing (manual), and radiography, These examinations were conducted using approved site / vendor procedures and personnel certified and qualified to an approved QA NDE Program.

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- FORir. NIS-1, OWNERS DATA REPORT for INSERVICE INSPECTION The NIS-1 Form as required by the governing code section will be supplemented with the ISI

. Examination Checklist, Examination Results Listing, and Limited Examination Listing for inspections conducted by GENE and NYPA Personnel. These supplements are Enclosures 1,3,4 and 7, O

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ISI EXAMINATION CHECKLIST The ISI Checklist was developed in accordance with the Second Ten-Year ISI Program Plan.

Technical Specifications, ASME Code Section 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 encompassed all of the examination requirements of the above as well as delineating the following:

Component / Weld Identification ASME Code Category ASME Code Item Number NUREG - 0313 Category Isometric Drawing Number NDE Method Utilized for Examination NDE Procedure Number Utilized UT Calibration Block (if applicable)

Examination Completion Date NDE Report Number Additional Remarks (if applicable)

The ISI Examination Checklist was used for both scheduling and tracking purposes. In this way, control was maintained over ISI activities.

/~'s JL EXAMINATION RESULTS d

The results of examinations documented in this section of the report are for inspections performed by GENE and are included in the Examination Result Listing. Examinations performed by NYPA OC personnel and their results are referenced in the NYPA Miscellaneous Examination Checklist section and in-Vessel Visual Inspections performed by GENE are referenced in the In-Vessel Inservice Inspection section.

m Indications Components 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 reinspection, to ensure any and all unacceptable results or conditions meet plant safety and continued operational criteria.

By using the examination Re sult Listing, items with indications can easily be accessed by system number and item nuniber. A variety of acronyms were used during the course of preparing examination reports and ihcse are also listed in this section.

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RPV Head Weld VC-TH-1-2 l

Examinations conducted on RPV Head Weld VC-TH-1-2 during RO12 were in accordance with Section XI requirements for reexamination of unacceptable indications under NRC Regulatory Guide 1.150 and ASME Section XI, IWB-3510. The examinations conducted during RO12 have successfully met the reexamination requested by the NRC.

The Authority will retum weld VC-TH-12 to a normalinspection scaedule based on ASME l

Section XI,

Reference:

NRC letter dated 12/27/96, Evaluation of Reactor Vessel Head Indication Inspection and Evaluation Submittal for JAF N.P.P. (TAC No. M97443) e Limited Examinations Components that have a limited examination can be accessed through the list which details Code Required Volume (CRV). Conditions that would result in a limited exam are l

component configuration, various types of permanent obstructions, and limited access.

l When a limitation was identified that precluded 100% coverage, calculations were performed to determine the percentage actually examined. A listing of the RO12's partial l

exams with their percentages completed is a part of the Limited Examination Listing.

l Application for relief of components that do not meet the criteria in Code Case N-460, will l

be submitted in accordance with 10CFR50.55a(a)(3)(ii) under separate cover.

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Y, CERTIFICATION / QUALIFICATIONS V

a Personnel All personnel performing NDE examinations 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 the Authority's Quality Assurance NDE Program. All personnel performing IGSCC-related examinations (i.e.: detection, sizing, and overlay repairs) have been qualified through the EPRI PDI Qualification Program and/or EPRI's lGSCC Oualification Program.

Certifications and qualifications are available for review upon request.

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a Equipment Certifications and qualifications for NDE equipment utilized in the performance of ISI and IGSCC examinations 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 l

Temperature Gauges Msgnetic Particle Equipment i

Ultrasonic Instruments Ultrasonic Transducers j

Ultrasonic Calibration Blocks Beam spread plots for transducers used for Reactor Pressure Vessel examinations and for those employed in conjunction with Reg. Guide 1.150 Rev.1 (RF Waveforms are available for review).

s Materials NDE materials utilized during ISI activities were reviewed and approved for use by the NYPA cognizant Level Ill. The material certifications covered by this statement are:

Magnetic Particle Powder p

Liquid Penetrant Materials Ultrasonic Couplant i

VI.

PROCEDURES Procedures used for performing nondestructive examinations of welds and components were prepared in accordance with ASME Section V and XI,1980 Edition up to and including Winter 1981 Addenda. When the above referencing codes did not apply, acceptable NRC and industry j

standards were used (i.e.: IGSCC Exams, RPV Shroud Exams).

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IN-VESSEL INSERVICE INSPECTION In-Vassel Visualinspection in-Vessel visual examinations were conducted inside the RPV by GENE utilizing personnel certified and qualified to ASME Section V and XI, who also met the guidelines as outlined in j

BWRVIP " Standards for Visualinspections of Core Shroud, and of Core Spray Piping, Spargers, and Associated Components",(two separate documents). Per requirements of these documents, I

NYPA conducted specific training for allinspection personnel addressing plant specific procedural requirements, core shroud and core spray configuration details, previous inspection results, inspection procedures, and any other pertinent information related to all inspections on the checklist, acceptance criteria and contingency plans, with emphasis on core shroud and core spray enhanced visualinspections. Enclosure 8 provides a summary report of examination results, the in-vessel visual inspection 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 dispositioned in accordance with NYPA's internal tracking system, and were found

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acceptable for continued operation.

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SECTION XI REPAIR AND REPLACEMENTS l

Section 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 plant's work control system. There were a total of seventy-one (71)Section 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 toting 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

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l 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 Class 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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X.

SNUBBERS Snubbers are inspected in accordance with the JAF Technical Specifications. Control and implementation of the Snubber inspection Program is conducted through the JAF Maintenance Department as discussed in the ISI Program Relief Request (R8). The listing of individual l

components and examinations conducted during RO12 are in the NYPA Miscellaneous Checklist.-

XI.

FEEDWATER NOZZLE LEAKAGE MONITORING SYSTEM l

The Authority, per NYPA letter, JPN-94-031, dated July 19,1994, is submitting the operating l

status of the Leakage Monitoring System (LMS) and the measured leakage for the Feedwater Nozzles at James A. FitzPatrick.

Leakaae Monitorina 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 calibrate the leakage monitoring system for the actual conditions in the annulus l

between the thermal sleeve and the feedwater nozzle, a finite element analysis of the nozzle configuration 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 l

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 smallleakage. For Nozzle C the previously.

estimated leakage of 0.75 gpm has decreased to approximately 0.5 gpm.

t 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-2182102.

CONCLUSION 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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XI.

FEEDWATER NOZZLE INSPECTIONS (NUREG 0619)

Inspections conducted on Feedwater Nozzles to satisfy NUREG 0619 during RO12 were conducted by performing inspections on Zones 1,2, & 3. These inspections are in accordance with NYPA Letter JPN-94-031, dated 7/19/94, which detau the extent of examination coverage performed during the 1990 Refuel Outage.

The Authority will continue to follow our present commitments-l

1. UT inspection of Zones 1,2, & 3

2. Visualinspection of the spargers and nozzles every forth refuel outage

3. Deletion of the PT exam on the inner nozzle bore. This is an approved alternative based on the NRC Letter, TAC No. M89950, dated 10/21/94.

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l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 e

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l ENCLOSURE 1 i

FORM NIS-1 OWNERS DATA REPORT FOR INSERVICE INSPECTIONS

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FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules a

New York Power Authority, 123 Main St., White Plains, NY 10601

1. Owner (Name and Address of Owner)

2. Plant James A. FitzPatrick N.P.P.,

P.O. Box 41, Lycoming, N.Y.

13093 (Name and Address of Plant)

N/A I

4. Owner Certificate of Authorisation (it @)

3. Plant Unit

5. Commercial Service Date 7/28/75

6. National 5oard Number for Unit 20764

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7. ComponentsI,,ected See Enclosures for Specific Components Inspected 1

Component or Manufacturer Appurtenance or Installer Reactor Pressure Vessel CE/CE CE-66108 N/A N/A Piping Kellogg/RCI/GE N/A N/A N/A JPI Assembly GE N/A N/A N/A RPV Internals GE N/A N/A N/A RHR HT.

Exchange Perfex N/A N/A N/A 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

FORM NIS 1 (back)

8. Examination Dates _10/27/96 12/15/97 9. Inspection Interval from 7/85 6/97 o

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work requirvd for current interval. Status of current interval and work are included in Sumary Report

11. Abstract of Conditions Noted See Su mary

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 mes-sures taken conform to the rules of the ASME Code,Section XI.

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19 Signed

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ofk%j Date e

d Owner [

Certificate of Authorization No. (if applicable)

N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel

, pctors and/or the State or Province of A/fW YdfM and employed by AffdA'/4# #dTI4 of in WALT #A/4. #A have inspected the components described in this Owners' Data Report during the period

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. 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 not 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 personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date ?E8AUAAY. Eb 19 SV Commissions AfR7Elb JVYAD7 AN.I, W

inspector's Signature National Board, State. Province and No.

