Text

Rept on Design & Stress Evaluation of Failed Main Steam Safety Valve Nozzle
	ML20086B573
Person / Time
Site:	Robinson
Issue date:	05/23/1970
From:	Foley W, Lofy R; PARAMETER, INC.
To:	; US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19289B536	List: ML20086B507; ML20086B516; ML20086B524; ML20086B528; ML20086B568; ML20086B573; ML20086B591;
References
	DC-67, NUDOCS 8311180051
	Download: ML20086B573 (46)
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3, Report on Design and Stress Evaluation of Failed Main Steam Safoty Valve Nozzle H. B. Robinson No. 2 Carolina Power and Light Co.

Report No. DC-67 May 23, 1970 e) 7' Prepared for:

U.S. Atomic Energy Commission

" * "#4 Division of Compliance AEC Contract AT(11-1)-165,8 f

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Copies:

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,. y AEC Reculatory Oroanization Division of Comoliance Technical Programs - Washington (2)

L. Kornblith, Jr., H. R. Denton Region-II, Atlanta (8)

W. C. Seidle, U. Potapovs AEC Contracts Division _

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.s Chicago Operation Offico (1)

H. N. Miller, E. Halman Parameter, Inc._

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Page 3 of Pg Table of_ Contents:

Pace:

-s I.

Introduction and Scope of Inspection II.

Summary of Findings III.

Discussion of Inspection Items IV. References V.

Appendix Exhibit-A Stresses for Safety Valve Nozzle As Presented by Ebasco, at 5/1S/70 Mooting Exhibit-B Schematic Arrangement of Main Steam Line Safety Valves as Presented by Westinghouse at 5/15/70 Mooting Attachment No. 1:

Sketch No. 1, General Arrangement -

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Safety Valve Nozzle, 26" Main Steam Line Attachment No. 2:

Sketch No. 2, Safety Valve Nozzle Fabrication Detail Attachment No. 3:

Sketch No. 3, General -Contour of Failure, Safoty Valve Nozzle

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Page 4 of p@g I.

Introduction and Scope of Inspection

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At the request of the Division of Compliance (Mr.

W. C. Seidic, Senior Reactor Inspector Region II and Mr. D. L. Pomeroy, Technical Support Branch, CO-Hg),

2 the writer attended a mooting held at Ebasco Services, Inc. officos in Now York on May 15 to review the i

recent failure of a safety valve in the main stream line of the H. B. Robinson No. 2 plant at Hartsvillo, S. C.

The writor accompanied Mr. W. C. Seidle, Senior 4

Reactor Inspector and Mr. U. Potapovs, Metallurgical j !,

Engineer, both of the Region II officos at Atlanta representing the AEC in this review.

ll The Robinson-2 plant is a 663 MW(c) Pressurized Water j l Reactor (PWR) generating station being built for j

Carolina Power and Light Co. under a turnkey contract l

by Westinghouse Electric Co.

Ebasco Services, Ir.c.

i is Designor and Constructor.

) !

he failure of the safety valve nozzle has been assumed.

i to be metallurgical and/or stress related and investi-($}

gations have boon pursued in those areas by Westing-house and Ebasco respectively.

A previous meeting (not attended by the writer) had been held at Westing-house Pittsburgh and was concerned with preliminary metallurgical findings and planned investigative effort. The prime purpose of this meeting was to il review further information on the metallurgical results and to obtain the results of Ebasco's design-analysis.

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Mr. Potapovs is expected to report all metallurgical aspects of the failure.

In this report, the author will document the meeting presentation related.to design and summarize Parameter's evaluation.of the

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safety valve connection in terms of-stress levels presumed to occur at time of failure.. In this later respect,-the basis'will be an independent estimate of~

stresses prepared by our Mr. W. J. Foley which is -

i appended as Attachment 4 1

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Introduction and Scope of Inspection - Continued

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Note:

Preparation of an independent ovaluation of strcosco in general para =ctric terms was agreed upon with Mt. Scidic after tho analysis cu= mary procented by Ebacco during the aceting was not complete or conclusive.

The Paramotor analysis would include the offects of pressure and thermal discontinuitics, and the possible superposed moment due to the safety valve discharging.

