Text

Forwards Suppl Response to NRC Bulletin 88-009, Thimble Tube Thinning... & Rept, ...Flux Thimbe Thermocouple Ultrasonic Profilometry & Eddy Current Encircling Coil Insp of Stored Thimble Tubes Jul-Aug 1993
	ML18100B132
Person / Time
Site:	Salem
Issue date:	12/20/1993
From:	Hagan J; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18100B133	List: ML18100B132; ML20069M222;
References
	IEB-88-009, IEB-88-9, NLR-N93190, NUDOCS 9406210238
	Download: ML18100B132 (93)
	v • d • e

Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations DEC 2 0 1993 NLR-N93190 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NRC BULLETIN 88-09 THIMBLE TUBE THINNING IN WESTINGHOUSE REACTORS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated November 2, 1988 (ref: NLR-N88161), Public Service Electric & Gas Company (PSE&G) provided its response to NRC Bulletin 88-09, "Thimble Tube Thinning in Westinghouse Reactors."

During the Unit 1 seventh refueling outage, and the Unit 2 fourth refueling outage, PSE&G replaced the thimble tubes with an improved design.

As a result of that modification, PSE&G discontinued its inspection program, but committed to provide a supplemental response with an evaluation of the new design at a later date. contains PSE&G's supplemental response to Bulletin 88-09. contains a report entitled "Inspection Results of Flux Thimble Thermocouple Ultrasonic Profilometry and Eddy Current Encircling Coil Inspection of Stored Thimble Tubes" performed by ABB Combustion Engineering Nuclear Services Company.

Based upon ABB's inspection results, PSE&G feels no periodic inspections are required.

PSE&G has completed all commitments required by Bulletin 88-09.

Based on the results of the inspection on the improved flux thimble design, no further submittals are anticipated.

Should there be any questions with regard to this submittal, please do not hesitate to contact us.

9406210238 931220 PDR ADOCK 05000272 Q

PDR

Document Control Desk NLR-N93190 c

Mr. J. c. Stone Licensing Project Manager Mr. c. Marschall Senior Resident Inspector 2

Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Manager IV New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 DEC20 aJ3

.Y ATTACHMENT 1

NRC BULLETIN 88 SUPPLEMENTAL RESPONSE.

THIMBLE THINNING - WESTINGHOUSE REACTORS.

PSE&G THIMBLE TUBE ONE TIME INSPECTION.

PSE&G FTTC INSPECTION PSE&G proposes to take exception to Part 1, of NRC Bulletin NO. 88-09.

PSE&G performed a one time Flux Thimble Thermocouple (FTTC) inspection.

During the Unit 1, 10th Refueling outage, 6 FTTCs were replaced in kind.

The flux thimbles were replaced because they were inaccessible to the incore neutron detectors, no thimble wear issues were involved. These 6 thimbles were used as the representative sample providing information as to the status of all the FTTCs.

In July of 1993, PSE&G contracted ABB/CE to inspect the thimble tubes stored in the Unit 1 spent fuel pool. ABB/CE provided personnel and equipment to perform the examination using a combination UT profilometry and eddy current encircling coil technique. The examination fixture was mounted in an empty spent fuel pool cell. The examination fixture consisted of 8 focused UT transducers equally spaced around the circumference of the thimble tube. Each focused UT transducer measured an axial path approximately.010 inch wide without making physical contact with the thimble tube. Off-line analysis was used to obtain the axial and circumferential extent and profile of all OD indications on each thimble tube.

The examination fixture also contained an encircling eddy current coil which locates tubing cracks and provides a secondary general sizing of any thimble tube wastage.

All examinations were conducted underwater for ALARA considerations.

Each thimble end was placed in a special tool which mechanically restored the flattened cut end of the thimble tube to its original shape. Underwater Hydroproducts cameras were used to visually examine the outside surface of the thimble tubes after the UT/ET inspection is performed.

The results of the report: "No significant wear was detected on any of the FTTCs. No FTTC tested had greater than.002 wear detected by ultrasonics at any elevation. Cross sectional area wall loss is therefore less than 3% at any elevation. "

Bulletin 88-09 entitled "Thimble Tube Thinning in Westinghouse Reactors."

Bulletin 88-09 entitled "Thimble Tube Thinning in Westinghouse Reactors,"

required licensees to submit a written response that (a) confirms that an inspection program consistent with Part 1 of the bulletin has been established and (b) confirms that inspections of the thimble tubes have been performed and corrective actions have been taken.

ACTION REQUESTED IAW Part 1, of NRC Bulletin NO. 88-09 each addressee is requested to establish an inspection program to monitor thimble tube performance.

Part 1 states that this inspection program should include:

the establishment, with technical justification, of appropriate thimble tube wear acceptance criterion (for example, percent throughwall loss). This acceptance criterion should include allowances for such items as inspection methodology and wear scar geometry uncertainties.

the establishment, with technical justification, of an appropriate inspection frequency (for example, every refueling outage).

the establishment of an inspection methodology that is capable of adequately detecting wear of the thimble tubes (such as eddy current testing).

ROOT CAUSE In February 1982, all Unit 1 flux thimbles were replaced. Three (3) leaking thimbles were sectioned and sent to the Westinghouse Nuclear Technology division hot cell facility for metallurgical investigation.

The metallurgical exams concluded: the through wall defect on the samples is formed as a result of repeated mechanical wear on a localized region on the O.D. surface of the tubing. The profile of the fuel assembly lower nozzle block penetration was clearly worn into the incore thimble tube over ~160° of the circumference. The decision is made to begin eddy current testing.

In 1987, PSE&G contracted the services of Combustion Engineering Nuclear Services (ABB CE) to conduct Salem specific tests to model the wear phenomenon and design wear resistant flux thimbles. These tests identified 2

the specific root cause of the thimble leaks at Salem; flow induced thimble tube vibration. PSE&G installed Flux Thimble Thermocouples (FTTCs),

which are thimble tubes of improved design, on Salem Units 1 and 2 during their seventh and fourth refueling outages respectively. This improved design, implemented with modifications to the Salem units lower core plate, greatly reduce flow induced vibrations.

CORRECTIVE ACTION - IMPROVED THIMBLE DESIGN FTTC assemblies consist of a seamless cold drawn outer pressure boundary tube and an inner tube to act as a dry guide path for the moveable incore neutron detectors. The outer sheath is designed to withstand 2500 psig and 650 °F, the inner sheath is also designed for these conditions. The tubes are fabricated from high strength lnconnel 600 as opposed to previously used stainless steel.

Type K (chromel-alumel) thermocouples and spacer cables are installed in the annulus between the two tubes. In addition the area of potential wear indication on these tubes is chrome plated. Also, wear inserts were installed in the lower core support plate reducing the forcing function and amplitude of flux thimble vibrational motion.

The addition of wear inserts decreases the wear rate by a factor of at least four by limiting the amplitude of the tube vibrations. The increase in wear area that the inserts afford decreases the wear rate by at least a factor of two. And finally, the chrome plating of the FTTC in the fuel bottom nozzle area reduces the wear rate by at least a factor of five. These reductions are multiplicative, and result in a possible reduction in the wear rate by a factor of forty. However to be conservative, ABB/CE concluded that the overall wear rate will be reduced by a factor of twenty.

Since the modified thimble tube design uses two concentric tubes with cable wound around the inner tube, eddy current testing conducted from within the inner tube would not yield meaningful results. As such PSE&G discontinued its program utilizing eddy current testing. No alternative in service inspection techniques existed at that time which would adequately detect wear from the ID of the thimble.

3 11

FTTC OPERATING PERFORMANCE.

Prior to the installation of the FTTCs. assuming a constant wall loss vs.

time, we had seen wear rates as high as 5% wall/month. Generally, wear appeared to progress at a rate of ~2% wall/month.

The results of the ABB/CE report: "No significant wear was detected on any of the FTTCs. No FTTC tested had greater than.002" wear detected by ultrasonics at any elevation. Cross sectional area wall loss is therefore less than 3% at any elevation. "

Without the new FTTC design, these thimble could have shown 50 to 90% wall loss. In service time: Unit 7, Cycle 8, to the end of Cycle 10.

As of November. 1993. no FTTC wear induced failures have occurred on either Salem Unit.

PSE&G's FTTC INSPECTION PHILOSOPHY In response to Bulletin 88-09, PSE&G committed to reevaluate the need for future thimble inspections. This reevaluation would be based on advancements made in in service inspection techniques and the operating performance of the FTTC assemblies. Within four months after the start of the Unit 2 seventh refueling outage, PSE&G was to supplement the original Bulletin response. This supplemental response outlines PSE&G thimble inspection plans.

The inspection data shows the design of the FTTCs reduces the thimble wear rate below the threshold value of concern. Instead of continuing to inspect wearing thimble tubes, PSE&G has proactively replaced and modified the thimble tubes so that wear is greatly reduced. Using a conservative interpretation of the wear rate reduction of a factor of twenty.

and the results of the ABB/CE inspection. it is PSE&G's position that no further inspections will be necessary.

Attachments

1.

2.

3.

4.

5.

Table 1 Figure 1 Figure 2 Figure 3 Report

- Salem flux thimble wear history.

- FTTC cross section.

- Wear insert.

- Core map showing inspected FTTC locations.

- ABB/CE final inspection report.

4

l SALEM GENERATING STATION, UNIT 1 - EQUIPMENT HISTORY:

INCORE FLUX THIMBLE WEAR Date Cycle# Vendor Thimble DescriQtion April 3

NIA H-11 Flux thimble leaking, cause unknown. Thimble isolated.

1981 July 3

N/A A-09 Flux thimble leaking, cause unknown. Thimble isolated.

1981 Nov.

3 N/A D-04 Flux thimble leaking, cause unknown. Thimble isolated.

1981 Feb.

1R3 NUS ALL All flux thimbles were replaced. The 3 leaking thimbles were 1982 sectioned and sent to the Westinghouse Nuclear Technology division hot cell facility for metallurgical investigation.

Aug.

4 West.

H-11, The metallurgical exams concluded: the through wall defect 1982 A-09, on the samples is formed as a result of repeated mechanical D-04 wear on a localized region on the O.D. surface of the tubing.

The decision is made to begin eddy current testing.

Oct.

1R4 Cramer 57insp Cramer & Lindell concluded: The "new" thimble tubes are in good 1982 1

conditions and no damage was recorded. 1 0 tubes were inspected Lindell blocked to the core plate.

July 1R5 Cramer 3 tubes Jan. 28, 1985; Cramer & Lindell concluded: a total of 22 tubes 1984

>40%. recorded possible external damage or inconsistencies at the core Lindell 4 tubes plate.

20 to 40%. 3 June 12, 1985; On the basis of a review of the results of the tubes metallurgical exam, Cramer & Lindell establishes external

< 20% vibrational/fretting wear as the cause of the thimble eddy current wall indications. Three (3) thimbles are isolated.

loss April 1R6 PSE&G ALL 32 thimbles with > 20% wall loss. 10 thimbles isolated.

1986 Res. &

Testing Lab June 7

N/A N/A A major design change is planned. Requests for proposals are 1986 sent to West., GE, B&W and CE to design, fabricate and install new flux thimbles.

Mar.

7 Comb.

NIA Combustion Engineering wear tests an improved thimble 1987 Eng.

tube design. Flux Thimble Thermocouples (FTTCsJ.

Oct. -

1R7 Comb.

ALL New FTTCs installed. Tube inside a tube, chrome plated in Dec.

Eng.

the wear region. The wear area is increased and cross flow 1987 vibration inhibited through the installation of wear inserts.

Eddy current exams of the thimbles were discontinued since no company provided this service for tube within a tube designs.

Mar 1R9 N/A P-09 FTTC P-09 kinked in two places during flux thimble 1991 re-insertion after core reload. Replacement planned during 1R10.

June 1992 July 1993 Oct 1993 1R10 11 11 West P-09, H-06, F-01, F-07, B-03, &

L-05.

ABB/CE P-09, H-06, F-01, F-07, B-03, &

L-05.

ABB/CE P-09, H-06, F-01, F-07, 8-03, &

L-05.

Flux thimbles were replaced with FTTCs purchased from Combustion Engineering. Six (6) FTTCs were replaced for 2 reasons:

1. All six (6) FTTCs were inaccessible to incore detectors.

2. 5-9 FlTCs was the minimum order from CE. No FTTC wear issues were involved.

ABB/CE performed a combination ultrasonic profilimetry, eddy current encircling coil and visual inspection of the irradiated ends of the FlTCs. The irradiated ends of the six (6) thimbles, (13 pieces), were stored in the Unit 1, Spent Fuel Pool, the non-irradiated sections of the thimbles were disposed of. The inspection of the RISO" chrome plated sections of the FTTCs was the primary goal.

Note: This inspection was performed in the Salem Unit 1, Spent Fuel Storage Pool.

ABB/CE final inspection report is received. The results of the report: "No significant wear was detected on any of the FTTCs. No FTTC tested had greater than.002" wear detected by ultrasonics at any elevation. Cross sectional area wall loss is therefore Jess than 3% at any elevation."

6

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SALEM NUCLEAR GENERATING STATION UNIT NO. 1 S1.RE-HA.Z2-0012(Q)

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Jl 1111

,.,1919 PUBLIC SERVICE ELECTRIC & GAS SALEM NUCLEAR POWER STATION UNIT 1 Flux Thimble Thermocouple Ultrasonic Profilometry and Eddy Current Encircling Coil Inspection of Stored Thimble Tubes FINAL REPORT PACKAGE July - August 1993 ABB Combustion Engineering Nuclear Services Combustion Engineering, Inc.

~406210246 931220 QDR ADOCK 05000272 PDr:::*

P.O. Box 500 1000 Prospect Hill Road Windsor. CT 06095-0500 Telephone (203) 688-1911 Fax (203) 285-9530

SECTION 1 SECTION 2 SECTION 3 SECTION 4 SECTION 5 TABLE OF CONTENTS Flux Thimble Thermocouple Ultrasonic Profilometry and Eddy Current Encircling Coil Inspection of Stored Thimble Tubes.

