ML19254E697

Forwards JB West 790910 Ltr,Me Fate 790727 Ltr & JB West 790724 Memo.Info Pertains to Board Question 15-1

ML19254E697
Person / Time
Site:	Black Fox
Issue date:	09/27/1979
From:	Gallo J ISHAM, LINCOLN & BEALE
To:	Purdom P, Shon F, Wolfe S Atomic Safety and Licensing Board Panel
References
NUDOCS 7911020177
Download: ML19254E697 (14)

Text

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NRC PUBLIC DOCUMENT nooy

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'b ISHAM, LINCOLN & BEALE COUNSELORS AT LAW

.k 1050 97!" STREET.N.W. SEVENTH FLOOR 3 N' y p ** wAS:4 4 N G T O N, 0. C. 2 O O 3 6

.p T EL C# HON E 202-833-9730 N CHICAGO OFFICE k,5 ? ONE F4RST NATION AL Ps AZ A p)V p

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• dy CHICAGO,4LLINOIS 60603 1f T E LE PHO NE 312-77,6-750 0 sgs, j T E t E x: 2- 51..

September 27, 1979 Sheldon J. Wolfe, Esquire Mr. Frederick J. Shon, Member Atomic Safaty and Licensing Atomic Safety and Licensing Board T Board Panel U.S. Nur . t egulatory U.S. Nuclear Regulatory Commise a Commission Washington ..C. 20555 Washington, D.C. 20555 Dr. Paul W. Purdom, Director Environmen*al Studies Group Drexel University 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 Re: In the Matter of the Application of )

Public Service Company of Oklahoma, )

Associated Electric Cooperative, Inc. ) Docket Nos. STN 50-556 and ) STN 50-557 Western Farmers Electric Cooperative )

)

(Black Fox Station, Units 1 and 2) )

Gentlemen:

Consistent with the tenets of full disclosure as articu-lated by the App.eal Board in McGuire,* Applicants are sub-mitting the enclosed memorandum and letters for the informa-tion of the Licensing Board and the parties. The enclosures consist of the following:

1. A letter dated September 10, 1979 from Dr. John B. West to Joseph Gallo, Esquire; 1261 _

320

• Duke Power Company (William B. McGuire Nuclear Station, Units 1 and 2), ALAB-143, 6 AEC 632 (1973).

7911020l'77

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2. a letter dated July 27, 1979 from Mr. Martin E. Fate, Jr. to Mr. William G. Gang; and

3. a memorandum date ' July 24, 1979 with enclo-sures* to Mr. Maroc E. Fate, Jr. from Dr. John B. West.

This information is relevant to Board Question 15-1 and the Applicants are presently pondering whether or not to file a proper motion requesting that this information be made a part of the evidentiar; reeved.

The foregoing information documents a decision made by the Applicants to replace the piping material for the Black Fox reactor recirculation system from 304 stainless steel to 316K stainless steel material. The purpose of this change is to mitigate to the maximum extent the occurrence of the intergranular stress corrosion cracking phenomenon in the reactor recirculation systems for the Black Fox Station.

Sincerely, Jose h Gallo One of the Attorneys for the Applicants 1261 321 Table II to the memorandum is not enclosed because it contains Company confidential financial information.

. ._ ..:.a.-.-..-.-~-.-....~......~.... - . - . . ~ . . . . . . .

e 6212 DIN 8-017-605 PUBLIC SERVICE COMPANY OF OKLAHOMA m c

,i A CENTRAL AND SOUTH WEST COMPANY k e a y v P.O. box 201/ TULSA. OKLAHOMA 74102 / (918) 583-3611 w Public Service Company of Oklahoma File 6212/6912.215.1412.21L Black Fox Station E212/6912.215.0200.21L IGSLC Mitigation Alternatives for Reactor Recirculation System September 10, 1979 Mr. Joseph Gallo Isham, Lincoln & Beale 105017th St. , N.W. , 7th Floor Washington, D.C. 20036

Dear Jae:

You will recall that during the Black Fox Station safety hearings PS0 indicated that we were studying alternatives for the mitigation of Inter-granular Stress Corrosion Cracking for the recirculation system piping.

We have concluded that substitution of 316 stainless steel piping (General Electric Company internal designation 316K) for 304 stainless steel is the most viable alternative and have so informed G.E. Attached is a memo submitted to Mr. ii. E. Fate, Jr. , presenting the BFS Engineering recommenda-t3n and a letter of intent to C.E. documenting the management decision to use 316 (316K) stainless steel.

