ML19209B645

Operating Procedure 1103-5,Revision 11, Pressurizer Operation.

ML19209B645
Person / Time
Site:	Three Mile Island
Issue date:	06/28/1979
From:	METROPOLITAN EDISON CO.
To:
References
1103-5, NUDOCS 7910100269
Download: ML19209B645 (29)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION

j WASHINGTON, D. C. 20555

,/ August 31, 1979 Dockets Nos.: 50-269, 270, 287, 289, 302, 312, 313 & 346 FACILITIES: OCONEF. NUCLEAR STATION, UNITS NOS.1, 2 & 3 THREE MILE ISLAND, UNIT N0. 1 CRYSTAL RIVER, UNIT N0. 3 RANCHO SEC0 NUCLEAR GENERATING STATION ARKANSAS NUCLEAR ONE, UNIT NO. 1 DAVIS-BESSE NUCLEAR POWER STATION, UNIT N0. 1 LICENSEES. DUKE POWER COMPANY METROPOLITAN EDIS0N COMPANY FLORIDA POWER CORPORATION SACRAMENTO MUNICIPAL UTILITY DISTRICT ARKANSAS POWER & LIGHT COMPANY TOLED0 EDIS0N COMPANY

SUBJECT:

SUK'1ARY OF MEETING HELD ON AUGUST 24, 1979, TO DISCUSS AN ALTERNATE PROPOSAL TO THE REQUIREMENTS OF IE BULLETIN 79-13 FOR BABC0CK &

WILC0X (B&W) OPERATING PLANTS On August 24, 1979, a meeting was held in Bethesda, Maryland, during which a subcommittee of the B&W Owner's Group presented to the NRC staff an alternate proposal to the requirements of Inspection and Enforcement (IE) Bulletin 79-13.

A list of attendees is provided as Enclosure 1.

Background

As a result of the discovery of cracks in feedwater lines at various nuclear power facilities, the Office of IE issued IE Bulletin H-13 dated June 25, 1979, requiring volumetric examinations of feMwater lines for all pressurized water reactor facilities with an operating lice,'se. For B&W facilities, this bulletin requires examination of all welds inside of .Pitainmeno and upstream of the external ring head or vessel nozzels for each steam generator. Also, all welds c.* one inlet riser on each feed ring of each steam generator are required to be examined. The examinations are to be completed during the next extended outage of sufficient duration, or at the next refueling outage. The examinaHans are to be performed using radiographic testing cupplemented by ultrasonic te ng as necessary.

j ] j 'j Discussion The basis of discussion by the B&W Owner's Group was contained in a letter from W. B. Garrett to N. C. Mosley dated August 13, 1979, shown as Enclosure 2.

Copies of each viewgraph used in Mr. Garrett's presentation during the meeting 16 0

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August 24, 1979 are provided in Enclosure 3. The primary thrust of the presentation was the emphasis on the design differences of the B&W steam generator when compared to those of Westinghouse and Combustion Engineering. Except for the auxiliary feedwater line connections on three B&W plants (Rancho Seco, Davis-Besse, Oconee 3), all main feedwater and auxiliary feedwater lines are through an external ring header. Risers from the headers are bolted, not welded, to the steam generator. The auxiliary feedwater lines for the three mentioned plants are connected to the steam generator by welded nozzles. For this reason, it was proposed that the examinations for B&W plants be limited to the auxiliary feedwater lines on these three plants.

Much of the staff's questioning concerned operations of the steam generators, including startup and shutdown. It was stated that a large concern at this point is the temperature difference between the steam generator's shell and incoming candwater. The B&W Owner's Group response was that a large temperature difference does not occur under normal operation.

Conclusion The owner's group was advised that the information presented at the meeting would be correlated with incoming reports from non-B&W plants to determine if any relief could be granted to the requirements of IE Bulletin 79-13. The staff agreed to make available to the group information received by NRC relating to reports from non-B&W plants on the results of inspections. No commitments were made by the licensees.

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August 13, 1979 Hr. Norman C. Hasicy ( .

Nuc1 car Regulatory Commission I Division of Reactor Operations Inspc tions 4350 East West Highway Washington, D. C. 20555 Docket Kos.: '50-313' Arkansas Muclear 1 50-302/ Crystal River 3

'50-346- Davis Besse 50-269 Oconee 1 50-270 Oconee 2 50-287 Oconee 3

• 50-312' Rancho Seco-

'50-289' n rae Mile Island I

. 50-320 n ree Mile Ialud II Dear Mr. Hoslay Acting as chairman of the Babcock and Wilcox (BW) Users Group Subcoausittee on ruedw tu r Pi pe Cracking. IE tullatin 79-13, the purpou of 1:iis intter is to confiru arrangements for a meeting between =~hers of your staff and of the utilities utilizing reactora designed by Babcock and Milcox (BI.W) to dis-c us.r. t.h e type and axtent of examinationa required to be per formed ==A*r the requirecents of IE Bulletin 79-13. Participating utilities are Sacramento Municipal Utility District, Arkansas Pcuer and Light, Hetropolitan Edisce, Florida Power Corporacico, Toledo Edison and Duke Power.