Other agenda items of the ccoting include a general review of the incident, a discussion of the status of the review of the romainder of plant piping, the status of a "dosign fi=", and the status of the investigation of the plant transient (primary system) due to the incident.

Theco items are not considered within the scope of this report except to make some comments as to the critoria for a satisfactory fix.

l The following personnc1 participated in the mooting

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hold on May 15, 1970 at Ebasco Services, Inc.,

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2 Rector Street, N.Y. N.Y. :

(Titics or function may be approximate.)

l Carolina Power and Licht Co.:

H.' Banks, Resident Engineer Westinchouse Electric Co.:

T. Erion, Project Manager, Robinson 2 R. Cunningham, Research - Pittsburgh Ebasco Services, Inc.:

J. Scarolla, Projects Manager (part time)

R. Pulito, Project Manager, Robinson-2 A. Rossi, Staff O

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Introductions and Scope of Inspection - Continued p

1 Ebasco Services Inc.:

continued C

B. Ma=o, Mota11urgist L. Labriola, Supervisor Stress Analysis S. Boone, Stross Analyst U.S. Atomic Enercy Commission. Division of Conolianco:

W. C. Seidle, Senior Reactor Inspector -

Region II, Atlanta U. Potapovo, Metallurgical Engincor -

Region II, Atlanta 3

R. A. Lofy, Consulting Engineer -

Paramotor, Inc., Elm Grovo, Wis.

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The writer's comments on the description and various

', 4 details of the failure incident are included with the narrativo report of the mooting in Scotion-III, Discussion of Inspection Items. Significant conclu-sions are reported in the S" mary of Findings, Scction-II following.

(Note:

All notes mado,, computer printouts and calculations performed in connection with this assignment are maintained on filo by PARAIGTER a

and availabic for futuro reference as required.)

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1 Page 7 of II Summary of Findinos:

1.

The cafety valvo no==lo was not analy:cd for tho load imposed by the jot reaction of the steam during dicchargo of the valvo. Tho strccsos duo to thic reaction can be expceted to comprico a largo fraction of the total maximum stress occuring when tho valvo "popt'!.

If the valvo popped, the resulting co=ont-reactiorcaction coupled with pressuro end load and struct-ural discontinuity stresses, can be considered a major contributor to the failuro.

If the valvo did not pop, it is not possible to explain the overload failuro in terms of pressurof weight, wind load and structural pressure discont-inuity stroscos.

Baccd on estimated temperaturo gradiento, thermal discontinuity ctressos across the failed arca turned out to be nominal.

Please refer to Attachment #4 for a summary of stroscos calculated in the trail analysis performed by Paramotor, Inc., and conclusions regarding tho probable stress related basis for the failure.

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It has boon dotormined that an axial tensile stress on the order of 60,000 psi can exist in the nozzlo q,

wall under the stcan discharging condicion.

(Calculation of this otreco requitied making como accumptions regarding the reaction forces as described in Attachment #4.)

This approximato stress 1cvol, without a stress concentration factor is sufficiently high to be

.y a prime contributory cause of failure without

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major nota 11urgical defects being present.

The Mill Test proporties of the material have been quoted at 48,500 psi Yiold and 75,700 psi U14:imato.

Specification minimums for this material aro 35,000 psi and 60,000 psi rgspectively.

The margin in material strength available and the uncertain-tics of assumptions cado in the trial analysic do -

not precludo the possibility that a minor metallur -

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gical defect could have boon a contributory factor -

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assuming the steam discharge modo.

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Summary of_Findinos:

contintted

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Although the Powor Piping Codo (B31.1.0-1967 accu =od to apply) does not appear to treat safoty valvo dis-charge forces directly, it is the opinion of tho writers that omission of this forco in. establishing the design is a violation of the conoral critoria of this code.

(Para.101.5 covers " Dynamic Effects" and para 101.5.1 " Impact" specifically in stating that-

" Impact forces caused by all external and int-4 j

ornal conditions shall be considered in tho piping design."

The valvo dischargo would ecst cortainly be considos-ed a dynamic offect and can be classified as an impact force.

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III.