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k ISI REPAIR / REPLACEMENT

SUMMARY

ISI COMPONENT REMARKS 1

CONTROL ROD DRIVES CRD 02-23 COMPONENT REPLACEMENT INC. BOLTING l

CRD 02-27 COMPONENT REPLACEMENT INC. BOLTING i

CRD 10-47 COMPONENT REPLACEMENT INC. BOLTING CRD 18-47 COMPONENT REPLACEMENT INC. BOLTING CRD 22-39 COMPONENT REPLACEMENT INC. BOLTING j

CR 3 3

P NE T EPLA M NT L

G CRD 30-47 COMPONENT REPLACEMENT INC. BOLTING l

CRD 34-23 COMPONENT REPLACEMENT INC. BOLTING l

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 1

CRD 10-15 COMPONENT REPLACEMENT INC. BOLTING CRD 22-35 COMPONENT REPLACEMENT INC. BOLTING CRD 26-23 COMPONENT REPLACEMENT INC. BOLTING i

O CRD 30-23 COMPONENT REPLACEMENT INC. BOLTING I

V CRD 38-19 COMPONENT REPLACEMENT INC. BOLTING l

1 CRD 06-19 COMPONENT REPLACEMENT INC. BOLTING l

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CRD 14-19 COMPONENT REPLACEMENT INC. BOLTING j

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CRD 30-27 COMPONENT REPLACEMENT INC. BOLTING CRD 06-23 COMPONENT REPLACEMENT INC. BOLTING l

j VALVES AND VALVE BOLTING I

29AOV-80D VALVE OVERHAUL j

29AOV-80A VALVE OVERHAUL 13MOV-16 VALVE OVERHAUL 34NRV-111B VALVE OVERHAUL I

I 12MOV-18 VALVE OVERHAUL 29AOV-808 VALVE OVERHAUL i

i 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 qy/

02RV-71B VALVE OVERHAUL Page1

02RV-71F VALVE OVERHAUL p)

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02RV-71E VALVE OVERHAUL 02RV-71G VALVE OVERHAUL COMPONENT REPLACEMENT 10RV-418 VALVE REPLACEMENT l

10SV-35B VALVE REPLACEMENT i

46RV-112A VALVE REPLACEMENT 46SWS-120K VALVE REPLACEMENT 46SWS-127B VALVE REPLACEMENT 46SWS-708 VALVE REPLACEMENT 46SWS-71B VAL"E REPLACEMENT 46ESW-10B VALVE REPLACEMENT 46ESW-28B VALVE REPLACEMENT t

46ESW-1218 VALVE REPLACEMENT 23MOV-14 VALVE REPLACEMENT 13MOV-131 PIPE SUPPORT REPAIRS PFSK-8953 RHR SUPPORT PFSK-1875 MAIN STEAM SUPPORT PFSK-4858 MAIN STEAM SUPPORT PFSK-3334 HPCI SUPPORT PFSK-2156 RHR SUPPORT BFSK-893 RB SERVICE WATER SUPPORT PFSK-3260 CRD SUPPORT H46-165 SERVICE WATER SUPPORT PIPINGNALVE REPLACEMENTS 10-16"-WS-151-308 RHR SERVICE WATER SYSTEM 46-8"-WES-151-116B EMERGENCY SERVICE WATER SYS.

13-4"-W22-902-4 RCIC SYSTEM UNIT COOLER 66UC-228 RB SERVICE WATER SYSTEM INLET PIPING BONNET RELIEF LINE HPCISYSTEM FOR 23MOV-19 BONNET RELIEF LINE RCIC SYSTEM FOR 13MOV-21 RHR SYSTEM 10MOV-89B REPLACE y

VALVE 10MOV-89A REPLACE RHR SYSTEM VALVE D

46-2"-WES-151-118 SERVICE WATER SYSTEM b

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT i

DOCKET NO. 50-333 3

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ENCLOSURE 2

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ISI EXAMINATION

SUMMARY

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GE INSPECTION SERVICES

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SUMMARY

OF INSERVICE INSPECTION EXAMINATIONS 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 examinations were conducted in accordance with Purchase Order No.C95 Z0083 and were performed to the applicable plant Technical Specifications and the ASME Boiler and Pressure Vessel Code, Section i

XI, " Rules for Inservice Inspection of Nuclear Power Plant Components",1980 Edition v

up to and including the Winter 1981 Addenda.

All Inservice Inspection activities were performed in accordance with controlled Checklists developed by NYPA ISI Engineering.

The inspection checklists we 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) ard 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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h GE INSPECTION SERVICES

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The organization of the JAF's RFO 12 ISI/EC Final Report, is as follows:

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1. Summary of the ISI and E/C activities Owners's Reports for Inservice Inspections, Form NIS-1

2. Final revision of controlled ISI Checklist

3. NDE personnel qualification records

4. NDE equipment and materials records

5. Final revision of approved NDE Procedures

6. ISI examination Data Reports I

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 p) 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 Inspection".

Section 2 ISI CHECKLIST The ISI Checklist was developed in accordance with the Plant's Second 10 Year ISI Program Plan, Plant Technical Specifications, ASME Section V and XI, and NUREG 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 purposes, as well as tracking of exams' progress.

The final revision of the controlled ISI Checklists are located within Section 2 "lSi O

Checklist", of this report.

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GE INSPECTION SERVICES O

Section 3 ISI NDE PERSONNEL A

This section contains the RFO 012 ISI NYPA/GE Organization, as well as, a matrix of Nondestructive examination (NDE) personnel, and copics of the supporting Qualification j

and Certification records.

The GE NDE personnel were qualified and certified in accordance with General Elect-Procedure 386HA480 " 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.

ISI and E/C NDE Personnel which have participated in the exams at J AF'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.

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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 IIW Blocks, Step Wedges and magnetic Yoke Lift Bar, as well as, consumable such as UT couplant, and Liquid Penetrants employed during the performance of the required examinations are indexed within Section 4

" 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.

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 Ger eral Electric Level Ill, NYPA Quality Assurance representative personnel and the Authorized Nuclear Inservice Inspector (ANII).

All examinations were performed in accordance with approved procedures.

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i' A complete index together with copies of the approved procedures are contained within i

Section 5 " Examination Procedures", of this report.

4 Section 6 ISI EXAMINATION DATA t

l The ultrasonic examinations are summarized in an " Examination Summary Sheet".

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The Summary sheets identify:

l-Weld's system, unique weld number, weld type and configuration i

Examiner's ID, ASNT Level and exam's NDE Procedure i

Reference (s) to applicable; l

UT Instrument Linearity Supporting UT Calibration Sheet (s) i A detailed report on the observations regarding the examination's l

Coverage l

Surface conditions Previous exams i

i-Supplemental scans i

l Examination results Disposition of recorded indications i-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 Ill, NYPA NDE i

representatives and the ANII.

Section 6.1 EXAMINATION RESULTS 4

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 Checkhst, five examinations with recordable indications were reported to the NYPA ISI Engineer.

RCIC Weld no. FW-74: The original Magnetic Particle examination of this weld resulted in the recording of a 2.20" long linear ir.dication. This condition was documented on DER 96-1448. 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 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 O

evaluation the weld was cut out and replaced.

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GE INSPECTION SERVICES n

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 scheduled 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 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.

/~'s V

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:

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 attachments, respectively.

RHR Wed nos. 24-10-142,24-10-143 and 24-10-144: The required ultrasonic examir ation 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 e

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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m hh GE INSPECTION SERVICES A'q)

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 relation to ultrasonic examinations. General Electric personnel in turn initiated 5 separate Non-conformance Reports to document corrective action and root cause of these incidents.

Copies of the NCRs and supporting clo' e-out documentation can be located within s

Volume 3, Section 6.3 of this report.

A Section 7 NYPA MISCELLANEOUS REPORTS 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 1.E.Bulletin 87-01, Generic Letter 89-13, EPRI's CHEt and CIIECMATE computer program, as well as, knowledge of previous problem areas and plant operating conditions.

A 6

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S If GE INSPECTION SERVICES U

I E/C EXAMINATION RESULTS As a result of the E/C examination conducted during RO-12, there were twenty-six (26)

Indication Notification Report Numbers (INRs). NYPA's E/C Engineer representative generated site Deficiency Engineering Reports (DERs) for further evaluation of the 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 CIIECKLIST The controlled 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 A

Reports DERs, site work request (WR) and Remarks, as well as, component's Nominal V

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 report 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.

DG 7

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i V

NYPA PROGRAM ENGINEERING iSI CHECKLIST Date:

1 m:

JA F#tzPatnck N.P.P.

SYSTEM:

Reactor Recirculation System (02-2) Overlays Welds RO12 NDE METHOD I

ON

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NDE DATE Weld or item Exam item NUREG PROCEDURE COMPLETED RE N S identification Cat.

