ML20070M759

Forwards Procedures Ultrasonic Exam for Detection of Intergranular Stress Corrosion Cracking, in Response to NRC 821108 Request for Addl Info Re Implementation of Rev 1, NUREG-0313

ML20070M759
Person / Time
Site:	FitzPatrick
Issue date:	01/19/1983
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20070M761	List: ML20070M759 ML20070M771 ML20070M781
References
RTR-NUREG-0313, RTR-NUREG-313 JPN-83-03, JPN-83-3, NUDOCS 8301250321
Download: ML20070M759 (27)

Text

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I POWER AUTHORITY OF THE STATE OF NEW YORK to CoLUMous CIRCLE NEW YORK. N. Y.10019 (212) 397.6200 LERO Y W. 98NCLAIR TRu37EES

."E ,$N .*,E*aa W A LTER T. KtCINSKI dOHN S. DYSON

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o. . ec u n GEORGE L INGALLS JOSEPH R. 5CHMIEDER

.N E SIDE N T & CMS E, RICH A RD M. FLYNN """'""""

January 19, 1983 R O 5E RT 1. MI LLO N 21 JPN-83-03 '.".".."h".^."..".......

t omas n A6 coums.6 J AMES L. LAROCC A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Domenic P 1'assallo, Chief Operating Rea*wors Branch No.2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Response to Request for Additional Information on Implementation of NUREG-0313, Rev. 1

References:

1) PASNY Letter, J.P. Bayne to T.A. Ippolito dated September 28, 1981 (JPN-81-76) regarding Technical Specifications Changes Relating to Implementation of NUREG-0313, Rev. 1

2) NRC Letter, D.B. Vassallo to L.W. Sinclair dated November 8, 1982 - Request for Additional Information Regarding Implements'lon of NUREG-0313, Rev. 1

Dear Sir:

The Power Authority submitted, via Reference 1, proposed changes to the FitzPatrick plant Technical Specifications which would incorporate the augmented inservice inspection requirements of NUREG-0313, Rev. 1. In Reference 2, additional information was requested regarding the implementation of NUREG-0313, Rev. 1 at the FitzPatrick plant. The questions outlined in Reference 2 are addressed in the enclosure to this letter.

/~ (~)301250321 830119 I PDR ADOCK 05000333 1 p PDR

The Power Authority is actively involved in industry groups working on improvements for the early detection of IGSCC, including the areas of: NDE techniques; training of technicians; prediction methods; and, appropriate weld wampling plans. Therefore, some of the information presented in items #3 and #4 is subject to change in the near future, as improvements and new developments are incorporated into the Power Authority's plans for IGSCC detection.

If you have any questions, regarding this subject, please

! contact J. A. Gray, Jr. of my si.af f.

Very truly yours,

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J.P. Bayne i Executive Vice President Nuclear Generation cc: Mr. J. Linville Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 136 Lycomino, NY 13093 J

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! POWER AUTHORITY OF THE STATE OF NEW YORK l

- JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 4

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ENCLOSURE 1 TO JPN l l

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1.Q. Reclassification of Snfo Ends (III.A.2 of NUREG-0313 Rsv. 1)

In the lettter from J. P. Bayne to T. A. Ippolito dated September 28, 1981 (JPN-81-76), it is mentioned that the

" safe-ends, previously reported as nonconforming, are 1

manufactured from low carbon stainless steel." Therefore, the safe-ends were reclassified as conforming.

Please supply a manufacturer's chemical composition certification of the safe-ends. This chemical composition should include the carbon level.

l.A. Attachment 1 is a copy of the mill test reports for the safe-ends of the recirculation system outlet and inlet nozzles, the core spray nozzles, and the CRD hydraulic return nozzle. These reports indicate a carbon content of

.023%.

Attachment 2 is a copy of the mill test report for the heat of material from which the jet pump instrumentation nozzle safe-ends were fabricated. This report indicates a maximum

! carbon content of .020%.