As you are auare, some plants of the Westinghouse design have exhibited cracking in fittings uelded to the u.ain feed. tater nozzles on steam generators.

To date, in all plants inspected, only the nozzle -to fitting wclds have arhi-

.bited degradation due to cracking.

Cracking has been postulated by plant personnel at Westinghouse facilities to be initiated by therral stress, propagsted by loading stress ssaisted by corrosion. Therch21 stresses have been of a low cycle, high stress type.

Inc tru=entation installod at a number of Westinghouse facilitics has shown that during plant secrtups, feedsator transients mud Auxiliary Foodwater pump t est inn, la r r,o teu,peraturo gradients exist across the nozzle to fit ting vold.

coirosion has been evidenced t the Westinrhouse facilities by pit ting inside no r.r ie s and fittings and by cracks filled with corrosion products.

Speci fic diiferences in configurac' ion and operations exist between BW and W. t i n gho us e ; 1cnts chich lead un to belicvo that this probles is not specific to n!.V facilitics for the reasons listed below:

P00RORENM

)tr. Norman C. Hosley August 13, 1979

1) B&W Onco Thru Steam Ceneratorn (OTSG) do not utilize nozzles for the attachment of liain Toedwater piping to the vessel.

Hsin Feedvater enters the OISG through a ring header attached to the UTSC by 32 riser pipes vigh bolted connections (=ce Figure 1) . Auxiliary Feeduster piping is also connected to the OTSC by means of an external ring header at tached to the OTSG with 7 risors with bolted connections at all plants except Rancho Seco. Davis Besse, and Oconee 3, where a velded nozzle connection with an internal ring header is used. This design dif fers f rom the Westinghouse design where liain and Auxiliary,Teedwater enter the steam generator through a single welded nozzle connection.

2) All B&W facilities utilize AVI che'aistry control and full flow demineralizers. In addition. all plants have recirculation Iceps wherein feedvater is cleaned up" to minicnsa requirerients prior to feeding the OTSG during startup. During sta rtup transients, feedwater level within the OTSC is maintained constant and no inte rmit tent feeding is utilized. All Westinghouse f acilit.ies initially utilized phosphate chemistry control. Only recently have some of the facilities switched to AVT control. Full ficru domineralizers are an uncommon feature of Westinghouse plants as

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a re feedvater recirculation loops.

3) A total of 95 velds has been examined at B&W facilities in Itain -

and Auxiliary Feedwater piping. A tabulation of these welds appears in Table 1. Of the 95 velds inspected, only 5 contained reportabic indications. Further, it is important to note that these reportable indications were construction type fabrication defects and not cracks.

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

- Rive r Unit 3 and at Davis Besse. These exandnations were ca rried out under NRC regional office direction and utilized radiographic inspection techniques. No velds were found with cracks.

1. a a result of the facts outlined above, we propone the inspection cut 1 I ns 4 below will provide compliance to, and smeet the intent o f, IE Bulletin 79-13 at SAW facilities: .

1) Volueetric inspection of all Auxiliary Feedvater nozzle to pfping velds at Davis Besse. Oconce 3 and Rancho Seco.

2) The addition"of ultrasonic testing as a " primary test." A pro-cedure with proven ability to detect. cracks which are of concer n and which has NRC staf f concurrence vould be utilized. It should be noted that nernal Secticn XI ultrasonic testing p roc c <f u r e n utilized at a nurber of Westinr. hound (ne t lit i tes con t irrxd ra d i o--

graphic r es ul t s: and in sote cases ww more than va : scen vith

{

Mr. Norsman C. Hoeley August 13, 1979

3) Evaluation and disposition of ultrasonic testing results in accor-dance with Section XI of the A5!!E Code and evaluation and disposition of radiographic resulen in accordance with the original construction code of the piping, g Results of the nozzle to pipe veld examinations will be reported in accordance with Item 4 of IE Bulletin 79-13.

As a result of the Ist performed to date at B&W f acil itica. aurmented exantnntions performed at Crystal Rive r Unit 3 and Davis Besse which found no ind i c n t t onte of cracking problems, and 'the fact that no cracks have been seen at any Uce.ingfiouse f acility in welds other than nor.cle to fitting velds, no additional cransnation of Main and Auxiliary Feedvater piping other than that norrually required by Section XI is deessed necessary or appropriate at any of the B&W facilitics.