Inspection Results.

Technical Operating Procedure, SALEM-400-019, Rev.

o with Work Order number 930615152 ACT:

01, Chemical Item Classification Permit and Transient Combustible Worksheet.

Personnel Certifications with Signature Log Equipment Certifications Certificate of Conformance

Jl 1111

,.,1,111 Flux Thimble Thermocouple Ultrasonic Profilometry and Eddy Current Encircling Coil of Stored Thimble Tubes Inspection Results From SALEM UNIT 1 July/August, 1993 A Report To Public Service Electric & Gas From ABB Combustion Engineering Nuclear Power Outage Services Windsor, Connecticut ABB Combustion Engineering Nuclear Services Combustion Engineering, Inc.

P.O. Box 500 1000 Prospect Hill Road Windsor, CT 06095-0500 Telephone (203) 688-1911 Fax (203) 285-9530

Jl 1111

,.,1919 October 15, 1993 To:

Public Service Electric & Gas Salem Power station Unit 1 CERTIFICATE OF CONFORMANCE ABB Combustion Engineering Nuclear Services hereby certifies that the activities associated with the Flux Thimble Thermocouple Ultrasonic Profilometry and Eddy current Encircling Coil Inspection of Stored Thimble Tubes at the Salem Power Station Unit 1 site during July and August, 1993 are in conformance with the PSE&G Purchase Orders, Numbers Pl-428978 and Pl-428976 including addenda and attachments. Documentation attesting to this conformance is contained within this Final Report Package.

/

~t<o Victor Roy Supervisor, Core Component Services ABB Combustion Engineering Nuclear Services Combustion Engineering, Inc.

P.O. Box 500 1000 Prospect Hill Road Windsor, CT 06095-0500 Telephone (203) 688-1911 Fax (203) 285-9530

1.0 Introduction Eleven stored thimble tubes were eddy current, ultrasonically and visually inspected at the Salem Unit 1 Nuclear station in July, August 1993.

A profilometry fixture utilized an ultrasonic technique to profile inspect thimble tube cladding for OD fretting wear and diameter changes.

An eddy current encircling coil was run in parallel with the ultrasonics inspection to detect cladding cracks and provided relative sizing for wear.

The profile examination was performed in accordance with ABB Combustion Engineering Procedure Number Salem-400-019, Revision o, Procedure for the Examination of Thimble Tubes.

2.0 summary The reported inspection data was analyzed to the requirements specified in the PSE&G Purchase Order number Pl-428976.

All thimble tube wear was analyzed using the UT profile data. The thimble tubes were examined for cracks by analyzing the eddy current encircling coil data and the results are reported in Section 5.0 and Table 2, "Encircling Coil Results".

No significant wear was detected on any of the thimble tubes. The largest indication detected was located on tube number 8 in the chrome plated portion of the thimble tube (less than 30.0"). This indication was determined and visually verified as an aborted tube cut scar, 0.021 inch deep. The attempted cut had displaced some cladding material outward and ovalized the tubing directly below the scar.

This aborted thimble cut location exhibited the highest amplitude eddy current signal reported as wear on any thimble tube.

Thimble tube number 7 also contained a partial tube cut, although not as deep as number 8. This was reported as the second largest wear by eddy current.

Thimble tube numbers 3, 4 & 9 had indications exhibiting "dent" characteristics, (Figure 5 ), that were not discernable with ultrasonics because of their extremely small size. Chrome transition areas (where they existed) were easily discernable with eddy current ( Figures 7 & 8) and could also be detected with ultrasonics (Figure'9).

Chrome transition areas are listed in Table 2. No cladding bulging or ovality was detected in the thimble tubes tested.

No thimble tubing tested had greater than 0.002 inch wear detected by ultrasonics at any elevation. Cross sectional area wall loss (CAWL) is therefore less than 3 percent at any elevation.

1

3.0 Measurement Method There were two types of testing performed during the examination of stored thimble tubes at Salem 1 Nuclear Station in July/ August, 1993.

Encircling coil testing is performed for the detection of cladding cracks. Based on the signal response from the ECT results the corresponding UT data was reviewed to quantify and provide cladding profiles of all indic~tions detected.

Profilometry testing is done using an array of 8 ultrasonic transducers evenly spaced around the circumference of the thimble (every 45 degrees).

The UT transducers measure outside diameter changes and the changes in thimble cladding thickness.

The UT transducers also determine the circumferential extent of any indications found.

Figure 1 shows the relative position of the 8 UT transducers and the eddy current encircling coil within the array housing.

3.1 Encircling Coil Test A modified Zetec MIZ-lSA eddy current tester was utilized for the encircling coil inspection.

An ADIC Digital Data Recorder was used to record the encircling coil data.

Eleven thimble tubes were inspected. The thimble tube lengths were estimated to be between 36.0 inches and 180.0 inches. The actual length of thimble tubes inspected varied between 24.0 and 144.0 inches. The inspection fixture was capable of inspecting up to 144.0 inches at a time. Eddy current and ultrasonic inspections took place during the withdrawal of the thimble tube from the inspection station.

The thimble tubes were manipulated and withdrawn by hand; by individuals using two poles, vice grip equipped. A steady rate of withdrawal was attempted, however most of the thimble tubes were bent (in several directions) and a constant rate of withdrawal was impossible. Therefore, length and location estimations are approximate. Indication analysis location calls are made from known locations, such as the cut end of the thimble tube or the chrome transition zones. Thimble tubes were turned around and retested (when required by the PSE&G representatives) to inspect the thimble tube material originally gripped by the vice grips, thus insuring the entire length of the thimble tube was inspected. Visual examinations were performed immediately after each NOE inspection.

2

The eddy current defect calibration standard used for set-up of the encircling coil test is composed of a representative sample of Inconel 600 tubing identical in size and composition to that of the flux thimble thermocouple cladding being tested.

The calibration standard contains manufactured defects designed to represent destructive mechanisms which have been observed to effect thimble tube cladding (see Figure 3).

These manufactured flaws are of a known measured size and shape and are described in detail on the calibration standard certification documentation included in this report.

Analysis is performed on the encircling coil data using a Zetec DDA4 (Digital Data Analysis System).

The DDA4 is a computerized data analysis system which uses a Hewlett Packard 9836 computer.

Specially designed software allows simultaneous display of operator selected testing parameters, strip chart recordings, CRT screen and numerical measurements (Figures 5 through 8).

The computer will automatically calculate signal phase angle, peak to peak voltage, percent circumferential area loss, and axial positions relative to any operator selected landmark.

The axial positions of all encircling coil indications are measured using the lower end cut or bullet nose tip of the thimble sample as the "O" inch datum point. The encircling coil frequency of 500 Khz/differential is used for the data analysis primary frequencyo An evaluation of OD wear indication signals is performed by comparing actual OD wear indication voltages to a cross-sectional area loss vs.

amplitude plot, derived from testing pre-characterized OD wear flaws on the defect calibration standard.

Cross-sectional area loss is analysed as well as depth of penetration to support plant accept/reject criteria.

The DDA4 requires three OD wear flaws (calibration points) from a calibration standard to generate an analysis curve.

The three calibration points are selected from the calibration standard by the data analyst and the same flaws are consistently used for analyzing all data tapes.

The following calibration point wear flaws were used from NSS-93-013 to generate the calibration curve.

0 0

0 B dimension, 0.017 = 85% wear (Depth) c dimension, o.oos = 40% wear D dimension, 0.004 = 20% wear

= 22% (CAWL) 10%

5%

o Set the dent signal horizontal (the first indication) with the initial signal excursion to the right.

o The MIZ-18A default span voltage is used for testing

Corrected and revised November a, 1993 3

o The Miz-lSA spans during analysis were adjusted such that the dent produced a signal amplitude of 2.06 volts on all channels.

o Based on UT results; comparing the cross-sectional area wall loss to the related ECT signal amplitude, all ECT signals were selected for further analysis using the UT data.

o ABB-CENS personnel analyzed both ECT and UT results in Windsor and graphed recorded voltage vs. percent wall loss to assure all indications would be reported.

The encircling coil signal amplitude for all wear indications is used as a secondary method of determining the relative cladding wall loss. In general the larger the wear signal amplitude the greater the wall loss. Based on the geometry and scar fretting process the larger voltage might not reflect a greater wall loss. This will be further discussed in Section 4.0 "Measurement Error".

3.2 Profile Test The N-16 Ultrasonic array system was utilized to profile inspect all eleven stored thimble tubes. As stated earlier UT data was recorded during the withdrawal of the thimble tube through the array housing.

The profile fixture array housing has eight (8) individual UT transducers spaced equally around the circumference of the rodlet, one transducer every 45 degrees.

Focused ultrasonic transducers are used to provide the most accurate profile measurement of the cylindrical thimble tube cladding surface.

The eight UT transducers in each array housing profile a 0.010 inch wide axial path over the entire length of the thimble.

A special array housing feature is the use of a constant distance reflector in front of each transducer.

The reflector provides a method of continuously monitoring for possible changes in the speed of sound due to water temperature variations or equipment malfunctions.

In effect a continual on-line calibration verification is performed using the fixed reflector.

The calibration standard, UT-Salem, with eight precision ground diameters from 0.3240 to 0.2917 inch is used to verify the actual speed of sound in the Spent Fuel Pool (SFP) water.

The actual sound speed is utilized during analysis to determine defect size.

The N-16 Ultrasonic Profile System indirectly measures the size of defects.

A sound energy pulse takes a specific amount of time to travel from the transducer to the rodlet surface and reflect back to the transducer.

When the sound 4

pulse encounters an indication the travel time is changed.

This travel time difference is used to determine the defect size.

The travel time difference in micro seconds is multiplied by the speed of sound (micro inches per second) in the SFP water, as determined with the calibration standard at the start of testing.

The travel time difference is comprised of round-trip travel and thus the result of the above calculation must be divided by 2 to yield the half path distance which is the size of the defect in inches.

All data is permanently recorded on an 800 Mbyte optical disk.

The data from a full length thimble piece (144 inches) fills approximately 0.5 MBytes of memory.

This capacity is based upon storing the complete A-scan, B-scan, and c-scan presentations to allow in-depth analysis at any time in the future.

The B-scans present a thimble tube profile trace and are pictured in Figures 9 through 12.

The A-scan can be used to verify the B-scan results and to measure wall thickness of the thimble tube cladding if desired.

All thimble tube data is stored as an ASCII file on the optical disk

A portion of which could be stored to another type of storage media.

4.0 Measurement Error The N-16 UT profile system has an accuracy of + 0.0005 inch based upon tests previously run at ABB CE.

A calibration defect standard fabricated by zetec Inc., Figure 13, was repeatedly inspected using the UT profile transducers.

The net result of these measurements is given in Table lA,B and shows the UT measurements are accurate to +/- 0.0005 inch.

The encircling coil has an accuracy of +/- 0.002 inch for OD wear depth estimates when the circumferential wear extent is known (an amplitude analysis is performed). The wear depth versus Amplitude Plots used to determine wear depth estimates was developed using the encircling coil data from the calibration standard wear defects.

A best fit curve was then drawn through the data points. The curve used to reduce the eddy current encircling coil data is conservative, i.e. it overestimates wear for wear scars accurately duplicated by the calibration standard.

The encircling coil analysis results have an additional conservatism due to the work hardening of the cladding which occurs as the thimble vibrates against the lower core plate transitions and guide paths

Work hardening changes the conductivity of the cladding material amplifying the eddy current signal from a guide induced wear scar relative to an equal size wear scar on the eddy current calibration standard.

The calibration standard defects are not work 5

hardened and thus the wear depth vs. amplitude plot, derived from the calibration standard defects does not produce accurate wear scar estimates for work hardened thimble tube cladding wear.

The wear depth vs. Amplitude Plot yields conservative wear estimates for work hardened wear since the amplified signals yield larger wear depth estimates. The profile fingers on the coil are not affected by the work hardening and thus a decrease in the size estimate of the wall depths is expected when the profile results are compared to the encircling coil results.

5.0 Encircling Coil Results The encircling coil analysis results are tabulated in Table 2 for all eleven thimble's. Typical DDA4 (Zetec analysis computer) screen displays are shown in Figures 5 through 8.

All axial measurements are given from the cut tip or bullet nose of the sample.

Operating limitations inherent to the hand operating of the handling poles and the bent condition of thimble samples prevented the full length inspection of the thimble tubes during one pass. During the inspection process no significant ECT indications were observed. A detailed analysis of the data concluded that no existence of wear indications or bulging were detected. Uniform and repeatable ECT signal response, on all absolute channels, was achieved from the region with chrome coatings.

OD wear indications are based upon an amplitude the percent wall loss).

thimble.

reported as a percent wall loss, analysis (voltage size determines All guide wear is reported for each Estimated thimble lengths and estimated inspection lengths are listed below:

Thimble Actual Inspected Condition Chrome section No.

length length present 1

60 11 24 11 bent,two ways (no) 2 180 11 144 11 bent,bottom 12 11 (yes), 20 11 3

168 11 48 11 bent,into a (no) shepherd's hook 4

168 11 132 11 bent,into a (yes), full,30" shepherd's hook 5

180 11 144" curved (yes),

no bullet nose 6

Thimble Actual Inspected Condition Chrome section No.

length length present 6

168 11 144 11 curved, stuck (no) 134 11 curved (no) two sided 7

156 11 144 11 straight (yes) 12 11 bullet nose 144 11 straight see above 8

180 11 144 11 straight (yes) 15 11 cut attempt in chrome, bullet nose 134 11 straight see above 9

132 11 120 11 curved (no) bullet nose 10 120 11 108 11 straight (yes) 18 11 (part of no.8?)