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2.0 Unidentified Leakage Monitoring (IV.B.a of NUREG-0313 l

l Rev. 1)

a. Identify the methods to detect and monitor unidentified leakage in the pressure boundary piping l

of your BWR, Some of these methods are enumerated in Regulatory Guide 1.45, Paragraph B.

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b. Pleaco fill out tha atteched table of information regarding the system identified in the above paragraph.

2.A. Unidentified leakage in the pressure boundary piping is monitored by surveying the leakage collection sumps. The sumps are monitored by measuring flow out of the sumps, measuring the sump level and the time required for pump outs, and measuring the time interval between sump pump outs. These functions enable detection of unidentified leakage from pressure boundary piping. Information on the detection and monitoring capabilities can be found in the attached Table 2-1. In addition, the drywell gaseous and particulate radiation monitors indicate the presence of coolant leakage.

3.0 Augmented ISI of Nonconforming Service Sensitive Pipe t

a. Please identify the methods for augmented ISI of the nonconforming service sensitive oipe.

b. Provide a copy of the specifications for the augmented l ISI mathods (IV.B. 3 of NUREG-0313 Rev . 1).

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c. Provide a copy of the augmented ISI methods used and I

the training and certification levels the individuals using those methods received. Indicate if cracked specimens are used in your training (IV.B.3 of NUREG-0313 Rev. 1).

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d. Identify the proportion of the nonconforming cervica sensitive pipe that is being inspected (IV.B.2.b of NUREG-0313 Rev. 1).

e. Identify the inspection interval of each system of the nonconforming service sensitive pipe (IV.B.2.b of NUREG-0313 Rev. 1).

f. Identify the Stress Rule Index Numbers for the welded joints in the nonconforming service sensitive pipe (IV.B.l.b (6) of NUREG-0313 Rev. 1).

3.A. Due to increased industry efforts in development and improvement of IGSCC detection procedures and training, the Authority's future IGSCC activities will reflect these improvements, and may, therefore, be different from those described below which were used for the Winter 1981-82 refueling outage.

a. The primary method for augmented ISI of nonconforming ser vice sensitive piping is ultrasonic examinntion.

Due to geometry, some branches, fittings (valves, tees, crosses) and connectior.s may have additional inspections performed using surface (dye penetrant) methods. The UT procedure used is essentially the EPRI developed, IGSCC oriented, shear wave technique.

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Spscifically, this rathod involves the use of caaller diameter, dual element, focused transducers with normally a 45 examination angle and frequency of 1.5 to 5.0 MHz.

b. Attachment 3 is a copy of the procedure used to perform the augmented ISI on nonconforming service sensitive piping. Attachment 4 is a copy of the a

0- procedure used to evaluate any indications discovered during the augmented ISI.

c. The NDE training of both the vendor personnel and'the Authority QA/ISI personnel is, in general, as required by ASME, ASNT Standards. In addition, specialized training was provided in the EPRI IGSCC technique that forms the basis for the procedures used. This initial training was received by an Authority NDE specialist at the EPRI NDE center in Charlotte, North Carolina in September, 1981. This involved the use of 12" schedule 80 pipe samples with IGSCC grown in them.

Such a pipe sample was subsequently used to train both vendor and Authority QA/QC personnel in these specialized IGSCC UT procedures.

Prior to the next refueling outage, both vendor and Authority QC/QA personnel, as well as the UT procedure (s), will be qualified on cracked pipe samples of greater wall thickness than that of the 12" schedule 80 specimen.

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d. Par the Authority's cubmittal of September 28, 1981, the following piping was considered to be nonconforming, service sensitive:

i. The Recirculation System 4" discharge bypass piping.

ii. The two 10" Core Spray piping segments.

iii. The CRD hydraulic return piping.

The 4" recirculation piping received 100% inspection during the 1977, 1978 and 1980 refueling outages.