If you have questions please do not hesitate to contact me.

Very truly yours, t-n B. West T I nager, BFS Engineering JBW:br 1261 322 Attachment cc:T.N. Ewing G.W.Muench J.K. Mar +in

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C.J. oss Black & Veatch J ggggg g -

7.['T CENTRAL AND SOUTH WEST SYSTEM

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Attochment #2 I6212DIr8-016-850 r

PUBUC SERVICE COMPANY OF OKLAHOMA A CENTRAL AND south WEST COMPANY [

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P.O. box 201/ TULSA. OKLAHOMA 74102 / (9181583-3611 Martin E fore..fr.

Eneartime Via hesUent

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Public Service Company of Oklahoma Black Fox Station NSSS Contract - Quote #86 July 27, 1979 Recirculation and RHR Suction Datej \6212/6912.312.5500.44L Piping Ma'.erial Modification File:

/ \

GE letter GSJ-79-842 of June 22, 1979, same subject Re: 1.

2. GE letter GSJ-79-832 of June 11, 1979 l

/

General Electric Company J 175 Curtner Avenue San Jose, California 95125 Jul. 2 71979 Attention: Mr. W. G. Gang, MC395 P"otrCT

. pecuy..t

~

i Gentlemen: \

\ /

It is the intent of-the Company to exercise and 6ontract for Option C (86C),

referenced letter one (1). Details of incorporation will be negotiated at a later date to be determined.

Ver truly yours, A -

6

./+n 1 xecu resident J MEF:JMR:skk cc: J. B. West C. E. Benson A. T. O'Toole M. J. Robinson C. J. Ross L. R. Cannard 1261 323 CENTRAL AND SOUTH WEST SYSTEM gngtP w rgrgL%ht gcgge, Company of Oklahoma }guthw tern rc Power gt,TegsyAties

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PUBLIC SERVICE COMPANY OF OKLAHJM A FOR INTRA-COMPANY CORRESPONDENCE ONLY M N ^# 8- 0 / 7- la dp File 6212/6912.215.1412.21L IGSCC Mitigation Alternatives for 6212/6912.215.0200.21L BFS Reactor Recirculation System oATE July 24.1979 SUBJ ECT M. E. Fate, Jr. o g p 7, Executive opp,c, toc,7,og 2-G0 To J. B. West N ogp7, E Engr. opp,cg toc,7,og OM FROM , x 7, Black Fox Station Engineering recommends that Public Service Company replace the 304 stainless steel piping in the BFS Reactor Recirculation System provided by G. E. with 316K material . For their internal purposes General Electric has designated as 316K.

stainless steel with a closely controlled low carbon, high nitrogen content which is within the code composition limits defined for 316 SS. By closeiy controlling the carbon content it is possible to retain the resistance to IGSCC of 316L stainless while maintaining the mechanical properties of 316 which are equal to or better than 304 stainless steel. We believe that this option, while the most costly of alterna-tives, provides the best currently available technical solution to mitigation of 1GSCC problems and provides the lea. c economic risk over the design lifetime of the station.

General Electric Company presented to PS0 four alternative proposals for mitigation of Intergranular Stress Corrosion Cracking (IGSCC) in the BFS reactor recirculation piping. We have considered three of these proposals as being technically acceptable and have rejected the fourth which incorporates heat sink welding. Of the three acceptable proposals, utilizing complete replacement of 304 stainless steel would provide PS0 with the least economic risk due to costs associated with ASME Section XI In-Service Inspect 4on and the potential for field weld repair. The use of 316K also would have ALARA benefit since it would avoid an increase in radiation expo-sure time due to In-Service Inspection. However, the initial cost for this option is approximately $2,000,000 greater than the option using 304 stainless steel pipe-ing with corrosion-resistant clad, solution heat treated shop welds and some small 316K spools or transition pieces. While the latter option is regarded as techni-call, acceptable, it would result in an increase in field construction complexity, with 18 corrosion resistant clad .' eld welds per unit and would make In-Service Inspection more difficult.

The third G.E. proposal, while technically adequate, increases substantially the number of welds in the system. There is a significant initial cost increment com-pared to the CRC /SHT options but with no compensating technical advantage.