11 180 11 132 11 straight (yes) 10 11 bullet nose 12 24 11 no NDE straight (no) VT only 13 n/a n/a bent stuck in basket The following is a brief explanation of the abbreviations used in Table 2:

CHROME -

DENT WEAR NDD Transition area, from Inconel 600 to Inconel 600 with chrome Deformation of the cladding without loss of material Sliding or fretting phenomena wear, elevation and wear method undetermined, samples without bullet noses or full chrome sections could not unequivocally be identified as to core location or positioning at lower core plate.

No Detectable Defect, 7

6.0 UT PROFILE RESULTS The UT profile inspection evaluated wear data to determine the extent of wear on tube samples at Salem Unit 1.

The UT profile displays for the inspection are presented in Figures 9 through 12. Typical examples of wear are attached.

A UT display interpretation key is provided, (Figure 4 A, B, C).

A display of the largest guide fretting wears (including the attempted cut on thimble number 8) are presented in the UT profile results Figures 10, 11.

Thimbles not shown had no cross-sectional area wall loss wear found on any thimble.

The displays presented in Figures 9 through 12 are composed of multiple B-scan (profile) displays.

The number of B scans presented is related to the circumferential extent of each individual indication.

Only the attempted thimble cuts on thimble numbers 7 and 8 displayed wear on more than one circumferential channel. The circumferential extent is based upon which transducers detect the indication.

The transducers with only the deepest indications are typically displayed on B scans.

8

Ultrasonic Measurement of the Tube Wall Thickness Along the Wear Scar Standard (A)

(B)

As built Ultrasonic Measuring Location Measurement Measurement Deviation (inch)

(inch)

(B - A =

inch)

Average Wa 11

.0250

.0250 0

Wearscar "A"

.0240

.0228

-.0012 Wearscar "8"

.0225

.0215

-.0010 Wearscar "C"

.0205

.0193

-.0012 Wearscar "D"

.0145

.0130

-.0015 Wearscar "E"

.0110

.0113

+.0003 Wearscar "F"

.0090

.0085

-.0005

+.0003 Maximum Deviation:

-.0015 inch Table lA

Ultrasonic Measurement of the Outside Diameter Profile Along the Wear Scar Standard Radial Deviation from the Nominal Outside Diameter

{A)

{B)

As built Ultrasonic Measuring Location Measurement Measurement Deviation (inch)

(inch)

(B - A =

Wearscar 11A 11

.0010

.0011

+.0001 Wearscar 11 8 11

.0025

.0022

-.0003 Wearscar 11 C"

.0045

.0041

-.0004 Hearscar "D"

.0105

.0105 0

Wearscar "£ 11

.0140

.0140 0

Wears car "F"

.0160

.0160 0

inch)

+

0001 Maximum Deviation:

.0004 inch Table lB

PLANT

'JNIT S/G LE F:EEL TO REEL DATE 3ALEM I

THIM

--0i -

08/03/93

~ " TfiM iJPS :JOLTS OEG GH# LOCATION

=::CENT

~il

/~

0 JAN N 2.32

?.7

.: s 1 ENO "t

--~

t-I.

~.::';

WEAR

!~ 2AIJ N

~-

9 25 END

-'-130. 75 liJEAF

~.

.(. {

! 5.. S \\

-:: * '7

""'I, 73 END

+106. 19 CHROME 0 3AU N

7!. 73

._J <20 ENO

+ 17.. 83 DENT

'0,35

..0 <20 ENO

.,. 27 *:.'.l*?

DENT

\\(:1.57

,.. ;; *71 END

~ :~., 1 DENT

., \\J *.&.. I 0.55

! 1 <20 END

+ 57.58 DENT 4.33 6

38 END i" 62.98 DENT

~ il.AU 999 0.00 TD

-~ 3*2. 00 CHROME 1 ?J?

-~ -:-*:.. J END

+ 42.85

\\~EAR

~;. 70 36 <20 END

+ 49.,....

ic 1.~EAR 0 SAU 399 i

15 :s <20 EMO

+ 10.02

(~EAR

1 ?5 4- <20 am 7-

0.. :.:.:G DENT

! 1.84 :21 65 END

+ '22. 56 CHROME 0 l:iAU 0

NOD 13 SBU

~

J. {ii}

-:.20 END

+ 22.39 WEAR 0 ?f;U 0

~.34

-i:.

(2~

END

+ 54. 28

~!EAR 9.28

-:. 60 END

+ 94. "'~

GUT IN CHROME

~ t.

0 ?BU

\\.?

!.69 27 21 END

..,. i 9.00 WEAR 14.43..:::.. L...:.

END

+ 79.28 CHROME I

0 8f\\U 0 18.71 32

'79 END

+ 91 r-CUT IN CHROME

.~::>

0 88U

.. ~

S.80 4-2 56 END

+ 6~2i.23 CHROME 0 9AU 0

\\i), SS

' <20 END

-t-10.87 DENT

0. 95 22 <:~

END

,. 59.22

~JEAR 0 18A 0 24.35 222 8E f:NO

-;- 45.24 CHROME 2.83 i?

9 END

+ 57.89

\\..iEfrR

~}

1A 0

0.86

=*'Zl <20 END

+ ! 5.70 WEAR i 9. i :1 Z2!

79 END

+ 59.84 CHROME Table 2 P1%E OF LEVEL :rrr--

PROPRIETARY 0

0 ARRAY HOUSING 7

5 RODLET CENTERING DEVICE (TYPICAL)

UT TRANSDUCERS ENCIRCLING COIL 45° UT TRANSDUCER IDENTIFICATION Figure 1

i I.

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23 5

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0.25 t

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.2917 0.3197 NOTES 1 VERIFIED \\./ITH

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~1./11<~~ 7/zf/?J C ~-'" l~s L. ync />l~lllf,,,;1' (iC. ~

SECTION

A"DIM "B"DIM B -

B

.o 11

.o 't'i c - c

,o "g I 0 t.Z.

D D -

D

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E I 00 ~

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OI' NSS-93-013 2

2 4

4.. ;j.J. -~;

3 2

1

UT SCREEN DISPLAY KEY 16 Yi:d 1280 01 YHI 12as.0j

.o.YI s.ej 15 14

~

13 12 11 10 Cladding Bulge (shown) ~--1 Top of thimble when data is collected while tube is moving.!:fil*

Figure 4 A

1.

76C180U

2.

3.

CH7

4.

5.

6.

x

7.

8.

9.

y UT SCREEN DISPLAY KEY "76 11 Represents the Thimble number "C" is the energized array set (see main text for an explanation)

"180" is the tube orientation in the fixture "U" is the direction (u-up or d-down) the -t-**'"'e..

was moving as test data was collected.

States the type of UT scan pictured, in this case a B-scan.

The transducer from which the image is produced.

The position of the first vertical cursor given in micro seconds measured along the radius of the rodlet (yellow line).

The position of the second vertical cursor, used in conjunction with vertical cursor XR to measure defect size (blue line).

The difference between the two vertical cursors given in micro seconds which multiplied by 2. 867 x

104 inch/second yields the defect size in inches.

The position of the first horizontal cursor given in data points measured along the axis of the rodlet (yellow line).

The position of the second horizontal cursor used in conjunction with the horizontal cursor YR to measure the* axial length of a defect (blue line).

The difference between the two horizontal cursors given in data points but directly equal to 10-1 inches.

Figure 4 B

10.

µS

11.

12.

13.

14.

15.

16.

UT SCREEN DISPLAY KEY The unit of measurement used in the display of the X axis, micro seconds in this instance.

The amount of radial ti.i.imble information displayed on the screen utilizing the units of measurement listed in number 10 above.

The expansion or compression factor of the x-axis display normally a scale of 1/1 is displayed.

A scale of 1/2 indicates each aquisi tion point is represented by two display uni ts which enlarges the display.

A scale of 2/1 indicates two aquisition points are represented by one display point which compresses the display.

The point at which the radial thimble information displayed on the screen starts. The transducer surface is O. 0000 micro seconds.

One boundry of the axial tli.imble information displayed on the screen given in data points.

The expansion of compression factor of the Y-axis display.

Normally a scale of 1/1 is displayed.

A scale of 1/2 indicates each aquisition point is represented by two display units which enlarges the display.

A scale of 2/1 indicates two aquisition points are represented by one display point which compresses the display.

One boundry of the axial t~imble information displayed on the screen given in data points.

Figure 4 C

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Figure 12 A Thimble number 2 Full Lenght

Figure 12 B Thimble 2 Full Length

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3/23/90 TITLE CUSTOM' WEAR SCAR STD.

A111067 0n133<!-1-A OWO NO 9-iT 1 OF

Page ~

of..J.__

SAT.EK GEHERATDIG STATIOH/TECBHICAL DEPARTMENT VS1.RE-IS.RC-0001(Q) -

REV. 0 ABB/CE FLUX TBDmLB TBERllOCOUPLE EXAMINATION FOR SALEK tJHrJ.' f1 (SALEll-400-019)

USB CATEGORY: I RBVJ:SIOU SOllllARY This is a vendor procedure written to perform Flux Thimble Thermocouple Ultrasonic, Eddy current and Visual Inspection for flux thimbles removed and stored in the spent fuel pool during Unit 1, 10th Refueling outage *

ssUEC: JUL.) 0 V!~;:

DY TD~

o-..1 fas document c:i:mn~ !:r? used in the liela a:~er t~e ncxr rcvi::o;i or 7 J~'./S 2rter tJ1() issue data.

DIPLEllEH'l'ATJ:OH REQomEMEHTS None APPROVED: /. ev. c;e:

LL.r~ A-7. ~"~*

TECHNICAL MANAGER

-'7 /1 c- /'j r*

DATE

PROCEDURE FOR THE EXAMINATION OF THIMBLE TUBES PROCEDURE NO. SALEM-400-019 OUTAGE SERVICES DEPARTMENT ABB COMBUSTION ENGINEERING NUCLEAR SERVICES WINDSOR,CONNECITCUT PREPARED BY: £1-fld! ~

~

I V.P

"/

DAlE: 7-z7,;.9c3 DATE: 7_ ?! ~ - 3 3

.I. Dashukewich UT J.,.,evel III

?

/

(_/,;. /

APPROVED BY:

....-* ~,,.. ~.... -~/

e!Z**Zt'.:-e ~..--c.

H. Labff. '. ec _,

ET~m /..L, ".

APPROVED BY: ~

A l--C ~

0 I

I.A. Colflesh DATE: 7f rf_s Manager, Component Services APPROVED BY: ~k

--==::

DATE: 7-2... <T-?:l

-f;.r G.S. Bloomquist Quality Operations 0

Rev. No. __

Date:'7-2.9-93 PAGE l of 18 SALEM-400-019. H.1.:v n

JUL 2'3 3.3 15: 48 TABLE OF CONTENfS SECTION TITLE PAGE 1.0 PURPOSE 3

2.0 REFERENCES

3 3.0 DEFINITIONS 3

4.0 PERSONNEL REQUIREMENTS 4

5.0 EXAMINATION REQUIREMENTS 4

6.0 EQUIPMENT SET-UP 6

7.0 EQIBPMENT CALIBRATION 7

8.0 INSPECITON PROCEDURE 8

9.0 EQUIPMENT TAKEDOWN 10 INSPECTION LOG DATA SHEET 11 APPENDIX A ENCIRCLING COIL TEST 12 APPENDIXB UT EQUIPMENT TEST 16 PAGE 2 of 18 SALEM:-400-019. i*: 0:*.

HC*C*

1_11_1 I Hl_lC =*** *- *=*

l.d l l*IL!

1.0 PURPOSE 1.1 INTENT This procedure describes the method for ultrasonic (UT) and eddy current (ET) inspection of Thimble Tubes.

This procedure describes the equipment setup, equipment calibration, and inspection procedure.

This procedure does not cover Thimble Tube handling, is done with air operated, handheld, gripping tools.

procedure does not cover other activities such as requirements which would be part of a radiation work or part of a foreign material exclusion procedure.

1.2 APPLICABILITY which This permit This procedure is applicable to Thimble Tube sections whose OD is accessible.

Thimble tube sections which can not be straightened per section 8.6 will not be inspected.

2.0 REFERENCES

None 3.0 DEFINITIONS 3.1 Test* Supervisor -

The ABB Task Manager responsible for the inspection program.

The duties of the Test Supervisor are to carry out the administrative and supervisory functions required to perform the examination program. The Test Supervisor may also operate equipment for which he is qualified.

3.2 Lead Inspector -

The NOE inspector on a shift responsible for the setup, calibration and operation of the inspection equipment.

The Lead Inspector shall be qualified as a Level II or higher in either UT or ET.

J.J NOE Operator -

The NOE qualified individual who performs setup, calibration, and data collection in accordance with this procedure.

The NOE Operator shall be qualified as a Level I or higher in the discipline for which work is performed.

PAGE 3 of 18 SALEM-400-019, Rn* 11

T ~~.;_l._0.:.,.1:,1._

1 :' -'*-**-'

4.0 PERSONNEL REQUIREMENTS 4.1 The Test Supervisor. Lead Inspectors and NOE Operators shall be certified in accordance with QAP 2 5.0 EXAMINATION REQUIREMENTS Note:

Examination requirements are contained within the body of the inspection procedure.

This section is a summary of the requirements.

5.1 EQUIPMENT Note:

5.1.1 5.1. 2

5. 1. J

5. 1. 4 5.1. 5 5.1. 6 5.1. 7 5.1. 8 Equipment uses 110 VAC. Nominal power requirements are two 20-AMP circuits.

Nl6 Ultrasonic Array system (Digital Multi-channel Inspection Unit)

Zetec Digital Multifrequency ET System (MIZ-lSA, HP 9836 computer, OCR)

Thimble Tube Inspection Fixture.

Array Housing Units (UT transducers and ET coil)

Array Selector Box (optional).

Diameter standard (UT)

Defect Standard (ET)

Underwater TV camera system 5.2 INSPECTION PARAMETERS 5.2.1 UT examination frequency is 10 MHz.