These inspections were performed using the standard

ASME code technique. In the 1981-82 outage, 4 of 10 welds in one loop were inspected using the IGSCC oriented technique. This inspection frequency follows NUREG 0313, Rev. 1, IV.B.2.b(1). Six different 4" welds are scheduled for inspection during the next (1983) outage, using the IGSCC oriented technique.

This will meet the above requirements of 100% of one redundant piping run in 36 months. Since the Stress Rule Index Calculations have been completed for the recirculation system, the 6 welds selected were chosen from those in Region III (the region of highest susceptibility to IGSCC).

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l The core spray piping consists of "A" and "B" runs.

l The "A" run was replaced during the 1981-82 outage after detection of fabrication induced intergranular l cracking. The replacement piping is of 316L type i

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etainicas steel, and in therefore now c1cacified ac conforming material. The "B" run had a 100%

inspection using the methods described in #3 a) and b) above during the 1981-82 outage. The frequency of inspection of this piping is 100% of the stainless steel welds in each 36 months as per NUREG 0313, Rev.

1, IV.B.2.b(1).

The CRD hydraulic return line is also'being examined as per section IV.B.2.b(1) of NUREG 0313, Rev. 1.

That is, 100% of the welds are to be inspected over a 36 month schedule.

e. See d) above.

f. Stress Rule Index Calculations for the nonconforming material (both service sensitive and nonservice sensitive) were originally not required for use in

, scheduling augmented ISI. The sampling plan for nonconforming service sensitive is, to date, as detailed in 3 d) above. However, Stress Rule Index Calculations have been performed for the recirculation system in consideration for possible implementation of Induction Heating Stress Improvement (IHSI).

Attachment 5 is the Stress Rule Index - carbon %

matrix for the recirculation system.

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The Authority in currently in the process of obtcining Stress Rule Index Calculations for the remaining nonccnforming material at FitzPatrick.

40 Augmented ISI cf Nonconforming Nonservice Sensitive Piping

a. Please identify the methods of augmented ISI of the nonconforming nor. service sensitive piping (IV.B.3 of NUREG-0313 Rev.1).

b. Please provide a copy of the specifications for the augmented ISI method or methods (IV.B.3 of NUREG-0313 Rev.1).

c. Identify each of the augmented ISI methods used and the training and certification levels the individuals using those methods received. Indicate if cracked specimens are used in your training (IV.B.3 of NUREG-0313 Rev. 1).

d. Identify the proportion of the nonconforming nonservice sensitive piping that is being inspected i (IV.B.2b of NUREG-0313 REV. 1).

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e. Identify the Stress Rule Index Numbers for the welded l

l joints in the nonconforming nonservice sensitive piping (IV.B.l.b (6) of NUREG-0313 Rev.1).

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f. Idsntify the propored incpection intervn1 for cach system of nonconforming nonservice sensitive piping (IV.B.l.b of hUREG-0313 Rev. 1).

4.A. a. The method (s) for augmented ISI of nonconforming nonservice sensitive piping are as described in 3 a).

b. See 3 b).

c. See 3 c).

d. The nonconforming, nonservice sensitive piping inspected on an augmented basis consists of the following:

i. 10 12" recirculation system risers.

ii. 2 22" recirculation system ring headers.

iii. 2 28" recirculation system pump suction and discharge piping runs.

iv. the 6" Reactor Water Clean-Up Piping between the RHR piping and valve RWC-46.

v. The 20" RHR piping between the recirculation piping and valve RHR-88.

vi. The 2 24" RHR piping runs between the recirculation piping and valves RHR-81A(B).

e. See Attachment 5 and Item 3 f).

f. Referring to the numbering in 4 d), the inspection intervals are as follows:

i. 100% (40 welds) inspection to be done in 40 l

l months. Inspected 27.5% in 1981-82 (using IGSCC

(

oriented method). 40% are scheduled for i

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inspection during tha 1983 outega - ths=o waro selected from Region III of the Stress Rule Index

, matrix (Attachment 5). The remaining 32.5% will be inspected in the 1984/85 outage.

ii. These welds were originally scheduled to be inspected on an 80 month schedule using the criteria detailed in NUREG 0313, Rev. 1, IV.B.1.b(2). Recent calculaticn of the Stress Rule Index for the Recirculation System has led to selection of candidate welds from Region III

., (high susceptibility) of that matrix. 50% (8 of

16) of the 22" welds have been selected for inspection during the 1983 outage, which more than meets the NUREG 0313, Rev. 1 requirements.

iii. As in (ii) above, the original frequency and criteria for inspection was per NUREG 0313, Rev.

