ML20247J735

Forwards Addl Info on 1989 Refueling Outage IGSCC Piping Insps & Mods,Per Generic Ltr 88-01.Calculation Re Weld Overlay Design for RWCU Weld CUAJ-5 Encl

ML20247J735
Person / Time
Site:	Millstone
Issue date:	05/17/1989
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-01, GL-88-1, TAC-B13249, NUDOCS 8906010118
Download: ML20247J735 (25)

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L M UTILETIES o.ner : Orvie.. . scia.n sir..t. s.riin. Conn.cticui 1 wesum ms.c m ns sac =c "" P.O. BOX 270 HARTFORD, CONNECTICUT 06141-0270 i:

k k J 7, " C E E "" Z (203) 665-5000 May 17, 1989 Docket No. 50-245 B13249 Re: IGSCC ISAP Topic No. 2.114 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 .

1 Gentlemen:

Millstone Nuclear Power Station, Unit No.1 (

1989 Interaranular Stress Corrosion Crackina Plan Resulti In a letter dated October 26, 1987,(I) the NRC Staff requested that Northeast  ;

Nuclear Energy ' Company (NNECO) provide plans for IGSCC piping inspections and/or modifications which will be completed during the 198f2[efueling outage

. (Reload 12) at Millstone Unit No.1. Generic Letter 88-01 requested that NNEC0 provide. plans for piping replacement, inspection, repair, and leakage 4 detection related Unit piping at Millstone to the No.mitigation

1. of IGSCC of austenitic sgnless NNEC0's July 27,1988 response steel to Generic Letter 88-01 provided our updated IGSCC program for Millstone Unit No. 1, which follows the guidelines of NUREG-0313, Revision 2. This submittal, in i providing answers to the five specific requests of Generic Letter 88-01, provided the majority of NNEC0's plans for IGSCC piping inspections to be conductedduringthecgent1989 on February 3, 1989, outage. A letter was submitted to the Staff which detailed our updated plan to address IGSCC j

j inspections during the 1989 refueling outage. J l

(1) M. L. Boyle letter to E. J. Mroczka, "1987 Refueling Outage IGSCC l Inspection," dated October 26, 1987.  !

(2) F. J. Miraglia Jr., letter to all licensees of operating boiling water reactors (BWRs) and holders of construction permits for BWRs, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," dated January 25, 1989.

(3) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, " Response to Generic Letter 88-01-IGSCC in Austenitic Stainless Steel Piping," dated i July 27, 1988.

'(4) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, " Updated IGSCC Inspection Plan for the 1989 Refueling Outage," dated February 3, 1989.

8906010118 890517 /

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U.S. Nuclear Regulatory Commission B13249/Page 2 May 17, 1989 In a letter dated May 4,1989,(5) NNEC0 provided the results of the weld examinations conducted during the ongoing refueling outage. Attachment 1 to that letter included a list of the results of the weld examinations in the inspection plan and a discussion explaining changes that were made to the plan. Since submittal of the May 4,1989 letter, further Staff questions have arisen on the IGSCC program. Attachment I to this letter provides responses to those questions.

Please contact us if you have further concerns.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY (

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E. J. fro'czka //

Senior Vice President ,

cc: W. T. Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 W. J., Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 Attachment l l

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i (5) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission," 1989 Intergranular Stress Corrosion Cracking Plan Results," dated May 4,1989, i

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Docket No. 50-245 B13249 Millstone Nuclear Power Station, Unit No. 1 Attachment 1 Additional Information on 1989 Refueling Outage IGSCC Examinations May 1989

v , . . . ' a' Attachment B13249/Page 1 Ouestion 1:

l Describe.the weld overlay design for weld CUAJ-5.

Response 1:

The design and application of this overlay are consistent with those previous-ly employed at Millstone Unit No.1. Based on the results of a crack growth evaluation per ASME Section XI, a full structural weld overlay has been designed. The minimum design dimensions are: 0.25" thick x 1.17" half length. The actual weld overlay dimensions are: 0.35" thick x 1.5" half length. Type ER308L weld filler metal, having a. delta ferrite content of 8FN to 17FN, will be used for the overlay. Credit is only taken . for deposited weld metal having a minimum delta ferrite content of 8FN.

NUSCO calculation number 88-014-1086GP; " Weld Overlay Design for Reactor Water Clean Up Weld CUAJ-5" is provided as Attachment-2.

Question 2:

List welds inspected by category.

ResDonse 2:

Number of welds inspected by NUREG 0313, Rev. 2 Category.

Total No. No. Welds Cateaory Welds Inspected A 117 14-B 0 0-C 76 17-D 184 100 E 12 12 F 0 0 G 21 12 A summary list of the IGSCC examinations including the applicable NUkEG-0313, Rev. 2 Category is provided as Attachment 3.