5.2.2 UT examination angle is o degree longitudinal wave.

5.2.J UT couplant is the pool water.

5.2.4 ET technique is encircling coil using frequencies of soo KHz, 200 KHz, 100 KHz. and 50 KHz in both absolute and differential modes.

PAGE 4 of 18 SALEM-400-019, Rt:v <l

JUL 29 "33 15: 50 5.3 CALIBRATION 5.3.l UT system calibration is performed with a multiple diameter rod standard (DIAMETER STANDARD).

This rod was machined to provide various diameters which were then measured and certified.

5.3.2 ET system calibration is performed with a defect standard (DEFECT STANDARD)

This standard was fabricated from a piece of tuQing of the same material and nominal dimensions as the Thimble Tubes to be inspected.

The tubing was machined to produce various defects which were then measured and certified.

5.4 INSPECTION RECORDS 5.4.l The permanent UT inspection data is recorded on optical disk(s).

5.4.2 The permanent ET inspection data is recorded on magnetic tape (data cartridges).

5.4.3 5.4.4 5.4.5 The following data as a minimum shall be recorded on the UT/ET data disk/tape:

Owner Calibration standard S/N Plant and Unit Procedure and revision no.

Date Test item identification Operator name Operator NDE level The completed data sheets contained within this procedure is the record of the Thimble Tubes inspected, times, test sequences, etc.

This inspection is a diagnostic examination of discharged and sectioned thimble tubes.

No acceptance or rejection criteria applies.

PAGE 5 of 18 SALEM-400-019. RC\\' (I

I.

+ 2C)3285 13530 F-:,.'77 T-f.:33 P-CnJ7 JUL 2'3 33 15: 50 6.0 EQUIPMENT SET-UP Note:

The major steps are listed in this section.

Detail setup steps are listed in the appendices.

Steps may be done in parallel where applicable.

6.1 Layout the UT and ET equipment and interconnect the equipment.

6.2 Layout the Thimble Tube INSPECTION FIXTURE (TEST FIXTURE) in the work area and install the ARRAY HOUSING UNIT(s) (TEST ARRAY} in the TEST FIXTURE.

6.3 Connect the TEST ARRAY cables to the UT and ET equipment.

NOTE:

step 6.4 must be performed by an NOE Operator

qualified Level II or higher (either UT or ET).

6.4 Verify proper setup of all equipment and proper connection of all cables.

(e.g. the TEST ARRAY in the TEST FIXTURE is connected to the Array A inputs 1 thru 8 on the selector box).

Cables shall be labeled so that if the cables are disconnected and reconnected this setup can be re-verified without removing the TEST FIXTURE from the pool.

6.5 Perform an ET/UT operational checkout I calibration checkout of the eqciipment to check* proper operation of all TEST ARRAY(s).

6.6 6.7 Note:

Installation of the fixture into the pool may require use of a crane.

The operation of the crane, rigging requirements, slings, etc.

shall be done in accordance with plant procedures as required.

The fixture is installed in a location as specified by the plant.

Install the TEST FIXTURE in the pool, typically next to an operator accessible pool wall.

Notify Station Quality Assurance (SQA) before starting the actual inspection of the*thimbles.

Record information below.

fh-t Su kr-f Name of SQA Person Contacted 7-Jl--fJ' I (Z3!()

I Date and Time Contacted

-wtJt:

PAGE 6 of 18 SALEM-400-019, Rev 0

_1*-*1.... --

'~*

J.~*.:.1.a.

7.0 EQUIPMENT CALIBRATION Note 1.:

Note 2:

Equipment calibration shall be checked by a Level II NOE Operator.

The DEFECT STANDARD and DIAMETER STANDARD may physically be mated together as one piece.

7.1 Using the DIAMETER STANDARD calibrate the UT system for each TEST ARRAY as follows:

1-1..1.

7.1. 2 7.1. 4 7.1. s 7.1. 6 Fully insert the DIAMETER STANDARD into the TEST ARRAY.

Turn on the UT electronics and name the file as a calibration run, up.

The calibration *file name will be specific to the TEST ARRAY used (if there is more than one).

Withdraw the DIAMETER STANDARD recording the data on the optical disk.

When the DIAMETER STANDARD is out of the TEST ARRAY stop recording.

Calibrate any remaining TEST ARRAY in the fixture in the same manner.

7.2 Using the DEFECT STANDARD calibrate the ET system for each TEST ARRAY as follows:

7.2.1 7.2.2 7.2.3 7.2.4 7.2.5 Fully insert the DEFECT STANDARD into the TEST ARRAY.

Name the ET data file as a calibration run.

Withdraw the DEFECT STANDARD, recording the data on the data cartridge recorder.

When the DEFECT STANDARD is out of the TEST ARRAY stop recording.

Calibrate any remaining TEST ARRAY in the fixture in the same manner.

PAGE 7 of 18 SALEM-400-019, l<i.:*. *

JUL 2'3 33 15: 51 7.3 Re-calibration is required only if there is a change in test equipment, TEST ARRAY, or ET coils.

Periodic calibration checks are done to check equipment performance and provide calibration signals for use by the data analyst.

Calibration checks shall be done as follows:

7.3.1 7.3.2 7.3.3 7.3.4 At the start of the inspection program.

At the beginning and end of a OCR tape. (ECT only)

At the beginning and end of a work shift (at minimum every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ).

At the end of the inspection program.

8.0 INSPECTION PROCEDURE 8.1 If required, verify the Thimble Tube location in the pool using an underwater TV camera.

8.2 If not already done, calibrate. the ET and UT systems per Appendix A and B.

8.3 Perform a calibration check by withdrawing the calibration standards thru each TEST ARRAY and recording the applicable UT and ET signals.

If these checks do not appear to be consistent with the calibration standard, inform the Lead Inspector.

B.4 If available use an overhead crane to pull the Thimble Tubes through the TEST FIXTURE. If the overhead crane is used, determine the speed of Thimble Tube lift.

(This step may be done in conjunction with the first Thimble Tube to be inspected. )

8.5 Mark the visegrip handling tool (graphite pole) using colored tape at the elevation determined by HP to ensure that the top of the thimble is not raised sufficiently near the top of the pool surf ace so as to create a radiation exposure hazard to personnel.

PAGE 8 of 18 SALEM-400-019, Rt:v I!

r--.:.... 1-r:.. =**.:.* r-u.L*-*

8.6 Inspect each Thimble Tube as follows:

8.6.1 NOTE:

8.6.2 8.6.3 8.6.4 8.. 6. 5 8.6.6 CAUTION EXTREME CARE SHALL BE EXERCISED IN THE HANDLING OF THE THIMBLE TUBE SECTIONS. DO NOT RAISE THE HANDLING TOOL OUT OF THE POOL ANY HIGHER THAN THE TAPE MARK (STEP 8.5).

Determine the Thimble Tube to be inspected and insert the crimped end of the Thiinble Tube into the crimp removal tool until the tool stop is reached.

The pressure gage on the hydraulic pump is used to determine the hydraulic line is pressurized and does not need to be calibrated.

Pressurize the crimp removal tool using a hydraulic pump, the pump has reached an adequate hydraulic pressure when the pump handle becomes hard to move.

Fully insert the THIMBLE TUBE into the TEST FIXTURE.

Select the appropriate ARRAY SET.

start the UT and ET data collection.

Signal to the Thimble TUbe handling operator to withdraw the Thimble Tube.

Stop data collection once the Thimble Tube is fully withdrawn.

Record the Thimble TUbe sequence number, inspection start time and inspection completion time in the Inspection Log.

Repeat test for other Thimble Tubes.

Perform re-calibration and/or calibration checks (standard runs) as specified in step 7.J.

8.7' If required, verify that the Thimble Tube's are in their correct orientation and location in the pool using an underwat~r TV camera and the site supervisory direction.

PAGE 9 of 18 SALEM-400-019, Rt!v 0

9.0 EQUIPMENT TAKEDOWN 9.l De-energize the UT and ET equipment and remove the interconnecting cables.

Pack the equipment in the shipping boxes.

Note:

Removal of the fixture may require use of a crane.

The operation of the crane, rigging requirements, slings, etc. shall be done in accordance with plant prqcedures as required.

HP requirements for rinsing, decontamination, etc. shall be done as specified in the plant's radiation work permit.

9.2 Remove the TEST FIXTURE from the pool and place it in a laydown area for disassembly and packup.

9.3 Remove the calibration standards from the pool.

PAGE 10 of 18 SALEM-400-019, R~v n

INSPECTION LOG DATA SHEET 1'1Cf '?,.

THIMBLE DATE/TIME DATE/TIME INITIAL REMARKS TUBE IN PROF.

OUT OF PROF.

I 7-31 ttf lfo

=? *.](

1 y '-( '7 (Ct~ L:fC

1...

r<'I JS30 7-*?/. J5V.S

-,'&/', L:IT 3

7--31. 'ra CJ 7- *)J 19 ~6-llVf ar.

1./

e*l O'iS5

~ -)..

76 I~

,eJivt L iI s-1

)631

~-J.

/o '(O lAiA L..Ir

~

~-l i31o e *.li

/3 "I..//

~,

rr Te.c... ~ ~

\\on~ (LJ) 7 s-.z It( ()0 8-l.. 1e:so fhv'I z..:rr Th~~

bo~ ~~

~

8-3 09f.2..

e,-3 OCi 1..0

~LP:, Te.~~). L--. b~ ~

4 8-3 C-'73 <::) 8*3 6Cf :3 b fJU1 l.Jr (D

8*3 o 4 '-IS B-3 oi tc+

~L$

ti S-3 too(

e> '3.

/0 6 b f.J.e.A.. L 7L. -

.\\

c'11-..-.~

p, -3, - 9: "3 LfT"L"Il :;.-,- L-i: em..., --ll~~nt'... ~

~

,/

I

~

~.

JV 1~-----.........__ --

~

The NOE Operator shall initial for each thimble inspected.

When complete the NOE Operator shall sign,. date and note his(her) NOE level on the next line in the log.

ET Standard S/N _:rr~'~~~~~

J\\lf.~

Cf 3. 0 13 UT Standard S/N UT-S.°'{~

}.J~ !:. * "r 3 - 0 I ~ re.II I If more Inspection Log Data Sheets are needed attach additional copies of this page to the completed procedure.

Record number of additional Data Sheets 0

attached.

PAGE 11of18 SALEM-400-019. Rc.:v ll

F-377 1-683 P-013 JUL 2'3 "33 15: 53 APPENDIX A ENCIRCLING COIL TEST The following interconnections should be made.

1.

Connect the GPIO interface card on the HP 9836 to the Data cartridge Recorder with a 50-pin GPIO cable.

2.

Connect the HPIB Interface on the HP 9836 to the HPIB/MIZ-18A interface with a GPIB cable.

3.

Connect the HPIB/MIZ-18A Interface to the MIZ-18A Remote Unit with the desired lenqth (10' to 100' typical) of MIZ-18A Remote Cables.

The IEEE-488 connector at the lower right corner of the MIZ-lSA Remote Unit should be used.

4.

The appropriate MIZ-lBA Probe Adaptor Splitter Cable connected to a PROBE connector on the MIZ-18A Remote Unit is used for standard test probe configurations.

A) one reference coil MUST be connected to the REFERENCE connector of the probe adaptor splitter cable.and reference standard inserted.into the reference coil.

Absolute data is now available for each test coil and frequency.

The following equipment precautions and notes *should be followed:

1)

When a MIZ-18A operator change occurs, identify the operators name and level in the message section.

2}

Do not enter Review Mode when testing.

Entering this *mode could cause a loss of data entries on tape.

After END TAPE and in safe position use Review Mode to check for complete data.

3)

When using the coil, periodic cycling through the channels during data collection is recommended to ensure proper operation of the coil.

4)

When the data cartridge is complete, a hard copy of Summary Information including updated test parameters should be included with the data cartridge package.

5)

Make sure the backup disk is initialized and not write protected.

6)

Make sure the cartridge is not in save mode or not write protected but after completion is put into the save mode.

PAGE 12 of 18 SALEM-400-019, I\\,*\\ *

r - _, I I

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- e,.. =........ r - *-*........

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7)

Be sure that the index backup is enabled to avoid loss of data.

8) care should be taken to ensure similar coils are used as reference probes to avoid an impedance mismatch.

SEQUENCE FOR MIZ-18A START UP AND OPERATION

1.

Load the MIZ-18A System Software (floppy disk into right disk drive) and a blank formatted diskette into left disk drive.

2.

Turn on power.

J.

The system will automatically boot into set clock and date mode.

4.

Set clock and date.

5.

Depress "TEST" (K9)

6.

Depress "SHIFT" and "CONFIGURE"* key (k3)

7.

The encircling coil will be configured to test at 500 KHz, 200 KHz, 100 KHz, and 50 KHz differential and absolute modes with the sampling rate set at 400 samples per second.

a.

Depress "CONFIGURE" key (kS) to achieve Test Mode.

9.

Depress "SHIFT" key and the "TEST" and "REVIEW" key (k9)

Twice simultaneously to achieve Utility Mode.

10.

Depress Disk Utility (k2) on function keyboard.

11.

Depress "SHIFT" and "INITIAL DISK" keys (kS) simultaneously to initialize unit.

1.2.

Depress "UTILITY" key (k9)

13.

Depress "SHIFT" and "UTILITY" key (k9) to achieve Test Mode.

14.

Depress "TAPE RCDR" (kS).

15.

Depress "BACKUP ON/OFF" key (k4) to ENABLE backup disk.

16.

Depress "TEST" key (k9) to achieve Test Mode.

PAGE 13 of 18 SALEM-400-019, Rev t)

I ;-;._,_

l I

I...

j' -

-'I I I

I

-**-*~ --

"'..J* *-'-'

17.

Load data cartridge -- wait approximately 90 seconds for completion of cycle.

18.

Depress "SUMM.~Y" key (K2) *

19.

Depress "TYPE DATA" (KO).