1. However, due to increased concern regarding early detection of IGSCC, 20 of the 40 total 28" welds will be inspected during the 1983 outage.

I Fifteen (15) of these are welds at terminal ends and all are from Region III of the Stress Rule Index matrix (Attachment 5).

iv. Frequency and extent of inspection are as per NUREG 0313, Rev. 1, IV.B.1.b(2). There are 2 welds in this run, one of which will be inspected in 1983.

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v. The frequency and extent of ingpsetion for the 5 welds in this run are scheduled as per NUREG 0313 Rev. 1,, IV.B.l.b.(2).

vi. These two runs consist of 3 pipe to valve welds per run. Again, the frequene/ and extent of inspection is per NUREG 0313, Rev. 1, IV.B.l.b(2).

5.0 Coolant Leakage (IV.B.a.b(2) of NUREG-0313 Rev. 1)

NUREG-0313 Rev. 1 rcquires that:

Plant shutdown should be initiated for inspection and corrective action when any leakage detection system indicates, within a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, an increase in rate of unidereified leakage in excess of 2 gallons per minute or its equivalent, or when the total unidentified leakage attains a rate of 5 gallons per minute or its equivalent, whichever occurs first. For sump level-

, monitoring systems with fixed-measurement interval method, the level should be monitored at 4-hour intervals or less.

t Please provide technical justification for not including this in your Technical Specifications. This justification

! should include data or operating experience.

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5.A. Attachmrnt 6 in that portion of thm Authority's propossd technical specification change submittal of September 28, 1981 which describes the FitzPatrick leakage detection system. It appears that the leakage detection system requirements of NUREG 0313, Rev. 1, IV.B.l.a were met by that submittal, and per telephone conversation with the staff of EG&G, no further information is required.

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, TABLE 2-1 INEORMATION REQUESPED ON LEAK DET. ELTION 1"SITN (1) (2) (3) (4) (5) (6) (7)

Type of Is Leak Time Is Oontrol Calibration tw ,= ntation System System Rate Required System Ibom or Testing Refarence Operable Sensitivity To Achieve Functional Indications During for (1)

(yes/no) (gpm) Sensitivity After SSE (alarms) Operation Thru (6) ,

(hours) (yes/no) (reccrders) (yes/no)

FIDI MEASUREMENT YES 1 INSTAN- NO RECORDER YES 11825-1.68-200A TANEOUSLY GEK-34640 11825-ESK-65B (INTEGRAL) YES 0.10 24 NO INTEGRA'IOR YES F-ISP-15 F-ISP-16 LEVEL MEASURENENT YES N/A INSTAN- NO ANNUNCIA'IOR NO SK-ll825-E455 TANE0JSLY LEVEL RECORDER NO F-IMP-20.5 PLEP OUP AND FILL TIMERS YES 4.279 NO TIMERS NO GEK-34632

.09 - 1.5 ALARM LIGff NO 11825-1.68-119B A21 UNCIA'IOR NO Page 13 of 13

c ,y ATTACHMENT N0. 1

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C E Power Sy:tems ie; o l 5 Joa Jo.i' l Combtestion Engin*+oeg int 911 W M,un Stro*'t Chattanong ) Tene mse 3 /4N Mrf 13 10 30.'". '"

POWER Pfft,7(?

