ML19320A449

Confirms 790824 Meeting W/Utils in Washington,Dc to Discuss Type & Extent of Exams Required Per IE Bulletin 79-13

ML19320A449
Person / Time
Site:	Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane
Issue date:	08/13/1979
From:	Garrett W SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Mosley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
IEB-79-13, NUDOCS 8006040502
Download: ML19320A449 (11)

Text

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August 13, 1979 Hr. Norman C. b ley Nucluar Rugulatory Commission i

Divicion of Reactor Operations Ins tions 4350 East West Highway Washington, D. C. 20555 Docket Nos.:

50-313 Arkansas Muclear 1 50-302 Crystal River 3 50-344 Davis Besse 50-269 oconee 1 50-270 Oconee 2 50-287 oconee 3

.IHIS DOCUMENT CONTAINS 50-312 mancho see -

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POOR QUAUTY PAGES 50-2ss thr== Mile Island I 50-320 three Mile Island II Dea r Hr. Hoslay 9

Acting as chairman of the Babcock and Wilcox (B&E) Users Group Subcommittee on Feeuw.tur F1pe Cracking. IE Lullatin 79-13, the purpoae of t:ais letter is to confirn arrangements for a meeting between -=hers of your staff and of the utilities utilizing reactors designed by Babcock and Wilcox (B&W) to dis-c us.r. the type and extent of examinations required to be performed under tha requirecents of IE Bulletin 79-13.

Participating utilitiam are Sacramento itunicipal Utility District, Arkansas Power and Light, 15etropo11taa Edison, Florida Power Corporation. Toledo Edison and Duke Power.

As you are aware, some pisnts of the Westinghouse design have enthited cracking in fittings uelded to the main feed.: ster nozzles on steam ponerators.

To data, in all plants inspected, only the nozzle -to fitting wclds have exhi-bited degradation due to cracking.

Cracking has been pocculated by plant personnel at Westinghotme facilities to be initiated by thereal stress, propagated by loading stress assistad by corrosion.

Thernal strasses have been of a low cycle, high stresa type.

Iuatrumentation installed at a number of Westinghouse facilities has shown that during plant 8tcrtups, facdeater transients and Auxiliary Fooduater pump testinc, largo tempe ra t ure gesdients exist across the nozzle to fitting wold.

Corros, ton haia becu evidenced t the Westinghouse facilities by pitting inside nozzles and fittings and by cracks filled with corrosion products.

Speel fic JJ f ferences in configuration and operations exist between B&W and ue. t i n ghous e plants seinich lead un to believe that this problean is not specific to n!.V fact 11 tics for the reasons listed halows soee*959A Q

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n Mr. Norman C. Mosley August 13, 1979 1)

B&W onco thru stoam Generatorn (OTsc) do not utilize nozzles for the attachsient of Main Foedwater piping to the vessel.

Main Feedwater enters the OTSC through a ring header attached to the OTSC by 32 riser pipes wiqh bolted connections (see Figure 1).

Auxiliary Feedvater piping is also conne eted t o the OTSC by means of an external ring header at tached to the OTSC with 7 risors with bolted connections at all plants emcept Rancho Seco. Davis Besse, and Oconee 3, where a welded nossla connection with an internal ring. header is used.

This design dif fers f rom the Westinghouse design where Main and Auxiliary,Feedwater enter the steam generator through a single weldod nozzle connection.

2) All B&W facilities utilize AYT che'mistry control and full flow demineralizers.

In cddition, all plants have recirculation Iceps wherein feedwater is cleaned up" to mininua requirements prior to feeding the OTSC during startup.

During startup transients, feedwater level within the OTSC is maintained constant and no intermittent feeding is utilized.

All Westin'ghouse facilit.ies initially utilized phosphate chemistry control.

Only recently have some of the facilities switched to AVT control.

Full flou domineralizers are an uncommon feature of Westinghouse plants as are feedwater recirculation loops.

3) A total of 95 welds ha s been examined at B&W facilities in liain -

and Auxiliary Feedwater piping.

A tabulation of these welds appears in Table 1.

Of the 95 welds inspected, only 5 contained reportabic indications.

Further, it is important to note that

'these reportable indications vers construction type fabrication defects and not cracks.

4) Augmented examinations of Main and Auxiliary Teedwater piping, risers and nozzles requested by NRC have been performed at Cryptal e

River Unit 3 and at Davis Besse.

These exandnations were ca rried out under NRC regional office direction and utilized radiographic l

inspection techniques.

No welds were found with cracks.

As a result of the facts outlined above, we propose the-ins pec t ion cut ! I na d below will provide compliance to, and meet the intent o f, IE pulletin 79-1 3 et R&W facilities:

1)

Volucietrie inspection of all Auxiliary Feedsster nozzle to piping welds at Davis Besse, Oconce 3 and Rancho Seco.

2) The addition of uit.rssonic testing as a " primary test."

A p ro-cedure with prnven ability to detect. cracks which are of concern and which has NRC staf f concurrence would be utilized.

It shoi1d be noted that nernal Section XI ultrasonic testing procc<turen utilized se o nur6*r of Westinr. house facilitites contirried radio-gra phic res ul t a and in some cases w w more than va: scen vich l

radiogra phy.

