ML20210T243

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Partially Withheld Memo Forwarding Potentially Generic Issue Data Sheet Re Steam Leaks in Main Steam Bypass Lines Due to Fatigue Failure.Diagrams & Deviation/Event Rept Also Encl
ML20210T243
Person / Time
Site: Grand Gulf, 05000000
Issue date: 10/19/1984
From: Robert Lewis
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Bishop T, Denise R, Partlow J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20210T193 List:
References
FOIA-87-50 NUDOCS 8702180125
Download: ML20210T243 (7)
v • d • e


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MB RANDUM FOR:

James G. Partlow, Deputy Director, Division of Quality Ur 4 g/.

Assurance, Safeguards and Inspection Programs, IE Richard W. 5tarostecki, Director, Division of Reactor ere. pct f u 2 I'?MI17,,

u- Director, Division of Reactor Projects, RIII -

Richard P. Denise, Director Projects, RIV '

Division of Reactor safety and Thomas W. Bishop Director, Division of Reactor Safety and Projects, RV '

FRC :

Richard C. Lewis, Director, Division of Reactor Projects SUE ECT:

PDTENTIALLY GENERIC PROBLEM AT GRAND GULF REGARDING THE MAIN STEAM BYPASS LINES.

l mat The enclosed potentially generic issue data sheet concerning s' team leaks in TI steam 5D0/3. bypass lines due to fatique failure is forwarded for information per i

hichard C Lewis q

Enc >sures: -

1. Potentially Generic Issue Data Sheet No. RII:DRP:84-16
2. Supporting Dats
3. System / Hardware Diagrams a

cc s ' enc 1:

  • C. . Heltenes, Jr. , AEDD R. I Bangart, RIV 6

I CON' ,CT:

  • l R. I Carroll Jr. -

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] ENCLOSURE 1 i

Dg Sheet No.:RII:DRP-84-16 -

Appendix A 1

TI 2500/3 4/1/80

, p0TENTIALLY GENERIC ISSUE DATA $NEET Fa liity Grand Gulf Docket No(s). 50-416 Da e of Event 9/16/84 and 9/23/84 Inspection or other Report F0-416/84-38 ' -

1. Brief Description of Issue (Not risquired if included in supporting data)

See Enclosure 2

2. How Found (If appropriate) -

Discovery of steam leaks in the turbine building ,

3. Why considered Potentially Gener1c (i.e. - reference applicable criteria or give reason) ~

These fatique failure induced torpass line steam leaks, have occurred at Grand Gulf and at a Bayernwerk facility (Grafenrhienfeld-KKG) in Germany.

Like Grand Gulf, who's turbine generator and associated hypass hardware were supplied by Allis-Chalmers, it is possible t. hat other nuclear power plants have a similar three line main steam bypass design. V

4. II R.I. Carroll P. R. Beets /D. N. Verre111 Region OrEginator . Section Chief / Branch Chief l
5. Dther Reeton Reportine That The Probles Has Also Been Identified By Them Region , , Chief _ , Reporting . Docket No.

l 6. Evaluat*:on by IE:HO Bu11ettei L/ Circular. / / Information Notice /_,/

Other No further action required /_/

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OCT 121984 ENQt.05URE. 2 5_! eortine Jata G: .nd Gulf unit 1, has empertenced two separate steam leaks in the "A" main steam b) : ass line (a non-safety related syn,5en) while tqypassing steam at the 155 to 2C%

pr 'er level. The first event (g/16) was due to e crack induced failure of the wi d which connected a 24-inch capped pipe stub to the "A" hypass line's pressure

b. ahdoun assembly (pBA); (See Enclosure 3). The failure of this weld was .

es .rlbuted to earlier vibration of a . drain line that was connected to the pipe p .b. (The drain line on all three bypass lines' PBAs had been removed earlier in the plant's life when preoperational testing shoued they were not required.)

Ti PBA. including a 1-foot section of 18-inch diameter P3 pipe and a 2%-inch d noter drain nozzle upstream, as well as a short section of 24-inch P1 pipe l

di nstream, was furnished by Utility power Corporation. Inc. (previously known as A' is-Chalmers). The PBA was manufactured in Germany using German steals., i Rt overy action included replacing the damaged PBA and a portion of tho' 18-inch st .edule 40 pipe located betueen the PBA and the "A" stop/yA"PBAaswell ss valve.

U'. .rasonic and magnetic particle testing w"as perfomed on the new 0: on the existing ones in the "B" and C bypass lines.