No.

0313 REQUIRED NUMBER Number UT PT MT 1 (2 3

l L

2842-2-33 84 89.11 E

MSK-3001 A6&L NDEP-9 4-25(J) 47 11/8/96 R-005 WR8954856940 C6&L 11/8/96 R405 2842-2-53 8-J 89.11 E

MSK-3001 A60'l NDEP-9 4-25(J) 47 11/8/96 R405 WR895-08508-00 C60'L 11/8/96 R405 2842-2-92 B-J 89.11 E

MSK-3002 A6&L NDEP-9 4-25(J) 47 11/9/96 R408 WR895-0859540 C6&L 11/9/96 R408 28-02-2-116 B-J 89.11 E

MSK-3002 A6&L NDEP-9 4-25(J) 47 11/9/96 R408 WR895-08596-00 C6&L 11/9/96 R408 l

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L NOTES:

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NEW YORK POWER AUTHORITY j

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50 333 3

i i

i n

ENCLOSURE 4 1

1 j

ISI EXAMINATION RESULTS & DISPOSITION i

kiO 4

1 O

GE INSPECTION SERVICES A

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.

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 961448. 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 recordable indications were noted. The indications were evaluated as slag and lack of i

fusion (construction defects) and documented on DER 96-1472. As a result of further i

evaluation the weld was cut out and replaced.

i 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 scheduled for next refuel outage.

Recire 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, f

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 i

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 i

subsequent evaluation results were evaluated and no significant change in the size or location of the reflectors was noted.

R V

l GE INSPECTION SERVICES O

Section 6.3 NON-CONFORMING CONDITIONS 1

As a result of the examination activities undertaken at J. A. Fitzpatrick NYPA site Quality Assurance personnelinitiated 3 DERs addressing procedural non-compliance in relation to ultrasonic examinations. General Electric personnel in turn initiated 5 separate Non-conformance Reports to document corrective action and root cause of these l

incidents.

Copies of the NCRs and supporting close-cat documentation can be located within this i

section.

i

O u

h OE Nuclear EnergyNon Conformance Report nu Project:

J. A. Fitzpatrick Project No.

IFRAA NCR No. NCR-lFRAA-001 Reference Documents:

G. E. Procedure GE-ADM-1001 V0 i

Description of Non Conformance: (State Cause)

NCR Code. 043 Cause Code:

F01 Pre examination Linearities were not performed prior to the beginning 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 initiated By Date /2/2.# QC Supervisor A. hDate

/s.u - t c f

10(TR21 Review. Ols, @ Is Not Reportable Signature A.1)%,Date /s-u t t Proposed Disposition and Technical Justification (Attach Extra Sheets, Sketches, Etc. as Necessary)

Accept-As-Is @

Repair O Rework O Reject O Other If Not Matl. Or items O 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 Project Manger:

Date: e/z.SQC Supervisor: ft., MDate. /s-9 rc j,-

i Fina: Dispositio'n Accept as is. Examinations were acceptable and no re-exams were required i

Date: th6

ANI Review p Date.M N

Client:

s Y

Project Manger:

Date: gyz3,QC Supervisor: A, lhe Date. /J-/.1-M

If Required [

/

Preventative Action:

Emphasize procedure adherence and proper equipment pre and post examination status during procedure training QC Approval: A, )_A e _ Date: iM-f r.

Disposition Completed And Non Conformance report Closed QC Supervisor. A. h Date:

/4-a -16

h GE Nuclear EnergyNon Conformance Report Project:

J. A. Fitzpatrick Project No.

IFRAA NCR No. NCR-lFRAA-002 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 search units used were not included on the EPRI PDI Table 1 as required (see attached Table)

Initiated By:

A Date a ve QC Supervisor: A [A:

_ Date e d4 7/r 6

/

10CFR21 Review: C is 8 Is Not Reportable Signature. /t.1A mDate. <a /a/n f

j Proposed Disposition and Technical Justification: (Attach Extra Sheets, Sketches, Etc. as Necessary) j i

Accept-As-Is E Repair O Rework O Reject O Other If Not Matl Or Items S i

Each search unit listed on the attached Table will be qualifted at EPRI and included on Table 1 provided j

l the PDI standards are met.

1 l

p V

l I

Project Manger-Date; e/r4 QC Supervisor: A. dV Date: uh zen

\\

j~'

/

Final Disposition i

Accept as is pending qualification results and Table 1 inclusion

Client: M Date:IZlM%* ANI Review:

Date:/2//f 6 Project anger:

Date: /Nv-SQC Supervisor: A. Ah - 2

_ Date: u -so pc

If Required f "'

Preventative Action:

Perform PDI specific pre-job breifing for all arplicable technicians, evaluation personnel and custcmer representative (s) prior to the start of examulation activities.

QC Approval: A, h% Date:

/-J-h p

Disposition Completed And Non Conformance report Closed QC Supersisor: f4. hm Date: / J-M

CE Nuclear Energy N:n C:nt:rmance RIport NCR-1FRAA-002 IGSCC EXAMINATIONS p3CEDURE CONFIG SCOPE SEARCH UNIT T

DIA.

g rUI UT 3 P-E SONIC 136 RTD TRL2 AUST 60*L 2(8X14)mm

.76 12*

4 P01-UT 3 PE SONIC,136 MEGA CGD 2.25 Mhz 70*L 2( 25*X>50-)

.76 12' FDI UT 2 NOZ SE SONIC 136 KSA C/ GAMMA 2.25mhz 45'S.25'

.90 53*00 4

PDI-UT 2 NO2 SE SONIC 136 KSA C/ GAMMA 1.5 Mhz 39'S.50' 90 53*00 J

P01 UT 2 NO.7 SE SONIC 136 MEGA CGD 2 25mhz 40*L 2( 25*X50*)

.90 53*00 P01-UT 2 NOX SE SONIC 136 RTO TRL2 AUST 60*L 2(8X14)mm

.90 5 3* C0 POI-UT 2 LN'i SM USK 70 KBA MSWS 1 Smhz 45*S.25'

.76 17 POI UT 2 P-L SONIC 136 KBA C/ GAMMA 2.25mnz 70 5 375*

76 17 i

PDI UT 2 Pd SONIC 136 KBA C/ GAMMA 2.25mhz 60*S 375*

76 IT P01-UT-2 P -E SONIC 136 KBA C/ GAMMA 1.5mnz 45'S 50'

.59/1 1 10,14 NOZ.SE 15/19 28*

a PDI-UT 2 PE USK 70 KBA C/ GAMMA 1.5mhz 45*S. 50 76 17 PDI-UT 2 P-E SONIC 136 KBA C/ GAMMA 15mhz 70*S.375*

76 17 PDI UT 2 P CAP SONIC 136 KBA C/ GAMMA

Smhz 45'S.375*

.68/1.1 53*00 P REDUC

.70/.52 8/12/14' NOZ SE OV E: Dunng the course of exammatens Megasorwes 70* L and 40' L search units were used wth sviser settegs outsuse of tncee requned by Pol-UT-2. Rev A,

, mole 2. The settmg used was 250ns. Table 2 requires a settog of 222ns These search units mil be qualified wth a pulser settog of 250ns and 222ns for melusion in PDI Table 1.

5 l

4 1

s

i EPRI NDE CENTER 1 -o)

Electnc Power Research Institute Leadership in Technology Transfer

,V Noncestructsve Evaluatuon Center January 2,1997 Mr. Richard Keck l

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 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 4

' # ef -

lastrummes A-

. Senseli ' i E Mf.

- Model Angle '-

Mode <-

- 75he - -

- Mem..

) desire 7 5

~

J {d

,7'#'

'J FMR ' ' '.

M' l Unit #),

oms _a assants 1

MEGA CGD 70 LoNG 2(.25 X 2.25 RECT 2

i L

.50) 2 RTD TRL 60 LoNG 2(8 X 14) 20 RECT 2

I I

MM Instrument 1 regsmary AQad

Rep. Rate Unit (s)

Mfg.

