ML20150E325

Discusses Mitigative Actions,Weld Overlay Upgrades & IGSCC Insps Performed During Reload 7 Outage.Updated Classification of Svc Sensitive Weldments Into 7 Categories Per NUREG-0313,Rev 2 Also Included

ML20150E325
Person / Time
Site:	Brunswick
Issue date:	03/25/1988
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19302D365	List: ML20150E325 ML20150E329 ML20150E332
References
RTR-NUREG-0313, RTR-NUREG-313 GL-88-01, GL-88-1, NLS-88-073, NLS-88-73, NUDOCS 8803310035
Download: ML20150E325 (20)

Text

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Cp&L Carolina Power & Light Company MAR 25 1988 Serial: NLS-88-073 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 IGSCC INSPECTION RESULTS - RELOAD 7 Gentlemen:

By letter dated October 2,1987, Carolina Power & Light Company (CP&L) apprised your staff of the Company's plans for performing mitigative actions, upgrading existing weld

- overlay repairs, and performing examinations for Intergranular Stress Corrosion Cracking (IGSCC) on Brunswick Steam Electric Plant, Unit 2 (BSEP-2) during the Reload 7 outage. The mitigative actions, weld overlay upgrades, and IGSCC inspections are complete. This letter contains descriptions of: 1) the IGSCC examination program,

2) th' mitigative actions taken including the Mechanical Stress Improvement Process (MSIP) that has been performed on selected inconel butter welds of the reactor pressure -

vessel nozzles and the current status of the Hydrogen Water Chemistry (HWC) Control System installation, and 3) the repairs performed during the current refueling outage, including the Weld Overlay Repair Upgrade Program, new weld overlay repairs applied; and repair performed on jet pump instrumentation (JPI) penetration seal. An updated classification, based upon the results of this refueling outage, of the "service sensitive" weldments into the seven categories as defined in NUREG-0313, Revision 2, is included as Table 1. In addition, this letter contains a basis for continued operation of Unit 2 until the next refueling outage, presently scheduled to begin in August 1989.

In response to your letter dated March 2,1988, weldments of resistant piping materials have been added to Category A of the IGSCC Classification List (Table 1). Other susceptible welds (i.e., non-classified) will be added and included as part of the Company's response to Generic Letter 88-01.

IGSCC EXAMINATION PROGRAM Scope of Examinations The ultrasonic testing (UT) performed during the Reload 7 outage are divided into the following categories (and included in Table 2):

1) Category C Welds Twenty-nine welds, subjected to stress improvement (IHSI) during the previous refueling outage, were examined.

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g 2) Category D Welds Twenty-nine welds were re-examined. This included pre and post examinations of the inconel butter welds scheduled to receive MSIP -

application. Based upon information provided during the January 27,1988 meeting with the NRC Staff, the scope was expanded to include examination of all 10 reactor recirculadon system.

thermal sleeve-to-safe end welds.

3) Category E Welds Twenty-one exisdng weld overlay repairy including-three which were upgraded this outage, were examined as part of the original inspection scope. ,

In addition, two new weld overlay repairs were also examined.

4) Category F Welds The two suction nozzle-to-safe end welds with existing axial indications were re-examined.

5) As a result of General Electric (GE) Service Information Letter (SIL) No. %2 issued on February 1,1988 concerning cracking of the shroud support access ,

hole cover attachment weld, the Company decided to inspect similar welds on BSEP-2. The UT examinations were performed using the same remote UT equipment as was utilized at the plant where indications were discovered. t Results of these examinations showed no defects. .

The criteria used for selection of welds to be examined was as follows:

a) The sample size of each category was determined following a review of Section 3.0 and Table 1 established in Draft NUREG-0313, Revis!on 2.

b) A representative sample from each IGSCC category based upon a review of susceptibility of welds as determined from prior inspections.  ;

i c) Welds receiving mitigation and weld overlay repairs being upgraded or entering multiple fuel cycles of service received higher consideration.

d) ALARA.

