ML20064C364

Forwards Relief Requests B-4,Rev 1,B-7 & C-8 to ISI Program, in Accordance W/Requirements of 10CFR50.55a(g)(5)(iii) & Draft NUREG-1482

ML20064C364
Person / Time
Site:	Comanche Peak
Issue date:	03/01/1994
From:	William Cahill, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1482 TXX-94050, NUDOCS 9403090335
Download: ML20064C364 (29)

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Log # TXX-94050 File # 10010.1 905.4 (clo)

Ref. # 10CFR50.55a(g)(5)(iii) r r

1UELECTRIC March 1, 1994 winia,n 3. cain.ir.

(imup Vuce President U. S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 1 DOCKET NO. 50-445 RELIEF REQUESTS TO THE UNIT 1 INSERVICE INSPECTION PROGRAM (1986 EDITION OF ASME CODE SECTION XI, NO ADDENDA, INTERVAL START DATE: AUGUST 13, 1990, 1ST INTERVAL)

REF:

NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comments," November 1993 Gentlemen:

TU Electric has determined that certain inspection requirements of Section XI of the ASME are impractical and is requesting relief in accordance with the requirements of 10CFR50.55a(g)(5)(iii) and consistent with the guidelines of draft NUREG-1482. This transmittal submits relief requests B-4 (Revision 1), B-7, and C-8 (Attachments 1, 2, and 3, respectively).

These relief requests have been implemented pending your approval.

If you have any questions, please contact Mr. Carl B. Corbin at (214) 812-8859.

Sincerely, William J. Cahill, Jr.

• U 1 i. 9 D. R. Woodlan Docket Licensing Manager 1

CBC/cbc l

Attachments l

c-Mr. L. J. Callan, Region IV Mr. Y. A. Yandell, Region IV Mr. T. A. Bergman, NRR d

Mr. G.

Bynog, TDLS

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Resident Inspectors (2) 9403090335 940301 b

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gDR ADOCK 05000445 00 N. OUw Smt L B.81 DaHas. Texas 75201 PDR

1 1 to TXX-94050 (21 pages)

RELIEF REQUEST B-4 REVISION 1 A.

Item for which relief is requested:

TBX-1 -2100- 1 11R, 12IR, 13IR, 14IR, 151R, 16IR TBX-1-3100- 1 A, 1 A, 2A, 2B, 3A, 3B, 4A, 4B Pressurizer and steam generator (primary side)

Nozzle inner radius sections a

Item Code Class:

1 C.

Examination requirement from which relief is requested:

ASME Section XI 1986 edition, no addenda.

The requirement for volumetric examination of the nozzle inside radius section for nozzles associated with the pressurizer and steam generators (primary side) as described in Table IWB-2500-1, Category B-D, Item Numbers 3.120 and B3.140.

D.

Basis for relief:

Specialized examination techniques and the design and fabrication of nozzle specific calibration blocks are required to obtain the best results for volumetric examination of the referenced inside radius sections. To determine which nozzles warranted the development of these enhanced techniques and the research required for the design of calibration blocks, an evaluation of each nozzle was performed. In this evaluation the nozzle stress and usage factor as well as the potential for thermal shock was considered. Of the referenced nozzles only the pressurizer surge and spray nozzle contains stresses and associated usage factor close to the allowable. Limited access due to the close proximity of the pressurizer heater connections and the fact that the nozzle stresses are below the allowable limits, indicate that the enhanced examination methodology is not warranted for the surge line. It is therefore concluded that only the pressurizer spey be subjected to the required volumetric examination using enhanced techniques and nozzle specific calibration blocks to maximize coverage.

For the remaining pressurizer nozzles, (relief and safeties) as well as the integrally cast primary side steam generator nozzles, a best effort examination will be performed as described below.

Page 1 of 2

e RELIEF REQUEST B-4

)

REVISION 1 (cont.)

4 E.

Substitute examination:

A best effort volumetric examination of the subject exam items will be performed and documented on a case by case basis. Prior to the scheduled examination, engineering and an NDE Level III will utilize the latest industry information available to establish the techniques, equipment and calibrations that would best enable detection of discontinuities that would be detrimental to the integrity of the nozzle inner radius section of each specif1c component. The first occurrence of this situation was associated with the examination of the steam generator number 1 primary side nozzle inner radius sections (TBX-1-3100-1A, IB).