Model -

Pulser Dessplug Ir Search;

- Pa8d 'g 4

j i

suvely Sonw 136 222 ns 500 ohms 2.25 off JK

l. 2 Suvely Sonw I36 250 ns 500 ohms 2 25 off 4K bi G

e.eeacne (34154' 6100 Oaanone N:aa Ca ooca 28262

=

GCC ma"4 Bove.a c a

c... : $4 6Me e-g,

m

,..., - ; v;., n 7-

Abbreviations:

Megasonics MEGA Longitudinal LONG RND Round Access "l" Dual Access "2" Single If I can be of further assistance please contact me at (704) 547-6140 Sincerely

//

Il s

Carl Latiolais Project Manager Level III Piping and Bolting Performance Demonstration O.

cc; Carl Osman Gary Lofthus F.L. Becker PD1 Correspondence file JAF2 DOC DOC 1

l

EPRI NDE CENTER rN Electnc Power Researen institute Non6estructive Evafua1\\on Center Leadership on Technology Transfe' January 2.1997

~

Mr. Richard Keck General Electric 12200 Herbert Wayne Court Hunterville. NC 28078

SUBJECT:

Generic Procedure Equipment Qualification

Dear Richard:

Per your requen. NDE Center staff have performed equipment qualifications on the following search unit int,trument combinations. The toitown,3 combinations have been successfully qualified for '.he detection of IGSCC flaws in austenitic piping welds utilizing Generic Procedure PDl-UT-2 Rev. A.

fgV Search Units i

f

. Modo q pygme.its <

~

A =

. Angis[s. ; ',~Q' sf 24%i fE 'qs. b, e..

{pl'f,'s ; g'*EI.;

M

Medal,,

Search <: e lfUsk#h} ih., [g. r 6

~

Mf})t, t >. ( ;.j j

's c,

.1

\\

~;.p.

a;;,

l KBA MSWCG 45 SHEAR

.25" 2.25 RND 1

2

1. '

2 KBA MSWCG 39 SHEAR

.50" i.5 RND 1

2 1, 2 3

MEGA CGD 40 LoNO 2(.25" X.50")

2 25 RECT 2

2 1

4 RTD TRL 60 LONG 2(8 XI4)MM 2.0 RECT 2

2

1. 2 5

KBA MSWS 45 SHEAR 25" l.3 RND I

I I. 2 6

KBA MSWCG 70 SHEAR

.375" 2.25 RND 1

2

1. 2 7

KBA MSWCG 60 SHEAR

.375" 2 25 RND 1

2

1. 2 8

KBA MSWCG 45 SHEAR

.50" 1.5 RND I

2

1. 2 9

KBA MSWCG 45 SHEAR

.50" 1.5 RND I

i

1. 2 to KBA MSWCG 70 SHEAR

.375" 1.5 RND 1

2

1. 2 11 KBA MSWCG 45 SHEAR

.375" t.5 RND 1

2 L. 2 U

C a"c"e he"- Ca'onna 28262 Teieorone 4"C4 54' 6 500 1300 Hans Boava o

'Ax

0a. 54' 6 68 0 0 Bei 209' Caa c" wta Ca oi.aa 2822'

)

'%)

Instrument 1 9gl.)[; hW:

."[j [N"r ?*r} j${@ liq {y%{f)7 T

5. 9 Krautkramer UsK 7D High Fixed 15 MHz oft High Instrument 2 Search Mfg.

Medel Pulser Damping Freepsency Reject Rep. Rate Unit (e) (MHz)

1. 3. 6. 7 suvely sonic t36 22: ns 500 ohms 2 25 Off JK

3. 4 stavely sonic 136 250 ns 500 ohms 2 25 off 4K 2.5.8 11 suvely sons 136 314 ns 500 0hms 2 25 off 4K Abbreviations:

MSWCG MSW-QC Benchmark Composite Gamma MEGA Megasonics A LONG Longitudinal (") RND Round Rectangular RECT Access "1" Dual Access "2" Single If I can be of further assistance please contact me at (704) 547-6140 f Sincerely ) / i Carl Latiolais Project Manager LevelIII Piping and Bolting Performance Demonstration CUja cc: Carl Osman Gary Lofthus F.L. Becker PDI Correspondence file J AFIDOC. doc m

h as Nuclear Energy Non Conformance Report O, 4 Project: J. A. Fitzpatrick Project No. 1FRAA NCR No. NCR-lFRAA-003 [' Reference Documents: GE-PDI-FPK-2VO REV 1. 4 Description of Non Conformance: (State Cause) NCR Code: 045 Cause Code: D02 i For IGSCC examinations the referenced ultrasonic procedure is limited to 1.5 Mhz search units only and does not allow for alternate search unit frequencies to be used. During examinations 2.25 Mhz search units were used. p y / ;l l 1 Initiated By:pfl y /d Date: /.vMQC Supervisor: A hDate: u A 7/pc, / j 10CFR21 P'eview O is E is Not Reponable Signature: A. LJ_. Date: <,/,7/n i Proposed Disposition and Technical Justification: (Attach Extra Sheets, Sketches, Etc. as Necessary) j Accept-As-Is E Repair O Rework O Reject O Other If Not Matt. Or items O e l Add statement to the procedure to allow for the use of 2.25 Mhz search units as necessary for IGSCC i examinations l / Project Manger: - Date: /NNd QC Supervisor: A. h Date: e s/,,ac Final Disposition Accept as is pending PDA review of proposed change Nhh6

Client:

Date!2]/ e Date:

ANI Review:

z Project h anger: Date /210 st,QC Supervisor: w.),e-Date: u h e/ft

If Required

/ Preventative Action: 1 Verify procedure adequacy prior to examinations QC Approval: A. Date: n/n/rc Disposition Completed And O-Non Conformance report Closed QC Supervisor A. h - Date:, a/> Vh

EPRI NDE CENTER /~s Electnc Power Research Instituto Leadership in Technology Transfer Nondestructsve Evaluatnon Center l l January 2,1997 l Mr. Richard Keck General Electric 12200 Herbert Wayne Court i Hunterville, NC 28078 l

SUBJECT:

Generic Procedure Clarification

Dear Richard:

1 The in'.ent of this letter is to provide guidance on the use of supplemental examinations when j utilizing the PDI Generic piping procedures. f Presently, the Generic procedures do not contain a statement addressing supplement examinations outside the evaluation requirements of the procedure. It is our position that, supplemental examinations performed above and beyond the procedurally required examinations are acceptable provided they are not used to: g 1) Ovenurn the results of exaininations obtained with the primary qualified search unit instrument combinations described within the generic procedures, 2) Obtain additional coverage in lieu of the qualified search units. A clarification of this position will be included in future revisions to the Generic procedures. l If I can be of further assistance please contact me at (704) 547-6140 j Sincerel,O Cl/ 'W'(N l Carl Latiolais Project Manager LevelIII Piping and Bolting Performance Demonstration i i CUja ec: Carl Osman [) Gary Lofthus U F.L. Becker PDI Correspondence file J AF3 doc DOC 1 046547 6100 7 Teteomone ce-aroce W-Ca'enna 26262 1300 Ma" 5 Boseva o e Qu '04 54M'66 P 7 B S T '.-r c"* S ~' - C a > N 2B22'

Non Conformance Report GE Nuclear Energy ,J Project: J. A. Fitzpatrick Project No. IFRAA NCR No. NCR-lFRAA-004 l Reference Documents: GE PDI-FPK-3V0 REV 0. /GE por-pM-JV6 TEK/ Description of Non Conformance: (State Cause) NCR Code: 045 Cause Code: D02 For IGSCC sizing examinations the referenced ultrasonic procedure does not allow for alternate search unit sizes to be used.During examinations an 8X14 mm search unit was used. Initiated By: Date:aint QC Supervisor: A. km Date: A /n / 10CFR21 Review: O Is E is Not Reportable Signature: 4. h Date:,4 n/n, / Proposed Disposition and Technical Justification. (Attach Extra Sheets, Sketches, Etc. as Necessary) Accept-As Is S Repair C Rework O Reject O Other If Not Matt. Or Items O The search unit used was 8X14 mm (.32"X.56") and the Table allows a maximum size of.25"X.50" This search unit is the metric equivalent of a.25"X.50" search unit i (D') Date: pyp#cQC Supervisor: A. h, Date: /,,/< 7/n Project Manger:.. jii Final Disposition Accept as is pending PDA review of proposed disposition Date: /2//I/95 Date:ld/0d4 *ANIReview: 2

Client:

Project h nger: Date: //fppAC Supervisor: A. hDate: n/s ohc

If Required [

[ Preventative Action: Verify procedure adequacy prior to examinations QC Approval: // h Date: ez /ig, pd Disposition Completed And Non Conformance report Closed QC Supervisor. e. h -- Date: f e/n/n

EPRI NDE CENTER gI Electric Power Research Instituto Leadership in Technology Transfer Noncestructive Evaluatson Centst ) January 2,1997 l i Mr. Richard Keck General Electric 12200 Herbert Wayne Court Hunterville, NC 28078

SUBJECT:

Generic Procedure Clarification

Dear Richard:

Presently, the Generic procedures PDI-UT-2 and 3 Rev. A states that the maximum search unit size for refracted longitudinal search units on nominal pipe diameters from 4" to 12" inclusive is 0.25" X 0.50". The procedures do not specify tolerances when converting from millimeters to inches. It is our position that an 8 X 14 mm search unit is equivalent to a 0.25" x 0.50" provided adequate contact can be maintained. Future revisions of the procedures will nV address this conversion problem. If I can be of further assistance please contact me at (704) 547-6140 Sincerel, f Carl Latiolais Project Manager Level III Piping and Botting Performance Demonstration CUja cc: Carl Osman Gary Lofthus F.L. Becker PDI Correspondence file JAF4 DOC. DOC ( )\\ Te eonone (704i 5476100 000 Ma ns Bov.e are