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Mr. Norwien C. Hoeley August 13, 1979 3)

Evaluation and disposition of ultrasonic testing results in accor-dance with Section XT of the AS!!E Code and evaluation and disposition C nal construction of radiographic resules in accordance with the ori i

code of the piping.

g Results of the nozzle to pipe weld examinations will be reported in accordance with Item 4 of IE Bulletin 79-13.

As a res ul t o f the IS I pe r fo rmed t o da t e a t B&W facil it f aa. atormented examinat ions performed at Crystal River Unit 3 and Davis Besse which found no indienttons of crccking problems, and 'the fact that no cracks have been seen at any hcr.inghouse fccility in welds other than nor.cle to fitting welds, no additionni eranination of Main and Auxiliary Teedwater piping other than that norruilly required by Section XI is deemed necessary or appropriate at any of the B&W facilitics.

Va understand this, meeting is to be held in Washington, D. C. on Friday. August 2L, 1979.

Va reques t that the authora of IE Dulletin 79-13, personnel who are rerponai blo for review of inspection results, and any other raembers of your sta f f you dece necessary, be present.

Please contact myself at Rancho Seco Nuclear GeneratJng

. Station (209) 748-2751 with any questions you may have.

Respectfully, c2 W. B. Ca rre t t Plant tkchanical Engineer Rancho Seco Nuclear Generating Station Chairman, B&W Us e rs Group Subcommittee on Feedwater Pipe Cracking. IE Bulletin 79-13 VBC:se Attachmenta est D. Raasch, Chairman, B&W Users Group, S!!UD S. W. Johnson, FPC C. T. Dafe, TECO H. White, AP&L J. Potte r, tie t. Ed.

J. D. Norton, Dtiko bcot R. J. Rodriguez J. V. McCollir,an D. C. Blachly Admin File

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SYS./ LOOP SIZE /SCitED.

iWELDS

1. EXty.S TYPES OF VELDS EXAHINED fREPORTAM,E/PIANT CODID;TS.

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TAIN 'A' 24" S/B0 4

4 9

PF 11 Rec OCO 1,2,3 20" 5/80 13 4

11 P-Pen (2)PF(7)FV(1)FF(llt 6 Rcc OCO 1.3 IB" S/80 3

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PF (2) PV (1) 4 Roc CR-3 l

14" S/80 11 10 1

PF 20 Rac OCO 1,2,3 &

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5/B0 8

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PF(4)FF(2)PN(1)PV(1) 3" S/80 9

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PF 7 Rae OCO 3 Report 20" S/80 11 2

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18" S/80 3

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PV(1) 12 Roc CR-3 cation 14" S/80 13

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PF(11) FF(2) 14 Rec,1 Rep OCO 2,3 defects 10" S/60 1

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S/80 2

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PV(1) 3 Rec OCO 1,3 3"

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PF(2) FF(1) 6 Rac CR-3 defects TOTALS:

95 72 27 116 Rac 6 Rap 99 P-PIPE FOTE: Total number of welds disagrees with T-FICING total numbcr of exams due to the fact V-VALVE that the P-Pen welds vers tested by R-N0ZILE both methods (R.S.).

j PEN-PC:ETRATION All reportable flaws are fabrication defects.

MEETING AGGENDA NRC/ B&W OWNERS GROUP FRIDAY-AUGUST 24, 1979 IhTRUDUCTIONS BACKGROUND i

. DISCUSSION OF B&W PLANTS

- Design differances between B&W and Westinghouse facilities j

Previous inspections

- Operation

' Chemistry control i

l PROPOSED PROGRAM DISCUSSION IMPLEMENTATION

SUMMARY

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ISI AND SUPPLEMENTAT. !!AIN AND AUX. FEEDWATER WEI.D EXAHS s.

• • . SYS./ LOOP SIZE /ScilED.

1. WELDS

1. EXAMS TYPF.S OF WEl.DS EXA!!INED

1. REPORTAhl.E/PI. ANT CO!'>'ENT

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11 P-Pen (2)PF(7)FV(1)FF(l) 6 Rec OCO 1,3 13" S/80 3

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14" S/80 11 10 1

PF 20 Rec OCO 1,2,3 &

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S/80 11 2

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PF(ll) FF(2) 14 Rec, 1 Rep OCO 2,3 de fects 10" -S/60 1

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6" S/SO 2

2 PF(1)

PV(1) 3 Rec OCO 1,3

& CR-3 3"

S/80 3

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PF(2)

FF(l) 8 Rec 3 Rep CR-3

'A' 6"

S/80 7

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PF(6)

P-Pen (1) 7 Roc OCO 1,2,3 6"

S/120 1

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PV 2 Rec OCO 3 3"

S/80 0

9 9

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'B' 6"

S/80 8

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PV(2) PF(5) PP(l) 12 Rec. 2 Rep CR-3 Reportab WWC 6"

S/120 1

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6" S/140 1

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3" S/80 3

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PF(2) FF(l) 6 Rec CR-3 de fec t s' catic

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4 TALS:

95 72 27 116 Rec 6 Rap 99 P-PIPE F-l'! TTING NOTE:

Total number of weldu u f ungreen with V-VALVE total nun.her of exams due to the fact that the P-Pen welds were touted by

-NOZZLE PEN-PENETRATION both methoda (R.S.).

All reportable flaws are fabrication defects.

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