20.

Type in the information requested and include the serial numbers of all the equipment used.

NOTE:

If there is an operator change during testing, the new operator will enter their name in a "MESSAGE".

21.

Depress "DONE" (kO) typed information will be transferred to data cartridge.

22.

Depress "SHIFT" key and the "TEST" and "REVIEW" key (k9) simultaneous to achieve utility mode.

23.

Depress "SET UP" key (kl).

This function will set the system up to change the identification header.

24; Depress "KEY (k7)" until you have "KEYBOARD INPUT (KBD INP) ".

This will allow I.D. header to be updated using the keyboard prior to the start of each coil scan.

25.

Depress "KEYS (kl), (k2) and (k3)" one at a time until they have no headers showing.

26.

Depress "SHIFT" key and (kl) key simultaneously.

This will enable you to type in the proper header.

Do this for the following keys (k2) and (kJ).

27.

Depress "UTILITY" key (k9).

28.

Depress "SHIFT" key and "UTILITY" key (k9).

This will bring you back into the "TEST" mode.

29.

Perform an "in air" and "in water" calibration standard run.

The hin air" test is run to verify the coil is working prior to putting the fixture in the pool.

31.

Depress "MIZ-18A OFF" (K4).

32.

Place defect standard in the test coil.

33.

with the coil at a no defect portion of the standard, depress "CONTINUE KEY" to balance the eddy current system.

PAGE 14 of 18 SALEM-400-019, Rl~v o

-,..:. o.:..*._o~*-* -* - - _.. _.

.'.* l. I,._

~* *-*i.....

~ -

34.

Depress the "RUN" key and slowly withdraw the standard fully from the coil (the calibration standard is run during withdrawal).

35.

When the defect standard exits the fixture depress the "PAUSE" key (this stops the testing).

3~.

Set span and rotation by setting the dent on the calibration standard horizontal with an initial excursion to the right.

37.

Depress "SPAN/ROT" key (k7)..

38.

Depress "SET SPAN" key (kl) or "SET ROT" key (k6) to achieve desired spans and rotationsQ Do this for all test channelso

39.

Depress "TEST" key (k4) to achieve test mode.

40.

Depress..

SUMMARY

" key (k2).

41.

Depress "UPDATE" key (k6).

This will update all spans and rotations.

42.

Depress "TYPE DATA" key (kO) followed by "DONE" key (kO).

43.

Depress "MIZ-1SA ON" (k4).

44.

Fill in the Thimble Tube number.

(Use Function Keys.)

45.

Lower Thimble Tube into the fixture.

46.

Depress "CONTINUE KEY" to balance.

(Balance must be done with the Thimble Tube in the coil).

47.

Start Data Recorder (Run Key).

48.

Test the Thimble Tube.

49.

stop Data Recorder (Pause Key).

50.

Test all remaining Thimble Tubes in the same manner.

PAGE 15 of 18 '

SALEM -400--019, Rev U

r- - :;, {,

I -r-=u~...J r- -~..:.I.L i APPENDIX B UT EQUIPMENT TEST

1.

Connect the Nl6 Ultrasonic Array Inspection System by following the instructions listed in the Ultrasonic Inspection system User Manual (Manual) an~ insert an optical disk into the N16.

2.

Prior to mounting a TEST ARRAY in the TEST FIXTURE check*

that each of TEST ARRAY'S cable ends is identified as beinq a particular transducer out of the 8 possible transducers.

3.

If the cable ends are not identified, physically trace eaeh cable from the individual UT transducer back to its cable connector.

Arbitrarily select any UT transducer as number-1 and label* the remaining transducers as numbers 2 thru 8 starting with the first transducer i~ a clockwise direction from transducer number 1.

4.

If the selector box is used connect the TEST ARRAY cables to Array A, inputs 1 thru a.

5.

If a backup TEST ARRAY is available and the selector box is.

used connect the TEST ARRAY cables to Array B, inputs 1 thru

8.

6.

If the selector box is not used connect the TEST ARRAY cables to the pulser/receiver connectors labeled Rl thru R2 respectively.

7.

Turn on the power to the N16, a special sequence of events occur when the equipment is turned on which are automatic and are described in the Manual.

8.

Dependent on reject criteria (supplied by the plant owner/client) adjust signal response and gating to maximize.

signal sensitivity.

Each individual channel set-up shall.be verified with the DIAMETER STANDARD.

9.

The system may be calibrated utilizing one*gate in the A:

scan.

The width of the gate will be determined by site supplied wear rejection criteria.

No gate is necessary if:::*

no rejection criteria is supplied.

10.

Gate #1 ("wear gate" colored yellow) is set to reflect an acceptable wear range.

Diameter wear signals will move right from nominal.

Movement of the signal out of this gate will reflect unacceptable wear indications.

PAGE 16 of 18 SALEM-400-019, Rev 0

11.

A)

Insert the DIAMETER STANDARD into the TEST FIXTURE insuring the nominal Thimble Tube diameter is reflected.

B)

By adjusting the gate width and the de1ay, adjust the signal {Channel 1) so that the first reflector is enclosed in*the new wear gate leaving 10% of gate open from the left extreme edge.

This allows for slight diameter changes or movement of the standard/rodlet within the array.

C)

Set the signal gain between 80-100% full screen height-~

D)

Withdraw the DIAMETER STANDARD until the site specified unacceptable reduced diameter range is reflected by the transducer array.

Verify that this signal is outside (right) of the "wear" gate.

E)

Repeat steps 11, B, C, D for all transducer channels.

12.

The colored multi-channel C-scan readout reflects changes in*

diameter both in and out of the acceptable diameter ranges.

Each color change will correlate to an actual measured reduced diameter depth.

Coloration will be pre-set to reflect site rejection criteria.

13.

The right indicator line of all channels correlate to the "wear" gate or diameter-loss.

14.

If the standard or rodlet signal remains in the set gated area the (right) indicator line of all channels will remain at the nominal dark blue color.

As the signal moves towards the wear indicator side, the coloration will change (dependent on wear depth) to light blue, green, yellow, orange to red and black.

Black will normally be set to indicate a rejectable indication.

15.

Using the DIAMETER STANDARD calibrate the UT system TEST ARRAY as follows:

15.1 Fully insert the DIAMETER STANDARD into the TEST ARRAY.

15.2 Turn on the UT electronics and name the file as a calibration run.

15.3 The calibration file name will be specific to the TEST ARRAY used as shown below:

(CAL) 1 (1) 2 (A) 3 (2)' (U) 5 PAGE 17 of 18 SALEM-400-019, I~,~...,

ABB OUTAGE ::;.ucs 1..1 I HD F - 377 T -E.:35 P-fl 1 '3/01 '3 JUL 2'3 "33 16: 05

1.

Record "CAL" indicating the fil.e contains DIAMETER STANDARD data.

2.

Specific TEST ARRAY identification, TEST ARRAY 1 in this case, a spare TEST ARRAY would be ARRAY 2.

3.

The specific array set, A or B, if the selector:

box is used.

Nothing is recorded here if the.

selector box is not* used.

4.

The sequence number for the TEST ARRAY calibration, the example indicates this is the*

second calibration run.

5.

Y-UP, testing during withdrawal.

~- DOWN, testing during insertion

16.

Withdraw the DIAMETER STANDARD recording the data on the optical. disk.

17.

When the DIAMETER STANDARD is out of the TEST ARRAY turn off the electronics.

18.

Load Recording Dialogue Window prior to testing the Thimb1e TUbe:

A)

"Recording Name", up to eight digit~.* This will be,* the Thimble Tube number with suffixes as shown:

1.

Thimble Tube number.

2.

.Specific array set (optional).

3.

Y-Up, testing of the Thimble Tube during withdrawal.

Q-Down, testing of the Thilnble TUbe during.

insertion.

PAGE 18 of 18 SALEM-400-019, lkv o

"' NfJCf;EAR DEPARTMENT WORK ACTIVITY PLANNED MAINTENANCE ACT TYPE FW TASK PL 1 llllU lllll lllll lllll llUI lllll lllll lilll lllll lllll llUllll11u11111111aa1 W/O:

930615152 ACT: 01

,NIT Sl PRI 3

RESP D/G SMD M:.

SECTION 1 -- TASK DESCRIPTION REPRINT 01 W/O

SUMMARY

PROVIDE SUPPORT FOR FTTC UT INSPECTION FEG/COMP ID: lRCEl MUC: C LOC: 06130003 SYSTEM: RC 1 REACT COOL REACTOR VESSEL SERIAL NBR:

ACT

SUMMARY

PROVIDE SUPPORT FOR FTTC UT INSPECTION ACT DESC-1: PROVIDE SUPPORT FOR COMBUSTION ENGINEERING FLUX THIMBLE THERMOCOUPLE INSPECTION, EDDY CURRENT INSPECTION. THIS INSPECTION WILL BE PERORMED IN MID JULY. PROVIDE SUPPORT BY OPERATING THE CASK HANDLING CRANE &

FUEL P.ANDLING CRANE AS REQUESTED BY RX. ENGINEERING. CONTACT SYSTEM ENGINEER

- DESCRIPTIONS CONTINUED ON NEXT PAGE. **

SECTION 2 -- PLANNING INFORMATION PLANNER: FIGUEROA 2767 /SWD SUPERVISOR:

BROWN $

SAl!'E'rY' RLTD SAFETY CLASS SEISMIC EO N

SR 1

1 ORI DCRI 00000 -

PKG 00000 RCI: 0063 AUTH NO:

WORK STANDARDS:

(HP W/STD):

TEMPORARY MODIFICATION t 00 0000 CODE JOB PKG ACCT NO: E530010 PRG PLN: I00013 LOC: 1614 PLN JOBI: 584818 SECTION 3 -- SCHEDULING INFORMATION SCHED START DATE: 07 /26/93 OVERDUE DA'rE:

ESTIMATED MANPOWER MAN EST COD NBR DUR EST RCA SMM 002 40.0 80.0

70.

SYSTEM OUTAGE:

LCO NO:

SCHEDULER:

SCHEDULER COMMENTS:

000 o.o 0.0

o.

000 0.0 0.0

o.

000 o.o o.o

o.

TOTAL HRS:

40. 0 SECTION 4 -- PERMISSION TO BEGIN DATE: fJUl 2 £',~ - TIME:

TAG NO:

SECTION 5 -- CLOSE OUT PERSON COMPLETING WORK BADGE DATE ACTUAL MANHOURS

_/_!_

MANPOWER: -- --- --- --

WORK SUPERVISOR BADGE DATE MEN REQ : -------

DURATION:

{

J (Y/N)

REPEAT WORK

~

S/S SIGNOFF:

DATE: _/_/_

L____

NC.NA-AP.ZZ-0038(Q)

REV. 1 CICP No: 800-0011 CHEMICAL I.Tl' CLASSIFICATION PERMIT Folio No:

~RPlication category: Hydraulic Fluid

~oduct Na~_i_ Ucon Hydraulic Fluid WS-34 supplier/M~qs Union Carbide chemical Family; Polyalkylene Glycol Primary function(s}i Hydraulic Fluid Use ClJ\\SSJ 3

May NOT be UHtid i.n direct contact with plant systems, and may NOT bQ drained or flueh~d to plant waete processing eystema.

~llowod Use: Thimble Tube UT/Eddy current Inspection Equipment.

total.

Unit 1 Spent Fuel Pool.

Q~!IA HAz;rd Communication category:

2 Quarts Physical Hazard U2..Li. Combustible vapors Health Hazard(s): Carcinog..:n.

~utagenic.

Toxic:.

E:ye, Lung & Skin Irritant NFPA 111\\ZARD CLASS:

Hea 1th (BLUE) On expoeure would cause irritation but only minor residual injury even if no treatment ie given.

Flammability {HED) Muet be preheated before ignition can occur.

Reactiyi ty ( YELLOfil -o-Normally stable, even under f ir:e expoaure conditiono and not rQactive with water.

Storage Gui~_linea; G~neral storage Shelt Life: None H~ndling Restriction:!; WtHtr gloves and goggles.

lJsa in wff l l ventilated areas.

Control Room H~bit~pilty Concern: NO NJ Right to Know: 1 Requires a NJRTK label.

~ispo~al Guidelines:

USED (OPENED):

E-HAZARDOUS: DISPOSE OF AS HAZARDOUS WASTE THRU SITE SERVICES UNUSED (UNOPENED):E-HJ\\ZARDOUS: DISPOSE OF 1\\S HAZARDOUS WASTE THRU SITE SERVICES Approved 0; Disapproved D Chemistry Services Enqineer:~__,I~~~*J==-.1..,__,.D~o~l~a~n::..;_

Date: 07/30/93

~

NC.NA-AP.ZZ-002S(Q EXHIBIT l II TRANSIENT.COMBUSTIBLE WORKSHEET HC ROOM ( S) ~ALEM AREA ( S j)

D 30 I Fq~I Hd/f/.871#-Z L FA - F H - 100 START DATE: zi.2f/t:J DURATION:

/()/~ W/0#:

9306 t'S-t._~.2.

I ALL PLANNERS AND SUPERVISORS SHALL STRIVE TO MINIMIZE THE AMOUNT OF TRANSIENT COMBUSTIBLES INTRODUCED INTO ALL AREAS JOB PLANNER:

G. fi~ Ut-rt7~

EXT. 2767 DATE:

7(37/f-3 7b;b:s JOB SUPERVISOR:

w'ifrclll &a,,s EXT.

2..0~ 2-DATE:

I EVALUATE THE TRANSIENT COMBUSTIBLES WHICH YOU ANTICIPATE BEING USED DUR.ING THE WORK ACTIVITY.

COMBUSTIBLE MATERIALS ESTIMATED HEAT CONTENT TOTAL BTU'S FLAMMABLE LIQUIDS 90,000 BTU/GAL.

COMBU~TIBLE LIQUIDs).S-~ r.l, 160,000 BTU/GAL.