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h GE Nuclear EnergyNon Conformance Report iG j (_) Project: 1 A. Fitzpatrick Project No. IFRAA NCR No. NCR-lFRAA 005 Reference Documents: GE-PDI FPK-2VO REV 1. Description of Non Conformance: (State Cause) NCR Code: 045 Cause Code: D02 The Search Unit Selection Table in Section 4.1.6 of PDI-UT-2 Rev. A, describes search unit selection based on nominal pipe diameter and does not address nozzle to safe end configurations which are non-standard Steps were taken to address the above in Section 6.3 of the referenced precedure but were not 4 adequate. i f ,03 fAM,/ Date: #/79t QC Supervisor: A.,h Date: u/e vr c. initiated By: 10CFR21 Re/ view: O is E Is Not Reportable Signature: A. Am Date: uny,6 4 Proposed Disposition and Technical Justification: (Attach Extra Sheets, Sketches, Etc. as Necessary) i Accept As Is 8 Repair O Rework O Reject O Other If Not Matt. Or items E Reword Section 6.3 to specifically address search unit selection for non-standard nozzle to safe end ) configurations ,f3 Project Manger:/ - Date: G/74 QC Supervisor: p. h Date: n./n/, c / Final Disposition 4 Accept as is PDI does not presently address nozzle to safe end or dissimilar metal welds. The examinations were performed using search unit sizes which provided optimized examination results rather than those listed in Table 4.1.6 i w Date: /2)/f/.95

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Preventative Action: Verify procedure accuracy prior to examinations QC Approval: A. d4 r-_ Date: Ws./r c O ?V Disposition Completed And Non Conformance report Closed QC Supervisor: A. %,6-Date: WMn

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O NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT j

DOCKET NO. 50-333 i l i l i 1 ENCLOSURE 5 i i i CERTIFICATIONS / QUALIFICATIONS i l Personnel Listing 1 i Equipment Listing !O Material Listing 1 i ) 1 i 4 i 't 4 I 4 1;O } i 1

I GE INSPECTION SERVICES l O Section 3.4 NDE Personnel Qualification and Certificatioa l Nondestructive examination (NDE) personnel were qualified and certified in accordance with General Flectric Procedure 386HA480 " 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 Overir.y, as well as, Performance Demonstration Initiative Program (PDI), in accordance with Section XI, Appendix Vill. I 3

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3 n GE INSPECTION SERVICES i Section 3.3 NDE Personnel Signature Log 1 i 1 4 I i k a I i i e i 1 i .I l l f h 4' s i 1 l k i l } f I l i' i i i f i d I i 1 i 4 i ) s i

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GE INSPECTION SERVICES o Section 4 NDE EQUIPMENT / MATERIALS Certification records pertaining to the nondestructive examination (NDE) equipment, such as ultrasonic instruments, transducers, surface thermometers, and reference calibration standards, such as llW Blocks, Step Wedges and magnetic Yoke Lift Bar, as well as, consumable such as UT couplant, and Liquid Penetrants employed during the performance of the required examinations are indexed within Section 4 " 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. N. V O

GE INSPECTION SERVICES 40 Section 4 NDE EQUIPMENT / MATERIALS 4 Section 4.1 Index Section 4.2 UT Instruments J Section 4.3 UT Transducers 1 Section 4.4 MT Lifting Standard 1 Section 4.5 Thermometers i Section 4.6 Calibration Blocks s Section 4.7 PT Material Certifications Section 4.8 MT Material Certification ] Section 4.9 Ultrasonic Couplant J Section 4.10 E/C Markers 4 i O 4

,\\ C) FITZPATRICK EQUIPMENT CERTIFICATION 12/01/96 ULTRASQMC SCOPES I MANUFACTURER MODEL SERIAL NUMBER DUE DATE STAVELEY SONIC 136 136P11038041318 4/16/97 STAVELEY SONIC 136P 136P1106B091353 9/18/97 STAVELEY SONIC 136P 136P991A071181 8/7/97 STAVELEY SONIC 136P-019 136P991A091220 8/7/97 STAVELEY SONIC 138P 138P-160PB 8/7/97 STAVELEY SONIC 136 717 H 2/11/97 PANAMETRIC 26DLP 92052503 10/13/97 PANAMETRIC 26DLP 93127706 8/27/97 PANAMETRIC 26DLP 93127806 8/27/97 PANAMETRIC 26DLP 93128006 8/27/97 PANAMETRIC 26DLP 95236703 1/28/97 PANAMETRIC 26DLP 96346108 10/13/97 O PANAMETRIC 26DLP 96355209 10/13/97 b PANAMETRIC 26DLP 96355909 10/13/97 KRAUTKRAMER USK7 KBA-USK7-018 8/11/97 27276-4640 j KRAUTKRAMER USK7S KBA-USK7-020 8/11/97 314594 943 KRAUTKRAMER USK7D KBA-USK7-025 8/11/97 32810-2021 KRAUTKRAMER USK7D KBA-USK7-026 1/25/97 32810-2050 KRAUTKRAMER USK7D KBA-USK7-028 10/09/97 32810-2043 KRAUTKRAMER USK-7D KBA-USK7-032 1/17/97 32810-1823 l TOMOSCAN MANUFACTURER MODEL SERIAL NUMBER DUE DATE ' TERCRAD TOMOSCAN TTP10094108 6/18/97 Page 1 of 5

i 4 0V l TRANSDUCERS MANUFACTURER EREQUENCY 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.5" M31148 KBA 2.25 Mhz .5" x.5" 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 4091 KBA 1.5 Mhz .50" diameter 4247 KBA 2.0 Mhz 2(3.5 x 10)mm 885 KBA 2.0 Mhz 10mm 896 KBA 4.0 Mhz 2(3.5 x 10)mm 984 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 .375" diameter 003YMC KBA 2.25 Mhz .375" diameter 003YMG KBA 2.25 Mhz .375" diameter 003YMJ KBA 2.25 Mhz .375" diameter 003YMR KBA 2.25 Mhz .375" diameter 003V8F KBA 10.0 Mhz .375" diameter 003V8T KBA 3.5 Mhz .5" diameter 003V8N KBA 2.25 Mhz .25" diameter 003V86 KBA 5.0 Mhz .5" diameter 003W50 \\/ KBA 2.25 Mhz .5" diameter 003WCR KBA 2.25 Mhz .25" diameter 003X5F Page 2 of 5

d -t O'O TRANSDUCERS (Cont'd) MANUFACTURER FREQUENCY SIZE 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 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 MEGA 2.25 Mhz .375" diameter C0273 PANAMETRICS 5.0 Mhz .312" diameter 19501 3 PANAMETRICS 5.0 Mhz .312" diameter 19502 PANAMETRICS 5.0 Mhz .2" diameter 19511 PANAMETRICS 7.5 Mhz .2" diameter 29526 PANAMETRICS 5.0 Mhz .312" diameter 39606 g PANAMETRICS 5.0 Mhz .312" diameter 59602 PANAMETRICS 5.0 Mhz .312" diameter 59604 PANAMETRICS 5.0 Mhz .312" diameter 59605 i l PANAMETRICS 5.0 Mhz .312" diameter 59606 PANAMETRICS 5.0 Mhz .2" diameter 59636 PANAMETRICS 5.0 Mhz .2" diameter 59638 3 PANAMETRICS 5.0 Mhz .2" diameter 201569 PANAMETRICS 5.0 Mhz .2" diameter 201573 PANAMETRICS 5.0 Mhz .2" diameter 201581 PANAMETRICS 5.0 Mhz .2" diameter 201582 1 l PANAMETRICS 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 IW iRL2 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 n RTD-TRL2 AUST 2.0 Mhz 2(8 x 14) mm 94-705 U 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 i Page 3 of 5

~--.._ i i f i MT LIFTBLOCK SERIAL NUMBER i i 10 LB MT LIFT PLATE CAL-10MT-002 i THERMOMETERS CALIBRATION l MANUFACTURER DUE DAIE SERIAL NUMBER l PTC 8/19/97 162887 1 PTC 8/19/97 164135 PTC 8/19/97 164203 I l PTC 8/19/97 167185 PTC 8/19/97 167282 PTC 8/19/97 167303 8/19/97 167305 PTC PTC 8/19/97 167335 PTC 8/19/97 169199 i l l I i l l i i l