UT Process The UT examinations were performed by GE and the UT personnel were qualified in j accordance with the EPRI/BWROG/NRC requirements including the latest requalification program. The examinations incorporated the use of the fully automated GE "Smart UT" System, where geometrically feasible. The SMART UT System utilizes the Ultra Image ll! computer-driven data acquisition system with the ALARA remote i

scanning device. The scanner is capable of positioning a transducer at any location circumferentially, axially, and at any angle to the weld centerline. Manual

exams supplemented the SMART UT exams where geometric limitations existed.

j The sizing of IGSCC indications was performed using 2 to 5 MHz refracted longitudinal transducers. The sizing methods used were those taught at EPRI, including Satellite Pulse Observation Technique (SPOT), Pulse Arrival Time Technique (PATT), ID and OD creeping wave technique, and tip dif fraction techniques, as applicable. ,

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NLS-88-073 / Page 3 UT RES'!_!.y Results of the UT examinations performed during the current Reload 7 outage revealed the fcilowing:

1) Of the 81 welds examined, flaws were detected in two of the unrepaired welds. An axial indication was confirmed in the pipe-to-elbow weld,12ARD2, and a circumferential indication (with axial components) was found in the safe end-to-nozzle inconel butter weld 12ARE5. A detailed description of the past and current examination data including the UT methods used for sizing is contained in Design Report No. SIR-88-003 prepared by Structural Integrity Associates, Inc.,(SIA), submitted as Enclosure 1 to this letter.

2) Results of the inspections performed during Reload 6 revealed a small axial indication in each of t.he 28-inch suction nozzle-to-safe end welds. Using the same techniques and equipment as previous inspections, these indications were re-examined during the current Reload 7 outage. No change in the indication size of each of these flaws was detected. An additional axial flaw was found in the 28BI weld. This indication, smaller than the existing one, had the following parameters: 26.9 inches from zero reference and 0.20 inches length x 0.20 inches through wall depth on the upstream (nozzle) side of the weld.

3) The welds (including the,two suction nozzle-to-safe end welds) which received MSIP were UT examined prior to and af ter the application. No relevant indications (other than those already described) were detected.

4) The three weld overlays, which were upgraded to a standard design, were UT examined following completion of the welding. No change in existing indications were recorded.

MITIGATIVE ACTIONS Mechanical Stress Improvement Process (MSIP)

MSIP was performed on 15 inconel butter welds on the reactor pressure vessel nozzles as indicated in Table 2. The MSIP application was performed by O'Donnell and Associates, Inc. (ODAI) in accordance with their approved procedures. MSIP has been qualified as a

, stress improvement process providing resistance to IGSCC in NUREG-0313, Revision 2.

( A design report performed by ODAI on the MSIP application is submitted as Enclosure 3 to this letter. The information contained in Enclosure 3 is considered to be proprietary.

An affidavit signed by CDAI, owner of the information, is provided as Enclosure 4 to this letter. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission in accordance with 10CFR2.790 (b)(1).

Hydrogen Water Chemistry i

Installation of the Hydrogen Water Chemistry Control System is in progress. The i Company currently projects that the start-up and operation of the Unit 2 system will be completed during the summer of 1988 following start-up of the unit.

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

NLS-88-073 / Page 4 IGSCC REPAIRS Weld Overlay Repair Upgrade Program During the current Reload 7 outage, CP&L upgraded three existing weld overlay repairs on BSEP-2 to meet the "standard design" requirements as described in NUREG-0313, Revision 2. Upgrading of these overlays (28A4,28B3, and 28B4) consisted of adding thickness to the overlay as required, and performing surface finishing such that the overlay repair can be inspected in accordance with the EPRI qualified UT technique for weld overlay repairs. A complete design report, SIR-88-010 performed by SIA, is submitted as Enclosure 2 to this letter.

12ARD2 Overlay A weld overlay was applied to the weld 12ARD2 in response to an indication detected in the weld joint during the current Reload 7 outage. The overlay meets the requirements for a "standard design" as described in NUREG-0313, Revision 2, and has the length and surface finish to facilitate inspection in accordance with the EPRI qualified UT technique for weld overlay repairs.