The report attached to this relief request documents the actual exam performed as well as the pre-outage planning related to the performance of this exam. A similar report will be included with the ASME XI IWA-6000 inservice inspection records corresponding with each of the outages that the remaining examinations are schedule in.

F.

Anticipated impact on the overall level of plant quality and safety:

The referenced evaluation indicates that only the pressurizer spray line experiences conditions under which the integrity of the inner radius might be compromised. This examination will be performed with specialized calibration blocks and exam techniques. Performing a best effort volumetric examination on the remaining nozzles utilizing component specific examination techniques will not introduce any anticipated impact on the overall plant quality and safety.

4 Page 2 of 2

TBX-1-3100-1A TBX-1-3100-1B 11/17/93 Attachment Report for Relief Request No. B-4 Rev.1 CPSES UNIT #1 STEAM GENERATOR NOZZLE INNER RADIUS VOLUMETRIC EXAMINATION i

Backstround ASME,Section XI. IWB-2500 exam category B-D item no. B3.140 requires that steam generator (SG) primary side nozzle inner radius be volumetrically examined. CPSES requested relief from the examination requirements per Relief Request No. B-4. (Attachment 1). For the reasons discussed in the relief request and in this report, a full code required examination is not feasible. It was determined that a best effort examination should be performed j

in an attempt to comply with Code requirements.

Discussion It was determined thru contact with EPRI NDE Center that SG inner radius j

calibration blocks are not available. A SG channel head with a machined notch was located at Florida Power and Light (FP&L). TU and Westinghouse ISI personnel traveled to FP&L to perform a calibration on this part to be stored in the instrument memory for possible utilization at CPSES. Prior to leaving CPSES, reactor vessel calibration block TBX-RV-1, which has a notch at the l

anticipated inner radius thickness range, was used as a basic calibration block and the instrument settings stored in memory. (Attachment 2)

The FP&L SG channel head is similar in material product form and thickness; however, the outer surface contours are different as the FP&L head is from a three loop system and CPSES is a four loop system.

Various transducer sizes and frequencies were used. A 1" round,.75MHz, 35 longitudinal wave transducer provided the best resolution. As can be seen in, the noise level was high, apparently due to a fillet weld attaching a retaining ring to the head approximately 1.7" from the inner radius.

Due to the difference in the outer surface contour between the FP&L channel head and the CPSES channel head, the consensus among the participants was that monitoring the clad roll in the inner radius area would be more meaningful than utilizing the FP&L channel head as a calibration block.

Upon returning to CPSES two Level II Westinghouse personnel and a TU Level III performed the examination on SG 1 inlet and outlet nozzle inner radius.

Calibration block TBX-RV-1 was used for initial calibration and the gain was increased so that the clad roll from the inner radius was approximately 10%

full screen height (FSH). Due to the uneven outer surface and changing outer radius contour, the gain was increased or decreased in order to maintain a 10% to 20% FSH clad roll. No reflectors were noted in excess of 50% FSH.

b Conclusion The SG inner radius examination was conducted on a best effort basis. It was concluded that any discontinuities in the inner radius which could be detrimental to the integrity of SG would have been detected.

l>>tC6 es Ragan R B.

a E Level III Codes and Standards Engineering Supervisor i

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Relisf Requaat B-4 Item for which Relief is Requested:

Nozzle inner radii Code Class:

1 Examination Requirement (s):

Table:

IWB-2500-1 Category:

B-D Item No.:

B3.120, B3.140 Table IVB-2500-1, Category B-D, Item Number 3.120 and 33.140 require volumetric examination of the nozzle inside radius section for nozzles associated with the pressurizer and steam generators (primary side).

Basis for Relief:

l Specialized techniques and nozzle specific calibration blocks are required to ensure meaningful results for volumetric examination of the i

referenced inside radius sections.

To determine which nozzles warranted the use of these enhanced techniques, an evaluation of each nozzle was i

performed.

In this evaluation the nozzle stress and usage factor as well as the potential for thermal shock was considered.