We understand this. meeting is to be held in Washington, D. C. on Friday. August 2 f. ,

1979. We request that the authorn of IE Bulletin 79-13, personnel who are responcf ble for review of inspection results, and any other members of your sta f f you deen necessary, be present. Please contact nryself at Rancho Seco T.uclear GeneratJng Station (209) 748-2751 with any questions you may have.

Respeetfully, C2 %

U. B. Carrett Plant ikcha* 21 Engineer Rancho Seco fiuclear Generating Station Chairman, B&W Users Group Subcornittee on Feedvater Pipe Cracking. IE Bulletin 79-13 WBC:se

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1 Attachmenta

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cat D. Raasch, Chairman, B&W Users Group, S!!UD S. W. Johnson, FPC ,

C. T. Daft, TECO H. White, AP&L J. Pot te r, !!e t . Ed.

J. D. Norton, Duke bes: R. J. Rodriguez J. V. McColligsh ^

D. C. Blachly ) ) } j.

Admin File .

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F.V. SYS./ LOOP SIZE /ScitED. NELDS # EXty.S TYPES OF VELDS EXAMINED fREPORTAN.E/PLAhT CCDIENTS' t RT ' trr (/J 1 FotND *.Y KT)  !

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}RIN ' A' 24" S/B0 4 4 9 PF 11 Rec 000 1,2,3 20" 5/B0 13 4 11 P-Pen (2)PF(7)FV(1)FF(1) 6 Rcc OCO 1,3 10" S/60 3 3 9 PF (2) PV (1) 4 Roc CR-3 14" S/80 11 10 1 PF 20 Rac OCO 1,2,3 10" 5/80 9 9 9 CR-3 6.75" .Rowall 1 9 1 PF 6" S/80 8 8 9 PF(4)FF(2)PH(1)FV(1) 3" S/80 9 9 9 MAIK 'B' 24" S/80 1 1 9 PF 7 Rac OCO 3 Reportabli 20" S/80 11 2 11 P-Pen (2)PF(7) FV(1)FF(1) wre fabr-18" S/80 3 3 $ PF(2) PV(1) 12 Roc CR-3 cation 14" S/80 13 ,11 2 PF(11) FF(2) 14 Rec, 1 Rep OCO 2,3 defects 10" S/60 1 1 9 i

& CR-3 6" S/80 2 2 9 PF(1) PV(1) 3 Rec OCO 1,3 3" S/80 3 3 9 PF(2) FF(l) 8 Rec, 3 Rep CR-3 .

AUX ' A' 6" S/80 7 6 1 PF(6) P-Pen (1) 7 Roc OCO 1,2,3 6" S/120 1 1 9 PV 2 Rec OCO '3 3" S/80 9 9 9 AUX 'B' 6" S/80 8' 8 9 PV(2) PF(5) PP(l) 12 Rec 2 Rep 3 Reportabl 6" S/120 1 1 9 PF 4 Rke OCO 2 were fabr 6" S/140 1 1 9 PF cation

_ 3" S/80 3 3 9 PF(2) TF(1) 6 Rac CR-3 defects

';". TOTA 1,S: 95 72 27 116 Rsc 6 Rap 99 C P-PIPE NOTE: Total numbor of wei6s disagrees with F-Fl*CING total number of exams due to the fact that the P-Pen welds were tacted by V-VALVE T-N0ZZLE I u%

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f both methods (R.S.) .

PEN-PC:ETRATION All reportable flaws are fabrication defacts.

Enclosure 3 MEETING AGGENDA NRC/ B&W OWNERS GROUP Fh. DAY- AUGUST 24, 1979 IhTRUDUCTIONS BACKGROUND DISCUSSION OF B&W PLANTS

- Design differances between B&W and Westinghouse facilities

- Previous inspections

- Operation

- Chemistry control PROPOSED PROGRAM DISCUSSION U1PLI TATION SUWARY

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,g PRIMARY INLET N0ZZLE

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PRIM ARY SIDE CL ADDING VENT B LEVEL SENSING 1 PRIMARY SIDE M ANWAY CONNECTION s ,

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BAFFLE c l 1 P SECONDARY SIDE HANDHOLES UPPER HIGH LEVEL SENSING % '

DRAIN CONNECTIONS

, CONNECTION FEEDWATER HEADER S INLET CONNECTIONS dfFEEDWATER HE ADER SUPPORTS

, I fy j g,,,,, LOWER CYLINDRICAL VERTICAL TEMPERATURE SENSING /fh_ ,

l k BAFFLE CONNECTION i h TUBE SUPPORT PLATES TYP.

a sQf r LOWER HIGH LEVEL SENSING L' l /~U' CONNECTION I i  !