The weld overlay design applied satisfies the requirements of IWB-3640, ASME Code Section XI, and NUREG-0313, Revision 2. A complete design report, SIR-88-010 performed by SIA, is submitted as Enclosure 2 to this letter.

12ARE5 Overlay An inconel weld overlay was applied to weld 12ARE5 in response to an indication detected in the weld joint during the current Reload 7 outage. Because of the proximity of the flaw to the low alloy steel (A508 Class 2) reactor pressure vessel nozzle, the repair technique involved applying an inconel "temperbead" weld overlay. The temperbead layers of the overlay were applied in accordance with IWA-4000, ASME Code Section XI and Code Case N.432.

A complete description of the weld overlay repair including description of repair process, i design criteria and analysis, and review of metallurgical considerations is provided in i

Design Report SIR-88-003 performed by SIA, submitted as Enclosure I to this letter.

JPl Penetration Seal Repair A thru-wall leak was discovered on a 3/4-inch JPl penetration seal connection weld.

Subsequent to the discovery of this leak, all other penetration seal connections (23 total) were examined and found to be free of defects.

The repair to the JPI penetration seal connection thru-wall leak consisted of adding weld reinforcement to the existing fillet welded socket to provide a "strengthened" fillet weld as described in Design Report SIR-88-010. The original fillet weld was approximately 0.168 inches (1.09 times thickness). The repair consisted of 0.17 inches (minimun) applied ,

on penetration fitting side and 0.375 inches (minimum) applied on 3/4-inch tube side.

Following completion of the repair, the weld was liquid penetrant examined.

__. _ _ ~ - _ _ _ _ _ . _ _ _ _ _ . . . . _ . _ _ - . . _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _

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NLS-88-073 / Pagn 5

SUMMARY

OF SUSCEPTIBLE WELD POPULATION The susceptible Class I weld population for BSEP-2, based upon NUREG-0313, Revision 2, including a summary of those welds mitigated or repaired is as follows (as shown in Table 2):

BSEP-2 Total number of IGSCC susceptible welds (not including nonclassified welds added per final issue of NUREG-0313, Rev. 2) 180 Number of welds replaced with resistant material 36 Number of welds repaired by overlay 41 Number of welds mitigated by IHSI 57 Number of welds mitigated by MSIP 15 Number of welds mitigated by Solution Annealing 8 Unmitigated (includes two 4-inch decon connections, ten 12-inch thermal sleeve to safe end welds, ten 12-inch pup picce to safe end welds, and one 6-inch tie-in to RWCU system) 23 COMPENSATORY ACTIONS The following special surveillance measures continue to be implemented at the Brunswick Plant.

1) As required by the Technical Specifications, plant shutdown shall be initiated for inspection and corrective action and shall be taken when any leakage detection system indicates, within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an increase in the rate of unidentified leakage in excess of 2 gpm. For sump level monitoring systems with fixed measurement interval method, the level shall be monitored at 4-hour intervals or less.

2) At least one of the leakage measurement instruments associated with each sump shall be operable and the outage time for inoperable instruments shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, an orderly shutdown will be immediately initiated.

These special surveillance measures are consistent with those given in Section 6.0 of NUREG-0313, Revision 2, and CP&L's ALARA program.

CONCLUSION Carolina Power & Light Company has completed IGSCC examinations and repairs on Unit 2.

The Mechanical Stress Improvement Process was applied to 15 inconel butter welds on the reactor pressure vessel nozzles.

NLS-88-073 / Page 6 Three existing weld overlays were upgraded to meet the standard design requirements described in NUREG-0313, Revision 2. Two new standard overlays were applied in response to indications detected. The 41 weld overlay repairs have sufficient length and surface finish to facilitate inspection using the EPRI qualified UT technique for weld overlay repairs.

One JPI penetration seal connection discovered to be leaking was repaired with a reinforced fillet weld. All other penetration seal connections were examined and found to be free of defects.