Of the referenced nozzles only the pressurizer surge and spray nozzles exhibit a potential for thermal shock and only the spray nozzle contains I

stresses and associated usage factor close to the allowable.

It is l

therefore concluded that only the pressurizer spray be subjected to the required volumetric examination using enhanced techniques to maximize t

coverage.

Limited access due to the close proximity of the pressurizer heater connections and the fact that the nozzle stresses do not approach the allowable limits, indicate that the additional cost and time associated with the enhanced examination methodology is not warranted for the surge line.

For the remaining pressurizer nozzles, (relief and safeties) as well as the integrally cast primary side steam generator nozzles, the cost and additional exposure associated with volumetric examination do not produce a corresponding increase in reliability or safety.

Alternative Examination (s):

None Safety Impact:

The referenced evaluation indicates that only the pressurizer spray line experiences conditions under which the integrity of the inner radius might be compromised. Not performing volumetric examination on the remaining nozzles will not introduce any anticipated impact on the overall plant quality and safety.

Radiological Concerns:

Performance of fewer inner radius examinations will result in less exposure. Also, a sipificant number of manhours in radiation areas will be saved by not installing scaffolding, removing and reinstalling insulation and then removing the scaffolding.

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Equipnant and Personnel Certifications O

'NDE CERTIFICATION RECORD edim.:

M.tft@tf/ L.w.1 W. G. Halley UT Level II

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2) Westinghouse NSID, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training in UT sizine and detection

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. Personnel Certification Summary Record Naas:

James O. Ragan SSN:

555-54-6532 This certification is in accordance with TUE Procedure NQA 1.16-3.01 Method:

Ultrasonic Testine invol: III Education

Background:

High School NA NDE and Associated training:

Data completed:

NA IAngth of course:

NA NDE and Associated work experience: Certified Level III in PT. MT. IPT. FT.

RT and,VT.

1 Eye examination: Date given:

8/6/92 Rasult: Passed Yes j

Certification r - ination:

i Type Data completed:

Raw Score:

Voight:

Crade:

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Basic 2/12/90 93.89 0.3 28.16 Exam:

Methods 2/13/90 os ss 0.4 18.77 Esas:

Specific 2/13/90 inn 0.3 30 96.38 Composite Grade:

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Remarks:

Certification to extend to 5 years in accordance with NOA 1.16-3.01.

Submitted & Approved By:

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NDE !avei III

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COMANCHE PEAK STEAM ELECTRIC STATION GLEN ROSE, TEXAS 76043

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Transducer Description Series S/N Nk b

A B

Iuency b b MHz Size!*

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Testine. Procedure The real time waveform shown in the photo above is the first return echo from a reflector selected with respect to transducer type. All contact (waarplate) transducers are tested on a flat steel (4340) plate while epoxy-faced shear wave transducers are tested on a flat polymer V 'ck.

Dual contact transducers are tested on a flat polymer block unless otherwise

.ified. Delay fingertip removable (Style DFR) transducers are tested off of the tip of the j

delay line. Nonfocused imersion transducers are tested in water over a flat steel plate usin a water path as specified above. Focused immersion transducers are tested the same as nonfocused transducers except that the water path used is equal to the actual focal length.

Using an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and a Tektronix 7L12 frequency spectrum analyzer in a 7704A Mainframe, the real time waveform, UTA-4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed.

Using the linear attenuator in the UTA-4 receiver, the a=plitude of the real time waveform is adjusted to a six centimeter amplitude ( 1 dB) on the CRT. With the vertical calibration of Trace II fixed at 100 millivolts per division, the amount of attenuation used provides a relative sensitivity rating for all transducers certified by Krautkramer Branson.

Real Time Waveform - Trace II Screen writing figures A and F provide the vertical and horizontal screen calibration respectively for Trace II.

Gate Marker - Trace I Screen writing figure C provides the vertical amplitude of the gate marker and is an inconsequential figure. The horizontal calibration for Trace I is the same as that for Trace II.

The portion of Trace II that falls within the gate time period is the signal fed to the frequency spectrum analyzer.

Precuency Spectrum - Trace III Screen writing figure E provides the horizontal calibration for Trace III.