F1 K°oo, ooo GREASE 150,000 BTU/GAL.

CHARCOAL 13,000 BTU/LB.

CLOTH S' /bf' 16,000 BTU/LB.

8°(Jt. otJO FIBERGLASS LADDER (6')

32,000 BTU/EA.

RUBBER S lbs 10,000 BTU/LB.

~~I o~t>

CAB°LE INSULATION SO//x.

12,000 BTU/LB.

~ {) ll1 OfJ (}

I CARDBOARD ;:z /b S 6,000 BTU/LB.

[2l0()0 j

PAPER /0(/,5 8,000 BTU/LB.

?Ol (JfJ o (453,000 BTU/CU. FT.)

PC'S 2/f;,5 16,000 BTU/LB.

3J., ooo

( 1 PC = l / 2 LB. )

I PLASTIC SP/6.s 20,000 BTU/LBe t,O~rJc.OIJO T

I WOOD 2.5' 9,000 BTU/LB.

.2..2, 90 (414,000 BTU/CU. FT.)

DRY ION RESINS 12,000 BTU/LB.

TITANIUM 8,500 BTU/LB.

~p COMB PERMIT #: 'I J.. - IF AF tilt>f2. Kjl TOTAL BTU, s:

10 b 7r;,,$"00 L_

MAKE SURE THE TRANSIENT COMBUSTIBLES ARE REMOVED UPON JOB COMPLETION Nuclear common Page 1 Of 1

'DA.. ~

PERSONNEL CERTIFICATIONS E. McGuffey R. McGuire

c. Provencher V. Roy Signature Log ET II, Eye Exam ET I, UT II, VT 1-4, Eye Exam ET I, Eye Exam ET III, Eye Exam

E u.....

0 CERTIFICATION RECORD Jl 1111 ASEA BROWN BOVERI METHOD:

EDDY CURRENT NAME:

Edward L. McGuffey LEVEL:

I I SOC. SEC. NO.: ~

CERTIFICATION DATE:

1/30/92 EXPIRATION DATE:

12/20/94 EDUCATION:

Connecticut State High School -

GED TRAINING:

ABB Combustion Engineering, Windsor, CT - February '1979 - 32 Hours ET L I Morch 1983 - 4 Hours ET L I

- August 19_84 -

40 Hours ET L II

- January l989 -

40 Hours ET L II EXPERIENCE:

Certified and experienced at ABB CE as a Level I from January 1980 to May 1989 and as a Level II from Moy 1989 to January 1992.

EXAMINATION:

General/Basic:

70.0 Specific/Method:

100.0 Practical/Specific:

90.0 Tota!:

260.0 3

=

86.7 COMPOSITE SCORE The above named individual has completed the qualification/training requirements for certification in the above examination method in accordance with ABB Combustion Engineering Nuclear Power procedure QAP 2.4 rev1s1on 1

CERTIFIED BY:.L-...;;.._---'--"-4-------

POSITION: ___

z.__ __________________________________ __.

I SEA BROWN BOVERI INC.

Prospect Hill Road JSt Office Box 500 Windsor, Connecticut 06095-0500 CERTIFICATION FOR FIELD SERVICES ACTIVITIES NAME _

__;E;;....d_wa;;;...;..r_d_M_c--'Gu'--f_fe_,,_y ____ SOCIAL SECURITY NO.*

llJll!IRIJ~-'.___ DA TE 1 /5 /93 (of Examination)

NEAR VISION - JAEGER R#

FAR VISION - SNELLEN R 20.

COLOR VISION

[ X'] ISHIHARA _A....._L.k""'efi

...... 'k-.-~--=.e_'"--------

[ ] WOOL(Holmgren) ______

- EYE EXAMINATION NATURAL L#

L 20.

B#

B 20.

R # __L__

R 20.

J.s CORRECTED L#_L_

L 20.

/3-~

B# I B 20.

EYE EXAMINATION ADMINISTERED BY: ~"

C~<-t-~ 4,.

Eye Examination Results "'

./"? ;_../..4,/

Reviewed & Accepted By: /....._.//

/'?"~

NDE Department "Required to be completed for NOE. certification only. Not ~uircd for qualification to rcspiratosy protcction devices.

PHYSICAL EXAMINATION HEIGHT 7' '/

WEIGHT

,,.1,;J. 1 BLOOD PRESSURE 1.1~Lz~

ltcf SKIN ~

~

EARS qQ 'l ~ NECK

~-

EYES

~GI +

,..{

HEAD

~

....... -~-~ HEART f2z ~ -_ -e CHEST ~

LUNGS CfZ:

~

?

PULMONARY FUNCTION TEST:

NORMAL

~ ABNORMAL This is to certify that this individual has been examined anC. no evi<lence has been found of any physical condition which might be aggravated by, or attributed to, occupational exposure to ionizing radiation. This individual has no history or evidence of previous radiation injury and has no history of exceeding the limits of 10 CFR 20.103 and is found to be physically qualified to perform duties involving occupational exposures to ionizing radiation.

This examination has also revealed no indications of aberrant behavior.

This individual has been examined in accordance with NUREG-0041 Section 7.4 and no evidence has been found of any physical or mental conditions in which the use of respiratory protection devices arc considered contraindi-cated.

THE ABOVE INDMDU~QUALIFIED FOR WORK INVOLVING RESPIRATORY PROTECTION D~CES:

LIMIT A TIO NS:

CORRECTIVE LENSES __

£...__ ___ DENTURES ---~----- OTHER __

0 _____

Joseph A. Amato, MD Medical Ex.:i.miner (Print)

Form #0020808 (7/90)

ABB Medical Department Dept. 54 20-1902 1000 Prospect Hill Road Windsor, CT 06095-0500 (203) 285-3339 Clinic Location

c;:

~

0 :;:

Jl 1111 1'111\\1,1*

CERTIFICATION RECORD ASEA BROWN BOVERI METHOD:

EDDY CURRENT NAME:

Robert 8. McGuire LEVEL:

~----------~

SOC. SEC. NO.:

CERTIFICATION DATE:

1 /8/92 EXPIRATION DATE:

12/18/94 EDUCATION:

Bristol Eastern High School, Bristol, CT -

Grad 1978 TRAINING:

ABB Combustion Engineering, Windsor, CT - June 1985 -

40 Hours ET Level I September 1986 -

18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months ET Level I Zetec, Inc, Issaquah, WA - January 1989 -

40 Hours_ ET Level II EXPERIENCE:

Certified and experienced at ABB CE as a Level 1-T roinee from June 1985 to September 1986 and as a Level I from September 1986 to January 1992.

EXAMINATION:

General/Basic:

88.0 Specific/Method:

75.0 Pro ct icol/Specific:

94.0 Total:

257.0 I 3

=

85.7 COMPOSITE SCORE The above named individual hos completed the qualification/training requirements for certification in the above examination method in accordance with ABB Combustion Engineering Nuclear Power procedure OAP 2.4 rev1s1on 1

-*./ /

/" -

/.. -

/.."'*------*-

/* I

/.. *'*,

CERTIFIED BY:

POSITION:

Eddy Current Level Ill

~------------~

1.----------------------------------------'

'"'=:.

c..

er 0

?.

0 ::;

jl II 111\\.111 CERTIFICATION RECORD ASEA BROWN 80\\:ERI METHOD:

ULTRASONIC NAME:

Robert B. McGuire LEVEL:

~~~~~~~~~-

soc. SEC. NO.:

CERTIFICATION DATE:

~~~~~~~~~~-

EXPIRATION DATE:

EDUCATION:

Bristol Eastern High School, Bristol, CT - Grad 1 978 TRAINING:

ABB Combustion Engineering, Windsor, CT-November 1984 - 40 Hours UT LI

- June 1990 - 40 Hours UT Lii EXPERIENCE:

II 5/20/93 5/20/96 Certified and experienced at ABB CE as a Level I-Trainee from November 1984 to June 1986, as a Level I from June 1986 to June 1990 and as a Level II from June 1990 to June 1993.

EXAMINATION:

General/Basic:

82.0 Specific/Method:

86.6 Practical/Specific:

95.0 Total:

263.6 I

3 87.9 COMPOSITE SCORE The above named individual has completed the qualification/training requirements for certification in the above examination method in accordance with ABB Combustion Engineering Nuclear Services procedure OAP 2.4 revision 1

CERTIFIED BY:

POSITION:

Ultrasonic Level Ill

Jl 1111 1'1\\1***

CERTIFICATION RECORD ASEA BROWN BOVERI METHOD:

VISUAL VT -1,2,3&4 NAME:

Robert B. McGuire LEVEL:

I I

-~~~~~~~~~~-

SOC. SEC. NO.:

CERT IF IC AT 10 N DATE:

5/29/91 EXPIRATION DATE:

5/28/94

. EDUCATION:

Bristol Eastern High School, Bristol, CT - Grad 1978 TRAINING:

ABB Combustion Engineering, Windsor, CT - September 1986 - 16 Hours VT 1 &3 May 1988 - 32 Hours AWS CWI Prep.

- October 1988 - 8 Hours VT 1,2,3,4 May 1991 - 4 Hours VT 1,2,3,4 EXPERIENCE:

Certified and experienced at ABB CE as a Level II VT 1 &3 from September 1986 to October 1988 and as a Level II 1,2,3,4 from October 1988 to May 1991 with additional experience obtained while performing ISi activities (UT and ET) from November 1984 to October 1988.

EXAMINATION:

General/Basic:

75.7 Specific/Method:

83.0 Practical/Specific:

87.5 Total:

246.2 I 3

=

82.1 COMPOSITE SCORE The above named individual has completed the qualification/training requirements for certification in the above examination method in accordance with ABB Combustion Engineering Nuclear Power procedure OAP 2.2/2.4 revision 1/1 CERTIFIED BY: ~/<('I ~

POSITION: ______

VT_L_ev_e_1 _11_1 -----

/\\SEA 13ROWN UOVERl INC.

Prospecl Hill RoaJ sl Office ilox 500 dinJsor, Connecticut (X>095-0500 CERTIFICATION FOR FIELD SERVICES ACTIVITIES NAME __

R_o_b_er_t_M_cG_u_i_r_e ____ SOCIALSECURITY NO.--- DATE 5/25/93 NEAR VISION -JAEGER R#

FAR VISION - SNELLEN R 2Q COLOR VISION

n ISHIHARA ___..b

____..... ~=--------

( ] WOOL (Holmgren)-------

(of Examination)

EYE EXAMINATION NATURAL CORRECTED L#_.i__

L#

B#

R#_j_

B#_I_

L2Q B2Q R2Q L2Q BW

'3C*

( ";)-

f3 EYE EXAMINATION ADMINISTERED BY: ~

~"?> <'?.-J.

Eye Examination Results Reviewed & Accepted By:

~

£.,,,e<- W:::-

NDE D tmcnt "Required 10 be completed for NDB ccniric:ation only. Not required for qualilica1ion to 1"'Car rcspintol)' protection devices..

PHYSICAL EXAMINATION

/

I/

I HEIGHT 73 'l WEIGHT i7-)°.{

BLOOD PRESSURE /; ~f 7 r (e, u)

SKIN ~

=="d.. <

EARS __

q?.f?___,;,___ ____ NECK

~

EYES

~

HEAD

~-

HEART fd:?l.?-,

r... -~ CHEST Ar.,,J) ;

LUNGS ~

PULMONARY FUNCTION TEST:

NORMAL V

ABNORMAL ~~~~~~~~~~

This is to certify that this individual has been examined and no evidence has been found of any physical condition which might be aggravated by, or attnbutcd to, occupational exposure to ionizing radiation.. This individual has no history or evidence of previous radiation injury and has no history of exceeding the limits of 10 CFR 20.103 and is found to be physically qualified to perform duties involving occupational exposures to ionizing radiation.

This examination has also revealed no indications of aberrant behavior.

This individual has been examined in accordance with NUREG-0041 Section 7.4 and no evidence has been found of any physical or mental conditions in which the use of respiratory protection devices arc considered contraindi-cated.

THE ABOVE INDMDuA@1s NOT QUALIFIED FOR WORK INVOLVING RESPIRATORY PROTECTION DEVICES:.

LIMITATIONS:

Joseph A. Amil to.

tyl D Medical Examiner (I' r int)

Form ii Off2(J.-;os (7/90)

ABB Medical Department Dept. 5'120-1902 1000 Prospect Hill Road Windsor, CT 06095-0500 (203) 285-3339 Clinic Loc;1t ion

Jl 1111

,.Ill****

CERTIFICATION RECORD ASEA BROWN BOVERI METHOD:

EDDY CURRENT NAME:

Calvin C. Provencher LEVEL:

SOC.S;E~C~.~N~O~.:~~liiiiiiiiiiiit"'°~~

CERTIFICATION DA TE:

8/6/92 EXPIRATION DATE:

8/3/95 EDUCATION:

Waterford High School, Waterford, CT - Grad 1988 TRAINING:

ABB Combustion Engineering, Chattanooga, TN - August 1992 - 80 Hours ET LI EXPERIENCE:

Experienced at ABB CE performing activities comparable to a Level I from October 1989 to August 1992.

EXAMINATION General/Basic:

88.0 Specific/Method:

85.0 Practical/Specific: 86.0 Total: 259.0

/

3

=

86.3 COMPOSITE The above named individual has completed the qualification/training requirements for certification in the above examination method in accordance with ABB Combustion Engineering Nuclear Services procedure OAP 2.4 revision 1

CERTIFIED BY~__,V\\,I:, -~---

Eddy Current Level Ill

Prospect Hill Road

.>st Office Box 500 Windsor, Connecticut 06095-0500 CERTIFICATION FOR FIELD SERVlCES ACTIVITIES NAME __

c"""'o"'"""l'""""i"'"'"n-'c"--'_~p"'-'ro"'"""vc...;:e'"'""n-=-ch'"""'e"-'-r __ SOCIAL SECURITY N O.J?*** =*-- DA TE t /.;vt /~ 3 (of Examination)

NEAR VISION - JAEGER R#_J__

EAR VISION - SNELLEN R 20 15-..L COLOR VISION EYE EXAMINATION NATURAL L#_L B#_j_

L 20 B 2il

/.i'J _,,

1-3 R#

R 20 CORRECTED L#

L 20 EYEEXAMINATION y

~

B# __

B 2il

[ ] ISHIHARA _______

ADMINISTERED BY: /'/.vt-,£if, ly414cG<-&<./, 4..-!