The history of IGSCC occurrences prompted G.E. to issue over the last several years a series of recommendations to PS0 concerning piping materials, welding and water chemistry control to mitigate IGSCC. In testimony before the ASLB, PS0 indicated that G.E.'s recommendations were under study and later we indicated we had re'erva-tions regarding the use of Heat Sink Welding (HSW), largely due to the lack of re-gulatory acceptance and lack of field experience. Ba:ed on the high evaluated costs of performing HSW in the erection of the recirculation system, PS0 requested that G.E. evaluate and propose additional options to PS0 which did not include HSW.

G.E. presented four alternate methods te mitigate IGSCC in the BFS reactor recircu-lation piping. These four alternate methods are outlined in letter GSJ-79-832 which is attached to this recommendation. The following is a discussion of what I parceive to be the relevant information PS0 must consider in the selections of one of these options:

1261 324 7 _.

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IGSCC Mitigation Alternatives for File 6212/6912.215.1412.21L BFS Reactor Recirculation System 6212/6912.215.0200.21L July 24,1979 Page 2 Option A - Combined use of Solution Heat Treatment, Corrosion-Resistant Cladding, and Heat Sink Welding. This is a no cost quotation to PSO. G.E. has provided this option as part of their BWR/6 improvement program. The use of heat sink welding in this option makes it technically unacceptable to PS0 for three reasons:

1. The NRC has defined their regulatory position for this topic in NUREG-0313. Thi's document does not mention heat sink welding as an acceptable IGSCC mitigation technique. Acceptable techniques mentioned include Solution Heat Treating (SHT), Corrosion Resistant Cladding (CRC) or the replacement of 304 and 316 stainless steel materials with low carbon materials not sensitive to IGSCC.

2. BFS Construction personnel and B&V have stated that heat sink welding will be very difficult to accomplish in the field. G.E. has stated that water quality mntrol and heat removal would have to be used to accomplish this tu of welding. Heat sink welding has not been used to erect a field piping system.

3. G.E.'s test data indicates that heat sink welding is the least effective IGSCC countermeasure.

NO BWR owner has accepted this option according to information available to PS0 (Table I).

Option B - Combined use of shop solution heat treatment, corresion resistant cladding and the use of some 316K spool pieces. This option would eliminate approximately 37 heat sink welds at a cost of about $280,000 per unit.

Major criticism of this option involves the corrosion resistant clad welds for which ultrasonic inspection is signi'icantly more difficult to conduct and inte.roret. Nine of the CRC welds are field welds for which fit-up and weld repair could potentially cause difficulty. The NRC has accepted the methods utilized in this option in NUREG-0313 and Regulatory Guide 1.44.

Option C - Re placement of the 304 stainless steel reactor recirculation piping with 316A stainless steel. G.E. has quoted costs of about $1.2 million for Unit One and $1.3 million for Unit Two.

This option has the distinct adv6ntages of ninimizing the total number of welds in the reactor recirculation system, deleting all heat sink welding and all corrosion resistant clad welds. Since the original 304 material has been delivered to the fabricator this option has the largest economic penalties. G.E. has included in this quote credits for NSSS money for the reactor recirculation piping for fabrication, a $12,000 scrap value of the 3L4 piping, and an undetermined amount which G.E. allowed as part of their product improvement program. The 316K material is an ASME-accepted material of controlled carbon and nitrogen contant.

1261 325

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IGSCC Mitigation Alternatives for File 6212/6912.215.1412.21L BFS Reactor Recirculation System 6212/6912.215.0200.21L July 24, 1979 Page 3 Option D - The recirculation system would be fabricated with the use of 304 stain-less steel and 316K stainless steel. All heat sink welding and corro-sion resistant cladding would be deleted. The cost would be about

$682,000 per unit.

This option has the advantage of having only 316K to 316K welds to per-form. Less time would be required to perform field welding than with the clad welds in Option B. Option D adds twenty-seven additional welds per unit.

Since the potential for IGSCC increases with the number of welds and these additional welds would require Section XI In-Service Tr.spection, this opticn is cusidered to be less desirabla than Options B of C.

Additional CRC Weld Considerations Welds in the Reactor Recirculation System come under ASME Section XI requit ements for In-Service Inspection (ISI) and there are some aspects of Option B which must be addressed. Past industry experience indicates that clad welds require two to four times as long to inspect and interpret. This is due to interference of the ultrasonic beam at the weld metal / base metal interface. The increased ISI has been estimated by B&V and is included in the attached cost comparison. The large penalty shown for Options B & D is associated with the number of welds added by these options and with clad weld ISI difficulties. In addition, since the Reactor Recirculation System is one of the highest radiation areas in the station, any in-crease in the inspection requirements would contribute to occupational exposure.