Figures B and

'ow the spectrum analyzer's attenuator and resolution settings respectively.

T KRAUTKRAMER BRANSON P. O. Box 350 Lewistown, PA 17044 I

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Transducer Description Series S/N l2h b A

B i

Tuency MH: Sl:e l.O Style Connector l

TRACE g.

j Contact I:=ersion Nonfocused I

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E F

l Testing Procedure The real time waveform shown in the photo above is the first return echo from a reflector

selected with respect to transducer type. All contact (wearplate) transducers are tested on a j flat steel (4340) plate while epoxy-faced shear wave transducers are tested on a flat polymer

block.

Dual contact transducers are tested on a flat polymer block unless otherwise ified. Delay fingertip removable (Style DFR) transducers are tested off of the tip of the

!u._ayline. Nonfocused imersion transducers are tested in water over a flat steel plate usin l

a water path as specified above.

Focused immersion transducers are tested the same as 4

nonfocused tran2ducers except that the water path used is equal to the actual focal length.

l Using an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and a Tektronix 7LI2 j frequency spectrum analyzer in a 7704A Mainframe, the real time waveform, UIA-4 gate signal,

{ and the frequency spectrum of the gated signal are simultaneously displayed and photographed.

l Using the linear attenuator in the UTA-4 receiver, the amplitude of the real time wavefom is j adjusted to a six centimeter amplitude ( l dB) on the CRT. With the vertical calibration of

! Trace II fixed at 100 millivolts per division, the amount of attenuation used provides a lrelativesensitivityratingforalltransducerscertifiedbyKrautkramerBranson.

Real Time Waveform - Trace II j

Screen writing figures A and'F provide the vertical and horizontal screen calibration j respectively for Trace II.

Ij Gate Marker - Trace I f

Screen writing figure C provides the vertical amplitude of the gate marker and is an i inconsequential figure. The horizontal calibration for Trace I is the same as that for Trace l II.

The portion of Trace II that falls within the gate time period is the signal fed to the jfrequencyspectrumanalyzer.

j Frecuency Seectrum - Trace III j

Screen writing figure E provides the hori ental calibration for Trace III.

Figures B and D -how the spectrum analyzer's attenuator and resolution settings respectively.

i i

KRAUTKRAMER BRANSON P. O. Box 350 Lewistown, PA 17044 1

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BRANCH OFFIC*5:

International Testing I,aboratories, Inc.

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Waighers, Samplers and Assayer 578 582 M ARKET STREET N EW A RK. N. J. 07t os p onssa sacta soo-477su REFORT OF TEST No.

559621 DATE January 2,1991 Echo Ultrasound From R.D. #2, Box 118 Reedsville, Penna.. 17004-9772 PUPfdASE ORDER.N_o_.

36076 SJK S D LE

Ultragel II, Batch 9092 TEST

SPECS,

ASTM-D-129 (81) Sulfur ASBI-D-808 (81) Halogens

RESULTS,

,ULTRAGEL II 1.

Sulfur 1.6 ppm 2.

Halogens :

14.1 ppm I, ?.brtin H. Sackoff, do hereby certify that the above is true and correct.

Swrn to snd subscribed before me rH s 2nd day of January,, 1991.

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.I'f Notarv Public Commission,ixpires Augt:st 14, 1994, To Echo Ultrasound Reedsville, Penna. 17084-9772 1

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INTERNATIONAL TESTING LABORATORIES, INC.

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pm Eche Ultrasound Poi s0016921756 Marked:

Batch 99092 Spoo. 15?H-D-512 submitted to P.O. 936731 - 5JK end us,show Water Leachable chlorides 47 ppm Fluoride 0.64 ppa I, Martin M. sackoff, Executive Director of Laboratories, do hereby certify-that the above is true and correct.

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1. bnti lndenttial Drtw., M erktta, deorgte 20064 a (444)413-1400

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CHEMICAL TEST REPORT Ref.