Eye Examination Results

/? d _,,,/ /

!/(] WOOL (Holmgren)

Mh.-ri-~{_

HEIGHT 7'!

14 11 SKIN ~---.....c-EA.RS HEAD

~HEART PULMONARY FUNCI10N TEST:

Reviewed & Accepted By:.;<..//~

NOE Department

Required to be completed for NDE certification only. Not rcquiRd for qualification to wear rcspintory protection dC"VKcs.

PHYSICAL EXAMINATION WEIGHT __

Ol.........;t:7.~~----BLOOD PRFSSURE /3;;-&a f?- U o-NECK o

EYES ci?-e---

P.,. 5 b-. o ~

CHEST A-----(

_.e..........:.._

LUNGS c..{2_p-:-

NORMAL ABNORMAL---------

This is to certify that this individual has been examined and no evidence has been found of any physical condition which might be aggravated by, or attnbutcd to, occupational exposure to ionizing radiation. This individual has no history or evidence of previous radiation injury and has no history of exceeding the limits of 10 CFR 20.103 and is found to be physically qualified to perform duties involving occupational exposures to ionizing radiation.

This examination bas also revealed no indications of aberrant behavior.

This individual has been examined in accordance with NUREG-0041 Section 7.4 and no evidence has been found of any physical or mental conditions in which the use of respiratory protection devices arc considered contraindi-cated.

THE ABOVE INDMDUA.i(i:ihs NOT QUALIFIED FOR WORK INVOLVING RESPIRATORY PROTECTION DmCES:

LIMITATIONS:

CORRECTIVE LENSES _ _=.v ____ DENTURES ___ u _____ OTHER __

o _____ _

RESPIRATOR GLASSES L/

Joseph J\\. J\\mato, MD Medical Examiner (Print)

Form #0020808 (7/'){l)

ABB Medical Department Dept. 5'120-1902 1000 Prospect Hill Road Windsor, CT 06095-0500 (203) 235-3339 Clinic Location

Jl 1111 jll\\l*I*

ASEA BROWN BOVERI NAME:

SOC. SEC. NO.:

EDUCATION:

Victor P. Roy CERTIF1CATION RECORD MEIHOD:

EDDY CURRENT LEVEL:

111

~~~~~~~~~~~

CERTIRCATION DATE:

1/31/91 EXPIRATION DATE:

1/31/94 Norwood High School, Norwood, MA - Grad 1970 Northeastern University, Boston, MA - BSME TRAINING ABB Combustion Engineering, Windsor, CT - July 1980 - 24 Hours ET LI EXPERIENCE:

- August 1980 - 8 Hours ET Lii

March 1981 - 34 Hours ET Lii

- August 1984 - 52 Hours ET llA( Fuel Analysis)

Certified and experienced at ABB CE as Level I-Trainee from April 1981 to June 1981, as a Level I from June 1981 to April 1982, as a Level II from April 1982 to October 1984, as a Level II-A Limited to Data Analysis for Fuel from October 1984 to January 1985 and as a Level Ill from January 1985 to January 1991.

EXAMINATION RESULTS:

General/Basic:

84.3 Specific/Method:

83.0 Practical/Specific:

82.1 Total:

249.4 I 3

83.1 COMPOSITE SCORE The above named individual has completed the qualification/training requirements for certification in the above examination method in accordance with ABB Combustion Engineering Nuclear Power procedure OAP 2.4 revision 1

CERTIFIED BY: ~/aJ_

POSmON:

Manager, Core Component Services

BROWN BOVERI INC.

CERTIFICATION FOR Prospect Hill Road usl Office Box 500 FIELD SERVICES ACTIVITIES Windsor, Connecticut 06095-0500 NAME Victor Roy SOCIALSECURITYNO.

DATE 719/93

~~~~~~~~~~~~-

-~~~~~~-

(of Examination)

EYE EXAMINATION NATURAL NEAR VISION - JAEGER R#__J_

L#___L L 2Q B#_L_

R# __

CORRECTED L#

B#

EAR VISION - SNELLEN R 2Q B 20.

R 2Q

/~

L 2Q 13 B 2Q

/0-/

COLOR VISION

[')(] ISHIHARA_~.:....;;..-~-----

EYE EXAMINATION ADMINISTERED BY:_~...._-=11'..... 4........,,_._~

......... "'-==:,--~.....:.",J.-,'--

Eyc Examination Results

/? /___/ 4 /

Reviewed & Accepted By:...

6--d"4.--=~:::~:'::-:::"

~vi~-=---=--==~-

NDE Department

[ ) WOOL{Holmgrcn)_-------

SKIN "Required to bc_complcted (or NOB ccrtificatioa only. Not required for qualification to wur respiratory pro~caion devices.

PHYSICAL EXAMINATION HEIGHT (o '"1 II WEIGHT I 'cf>' &lk.

_£: '"2"... -

EARS *./!-- --~

NECK_.....__........._ __

HEAD ~

HEART JZ..ez~ -

CHEST _______

LUNGS.J....:~::=::::.._

PULMONARY FUNcnONTEST:

NORMAL ___ V--

____ ABNORMAL _______ _

This is to certify that this individual has been examined and no evidence has been found of any physical condition which might be aggravated by, or attributed to, occupational exposure to ionizing radiation. This individual has no history or evidence of previous radiation injury and has no history of exceeding the limits of 10 CFR 20.103 and is found to be physically qualified to perform duties involving occupational exposures to ionizing radiation.

This examination has also revealed no indications of aberrant behavior.

This individual has been examined in accordance with NUREG-0041 Section 7.4 and no evidence Las been found of any physical or mental conditions in which the use of respiratory protection devices arc considered contraindi-cated.

THE ABOVE INDMDUAI@is NOT QUALIFIED FOR WORK INVOLVING RESPIRATORY PROTECTION DEVICES:

LIMITATIONS:

CORRECTIVE LENSES

.-f-DENTURES 0:

OTIIER

~---~~~~

--~......_~~~~-

~~~~~~~-

RESPIRATOR GLASSES

~--~~~~

~~'?

Joseph A. Amato, MD Medical Examiner (Print)

Fnrm 110020808 (7/90)

ABB Medical Department Dept. 5420-1902 1000 Prospect Hill Road Windsor, CT 06095-0500 (203) 285-3339 Clinic Location

OUTAGE SERVICES

~BUSTION~ ENGINEERING SIGNATURE LOG Approximate Dates Work Activity: £1!!~-.:th-~~~-J.sf of Work Activity: _ _1_:-_-3:_~ __.:_~:~_-C( 3 The following individuals are associated with the subject wor~ activity

~nd may sign-off on data sheets and other quality documentation.

--~e~~-JI~Q§~Q~-f~in11 __

__ K_'2_}>_~!".+/-_ __ ~_.: _ _r1_:-.2_~~ rL

_ Ccl.l.L\\) __ c_ _

_p_g_o_\\l_~~ ie M~

AQ.i1Lfi.f?d2._!:..:.. __ LL __ ""':.~f.E~ I

-~~~_i:_, __ 'B,.~------

--~~~--------------------

~-----------

~--------*

Power Systems Combustion Engineering, Inc.

., *'**,*il-

_;Jj_ _____________ _

1000 Prospect Hill Road Post Office Box 500 2ML\\_ __

-~-

P¢t Jfk (203) 688-1911 Telex: 99297 Windsor. Connecticut 06095-0500

EQUIPMENT CERTIFICATIONS

1)

ICI Thimble Defect Standard (Package, 6 pages)

2)

ICI Thimble Diameter Standard (Package, 2 pages)

3)

Miz 18A S/N 043 Certification (Package, 6 pages)

Jl 1111

.l'l\\1919 Defect STD #

NSS-93-013 Serial #1 July 30, 1993 Page 1 of 5 Certification of ICI Thimble Defect Calibration standard NSS-93-013 Serial #1 ICI Thimble Calibration Standard (NSS-93-013 Serial #1) was manufactured from tubing of the same nominal size (diameter and wall thickness) and material (INCONEL 600) as the tubing to be examined.

The pertinent as-built dimensions and material certifications are attached.

ECT Level III Date 7-.Jo-7..J Field Quality Operations Date ABB Combustion Engineering Nuclear Services 1 :umnus:.on E:-ig1nP.e11nq 1*~~

PO Sr)**.:*_.

10r:1i) Pr!;.::... :-r.! Hill Rn:v:

.'i:r:(:~ *. :-*r

-~... *'Jf10~5-0::ii:J!"J

T!J,t IMAGING & SENSING TECHNOLOGY 22 July 1993 CERTIFICATE OF CONFORMANCE 465 Debbie Drive Cambridge. Ontario, Canada N1R 5X9 Tel.: (519) 523-4880 Fax: (519) 623-4686 93/07/B IT IS HEREBY CERTIFIED THAT THE 24" PIECE OF SWAGED ICI*THIMBLE MATERIAL SUPPLIED ON ABB-COMBUSTION ENGINEERING PURCHASE ORDER NUMBER 9307888 WAS CUT FROM THE ICI THIMBLES ORDERED ON PURCHASE ORDER 768533-01.

Quality Manager NOTE:

IST JOB NO: NS-7F MATERIAL CERTIFICATION FOR OUTER SHEATH TUBE ATTACHED.

NSS-93-013 Serial f.i l Page 2 o:E 5

2000 Industrial Parkway Salisbury, MD 21801 SOLDTO:

Reuter-Stokes Can. LTD.

465 Dobbie Drive CERTIFICATION APPROVAL CERT. flo *..1-,,_L Jos2?-J{C.

EST REPORT BY Q.C~ --*DAT[/~/

DAT :

Mav 28. 1987 Cambridge, Ontari* o, Canada, N 1 R 5x9.

CUS ORO #

20637

--~~:------=.....:.....--~~-'--~~----i~;........;:~-~~~------...:::.::.=:.

__..;;;;-=.=...:::...:...... ______ ~-

SPECIFICATION(S):

292 I. D. X. 0205 Wall Alloy 600S MILL ORD. # _

_.5u.7_-0~l=.=l:..:l ____ _

ASME SB-163 REUTER STOKES # SPI-163-1 Rev.4 YIELD ULTIMATE ELONG HARO-

µ1N.

HEAT I O.D.

WALL P.S.I.

P.S.I.

,4 NESS

.f TESTS

'i8. 7'i0/ 107.000 v v

2

,...... i,....-

NX1561

.33l'i.021 36 v 62-~0T 10-1; FLARE ***** OK **.

I I. D.. 28Q I FLATTEN *********

v NX15~5

)

v

/

2

.3315.021 61,250 111,000 36V 64-30!

8-:1~ FLANGE *********

./

I I.D.. 289 REV.FLAT ********

REV. BENO *******

EDDY CURRENT ***

ANALYSIS OK ULTRASONIC *****

c

Mn p

s SI Cr Ma NI Cu Co Fe P-03 REV. 1 v""

sa~5l.3Bz........

./

v v

V'.Z9 V"'

NX1561 L

.03

.27

.009

.001.18 15.02 --

74$3

.05,/ 9.28 GRAIN SIZE f/7.. Y.

r/

v v

v" gi:-48 NX1561 c

.03

.28.010

.007.19 15.02 --

74.8<

.28

.05 v CORROSION TEST *

./'

V'

.dbi v

V' y

NX1565 L

.03

.29

.008

.27 15.30 -- 1!4.'ft

.34

.07 v' 9.01 *****************

/

2(1.009 c

v

,/

v

~5~

./

.01¥ v

NX1565

.03

.003.26 14.76 --

.33 8.92 OK I

HYDRO TEST ***** 1 v L

1000 PSI @ 5 S ~c c

PASSIVATION *****

L THIS ~TERil~ PRO 1UCED IN A~CORDA ~CE W TH 0 I.JR QUA.. ITY OK

~v INT.CLEAN *******

I c o <:;~!JR ~Mr.F. M *.NUAL EV.

04.

ALL U T. S TUPS AND Tc.STS I T.C.C.*** ~-~~-.~.

L *EV ALU l\\TED B A LE ITEL I I IN SPECTO ~-

J OCFR ~l APP.. IES.

SLEEVE CAP **.*..*******

c VISUAL-OK C!J PRODUCT BRIGHT ANNEALED c 1900"F MINIMUM AND RAPIDLY COOLED.

BLOW.286" DIA. X.875L BULLET THRU EACH TUBE DITIONAL REQUIREMENTS *. ~. -~ ~ P.*.. M~q~.Q~~-q-1_ X~-~~?.l-!. 9.~. 'J.qf ~_q: ~. ON BOTTOM

...... TOLERANCES.:... 1. D.... -;-_., 0.00'.'/:-.*.00.3.'~ (JU~. J9.~"!'.-.Q99/:-.*.q9.~"

WALL+/-.0015"/AIM FOR +/-.001"

-THE INFORMATION JR;sE~TEO ABOVE CONFO.,?'S TO THE ~RCHASE ORDER.

~

) ~

//_,/ /a. A

/' r' NSS-93-013 Serial ;fl Page 3 of 5

en.

~

Stan Bambenek Plymouth Tube Company 2000 Industrial Parkway Salisbury, MO 21801 RECEIVED 2 Pieces Tubing.332.Dla..

IDENT AS follows MATUCOND lnco 600 I Annealed Report Number Report Date

Cllent Number Cllent Order

31422 4-JUN-87 666200 PR 11404

TEST TO ASME 56163 Alloy N06600 and P/0 Instructions PHONE 301-749-1666 QUANTITATIVE ANALYSIS BY XR~MB ID Samples:

HN NX1561 HN NX1565 Fe 9.28 /

9.01 V PJ

.22

.26 SI

.15/

.23 v Cu

.29v

.33v

. Mn

.28 v

.30 v NI 73.85 v 73.44 Y"""'

Cr 15.15 v 15.48 /

Co

-.04v

.01../

Pb

<.01

<.01 Mg

<.01 i/

<.01 Y""'

s

.. 001 ;./"

.001.........

c

.03,,_.....

.04 v B

.003

.004 Dlsp:

In Spec In Spec CERTffiC~ATION APPROVAL CERT. No.:l" 39/ __ JOB.... M*// ~-

BY Q.~l

...... DATE./~~2 SFES.. ____.I_fI.:::.5.'g.::/.'7.i ___

FORM I #..... Y2... <fo)-9:.2'I,.__,/ _

NSS-93-013 ti 1 of 5

... WE CERTIFY THIS IS" A muE COPY OF OUR RECORDS Signed for J. Olr..it.j and Co. by Eric Dlrats, Clerk NOTE: The recording. of false, fictitious or fraudulent statements or

\\

I...

~

en

z 0

("")

0.

z

("")

JUL 30 '93 9:37 FROM PINE MEADOW MACHINE PAGE.001 Pine Meadow Machine Co., Inc.

5 WEBB STREEr WINDSOR LOCKS, CONN. 06096 Ta 203-623-4494 FAX 203-623-7853 CERTIFICATE OF CONFORMANCE TO:

ABB COMBUSTION ENGINEERING,INC.

ORDER NO.

9)08107 PART NO.

QUANTITY NSS-93-013 REV. 4 1

EDDY CURRENT ST.ANDA.RD

S/N #1 THESE SUPPLIES CONTAIN NO MERCURY COMPOUNDS OR METALLIC MERCURY AND REASONAaLE STEPS WERE T1µ{EN°TO ENSURE THESE SOPPLrES.WERE NOT CONTAMINATED w:ITH METALLIC MERCURY OR MERCURY COMPOONDS.

PINE MEADOW FURTHER CERTIFIES THE ABOVE REPERENCEO SUPPLIES WERE FABllCATED, TESTED AND INSPECTED IN ACCORDANCE WITH PURCHASE ORDER/MANUFACTURING ORDER REQUIREMENTS, TOGETHER WITH REFER.ENCE CODES, "SPECIFICATIONS AND IS ACCEPTABLE FOR SHIPI-f.ENT.

7/30/93 J;TEM NO.

QTY.

PART NO..

REV.

PART NAME

1\\

RECORD HEAT tt 1S-&s H

A SERIAL It A

J G

0.238R NOMINAL SEE NOTE l

1*J F

0.318GI NOMINAL SECTION "A"DIM 0 B"DIM B -

B

.on

.o 't'i c - c

,oDS I 0 t.Z.

D D -

D

'" o't I OJ t.

E E

){..

~l.io 0

I 00 ~

ROTATED 90° t)/,,.,t?~s;,.ons fJ 1 C o,-.-(;>M-~c./)

u...s111:; /Jt"_,.,,;,.f*f(';r.J NOTES EL- /S-9S ~:;.,,.cf) EL-I 9c/f I> DRILL. PIN. PLUG VELD

~.J-1./ 7~~'?.:.~J' AND GRIND fLUSH

/-J?'.P< ""----:

2> ROLLED DENi -

ND MATERIAL

. l "'-.JO: (.~

REMOVED c

~~:;,SCALE :,.::a. -

NSS-93-013 2

2 4

7 6

5 3

2 1

Certification of ICI Thimble Diameter Calibration Standard UT -

SALEM ICI Thimble Diameter Calibration Standard, UT-SALEM, was manufactured from stainless steel rod, to specific diameters.

The pertinent as-built dimensions are attached.

(Ref. Sketch NSS-93-012 Rev. 1)

Cd!U

~

Field Qualit~s 7-ZC)-93 Date ABB Combustion Engineering Nuclear Services

= -, 30'( 5 :*J

-. *. ',. ?.. i:*~:*~C-! H.: Rna.d

. --;~'.)' *.: 7.)6095-0500

--

-:-"'Jn~'? i203* i::;.~g::

~~. ?031 285*~~~=

, I

, I 11 I 1 I

I 23.5 f

l/ 4 NPT 0.75 0.750

!J.25 t

SN UT-SALEM 0.3199 0.3240 t

0.3135 0.50 TYP 0.3090 t

0.3057 0.3012

~0.2968

--j~L.2917 I

I 10 I

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----~*~*

i

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NOTES V E R IF I E D \\./ I TH EL-1948 CAL. DUE ? 'S/93 BY BH NELSON ON 7 27133

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I

(

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8 7

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f=PR~26-1993 14:12 FRa1 R.G.&E.

TO 8401 P.01 E~"i~IC TRM'.ll:if<ll:::i~IUr°"

j)JlQ DISTRIBUTION DIVISION Category~

lfl.cv1ewed ~

_..t =

ELECTRIC LABORATORY & TELECOMMUNICATIONS TEST PROCEDURE

'l'EST DATE //-J.i-.. 9 Z.

LABORATOR~*TEST PROCEDURE FOR:

ASSIGNMENT 1?5(NDc)

EFFECTIVE DATE _

__:A~s~A:.c:l?...;:.P.::..r::..ov=..:e=d::..--__

The calibration of Zetec Eddy Current Test Sy~tem components.

.C: F "416 "'"' **

---*-~---

Nol<!:

_,-A1S ~roc.e. /14,-c, O-+AllJ.r" CONTROLLED

- DOCUMENT C3J CAu&l'A"f'JoYJr f'Y1 JC.* I 'i' SN* e;, f' ~

tn1e-1s

~N* of.13 J'i11?.- I?

S#* *o J 1 APPROVEp FOR USE

-~v/3~

SUPERVISO~, ELECTRIC TEST LABORATORY

~

SUPERINTENDENT, ELECTRIC LABORATORY AND TELECOMMUNICATIONS fDATE I This procedure contains Y°'z I\\ pages.

~-26-1993 14:13 FR01 R.G.&E.

TO 1.0 1.1 This procedure is used for calibrating various canponents of the zetec Eddy eurrent Testing System to factory standards applicable tmless otherwise noted.

2.0 2.l 3.0 3.l 3.2 3.3 3.4 Zetec F.ddy eurrent technical procedures, as applicable, for particular CCJ?i>onents.

Notify surveillance personnel of this activity.

Verify that personnel performi.nq *this activity qualified pet ql'&D-ll03

Rem:We certification sticker fran instrunent, if any.

Verify that standards used are certified per Ql'&D-1201 to an accuracy of, at least, four t~ better than the stated tolerances in the rmnufactures references, or the 8401 P.02 LTP-ECT Revision 3~

Page 1 of$ 11 best available.standards noting all* exceptions of /1.

tolerance, if any.

~

3.5 Enter the headinq inforrration on the attached Data Sheet end perform the certification tests as indicated in the referenced Zetee procedure(s), recording the ".AS FaJND"

,/'/

data, on the Data Sheet.

~

NCYI'E:

E:quivalent test instrummts and methods may be substituted.

.\\

i J

~

~-26-1993 14: 13 FRa1 R.G.&E.

TO

3. 7

~re the "AS FOli"ND" data with the given tolerances in the Zetec procedures, and initial the applicable line, N/A the remaining line.

Data in tolerance: transfer results to the "AS LEFT" col Ulm or tMke adjustments for better accuracy and enter the final in-tolerance values in the "AS LEF'i'u colunn.

Data out of tolerance: instrument can be re-calibrated and/ or repaired and record final "AS LEE"l'" results.

Record notes of repairs, notes of problems found and work done (enter this infoz:maticn as c:annents en this procedure).

C&U.bz:ations are perforrmd as a service to RSNDE who is responsible for non-confci:mance follow-up.

8401 P.03 ure-EX:r Revision 31\\.....

Page 2 of Z fl 3.9 If "AS ~* data is in tolerance, c~lete a new certificate; nark it "QA approvedtt and indicate a due /7

date of 1 year or N/A this step.

~

o:M:..fE?iTS: (Indicate any maintenance perfor:rred) 4.0 4.1 4.2 REX:ORDS:

Attach copy of applicable carq;ileted Data Sheets to each sL instrument beinq retw:ned. to RSNDE.

Oive this cOO'i)leted procedure to a record reviewer, who will subnt t a copy to Gimm Central Records, after

~

review.

~

Record Reviewer:_..::;.~~::::.....t:::---1...1'-=::..::L;:.=_;._+.

Date.sent to OCR: ____

/ _t.,_/_'l..._1.~/ __ 9_'-_. ___ _

J

.~

APR-26-1993 14: 19 FRa1 R.G.&E.

TO 8401 MIZ-18 CALIBRATION SPECIFICATIONS s1m"'"

S/N 43 ROT 0

SPAN 100 FIRST CHANNEL 1

LAST CHANNEL 16 MlN-HPiX HOR. TO VERT. GAIN OE*JIATION OF ALL CHAtJNELS OF ALL FREQUENCIES IN SCAN FREQUENCY TABLE c 5.f.TJ CHN#

FREQ H-VDE1J SPEC 15 25000 1-0.007.

+I-1%

6 90000

+0.ssr.

+I-It MIN-MAX QUADRATURE DEVIATION OF ALL CHANNELS OF ALL FREQUENCIES INS.F.T.

CHN#

FREQ OOEV SPEC 12 10000 0.00 DEG 3.00 DEG 3

120000 1.49 DEG 3.00 OE6 DEVIATION FROM I HZ INJECTION AT 400KHZ CHNll:

FREQ H-HOEV V-VOEV FREO H-HOEV 1J-VOEV SPEC 1

401000 2.97.

- 2.sr.

400100

+ 0.07.

-15X 2

401000

- 6.1 %

- 2.er.

400100

+ 0.lX

+ 0.0~

. -15" 3

401000 3.el:X

- 2.9%

400100

": 0. 07.

+ 0.0r.

-IS~

4 401000 3.0~

- 2.7%

400100

+ 0.07.

+ 0.1r.

-15~

5 401000

- 3.97.

- 3.8:4 400100

+ 0.0~

+ 0.1 r.

-15~

6 401000 4.t:X

- :;,ar.

400100

.+ 0.0%

- 0.27.

-15~

7 401000

- 3.9%

3.a~

40011110

+ 0.0:t:

-+ 0.0r.

-157.

B 401000 4.0r.

- 3.7)!

400100

+ 0.0%

- 0. I 1.

-IS~

9 401000

- 4.1 x

- 3.ar.

400100 0.2~

- 0.1 ~

-157.

10 401000 4.0~

- 3.9%

400100 0.1~

+ 0.0%

-15%

11 401000 4.e~

3.S~

400100

+ 0.0%

+ 0.0X

-15~

12 401000

- 4.0%

- 3.5Z 400100

- 0.1 ~

+ 0.0~

-157.

13 401000 4.1 i 3.B~

400100 0.2~

- 0.1x

-15~

'14 401000

- 3.9" 3.9~

400100

+ 0.0~

0.1~

-ISX 15 401000

- 3.9" 3.6~

400100

- 0. 27.

0.1~

-15~

IS 401000 4.1~

- 3.7%

40010e

- z.24

~* 0.0r.

-15~

CIC OEU : MAXIMUM GAIN DEVIATION OF ALL CHANNELS WITHIN A SPECIFIC CHN#

14 3

FREQUENCY IN S.F.T FREQ H

V 25000 1401 25000 1457 C/COEV SPEC t3.9Y.

10:!

F/F DEV : MAXIMUM GAIN DEVIATION OF ALL CHANNELS OF ALL FREQUENCIES CHN; 2

2

. rN S.F.T.

FREQ H

340000 1000000 TECHNICIAN J.MP1NLEY v

1?;75 1527 FtFDEV SPEC i-1 I

0~!

P.04

' dP !I

\\

i=F'R-26-1993 14:19 FRCt1 R.G.&E.

Electric Laboratory

- - ~

TEST REPORT APPARATUSTESTEO: U~ /1'J6 -/,f @qt.t OWNED BY:. 8u 1

.f C STANDARDS USED: ~

pcewCXA.S :sheet

~e.c...

As

~JI(),

,4fAR_d V.t?

~

L,~

-J$"~T 9./

/)/"

9. 2 n~

v. j'

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it_q t)J:.

51.~

t"}r_

3~

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X.9

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x:o 1 nJ:.-

As-

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/'"JP'

~/(.

"'y

/.ik.

/.)}:

nk.

TO 8401 P.05 70-58 2/111 pl No.:

CJYJ l..Dcation:

Sj-~el Room Temp: Z 1 ° C/

Tested By: "1zVL'J'.. ~

Data:

//-J.S*9 Z, ct**8dBy: ~*

Sheet No:

7 of //

Te&tNo.:

I TOTi::L P.05

~-26-1993 14: 15 FRCl1 R. G. &E.

TO Electric Laboratory

~ TEST REPORT APPARATUS TESTED: Utec. 4 2 - If! RtJ&ll OWNED BY: ~

(c 7

STANDARDS USED:f/P ~N Gm* SM' 111./RAl,S-'ftJ 7 tlP C&01.fe,..

S'At z 112 ArJ 9'1ZZ 8401 P.06 Cs fl* '"""""'-,o /Io fir"

'j2..e.c.t. 0 70'.A 21111 pf No.:

JJ.!i.... 1 __

Location:..Ste ?A/,.

Room Temp:..ZS" C Tei:tad By: ~wq *.5j,,,.~

Date:

.//*)':£*91-Chack.od By:.

, iJ:::

Sheet No:

t of I/

ToetNo.:

ML18100B132

Contents

Text

2.0 REFERENCES

2.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

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ML18100B132

Text

2.0 REFERENCES

2.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

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