The suction nozzle inconel butters (28Al and 28B1) have been examined. Existing flaws detected during the previous refueling outage have not changed in size. Indication sizes from UT examinations performed last outage, pre-MSIP application and post-MSIP application, are provided in Table 3. Both welds received MSIP applications. Analysis performed by GE and SIA show that these indications meet the ASME Code Section XI safety margins for at least one additional 18-month fuel cycle. The re-examination of these welds, which detected no change in size, in conjunction with the MSIP application provides a preliminary basis for reclassifying these joints to Category E. based on the results of subsequent inspections to be performed during the next refueling outage.

UT examinations were performed on a total of 81 welds in NUREG-0313, Revision 2, Categories C, D, E, and F using the GE SMART UT System where geometrically feasible. The scope of the examinations were in accordance with schedules listed in Section 5.3.2 and Table 1 of NUREG-0313, Revision 2.

As a result of the mitigative actions taken, the state-of-the-art inspections performed, and the continuation of enhanced surveillance requirements for drywell leakage detection, CP&L believes that start-up and continued operation of BSEP-2 until the next refueling cycle (presently scheduled for August 1989)is justified and will not adversely l affect the health and safety of the public. Based upon the favorable results of the l Reload 7 outage examinations, the Company intends to proceed with start-up of BSEP-2 as scheduled on April 8,1988.

An inspection plan will be submitted three months prior to the start of the next BSEP-2 refueling outage (currently scheduled to begin September 1989). Should you have any questions regarding this submittal, please contact Mr. S. D. Floyd at (919) 836-6901.

Yours very truly, L. . ofli M nager Nuclear Licensi g Section LIL/ECN/che

Enclosures:

1. Design Report No. SIR-88-003

2. Design Report No. SIR-88-010

3. MSIP Application Performed by ODAl (Proprietary)

4. ODAl Affidavit cc: Dr. J. Nelson Grace (NRC-Ril)

Mr. W. H. Rutand (NRC-BNP)

Mr. E. D. Sylvester (NRC)

ENCLOSURE 4 0'DONNELL AND ASSOCIATES INC. AFFIDAVIT l

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COMMONWEALTH OF PENNSYLVANIA )

COUNTY OF ALLEGHENY - ) S.S.

AFFIDAVIT Before me, a Notary Public in and for said Commonwealth, appeared Edward J. Hampton, to me known, who, being by me duly sworn according to law, deposed as follows:

1. I am the Vice President, Operations, of 0'Donnell & Associates, Inc. ("0'Donnell"), a design and analysis firm doing business at 241 Curry Hollow Road, Pittsburgh, Pennsylvania 15236. I am authorized to apply for the withholding from public disclosure of the information discussed in this Affidavit.

2. This Affidavit is made in support of the application of 0'Donnell to have the materials, . documents and information described in paragraph 3 (hereinaf ter referred to as "proprietary information") withheld from public disclosure and treated and protected by the Nuclear Regulatory Commission as trade secrets or confidential and privileged commercial information. This Affidavit is made in conformance with the provisions of 10 CFR g 2.790 of the Commission's regulations.

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3. The specific matter which O'Donnell wishes withheld from disclosure is identified in Analytical Verification of the Mechanical Stress Improvement Process For 4" Nozzle, prepared for Carolina Power & Light Company, Southport, NC 28461-0429, 1909-404-001-00; Analytical Verification of the Mechanical Stress Improvement Process for 10" Nozzle, prepared for Carolina Power & Light Company, Southport, NC 28461-0429, 1909-410-001-00; Analytical Verification of the Mechanical Stress improvement Process for 12" Nozzle, prepared for

2 Carolina Power & Light Company, Southport, NC 28461-0429, 1909-412-001-00; Analytical Verification of the Mechanical Stress Improvement Process for 28" Nozzle, prepared for Carolina Power & Light Company, Southport, NC 28461-0429, 1909-428-001-00 Report (s) dated January,1988, which is intended to be used in the application of O'Donnell's mechanical stress improvement process

("h5IP"). The proprietary information has great value and potential for use in the nuclear power industry and in the power industry in general. O'Donnell has expended much time and money in the development, analysis and testing of its mechanical stress improvement process. The cost of development exceeds

$4,000,000.00

4. The proprietary information is of a type customarily held in confidence by O'Donnell and not customarily disclosed to the public.