C43225-3 Date September 20,1992 Page 1 of I

Customen _.Feho Ultrasound. R, Dlqx 118. Reedsville. Penn.svivania 17084 97_7_2 Attention Sco'tt Walters_.

j Purchaw Order #:

4524 SJK Part #/Narne: Ultragel II(Batch 093051)

Materla1%esignation: Ultra nic C.quplant l

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Special dequirement: N/A I.ab Comment-Analv7ed bv'CLCP)_ainmie emission. electrometrie. wet chemical scshniaues l

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Test Results 4

Composition: (Parts ':>er Million)

Identifi. cation cid.s (1)l A!!ofor Spec. Req. (1) h_...

.agel 11 17 (Batch D')105 l}

y Analysis Guideling ASTM-D512-89 ASTM-C871-84 l

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._.I (1) ASTM C871/D512 (Lea;chable Chloride)

Prepared by W M..Kall< r

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Senior Cherhi.st Approved by

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C43225 1 Date September 20,1992 Page 1 of 1

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Customer _. Echo Ultrasogn]. R. D Box 118. Reedsville Pennsvivania_17084 9772 _

l Attention Scott Walters l

Purchase Order #:

45247 SIK Part #/Name: Ultracel II(Batch 093051)

Mat crial. Designation: _Uhdnie Couelant l

Special Requirement: N/Al l

I ab Comment: Ana,1vred bv7ICP) atomic emissiert electrometric wet chemical technicues. ___,.._ _,,, _

Test Results Composition: (Parts per Million)

Identincation Sl C1 Alloj or Spoc. Acq. (1)

(1)'

(2) i..-

eltragel11 3-15 match (mnS f),,_,

Anah sis Guidelines 4.....

ASTM.D129-64 ASTM-D808-91 b

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(1) ASTM D129/ICP-AE(TotalSulfur)

(2) ASTM D808/D512.Hg hh)2 Method (Totdl Chlorine)

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Prepared by

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i to TXX-94050 (4 pages)

RELIEF REQUEST B-7 1

A.

Item for which relief is requested:

TBX-1-3100 1 TBX-1-3100 1 TBX-1-3100 1 TBX-1-3100 1 Steam generator tubesheet-to-channel head welds R

Item Code Class:

1 C.

Examination requirement from which relief is requested:

ASME Section XI 1986 edition, no addenda.

The requirement for volumetric examination of 100% of each of the steam generator tubesheet-to-channel head welds as described in Table IWB-2500-1, Examination Category B-B, Item No. B2.40.

D.

Basis for relief:

Interference from the steam generator tube sheet flange conflguration, welded insulation support pads and a welded component name tag preclude ultrasonic examination of 31% of the volume described in Fig.

IWB-2500-6 as applied to this weld on each of the four steam generators.

See pages 2 thru 4 for an example of the typical configuration obtained from the examination of TBX-1-3100-1-1.

E.

Substitute examinations:

None - however, manufacturers shop volumetric exam records are available in permanent plant files.

F.

Anticipated impact on the overall level of plant quality and safety:

None Page 1 of 4

RebeS Request m B-7

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4 to TXX-94050 (3 pages)

RELIEF REQUEST C-8 A.

Item for which relief is requested:

TBX-2-2530-29 TBX-2-2530-30 Circumferential Piping Welds a

Item Code Class:

2 C

Examination requirement from which relief is requested:

ASME Section XI 1986 edition, no addenda.

11e requirement for volumetric examination of 100% of the weld length as described in Table IWC-2500-1. Examination Category C-F-1, Item No.

C5.11.

D.

Basis for relief:

The specific examination area geometry of these pipe to valve welds precludes the complete ultrasonic examination of the volume required by Fig. IWC-2500-7. Approximately 15% of the exam volume for weld TBX 2530-29 and 20% of the exam volume for weld TBX-2-2530-30 did not receive the full code required coverage.

Best effort examinations consisting of two separate base metal angle shear and longitudinal waves were performed. Full circumferential scan coverage was obtained for both welds. Axial scan coverage was achieved in at least 1 beam path direction with 2 beam angles for the entire exam volume of both welds (see pages 2 and 3).

There were no recordable indications identified by the best effort volumetric exam or by the required surface exam performed.

E.

Substitute examinations:

None F.

Anticipated impact on the overall level of plant quality and safety:

None Page 1 of 3

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1. EV. 2 EXAMINER DATE

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