Tl 9/23 occurrence resulted from a 7-inch crack, propagating in both directions l'

ft m the new repair weld connecting the existing 18-inch pipe to that portion of It inch pipe that was replaced during the 9/16 recovery period. Off-stte anal-y: s confimed that both the 9/16 and 9/23 events were due to fatique failure; welding deficiencies. The 9/23 event has been attributed to pulsating / Y

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nt rr onste vibration in the 18-inch schedule 40. pipe when steam flow was passing tt ough the line. It is also believed that this resonate vibration was the ur '.orlying cause of the 9/16 event.  ;

5t . sequent modifications to all three hypass lines included replacing the 18-inch st .edule 40 piping with schedule 100 : piping. (That portion of the PBAs con-ta ning the Zh-inch capped pipe stub was also eliminated.) The two welds in each

b3 . ass line which connects the 18-inch schedule 100 piping to the stop/ bypass vi ve and the remaining portion of the, PBA were stress relieved a'nd radiograph-it 11y tested. These modifications were based on those made at a Bayernwerk l

' fa ility (Grafenrhienfeld-KKG) in Gemany, which experienced two similar occur-

r4 ces in 1979. No further problems have been encountered there since these m( .ifications were made. ,

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 - Edison                            Deviation / Event Report                                  Nembe, wss-,oi               ,a,. t et pg
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Part 1 - 4 Identification and Description A. Title 30" By Pass Line Field Weld 25 & 26 

    . Occurrence Date                  Time                          C. Safety Related      D. 5ystem              f. PIS t1_?_Rt                      1                                 0 y,s B No y 13 in l-li 17 el 31 il a d d a a d A F. Description of occurrence or condition Nuclear Operations Welding Manual Sect. VII states that if a split backinn is to be used the split shall not exceed 3/32" contrary to this the split in backing for field weld 25 & 26 is approx 1/2" also during the welding of this field weld it was noted that weld layers were 7/8" to 1" wide, the max that can be carried is 5 times the diameter of electrod. 1/8" diameter electrodswere being used.

G. Im mediate action 

                      . /

Ff W H. References L init ~ t r Org./Section Date e Nuclear Operations Weldinz Manual / ve/In M M/7//Arar I //~h Yf Part 2 , Repoltability A. 10CFR50 72 O ves E No Person Contacted n t Hr O 4 Hr. Date Time 10CFR$0 73 n Yes IX No LE R Number 10CFR21 O Yes [M No LE R Due Date

8. Detconined ByM ( M~

orarsec C atfL b A/o Cate f 8 9 7 Part 3 l:  : l CARB Review l. A. Accept description of occurrence and immediate action (X Yes M No Accept reportability determination M Yes M No 

    . 0$RO meeting required           n Yes IMNo                           Meetinq No      A) A                              Date D. Evaluation and Action t ssignment :                                 F. Carb.N P Only                    M RadChe n M NQA         R NT           C NA            O NOM                  n Maintenance                   M Technical f5L NE        D N5           M NP            M MNPM                 M Operations                    M Other E-aluator                                Section                       Evaluator      ,                     Section E. Evaluation due date                                                 G. AR8 App ital
  • Date
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Evaluatfon l l A. Describe the root cause of the devsstion PE R. WNCf . DER FDtJ% Ally 'Td[ FJ T-t)b 19A/d 11 I6LOlhh

Dln A/D T FCLL6h) 774E /ALSTJtLJd YsCN S BN ~7 d~ G /dELb PROCESS C n N T R n L_ S//EtT ffAP( 6 )
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IN.A T>LO LT)ch A NN AN3 7 RC Jh ~rntNhnifi) ' l Determined By heum/[ Ora /Section Mvl th [wfHA/1 F>t/M/# Date /J-/3* A8

8. Remarks [

\ (If reauired, attach a Corrective Action Sheet) Part 5 l Work Completion 7~"  ! C. Approved By

  • Org / Section Date I

Part 6 l- NQA. Cornpletion Review tviewed By Section Da'e I l l

  • Send To CAC DE 961-663108-85X l

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O l Of 963 66331184C5 l Detroit

Edison Corrective Action Sheet Dr R ue Paca c8 l

Part 4 l Evaluation l Part 5 l l Completion l- l C. Proposed Remedial Corrective Action: 1. 05RO meeting A. Remedial Action Taken: _1st R w. m n n .sr_ rne D ves t% no 

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h Date/JdM C. Approved by Date E PicposedCorr/sve Actionto Prevent 1 dSRO meeting O Action Tab en to Prewent Recurrente' Recurrence: "Jg" r f~p ,tt,f,w _ O yes D no idftbE*f_ '. AA/A 7~s r 7 s E 6 2 Prior to declaring operable 

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