O'Donnell has a rational basis, described in this Affidavit, for treating the proprietary information as confidential. The information in the reports identified above have been treated and protected as confidential proprietary matter. All drawings, pictures and correspondence have been clearly marked Proprietary. Contracts with clients and suppliers have provided for this protection and signed confidentiality agreements were obtained from these parties.

5. The proprietary information represents the professional engineering product of O'Donnell and is entitled to protection from public disclosure under trade secret laws and Commission regulations.

6. The proprietary information in the subject reports are labeled Proprietary and are being transmitted to Carolina Power & Light Company so 7

l that they may elect to transmit them to the Nuclear Regulatory Commission in confidence; and under 10 CFR g 2.790, these documents are to be received in confidence by the Commission, t

3

7. The proprietary information is a product of the engineering experience and judgment of O'Donnell and its staff and constitutes valuable commercial assets of 0'Donnell's employees. The proprietary information is not known to any O'Donnell competitor and is not available in any public source to the best of my knowledge and belief.

8. O'Donnell has invested hundreds of man-months of engineering effort and has spent or committed in excess of $4,000,000.00 in the development of MSIP. This is a very significant investment for a firm whose annual sales are of the order of $7,000,000. Confidential possession of the proprietary information is an asset of 0'Donnell and gives us a commercial advantage in selling the MSIP applications described in the above identified reports.

Public disclosure of this information would substantially harm O'Donnell's competitive position since O'Donnell's unique background of theoretical and practical experience in the nuclear design analysis and testing field and in MSIP technology have rPde the development of the MSIP service business possible. If this information were publicly disclosed, it would enhance the r.bility of 0'Donnell's competitors to design, analyze, verify, sell and install the aforementioned technology without commensurate expense. Moreover, the proprietary information may contain patentable ideas for which patent protection may be desirable. Any such patentable ideas are entitled to protection against public disclosure.

9. O'Donnell's competitors could only acquire or duplicate the proprietary information with difficulty and at significant expense by performing the same type of development ef fort including the full scale test program as has been expended by O'Donnell and by investing similar sums of money. If the proprietary information sought to be protected was publicly disclosed, O'Donnell's competitors would have the use of that information without having made any payment to O'Donnell for the right of such use and could undersell O'Donnell in offering similar services to potential customers.

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10. For all the reasons discussed in the paragraphs of this Affidavit, O'Donnell would be harmed by any public disclosure of the O'Donnell proprietary information.

And further deponent sayeth not.

bf s t Edward J.[aInpt ice President, Operations Sworn to and subscribed before me this 24 day of March, 1988.