Question 3:

Explain expansion sample size and composition.

Response 3:

NUREG 0313, Rev. 2 does not specify expansion requirements for Category D welds. In NNECO's July 27, 1988 response to Generic Letter 88-01, a sample

Attachment B13249/Page 2 expansion was proposed. No exception to this expansion selection was taken by the Staff, and it was used during the 1989 refuel outage.

The additional sample of welds was selected based on the welds that are determined to contain suspected cracks. The number of welds will be approxi-mately equal to and distributed by the same pipe size and system parameters that were included in the original sample, unless it could be determined that there is a technical reason to select a different distribution.

The RWCU system contains welds of Categories A, D, and G consistent with the guidelines of NUREG-0313, Rev. 2. Four (4) Category D welds were inspected for IGSCC in the RWCU supply line (including CUAJ-5). Therefore, an equal number of welds were inspected in the expansion sample. Please refer to Table 3, pages T3.8 and T3.9 of our response to Generic Letter 88-01, dated July 27, 1988.

Per NUREG-0313, Rev. 2, all Category D welds are inspected within 2 refuel cycles (50% each refuel outage per Millstone Unit No. I's IGSCC plan). All of the Category D welds were inspected during the 1987 and 1989 outages.

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Docket No.50-24E B13249 Millstone Nuclear Power Station, Unit No. 1 Attachment 2 Weld Overlay Design for RWCU Weld CUAJ-5 May 1989

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SAN JOSE , CA ( 408 )978-8200 VERSION 1.2 STRUCTURAL REINFORCEMENT SIZING EVALUATION USING SOURCE EQUATIONS FOR CIRCUMFERENTIAL CRACK MP1 RWCU WELD CUAJ-5 OVERLAY DESIGN WALL THICKNESS = 0.5000 MEMBRANE STRESS = 3S78.OOOO SAFETY FACTOR = 3.0000

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Millstone Nuclear Power Station, Unit No. 1 Attachment 3 Summary List of IGSCC Examinations l

May 1989

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. a; 3e, 1. ; j

, " MILLSTONE UNIT NO. 1 '

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________________1_20_____CO.~ME.LL.IG ICBC-F-22A D 8" X__________________1920 COMELgIE

{13) ICBC-F-23 D G" X ___,010_____GDdELgIE EN-ISI-RB- UT INSP. CORE SPRAY "B" ACCEPT REJECT EXPOSURE COMMENT CSBJ-13 D lo" __ X _ __ _ _ _ __ __ _ _ __ __ _ _,.000_____C 0 DEL ET E CSBJ D 10"__ x ,.ggg_____G0 DELETE CSBJ-15 D 10"_.--_____________X.__________________t000 COM..ELg-_Tg a

CSBJ-16 D to" X__________________,.999_____GgMELgIE .,

<5} CSBC-e--2 D to"_ X__________________1990_____GOMELEIE EN-ISI-RB 'UT INSP. CLEANUP SUP. ACCEPT REJECT EXPOSURE COMMENT CUAJ-14 D 8" X _ _ _ _ ,. 9 2 0 G0debere Cun---9 D B" x__________________tigg_____GDMELEIE

<3} CUA--to D a"_ ______________x__________________tigg_____GOMELgIg EN-ISI-RB- UT INSP. CLEANUP RET. ACCEPT REJECT EXPOSURE COMMENT CUBJ-18 D B" X__________________t02M_____GOMELgIE (2} CuBJ-19 D e"_. ______________X______.____________tegg_____GOMELgIg HELD _DYEBLAYS EN-ISI-DW- UT INSP. RECTRC. RISERS ACCEPT REJECT EXPOSURE COMMENT RRAJ-4 E 12"_. _____________K__________________ 0f!D_____G0dELEIE RRBJ-1 E 12" X__________________,.06D_____GOMELEIG RRBJ-2 E 12" X _________1960____,GOMELEIG RRCJ-3 E 12" __

X .02D_____GDMELETE RREJ-3 E 12" X 3070_____GQUELEIE RRFJ-1 E 12" ..______________X_,,____________,___..,_060

_ GQdELEIE (7} CUAJ-5 E 8"_. ._________..___________________,____________D8DELINE l EN-ISI-DW- UT INSP. REC 1RC. MAN. ACCEPT REJECT EXPOSURE COMMENT

{1) RMBJ--1 E 22" X ___,.9Dg_____GOMELgIE a

EN-ISI-RB- UT INSP. ISO.COND SUP. ACCEPT REJECT EXPOSURE COMMENT

{1} ICAC-F--3 'E 16"________________X__________________1900_____GOMELgIS i

(101} DRYWELL EXAMS

{53) REACTOR BUILDING FXAMS *

(155} TOTAL IGSCC EXAMS ,

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