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) kJ CALIBRATION BLOCKS NAME STEEL RANGE OF S.W. SERIAL NUMBER i DEPTH HT.#470715 CAL-DPTH-037 f IlW2 304 SS CAL-ilW2-018 llW2 304 SS CAL-IlW2-020 llW2 1018 CS CAL-ilW2-026 llW2 1018 CS CAL-ilW2-027 STEP WEDGE SS .25-1.00 CAL-STEP-013 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 CAL-STEP-057 STEP WEDGE 4340 CS .25-2.00 CAL-STEP-065 STEP WEDGE 1018 CS .050.500 CAL-STEP-071 STEP WEDG'- 4340 CS .25-2.00 CAL-STEP-079 O' 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 WILLY 304 SS CAL-WILLY-017 ROMPUS CAL-RHOM-036 95-5947 ROMPUS CAL-RHOM-050 96-5534 ROMPUS CAL-RHOM-051 96-5535 ROMPUS CAL-RHOM-G44 96-5539 ROMPUS CAL-RHOM-045 96-5540 ROMPUS CAL-RHOM-056 96-5702 Page 5 of 5

n,,r, m ,a A,.-4 a 4 ,ea.-.a A.a a .a. a,.. -,1 PT MATERIAL CERTIFICATIONS O BATCH TYPE MANUFACTURER CODE 94LO7K SPOTCHECK CLEANER / REMOVER MAGNAFLUX SKC-S 94L12K ! SPOTCHECK DEVELOPER MAGNAFLUX SKD S2 I l 94M05K I SPOTCHECK PENETRANT MAGNAFLUX l SKL-SP i 4 O Page1

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ULTRASONIC COUPLANT 1 j V BATCH NUMBER MANUFACTURER 4 I 19565A HUMEX a a 1 i I d 4 t i O 4 4 i i l i 4 i i 4 4 i O Page 1

i i E/C MARKERS !O CERTIFICATION LISTING Mark-Tex #33 Black Ink Lot #187 GE P.O.# 528-93161T/189 i Action Makers #44 Black ink Lot #187 GE P.O. # 1DNA2-159 J e I l i C 1 i U 4 O

!O e NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l DOCKET NO. 50-333 i i i i l ENCLOSURE 6 NYPA/QC MISCELLANEOUS ISI CHECKLIST i O O

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l l i i ] i I i 1 i NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 j d i 4 4 t l t J d i ENCLOSURE 7 I I LIMITED EXAMINATIONS 4 i O o l l l l l 2 I i 4 J t 4 4

I GE INSPECTION SERVICES 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-l A, SUP-2A, SUP-3 A and SUP-4A: 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 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%. o [v a

) NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT j DOCKET NO. 50-333 i i i ENCLOSURE 8 ] IN-VESSEL INSERVICE INSPECTION l In-Vessel Visual inspection summary in-Vessel Visual inspection Checklist In-Vessel Visual inspection Results & Disposition O

l GE INSPECTION SERVICES J. A. FITZPATRICK RFO-12 REACTOR PRESSURE VESSEL INVESSEL VISUAL INSPECTION

SUMMARY

EXECUTIVE

SUMMARY

invessel Visual Inspections of the J. A. Fitzpatrick Nuclear Power Plant were conducted 4 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-Z0038. 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 (O and were found acceptable for continued use. 4; V 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 retorquing or replacement of the Tie Rod nuts of tlae 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. 4 4 . m,a 2. ...a i

=. INTRODUCTION Remote visual examinations of the James A. Fitzpatrick Nuclear Power Plant reactor pressure vessel interior and its internal components were conducted from October 1 30,1996 through November 14,1996 per the requirements of New York Power Authority (NYPA) contract number C-91-Z0038. These examinations were conducted in accordance with ASME Section XI,1980 Edition, Winter 1981 Addenda, the L A. Fitzpatrick RFO 12 Controlled IVVI Checklist, Revision 3, and various Augmented Inspection Commitments. i l 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 Structures and j Interior Attachments to Reactor Vessels, Code Category BN-3 Removable Core Support Stmetures and numerous Augmented Inspections. Reference the attached Table for 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 v 4 Reactor Pressure Vessel Internals" dated October 25,1996. Examination personnel were qualified and certified in accordance with General Electric Procedure 386HA480 " Procedure for the Examination and Certification of Nondestructive Examination Personnel". The performance of the GERIS Beltline Accessibility study was conducted in accordance with General Electric Procedure ADM FPK-2019V0, Revision 1. All procedures were reviewed and approved prior to use by the applicable hTPA personnel in accordance with 1 A. Fitzpatrick APO-19-06, Revision 2. RECORDING AND EVALUATION l The Remote Visual Examinations of the Feedwater Spargers and associated Brackets were conducted using a Remotely Ope 6sted Underwater Vehicle (ROV) utilizing a RGB color camera. In addition the color camt.ra format 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 p lighting was provided for Enhanced Visual VT-1 examinations by use of a 500 watt l, auxiliary light. All examinations were recorded on Super VHS format video tape and data review and analysis was conducted either on-line in real time or post-examination by 'N/1 2 mooa .n.::

rO 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. EXAMINATION RESULTS Access Hole Cover The Shroud Support Access Hole Cover at 0 was examined and no recordable indications were reported. Core Spray Spargers 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 examined. As a result of these examinations an indication characterized as weld profile deficiency was recorded on spray nozzle D-28. The indication was documented on DER 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 The Loop A and Loop B Core Spray Piping Internal to the vessel was examined in two separate steps. The initial examination was performed to satisfy BWR VIP G recommendations and entailed an Enhanced VT-1 of all piping welds after power fV brushing. 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 indications 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 suppon brackets located at 45 and 135 were examined using the GE Phantom remotely 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 The J. A. Fitzpatrick Shroud was repaired during a the 1994/1995 refueling outage and as part of the IVVI scope of examinations various areas and components of the repair p were examined. These included Tie Rods at 15,135 and 255. In addition the Gusset d welds at those locations as well as 12" of the Shroud Support to Vessel weld SH9 each 3 m n a c, , d.':: /.'

side of the Gusset were examined. No recordable indications were noted as a result of these examinations Shroud Vertical Welds A representative sample of the Shroud Vertical and Ring Segment welds were examined using the Enhanced VT-1 technique after power bmshing. The required examinations of welds SVIB, 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 v.cre reported. The weld was reexamined using multiple camera angles - and enhanced supplemental lighting and the indications were evaluated as small welding anomalies. The examination of the ID surface of weld SVS A resulted in the recording of one crack like indication which was documented on DER 96-1490. During the OD examination of weld SVS A five (5) crack-like linear indications were recorded and 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 subsequent examinations. Shroud Circuni.'rential Weld Shroud circumferential weld SR2 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 bmshing. 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. Control Rod Drive Nozzle The nozzle inner radius section of the Control Rod Drive nozzle at 135* was examined and no recordable indications were noted. RPV Beltline Weld Survey As a part of scheduled IVVI activities a survey ofin-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 this data will be provided under a separate report. O 4 n n o ;, ,i

'/\\

_ =. -. _ i 4 .4 i Fuel Support Casting 34-07 e i During the movement of Control Blades within the reactor vessel an incident occurred that resulted in the dislodging of Fuel Support Casting 34-07. The incident was documented on DER %-1540 and the condition was corrected in accordance with NYPA Temporary Operating Procedure TOP-241 Rev. O. As part of the corrective action an examination of the Fuel Support Casting was performed (not part of the original IVVI workscope). No recordable indications were noted. In addition Control Blades and IRMs and LPRMs in the cells adjacent to loct. tion 34-07 were examined and no recordable i indications were reported. Fuel Support Castings General Electric refueling personnel performed the scheduled Control Rod Blade shuffle i utilizing the Remtek 11 tool. The use of this tool made the Fuel Support Castings in those i 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 j 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. O 5 oooO ,/ 4 P : : a & c' 4

James A. FitzPatrick 41 Lycoming, hem,Yo,k 13003 Msmorandum

== o @ New York Power V W Authority November 26, 1996 PEP-PO-96-355 To

Distribution From

P. Okas Subject : James A. FitzPatrick Nuclear Power Plant i

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. h bh P. Okas Sr. Project Engineer Engineering Programs 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) rh

_ ~. 9 o - o GE NudearEnergy ~ INSPECTION CHECKLIST Page I of 4 James A. Fitznatrick Station October 18,1996 19% RFI2 INSPECTION STATUS ,9/ D VVI C CKLIST REVISION _J COyO y,M (., [/ M[2h /' '9f (CHECK COMPLETE) . AI PROVED FOR NYPA BY: 4-MeJ 5 APPROVED FOR GE BY _ a. v e r COMPONENT ,WR { TYPE AUG EXAM PROCEDURE S H ID REPORT NOTES GE NYPA ,v-r. No. / REQ'D EXAM REVIEW r j[ Access flole Cover @ 0* 954941940 VT-1 SIL 462 VT-FPK-202VI An h l6 s Core Spray (CS) Upper C Spargers 95-09416 4 0 MVT-3 NUREGCR-VT-TPK-202VI Attachnwns !! 100% ofaccessible welds //e/d f4 ff,/0$ (Inlet T-Box 170') EVT-1 (T Box) 4523 A REF.2 OO /[ Cere t:vay (CS) tower D Spargers 9549416-00 MVT-l NUREGCR-VT-FPK-202VI Anaclaneve ll 100% ef accessible welds jh/cy 96 jf,jgl/( (Inlet T-Box 190*) EVT-I (T Bok) 4523 A REF. 2