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Notary Public ,

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TABLE I IGSCC INSFECTION ClASSIRCATIONS - BSEP 2 CATEGORY A CATEGCRY C CA TEGOR Y D CA TEGOR Y E ggg,g7,n7 u gt,g, NON-ReSiS TANTMA T'L. NON RESISTAN T NA T'L. CRACKED St AFTER 2 YPS. OPER. NO SZ OVERLAYED O.? SC 22AM5BCA 28A2 2882 28 A 98CI 22AM38CB 28A3 2886 28892C 28A4 2883 22AM$%A 28A5 2887 28A80 2884 22AM58CB 28A6 2888 12 ARA 4A 28Al3 0 2885 0 228MIBCA 28A7 2889 12AR84A 288ll 0 228MIBC8 28A3 25810 12 ARC 4A 228M3BCA 28AIO 288l2 12ARD4A 22AMS 228Mi 228M3BCD 28A ll 288 /28CI 12ARE4A 29Al2 28813 128Rf4A 12 ARA 2 128PF2 28A l28C 298I4 I28PG4A 12APA3 128RF3 R9A 29AI4 29 BIS I28RH4A 12ARB2 128RF4 R8A 28A IS 28BISBCI 12BRJ4A 12AR83 128RGI 1993 28A ISKI 28 BIG 128PK4A 12ARCI 12BRG2 1992 28A l6 29817 12 ARC 2 12BRG3 1991 28Al7 298I8 A THERMAL SlHvE(N2) 12 ARC 3 128RG4 1990A 28AIS B I2 ARC 4 128RH2 1989 24Al2 24812 C 12ARDI 128RH4 1988 22AMI 228M2 O 12ARD2 128RJ2 1987 22AM2 228M3 E 12ARD4 128RJ3 22BM4 e 12 APE 2 126RK2 2007 22AM3 2006 22AM4 G 12ARE3 I2BRK3 RSA 22AM6 H 12ARE4 R4A 20AI J 12ARE$ IB K U 2003 20Al8C 2002 20A2 4A I 481 2001 12ARAI 12BP'l , R IOA 4A ll 48tl RI8 12APA4 12BRFS W TO TA L 41 4678 12APA5 & 12BPG5 $

CATEGORY F aA2 ae2 AP '**""b pH 4A3 483 I2APBS I28PHS$ CRACKED INADEOVATE 4A 4 484 I2APC5 128PJI OR to REPAIR 4A D 48 5 12ARD3 128PJ4 29 A I 4A6 48 6 12ARDS & 12BPJS $ 28 8 I 4A 7 48 7 12AREI 12BPKI 4AB 48~ 8 I2BPK4 4A 9 48 9 128PK5&

4AIO 4810 ION $A & IONSG 4N8A @ JNd 8 _;

TO TA I. = 70 TO TA L = 23 TOTA L = 2 TOTA L s 44 NOTES

1. REMAINING SUSCEPTIBLE WELDS TO BE ADDED IN CP*L RESKWSE TO GmEPIC l.ET

2. NO NELDS CURRENTLY LIS TEDIN CATEGORIES B OR G.

3. FCR CETAILED WELD INFO, SE TABL E 2,

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TABLE 2 (CONT'D) I' AGE 4 Or G HELD OR ISI DESCRIPTION IGSCC CATEGORY WELD OVERLAY LAST REF. NO. SYS JOIN T PRE PL'7 RET RL"7

" ' OPIGINAL UP3RADE INSPECTICt. REAI & S 2881 832 N - SE F E AISI P Y RL 7 2882 __

l SE - P C C IHSI N RL 7 2883 ^ P-E E E Y RL G PL 7 RL 7 STAllDARD O/L

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Y RL 6 _

RL 7 DESIGNED ~OfL 2887 P -E C C IMSI ~

N ~~

RL 6 2888 E '- V C C IH 51 N RL 6 2889 V -P ~~ C C 1HSI N I?L 6 2889BC W D D N RL 7 28810 ~~

P-E C C IHSI N RL 6 kB55I E -RJMP E E IHSI Y RL 6 N/A ' RL 6 DESIGNED O/L fGBl2 _ _ _ _ __ __ j _ RfAtP- P_ C _ C__ IHSI N RL 6_ __

IHSI _

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?BBI3 j_ __P - V C C IHSI N RL 6 28814 g V-E C C IHSI  !! _ RL 6 28815 E-P _ C C IHSI N HL 6 28Bl5BC1 W C C IHSI N RL 7 2855G_ l P-T C C IH Sl _ 'N RL 7 _

28B17 T-C C C IHSI ll RL 6 29 BIB C-R C C IM S I N RL G 24812 T-V C C IHSI N RL 6 226At I _

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I2BRF4A P - SE D D N PL 7 I2BRF5 $ SE - it D C MSIP N RL 7 INCONEL BUTTER