SYSTEMS May 14,' 1982 CO N Y i'-Ji g .y. ..t Mr. Glen M. Lozier Power Authority of the State of New York 10 Columbus Circle New York, New York 10019

Dear Mr. Lozier:

- In response to your letter GML-82-10 dated May 6, 1982, the replacement stainless steel nozzle safe ends on your Fitzpatrick vessel are identified as follows:

Code No. G-3696 - Recirculation Outlet Code No. G-3697 - Recirculation Inlet Code No. G-3698 - Core Spray Code No. G-3699 - CRD Hydro Return I have included additional copics of the mill test reports and copies of the material identification drawing which identifies all of the materials in your vessel as furnished.

If I can be of further assistance, please advise.

Sincerely, COMBUSTION ENGINEERING, INC.

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40-83114 $UPP.

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00040 001 ,Aos 10, 2 RsON R Fain Davis 190 To 74809 .__.,_..__.._.__._.___,

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SHIP TO AND MARM Western Forge & Flange Co. Combustion Engineering, Inc.

. Grant & Read Streets P.O. Box 327 West Main Street Warehouse Santa Clara, California P.O. 40-83114 ,

Chattanooga, Tennessee

- l TE RMS: BUYER W.P.O. NUM45R NO.

27.10 net 30 S.R. McFalls 215 CONTRA [6 NP JOBOR&qCT,5%

V-/U1 f.O R. POLNF SMiPP&hJ CHARGES $441P E1A___ _ _ _ . , _ _ gggy ON _

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5-22-70 ~

QUANT 3TY DESCRIPTION PRICE ITEM l l REPLACEMENT N0ZZLE-SAFE ENDS Code #G-369'6

1. 2/ca. 29 1/16" 0.D. x 24-7/8" I.D. x 8 11/16 lg. (recir.

outlet) ,

Code #G-3697 /

2. 10/en. 14 3/8" O.D. x 11 3/16" I.D. x 9 5/16" lg. (recir. t inlet)  ;

Code #G-3698

3. 2/ca. 13 7/16" O.D. x 9 3/8" 1.D. x 11 1/4" lg. (core  !

spray)  :

Code #G-3699

4. 1/ca. 5 3/8" 0.D. x 2 5/8" 1.D. x 8 5/32" lg. (crd. hydro return)

- sam /ft C--MLE Nuc Nuc. Mat. & Weld lnQ *Nuc. Cost Acct.

Nuc. Cont. Eng.

Nuc. Prod. Control 2 Cont. Ad:9 Nuc. Process Eng. Nuc. Prop. Dept. 2 CO =. COD CO =.vAtus veAR wien Nuc. Q.C. S.R. McFalls 2 23002 70 24 I

iNvon(t I AR CON N ECficui 5 28611 P(N N $YLVANI A 99 40443 OTHER RIGisTRAfrON NO INDI AN A 34925 ftNNESSEE 331-773 41759 DO NOT INvos(t t Au MI550Une 76197 PLE ASE INDICATE YOUR ACCEPTANCE OF THis ORDER BY SIGNING UNDER THE WORD "ACCLPTED" ON THE ACKNOWLEDGMENT COPY AND RETURN SAME TO US PROMPTLY GIVING DEFINITE SHtPriNr, D ATE ett s+ 1 .s 'Nsteucis o em w,tt s. ,s.

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83T14 --- - 4 -o,- 2---- t DESCR;F OON PRICE OVANii1P HEM l TOLERANCES 5 Plua 1/16" Minus 0" O.D. x plus or minus 1/64" I.D. x plus or uinus 1/16" on length. .,

0.D. & I.D. to be concentric within .015" All surfaces to have a 250 RMS finish or better Price: Your wx dated 4-16-70 tdctarial is to be stainless steel type 304 in accordance with C.E.

Purchase Spec. P8C3 (C) _

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Th3 1968 sections II & III ASME codes tnd all applicable addenda thru cummer 1968 applies to this order.

Attached is a copy of General Electric Co's inspection and witness points which is to be made a part of this order.

Advise CE at least five (5) days in advance.