FEED'n' ATE HEATING CHAMBE l ,

ALIGNMENT PINS UPPER LOW LEVEL SENSING L a i

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r TYP THERMOCOUPLE WELD PAD WATER PORTS I DRAIN CONNECTION ORIFICE PLATE tN l _ V SECONDARY S10E HANDHOLES 'O w S SECONDARY SIDE MANWAY

• f TEMPERATURE SENSING CONNECTION LOWER LOYi LEVEL SENSING'.p.- T ORAIN CONNECTIONS CONNECTION i l l-LOWER TUBE SHEET N PRIMARY SIDE CLADDING

) yPRIMARY SIDE MANVIAY PRIMARY OUTLET N0ZZLE

-PRIMARY SIDE INSPECTION OPENING SUPPORT SKIRT M 3 gN ORAIN CONNECTION l

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ISI AND SUPPLEMENTA1,11AIN AND AUX. FEEDWATER WEI.D EXAMS

• !. SYS./ LOOP S T 7.E/S CllED. JUELDS # EXAMS TYPF.S OF WELDS EXA!!1NED #REPORTAHl.E/Pl. ANT C0!' MENT'

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N 'A' 24" S/80 4 4 0 PP 20" S/80 13 4 11 Rec OCO 1,2,3 11 P-Pen (2)PF(7) FV(1)FF(l) 6 Rec IS" S/80 3 OCO 1,3 3 0 PF (2) PV (1) 14" S/80 11 4 Rec CR-3 10 1 PF 10" S/80 20 Rec OCO 1,2,3 &

0 0 0 6.75" .80 wall 1 CR-3 0 1 PF 6" S/MO 8 8 0 3" S/SO PF(4) FF(2) P:!(1)PV(1)

O O O IN 'B' 24" S/80 1 1 0 PF 20" S/80 7 Rec OCO 3 Repcrtab' 11 2 11 18" S/B0 P-Pen (2) PF(7)FV(1)FF(l) wers fab' 3 3 0 PF(2) PV(1) 14" S/30 12 Rec .CR-3 cation 13 11 2 PF(31) FF(2) 10" S/60 14 Rec, 1 Rep OCO 2,3 defects 1 !l 0 6 CR-3 6" S/80 2 PF(1) 3"

. O PV(1) 3 Rec OCO 1,3 S/80 3 3 0 PF(2) FF(l) 8 Rec 3 Rep CR-3

< 'A' 6" S/80 7 6 1 PF(6) 6" S/120 P-Pen (1) 7 Rcc OCO 1,2,3 1 1 0 PV 3" S/80 2 Rec OCO 3 0 0 0 X 'B' 6" S/80 8 8 6to TT 0 PV(2) PF(5) PP(l) 6" S/120 1 12 Rec. 2 Rep CR-3 Reportah 1 0 PF 4 Rec 6" S/140 , OCO 2 were fab 1 1 0 PF 3" S/SO 3 3 ca: ion 0 PF(2) FF(l) 6 Rec CR-3 defects TALS:

95 72 27 116 Rec 6 Rep 99 P-PIPE

__. F-FITTING NOTE: Total numhcr of wa:Idu disagrees with

__m V-VALVE total nun.ber of exams due to the fact L4 N-NOZZLE that the P-Pen welds were tested by PEN-PCNETRATION y

IQ Jga both methodn (R.S.).

{ All reportable flaws are fabrication defects.

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S-v &

w%.

MEETING St#ittARY DISTRIBUTION ORB #4 cc: Mr. William 0. Parker, Jr. - Duke Power Company Mr. R. C. Arnold - Metropolitan Edison Company .

Mr. W. P. Stewart - Florida Power Corporation Mr. J. J. Mattimoe - Sacramento Municipal Utility District Mr. William Cavanaugh, III - Arkansas Power & Light Company Mr. Lowell E. Roe - Toledo Edison Company Daket File R. Reid NRL PDR V. Noonan L PDR P. Check ORB #4 Rdg G. Lainas NRR Rdg G. Knighton H. Denton Project Manager E. G. Case OELD OI&E (3)

D. Eisenhut R. Ingram R. Vollmer R. Fraley, ACRS (16)

W. Russell Program Support Branch B. Grimes TERA T. J. Carter J. R. Buchanan A. Schwencer Meeting Summary File D. Ziemann NRC Participants T. Ippolito EJordan W. Gamill BCrowley, IE, Reg. 3 L. Shao WHazelton J. R. Miller '

RHermann TLiu CSellers

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