No man-rem cost penalty was included in the B&V cost comparison.

Cost Comparison Table I, attached, indicates that of the three technically acceptable Options (B,C, and D) that Option B is the most cost effective. Tnis cost analysis uses B&V's pre-vious estimates for field heat sink welding. Also attached as Table II is the pro sent status of BWR's under construction, awaiting CP's or LWA's.

I would appreciate the opportunity to discuss this recomendation with you at your convenience.

CL h% n B. est n

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JBW:br Attachments cc: .T.N. Ewing G.W.Muench V.L.Conrad J.R. Corn 1261 326 J.M.Royce

TABLE I .

BWR RR PIPING STATUS .

304 -

PLANT STATUS REPLACEMEN's STATUS

• ALLENS CREEK IN FABRICATION QUOTE LIK$LY TO GO 316K BLACK F0x (TWO UNITS) MATERIAL DELIVERED FABRICATION ON FOUR OPTIONS 3 HOLD c CLINTON DELIVERED TO SITE WILL USE CRC AND 316K l RISERS NO HSW ACCEPTED .

t GRANDGULF 1 DELIVERED TO SITE 304 INSTALLED WITH CRC i

• GRANDGULF 2 DELIVERED TO SITE WILL REPLACE WITH 316K

- t

• Hi.RTSVILLE (FOUR UNITS) DELIVERED TO SITE WILL REPLACE WITH 316K  ;

HOPE CREEK BEING INSTALLED CRC FOR ALL WELDS

{

• LIMERICK DELIVERED TO SITE WILL REPLACE WITH 316K j

• NINE MILE 2 IN FABRICATOR'S SHOP QUOTED-LIKELY TO GO 316K PERRY l BEING INSTALLED CRC FOR ALL WELDS PERRY 2 DELIVERED TO SITE CRC FOR ALL WELDS T

• PHIPPS BEND (TWO UNITS) IN FABRICATION WILL REPLACE WITH 316K  ;

S LIVE O ITE ET OT D

- FERMI 2  !

N

$ LASALLE SHOREHAM VARIOUS STAGES OF INSTALLATION SHTONRISERSjSOMEOF u f N

y HANFORD 2 AT PLANT SITE THESE PLANTS HAVE LRC 3 SUSQUEHANNA N RISERS

> *8 UNITS 316K

• 2 UNITS LIKELY TO GO 316K  !

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. WORKING FIG GEN ER AL h ELECTRIC NUCLEAR ENERGY PROJECTS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 395, (408) 925-3129 June 11, 1979 GSJ-79-832 12.it. DIN 3 -o IL 'JA~2 g_ 42.t 2.- 312-55oo. $rg (IR5B M JHRoum)

Mr. T. N. Ewing RECEIVED AND F11ED TBW" Project Manager TBP ~ Black Fox Station Nuclear Project gyg., Public Service Company of Oklahoma JUN 141979 P. O. Box 201 N" Tulsa, OK 74102 PROJECT MCMENT CONTROL WTE >

BIG ] Attention: J. B. West /J. K. Martin HHE Sentlemen:

64N rt

SUBJECT:

~~

INTERGRANULAR STRESS CORROSION CRACKING COUNTERMEASURES (IGSCC) FOR BLACK FOX RECIRCULATION PIPING SYSTEM

Reference:

GE letter GSJ-78-592, from W. G. Gang to T. N. Ewing, dated 7/24/78 The purpose of this letter is to describe the various options for the recirc piping IGSCC for Black Fox Station. A quote is now being prepared for PS0 consideration for each of these options. The options are as follows:

Option A Recirc piping system would be fabricated to the ICSCC AID 40-78 which includes solution heat treat (SHT), corrosion resistant clad (CRC) and heat sink welding (HSW). aid 40-78 was trans-mitted to PS0 by the referenced letter.

Option B Recirc piping would be fabricated with SHT, CRC and some material replacement with 316K stainless steel. This option deletes all HSW and decreases the number of CRC weld joints.

Details of this option are given in Figure 1 (attached).

Option C This option is a complete new system fabricated from 316K material. This approach deletes all HSW and CRC and minimizes the number of weld joints. The reference document for this option is the present Recirculation Loop Piping Purchase Part Drawing 762E843 (833-G001).

transmitted to Black and VeatchThisdocumenthasbeenpreviously%

and PSO.