Furnish ten (10) copies of Test Reports CE INC Quality Control procedure specification Qcps. no 11.1, rev. 1 is to be made a part of this order.

Confirming Order DO NOT DUPLICATE l

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S.R. McFalls 21566 NP V-70105

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oVANTITY ITEM l l DESCRIPTION - -. -

PRICE Replacement Nozzle -Safe' Ends Please refer to the above numbered purchase order and be advised as follows:

1) The safe-ends on this order are to be made from heat of material SA-182, gr. F-304 with the following chemistry as reported by the vendor.

C .023, mn-1.75, P .024, S.010, SI .60 NI-9.43, CR-18.4, MO .08, SN .01, CU .10, & CO .12

2) Solution Annealing to be perfonned after all forging and sizing operations are completed by the Forging Vendor.

3) Annealing Temperature 1900 F. min. 1950 max. , holding time 1/2 l

hour per inch ot thickness with 1/2 hour min. & 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> max. ,

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op. 2 *Nuc. Cost Acct.

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invoice tam CONNECTICUT S128011 PE N N $ YL V A NI A 99 00443 OTHER REGISta AtlON NO. INDI AN A 34925 f(NNES$tt 331 773 01759 DO NOT INvotCE T Am aMisovat 76197 PLEASE SAME TO U$INDICATE PROMPTLY. GiviNG YOUR ACCEPT DE FINITE ANCE

$ HIPPING DATEOF TH!S ORDER BY 5tGNING UNDER THE WORD " ACCEPTED ' ON THE ACFNOW WILL $ HIP As tNstavCTE D ON Witt $ HIP FeOu COMBU oN ENGINEERING. INC.

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4) Grein Size 4 or finer

' 5) Rockwell B hardness to be reported for information Also change prices to read instead as follows:

Code G-3696 a G-3697 ..-

G-3690 .

G-3699 .

C nfirms telcon with your Mr. Payne to proceed accordingly.

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^ Western Forge and Fla %Company..,J

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P. O. Box 327 nge if -j . #mi.'. ' . . ' f.6 ?KJFr Santa Clara , California, .... .>,- . . .. . . .

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Size M A T E ?. I A L Stren;,th Sireng!*i in 2" Ar ,J p:1 of pu , . 7, 'A $;cci:non Test 1;vr Narhed 0.27, oCfset '  : /

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lit I?H031 33.700' 83.000 56.5 75 0 . 503" d iar.. .

.e Required Minirnurn 30,000 75,000 45 50 -

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Specifications: A.S.T.M. A182 F304

Reinorks: Yiefd strcagth ct ext:nsion under lo:d of inch p::r inch.

Cheraical Analys is Grain Size: No. 4.5 Ele:nent

~~ "/< f'ound/ 7. Specified '

C "O702 < ~0 03 Nax .

Mn 2.00 Max.

P 1.5 /

0.02 0.04 Max.

S Si 0.02 0.03 Max.

0.67 1r; I f 1.00 Max.

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P. O. Box 327 . ,

Santa Clara. Cali fornia 9S052 Physical Test Yictd Tensite Et cr.g. Red. of Size -

i.*. cia rial Str:ngth Strongth in 2" Arco , of p.s.i. p.s.l. <% %_ Sp:cim:n Test Sar Marked 0.27. /

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Ht. 58241 43,000 82,000 56.5 74 0.507" diam.

n:q : ired r*:r.imum 50 25.000 65,000 30 _ .

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Specificati:ns: ASME SA182 F304 -

i'::..cths: Yit!d strcncth at c:!:nsion under tecd of inch ;:ar inch.

Chemical Analvsis: .

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SaeetCted Grain Size:

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C 02 0.08 Max. .

Si 0.4 1.00 ax. . .

n 1.3 2.00 Max.

P 0.03 0. 04 :'e x.

S 0.02 0. 0 3 2 x,

t 30.1 S.00 11.00 .c.

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~. c 18. / 13.00 - 20.00 F " ' ' ' 9. -

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M ATTACHMENT NO. 3 t

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