42%

gl]Q Core Spray (CS) NIR @ 270* 95-09416-00 VT-1 REF. 2 VT-FPK-202VI Attacivnent l0 /r'2[4 Core Spray (CS) NIR @ 90* 95 09416 00 VT-1 REF. 2 VT-FPK-202VI Anacionent IO Core Spray (CS) Piping loop A @ 95 49416-00 MVT I Piping A SIL289 RI S2 A VT-FPK-202VI Anacinent 9 A 10 100% ofAable NNb welds 90* (2I welA) Cornponents (Elbows) REF. 2 A 1 EVT-I Piping welds and brackets to RPV Core Spray (CS) Piping Imop B @ 95-0941Mio MVT-1 Piping A Sit 289 RI S2 & VT-FPK-202VI Attachnwnt 9 A 10 100%ofeable MU#b 0 N welds 270' (22 welds) Components (Elbows) REF.2 A 3 EVT-1 Piping welds and trackets to RPV CoreSpray(CS) Upper ASpargers 954941640 MVT-l NUREGCR-VT-FPK-202VI Anaciunent il 100 laccesmile welds f/-/cfC f),M l (Inlet T-Box IJ') EVF-I (T Box) 4523 & REF. 2 Core Spray (CS)Imwr B Spargers 95-09416-00 MVT-l NUREGTR-VT-FPK-202VI Anschnwns 11 100%of-- ble welds (g./c-9( //, (:nlet T-Box 350*) EVT-1 (T Box) 4523 & REF. 2 cedwater Sparger @ 045* 95-0941740 VT-3 Ft.78436 VT-FPK-202VI Anaciunent 7 DER 954957NRC [ /8 con nan== can not be "J/ z A.f/ # repiacen ni deferred f NUREG 0619 Feedwater Sparger @ l35' 95-09417-00 VT-3 F1-78436 VT-FPK-202VI DER 954957NRC a comnutement can not be jf-sO N / replacenwns. deferred NUREG 0619 f m.ith e w $sFtk/A E

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O g v s 9' ~ lNSPECTION CHECKLIST GE Nudear Encrgy Page 2 of 4 James A Fitzpatrick Station October 18.1996 19% RF12 INSPECTION STATUS CONTROLLED IVVI CIECKLIST REVISION 3 (CHECK COMPLETE) COMPONENT WR EXAM TYPE AUG EXAM PROCEDURE SKETCH ID REPORT NOTES GE NYPA No. REQ'D 'JXAM REVIEW M Guide Rod - 0* Bracket Welds 9549421-00 VT-3 VT FPK-202VI Anadenent 2 gfc4r -cc, Guide Rod @ 0* 95-09421 00 VT-3 VT-FPK-202VI Anachmere 2 /tf e;.z -ec) f pg gy k Shroud - Gusset Plate Welds @ 015' 964002240 EVTI JPN-96-030 A VT-FPK-202VI Anachnunt I4 100% ofwelds aSOH A RGV(both sides) and 12"of weld at / REF.IA4 each side on H9(tois! / M 96 Ng/ 24") ([ Stroud -Gusset Plate Welds @ l3/ 96-00022 00 EVT-1 JPN-96-030 A VT-FPK-702VI Anachment l4 A 100% ofwelda nt SOH REF. I A 4 Drawing FW-26B A ROV (both sides) and 12 or-id. //w g p/it ct4 l l each side on H9 (total 24") [ Shroud - Gusset Plate Welds @ 255* 964002240 EVT-l JPN-96430 A VT-FPK-202VI Anadeners 14 A 100% ofwelds at SGH REF. I A 4 Drawing FW-26B A RGV(both sides) and i2 orweid e //-EG g -*.ch side on H9 (total 14") Shroud - Ring Segment Weld SV38 9640021-00 EVT-1 JPN-96-030 A YT-FPK-202VI Anaciv wnt IS A 100% ofwelds(33%of kN REF.IA4 Drawing FW-26B total areas) jfdl.T b tl 6 Shroud - Ring Segment Weld SV3E 96-00021 40 EVT-l JPN-96430 A VT-FPK-202VI Anadunent IS A 100*4 of welds (33% of REF. I A 4 Drawing FW-26B total areas) O' il c4 (lfthh Slwaud -Tie Rod @ 015* deg. 96-00019 4 0 VT-3 JPN-96430 A VT-FPK-202VI Anacfunent 3i Tie rods A hO ff n,7(, j EVT-l (For Nut REF. I A 4 ADWG FV-268 locking dences, j j engagenent only) Reference 4 criticalcontact areas. f F Shromi-Tie Rod @ 135' deg. 9640019-00 VT-3 JPN-96-030 A VT-FPK-202VI Anachment 31 Tierods, Accessible MD h[ EVT-1 (For Nut REF.IA4 ADWG FV-26B locking devices, g,jg <f engagement only) Reference 4 critical contact arent FTzlNSPS DOC

V U Oml m GE NuclearEnergy ~ INSPECTION CHECKLIST Page 3 of 4 James A. Fitzpatrick Station October 18.1996 19% PF12 INSPECTION STATUS COPTTROLLED IVVI CHECKLIST REVISION 3 (CHECK COMPLETE) COMPONE?ff WR EXAM TYPE AUG EXAM PROCEDURE SKETCH ID REPORT NOTES GE NYPA No. REQ'D EXAM REVIEW [gg Shrcud - Te Rod @ 235% 96-00019 40 VF-3 JPN-96-030 A VT-FPK 202VI Attachmere 31 A Tie rods, Accessible ] EVT-1 (For Nur REF,1 DWO FV 26B locking dences, t Reference 4 critical contact arent fj,/f, ff I (_Z4ff. engny..-. only) S!woud - Weld 112 azinusths 80

to 964002140 EVT-1 JPN-96-030 A VT-FPK-202VI Attachment IS As noted for weldR50D g

REF.I ADWG FV26B only. Weld to be hY 130* and 320* to 350* ' pectedis 4 gg m approximately IW [ Sivoud - Weld SVIB 96-00020-00 EVT-1 JPN-96-030 A VT-FPK-202VI Attachment IS A 100% weld (OD) REF. I A 4 DWG FV 268 f )Q'J(y D ll Slumid - Weld SV II'. 94Wm2040 IVF1 JPN-96430 A VF-t PK-202VI Attadment 15 A 100% welJ (OD) [ REF. I A 4 DWG FV268 gg off, gh fik M Slwom!- Weld SV2 n 96 40020-00 INT-I JPN-96 030 A vr FPK-202VI Attadm-nt 15 A 100% weLi(OD) lt'll'h stk t L L ltEF.I A 4 DWG FV 26B S!woud - Weld SV4 A 964002040 EVT-1 JPN-96430 A VT-FPK-202VI 5 A 100% weld (ID OD) hN REF.IA4 DWO FV 26B j/-// Cfs t\\\\t%%( S!woud - Weld SYS A 96-00020 4 0 EVT-1 JPN-96430 A VT-FPK-202VI Attachnwnt 15 A 100% weld (ID,OD) i k' REF.IA4 DWO FV26B