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GENER AL @ ELECTRIC Mr. T. H. Ewing Page 2 June 11, 1979 USJ-79-832 Option D This option would be to modify the existing Type 304 piping system by add.qg 316K short spool pieces (pups) and fittings to delete all HSW and CRC weld joints. Details of this option are given in Figure 2 (attached).

The 316K material for Options B and D are shown by the cross-hatening on attached figures. The 316K material is a GE designation for 316 stainless steel with special requirements to meet the recirculation piping appli-cation.

The above options also will cover the RHR suction line. The RHR suction line has a 304 stainless steel spool piece between the recirc tee and the vertical elbow of the RHR suction line (see GE Drawing 112D1470).

For Option A, the spool will be CRC at the weld joints. For Options B, C and D, the spool will be replaced with a 316K spool.

The giotation for the above options are scheduled to be transmitted to PS0 during the week of June 18. Due to the time limitations on the piping vendor quotations, the quote will be valid only until July 27, 1979.

If you have any questions or concerns about the above options, please contact Mr. G. L. Hayes at (408) 925-2374 at your earliest convenience.

Very truly yours, A!)3I 23-Will"am G. Gang Project Manager Black Fox Project WGG:bjr/1177-78 Attachment cc: J. R. Corn, (PSD), w/ attach Dr. M. J. Robinson, w/ attach.

L. R. Cannard, w/ attach.

C. J. Ross, (B&V), w/ attach.

J. M. Royce (P50), w/ attach.

1261 329

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of the Application of )

Public Service Company of Oklahoma, )

Associated Electric Cooperative, Inc. ) Docket Nos. STN 50-556 and ) STN 50-557 Western Farmers Electric Cooperative )

)

(Black Fox Station, Units 1 and 2) )

CERTIFICATE OF SERVICE I hereby certify that the following:

Letter to the Atomic Safety and Licensing Board from Joseph Gallo, dated September 27, 1979 in the above-captioned proceeding was served upon the persons shown on the attached list by depositing copies thereof in the United States mail, first class postage prepaid, this.

27th day of September, 1979.

A2.

J PH ALLO'

- e of the Attorneys for the Applicants 1261 332

Sheldon J. Wolfe, Esquire Mr. Clyde Wisner Atomic Safety and Licensing NRC Region 4 Board Panel Public Affairs Officer U.S. Nuclear Regulato;y 611 Ryan Plaza Drive Commission Suite 1000 Washington, D.C. 20555 Arlington, Texas 76011 Mr. Frederick J. Shon, Member Andrew T. Dalton, Esquire Atomic Safety and Licensing 1437 South Main Street Board Panel Room 302 U.S. Nuclear Regulatory Tulsa, Oklahoma 74119 Commission Washington, D.C. 20555 Mrs. Carrie Dickerson Citizens Action for Safe Dr. Paul W. Purdom, Director Energy, Inc.

Environmental Studies Group P.O. Box 924 Drexel University Claremore, Oklahoma 74107 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 Mrs. Ilene H. Younghein 3900 Cashion Place Docketing and Service Section Oklahoma City, Oklahoma 73112 Office of the Secretary of the Commission Mr. Lawrence Burrell U.S. Nuclear Regulatory Route 1, Box 197 Commission Fairview, Oklahoma 73737 Washington, D.C. 20555 (20 copies) Mr. Maynard Human General Manager Atomic Safety and Licensing Western Farmers Electric Cooperative Board Panel P.O. Box 429 U.S. Nuclear Regulatory Andarko, Oklahoma 73005 Commission Washington, D.C. 20555 Mr. Gerald F. Diddle General Manager Atomic Safety and Licensing Associated Electric Cooperative, Inc.

Appeal Board Panel P.O. Box 754 U.S. Nuclear Regulatory Springfield, Missouri 65801 Commission Washington, D.C. 20555 Mr. Vaughn L. Conrad Public Service Company of Oklahoma L. Dow Davis, Esquire P.O. Box 201 Counsel for NRC Staff Tulsa, Oklahoma 74102 U.S. Nuclear Regulatory Commission Mr. T. N. Ewing, Manager Washington, D.C. 20555 Black Fox Station Nuclear Project Public Service Company of Oklahoma Joseph R. Farris, Esquire P.O. Box 201 John R. Woodard, III, Esquire Tulsa, Oklahoma 74102 Feldman, Hall, Franden, Reed

& Woodard Charles S. Rogers, Esquire j}{j} 816 Enterprise Building Assistant Attorney General Tulsa, Oklahoma 74103 112 State Capitol Building Oklahoma City, Oklahoma 73105}}