TABLE 2 (CONT 'O l PAGE 5 Of G WELD ORISI DESCRIP TION 4GSCC CA TEGORY REL D OVERLA Y LAST

,g ,,9 gg pgg REF NO. SYS JOIN T PRE PL'7 f rYT RL 7 ORIGINAL UlYPADE INSFECTION 12BRGI B32 S-P E E IHSI Y PL G N/A RL 6 STAliDARD 0 IL 12BRG2 P-E E E Y PL G N /A PL 7 STAIJDARD 0/L 12BRG3 E -_P- - . . E E PL 6 N /A PL 7 STANDARG O' L

- -- - . . - - . - - - - . ..Y - - .-

128RG4A ~~

P - SE ~D~ D~ ~

N PL 6 ~~

I2BRGS SE - N D C ~Af St V~ ~~~N PL 7 INCONEL BUTTER 12BRHI S-P C C IHSI N RL 7 12BRn2 P-E E E Y QG N/A RL G STANDARD OfL '~

12BRil 3 E-P C C IHSI N RL 7 12BRH4 P-P E E Y PL G ~~ N ]5 RL G STANDARD OlL 12BPH4A_ _ _ __ P - SE__ D _DC _

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TABL E 2 (CONT'D.) PAGE G Of G WELO OR ISI DESCPIPTION IGSCC L.ATEGOK)  ? Wil ObERLAY LAS T pggggg TO M MM@

, REF NO SYS JOINT 11E RL*7 ftET RL*7 OFIGINAL UWRADE INSPECTION 488 832 V-P A A .

N RL I f4 Pita 3 REFLACED(3LML)19M 489 P-E A A N RL l h

4810 E-P A A N RL i 1 4 P i l _ __ P-W_ _ E_ _ _ _

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N PL 6 N /A RL 7 STAPCAR$ lL

~ ~

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E2 ~ SE - N O C ~ ils!N~ ~ ^ ' tl RL 7 INCONEL BUTTER t

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4N88 _ B21 SE - N _D _ _

C AISI P __N' RL 7 INCUEL BUTTER ABBREV 1ATIONS N-NOHIE RL__ - RELOAD (REFLEd EE-SAFE END $ 1984 B21 - NUGEAR BOILER SYS. (JPI)

P- PIPE 6 - 1996 B32 - REACICR RECl%ULATION SYS.

E -ELBOW 7 - 1988 Ell - RESIDUAL HEAT REMOVAL S6.

T - TEE E2I - CORE SPRAY SYS.

Pp-PUAIP AISIP-MECHANICAL STRESS IMIR?VEAIENT PROCESS G31 - REACTOR WATER CLEAN-UP SYS.

C-CROSS SA - SOLUTION ANNEALED i V- VALVE IHSI -INDUC?lai HEATING STIESS IMPFOVEMENT TS-THERAIAL SLEEVE h W- WELDOLET Y- YES F- FLANGE N - NO S - SWEEPOLET O/L OVERLAY R WDUCER NOTES-

1. REAIAINING SUCCEPTICLE WELD {NON-CLASS I ) TO BE ADDED IN CP*L RESPONSE TO GENERIC LETTER 88-01

4 TABLE 3 e

SUCTION WZZLE IM:01EL IRITTER IWICATIONS Reload 6 Weld 28Al' 2881

, Olstance from Reference On 10.1"

- Lergth 0.300" 0.250"

• Through Wall Death 0.250" 0.250" i Side Upstress (Nozzle) Upstream (Nozzle)

Orientation Axlal Axlal 7 Pre WSIP Distance from Reference 0" 10.1" 26.9" g Length 0.300" 0 .250 " 0.200" Through Walt Depth 0.250" 0.250" 0.200" Side Upstream (Nozzle) Upstream (Nozzle)

Orientation Awlal Axial Axial r l

j ,

Post-MSIP Distance from Reference 0" 10.1" 26.9" f Length 0.300" 0.250" 0.200" (

Through Walt Depth 0.250" 0.250" 0.200" q

Side Upstream (Nozzle) Upstream (Nozzle) j Orientation Axial Axial Axlal t

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4Je m 5 ENCLOSURE 1 STRUCTURAL INTEGRITY ASSOCIATES INC.

DESIGN REPORT NO. SIR 88 003 I

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