W-96 //sh/

N M Siwoud - Weld SV6A 96-00020 40 EVT-l JPN-96 030 A VT-FPK-202VI Attactunent l5 A 100% wehf(ID. OD) llr/l'7(a uht REF. I A 4 DWO FV 268 / Sivnud - Weld SV711 964002040 EVT1 JPN-96-030 & Yr-FPK-202VI 5 A 100% weld (OD) REF. I A 4 DWO FV 268 /f /// 7(c, Ohhf. S!woud - Weld SYSA 96-00020-00 EVT-l JPN-96-030 A VT-FPK-202VI Attachment IS A 100% weld (OD) b M REF.1 & 4 DWO FV268 y f-f y 'f 6 dh(, Shroud - Weld SV9C 964002040 EVT-1 JPN-96-030 A VT-FPK-202VI Attachmera 15 A 100% weld (OD only ) [ REF.1 & 4 DWO FV268 g.yg, 4 tt tt h nzusn wc

f) ) GE NudearEnergy INSPECTION CHECKLIST Page 4 of 4 James A. Filzpatrick Station October 18,1996 19% RF12 INSPECTION STATUS CONTROLLED IVVI CHECKLIST REVISION 3 (CHECK COMPLETE) COMPONENT WR EXAM TYPE AUG EXAM PROCEDURE SKETCH ID REPORT NOTES GE NYPA No. REQ'D EXAM REVIEW N CRD Nozzle NIR - 95494 tit-00 VT! NUREG 0619 VT-FPK-202VI Attad....t 19 Jg RPV Behline Weld Survey 954942040 N/A VT-FPK-202VI Attaciuners I ,g Fuel Support Castings e/A VT-3 VT-FPK-202V1 4 P6ME Sect. XI (BN-3) Note 2 REFERENCE 1 IlWRV!P ~ Guideline for Reimpection of flWR Core Strcuds. EPRI TR 105747 ( DWRVIP-07). Sectkm 4 (1996) REFERENCE 2 !!WR VIP Standards for " Visual lnspedim of core Spray Piping. Spargers, and Associated Components ~(1996). REFERENCE 3 IlWRVIP - BWR Core Spray Intemals impectite and I' law Evaluation Guidelines (BWRVIP - t 8) TR - 106740, Revised Project B301. Dran Repat. June,1996. l REFERENCE 4 Inspection and Acceptance Criterta for the Repaired Shroud, Resiston 1; by !LIPR. July.1996. Will have Ultrasonic availibility for Core Sivoud and Core Spray piping NOTE 1: The following Fuel Support Castings were visually examined by G.E. and NYPA Level III 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, 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. rrmsps ooc

James A. FitrPetrick l* t"i,~ ~ Lycomws, New Yort: 13003 315 M12@

>f Authorlihr New York Power (l

1Gf November 14, 1996 PEP-PO-96-341 To R. Plasse From P. Okas

James A. FitzPatrick Nuclear Power Plant Subject IVVI Core Shroud Inspection Results-RO12 Meetino 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 SV5A. I have attached for your information and use a copy of the sumn.ary report discussed with the Residents.

(~') If you have any questions on the attached material, please call me \\s / at JAF x-6624. . Okas Sr. Project Engineer Engineering Programs cc: M.

Colomb, T.

Dougherty, W.

Josiger, D.

Lindsey, R.

Penny,

r. Ruddy, A.

Zaremba, Records Sta-WPO; (all w/ attach) e~x

l JAMES A. FITZPATRICK NUCLEAR POWER PLANT l CORE SHROUD INSPECTION AND RESULTS-RO12

SUMMARY

REPORT FOR MEETING WITH NRC AT JAF-11/14/96 ipG

1. COMM TMENT IN LETTER TO NRC JPN-96-030-01 FOR R12/C13 RFC

Implement augmented ISI plan for the core shroud tie red assemblies and core shroud welds per EPRI TR-105747.

2. INDUSTRY GUIDELINES ANL 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 the Repaired Shroud by MPR (9/96).

3. INSPECTION REQUIREMENTS, RESULTS AND CONCLUSIONS Inspect 25% of all vertical welds not structurally replaced a) by the shroud repair (EPRI). Inspect 50% of vertical welds in Belt Line Region (H3 to H6) (GE-NE).

/~h k-) 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/CD. Criteria Met: Inspected 100% of accessible welds ID/OD where crack like indications were detected, (SVSA weld). d) If cracking at individual weld is less than or equal to 10 of weld, then inspection is complete. Otherwise, percent 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. r~ g O

T,EACTOR PRESSURE VESSEL IMERNAL VISUAL EXAMINATION DATA SHEET Gk.) GE NucIzr Energy Prooduro No. VT.FPK-202V1, RevtSioni Page of 5 - Shroud - WELD SV5A Page 1 of 2 PLANT: UNIT: OUTAGE: IDENTIFICATION OF COMPONENT (S) EXAMINED: j James A. 1 RFO 12 Shroud - Weld No. SV5A Fitzpatrick EVT-1 For welds & Tie Rod Nut Engagement Station VT-3 For Tie Rod Assembly TECHNIQUE EQUIPMENT LIGHTING TOOLS RESOLUTION

IEWoTE a REWoTE SM Vioso a HilNTENSITY c stoat Box o VT.t,1/32* uht l

0 oiRECT C REMoTtCotoRVCEo o FLASMuGHT o BiNoCutAR$ x 0 00t* wire O MIRROR 0 AM8iENT Q oTHER x 0 0C05* w1RE Q MAoNiriER c oTHER NA Q VT 3 O oTHEst c oTHER Reference (s)/ Cross Reference (s)(e s veeoraceid/counterorvios etcS TAPE NOS. 96-13,96-16, 96-17,AND 96-18 EXAMINATION CHECKLIST EXAMINATION RESULTS / REMARKS DESCRIPTION /3 c.,,. ex.on a c..n,=a uw o ~oei.,.., amo. nonae c ~m td v.c. canamon a e. s a su..u. u w s u -fani..eem e = ~Ri N. c a o

e. m.ncyno. cion v e..n<eue Tm.

ot n.,oc.i.a wi .a u co,. m.i. . nam. =,mo. If cond.on. 4 9hfl.d dunng e..K.ne.uon.. r.Qwr.d o.qqr.onO O NRI NA g /[//'J/M e 22 x.oon. ~ wi.e.,.. e c. c.i ces..n. m. me.e.aavan. coco. e m.

e. v.c..cc.n

- s u,.ca ia. ecmo x e/ iuoicAfon nofso Axiat to frE wsto APenox. ir2 incn is tE~cT-APPROX. 30 INCHES rRoM CtRcVMrRENTIAt wEto SH4 I ////y# . = =.ner.ea, c.onee..ne=a T%.. e...iocm o .ne.ce,.em.no A w io,o.a. 3 n eono on. v...n a.o amna u.umn.uon..r r.o,n o.c.amon x al.n= rus nEtEvtwT inoicATens noTso nErsnEnce ATTAcuto onAwisc rea oiMENSCNS AND APPRoJ0 MATS toCATCN e 22 s.. . e. u.o. nu e e.. a m em cant = wo.ciinoa.ons. n maaoon.. no.4 avano u.oma. n, r.o.on.or.ono a um wA e 22 2. e22 3., a 22 s..ac.on. n,oua o en., w, ,.a av = n,io =.onn.o n.cora u cuan norar .e u n,=a ui =n.4. x o um weto wo svs*vunTicAtwcto o so-I con.om e r. noo A,, y o a um wA nErERancs ArrAcsuori st ron Tie noo wumTow l l y NYPAISS o.t.////J[f f i En,n..,ine R.*.. o.t. NYP v w Examiner's Signature Independent Review Signature M M 9[ K. RO EAU f M,BI I R.L.KEcK 'aan a=* o =i. VT Level 11 Date 11/11/96 VT Level 11 Date 11/12/96 A-Sketches are provided for convenoence purposes only and enay not represent actualplant configuration and are not to scale 8C0" coC

1 l l REACTOR PRESSURE VESSEL INTERNAL VISUAL EXAMINATION DATA SHEET

^)

GE Nuclear Energy l,[l (t p promour.no.vr rex.2ervi,R.vs oni Page of

Attachment 15 - Shroud - ACPE noiesrvoa care,sena, 0 Y'"XlY
40d 4,r;if"4 C'U CMdUD d.D 9

8 0,VZ. *,4A'/,4f., J.deAtTCO CAJ CMdUd 40 O For Shroua tayout. refer to NYPA & 2. " 4 04 C/fCdO/x)4L 46 d4r[D orawing #FV 268. Latest Revision gg g g,6Cdd 6 D, i -- l & / ~46NG/7*dd/,4)4b p p _n g$3 ~ / AMfd0 C'US$0 f t p' l ll lh'll @l l 1 u w-o ~ : : i ll C N SHA000 Z~O. /

I

/ 4C4Cdfd,0/d*9L @ 21 1 an- %p 8 p AcM rco en s k eoD 6 D. ~3 O 90 ocTG: forgt, scs]6ra l WD JDo /64 f/o MS H4 '(, M'" 9i e u.o xe. S @ 6 '*. l ro rst. sene.ra e r 10 dx$ic.4 rienS /s K.* g, I qg T/lE56 /s0D/6A7~OQf 8AE 6,h? d.f /XE" H5 ~ /4' A247046 )1 h6A N A6B H7 / H8 hD m JAMES A. FliZPATRICK NUCLEAR POVER PLANT REACTOR SHROUD SHOVING VELDS Hi THROUGH H8 ";'.;L g f p k "~ p@ y o [ Ost. NY R.v V sminer's Signature independent Review Signature // [g ~ ra M b h'( K. HoBloEAU -.a ....p/5/4 i .. L. - i v i to.i ii o.t. un m. vi i...si iii o.t. u n 2,se Sker:hes are provided for convenience curcoses only and may not represent actualplant configuration and are not to scale}}

ML20136B705

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