Diccuccion of Inspection Items

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In introducing the nocting attendecc to the back-cround and circumstancco under which the etcan lino cafety valve failed, Mr. T. Erion of Wootinghouco ~

precented a brief deceription of the plant arrange-cent and tcots in progreco at the t=o of failuro.

s "y Each of the thrco nain stcan lince A, B and C (or 1, 2 and 3) from the Nuc1 car Stcan Supply System (NSSS) contain one power operated bicu-off valvo and four (4) cpring loaded cafety valvos cet to rolicvo at 1075,1105,1125 and 1140 pcig rccpectively. Thoco valvoc are located outcido of the containment and upstream from the main otcan icolation valvoc,which ;

woro cloced, and check valvoc.

Exhibit-B chows tho l

relativo position of theco valvcc cchematically as i

procented to the group on the blackboard.

The failed nocelo was accociated with the highcot cotting cafoty, valvo (1140 poig) located in lino C(1) as indicated on Exhibit-B. The cafoty valvo was idcntificd as a Crocby Style No. !!CU-65W (Ref.1). Two cizco aro

('9 used in the cyctem, 6" (inlot) by 10" (outlot) and.

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, r 6" x 0".

The failed valve was believed to be a 6" x B" ac stated by Mr. Erion.

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(Noto:

Inquiry Mc=oranda (References 1 and 2) 7*

woro mado available to tho writor prior to tho nocting and contain portinent data regarding test conditions (proccuros and temperaturoc) before and after tho incident, and records of

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l prior inspections.)

The Robincon plant was in the last stagcc of hot functional touts at the timo of the incident.

Mr. Erion explained that tho valvo testing was left 1

as one of the last ite=c in their toct program.

Crosby personnel had boon called in for the testo to' mako any adjustments to valvo sottings that might be required. They had comploted tecto on steam linco

,4 A(1) and B(2) and woro working on C(3) at the time.

of the failure.

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III.

Discussion of Inspection Itons:

continued k./

The tcot proceduro was doccribed approximately no follows:

With cteam prcocuro below the valvo dic-chargo setting (cay 900 poig) a pneumatically operated lift devico is attached to the valvo and y

enough precouro applied to cimulate the differential between the actual cteam proccuro and the blow-off proccure. The proccure to the lift device was applied by means of a nitrocon bottle and regulator. The o' object is to add just enough precouro to got the valvo to "cimmer" or leak cteam. This is the calibration

point, flowever, it is chhracteristic of the valvo to " pop" wide open then only clightly higher than l

"cic=or" proccuro is reached.

Ac an examplo of tho delicato balanco, betwcon "cic=oring" and " popping",

of the eight (8) valves previously tected by experi-cnced Crosby perconnel in thic corics, three (3) cic=ored only, but fivo (5) popped.

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The writor asked how long the system was at olevated temperaturo and prescuro prior to the failure.

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Mr. Erion rcplied that tho hot functional tests had l

been in progrocs with tho steam linco heated for nino (g) days.

This etcady ctato condition precludos the need to J'

considor temperaturo and pressure transients in our evaluation of the failure.

!!owever, steady ctato conditions do not imply that uniform temperatures exist in tho area of the valve to header connection because of the termination of the insulation and change in sections and curface i

areas at this point.

Mr. Erion went on to explain how, immediately after the incidont, an investigation team was set up to conduct the:

1)

Design review,

_f 2)

Mota11urgical investigation, and 3) To evaluate offects of the transient on the r

g primary system.

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Discuccion of Inspection Items:

continued Tho writer acked whether an cctinato of the tc=pora-ture of the valve was availablo. Ebacco porconnel indicated that one could put his hand on the valvo in the upper arca, but they had no data on the overall tc=poraturo.profilo or the cpecific to=peratures in tho transition arca adjacent to the noccio.

It was pointed out that actual in-ccrvico curface tempora-tures of thoco valvcc would be relatively cacy to obtain by "Tempil" ctick or thermocouple.

Valvo body temperaturo could be an inportant consideration in analycio of the failuro area.

For our trial analycio of Attach =cnt #4, wo have cotinated a nunbar of temperaturo profiles to octablich a trend of thor =al strcco vercun tc=poraturo gradient and to dotormino its significanco.

The main steam header was doccribed as being lagged with canned Uniboctos type inculation.

Study of (th photon of the installation chowed the insulation as terminating near the top of the taper at the lower s

cnd of the valvo body.

The fabrication design of tho valve to heador joint was doccribed by a layout dic-played during the necting.

On the bacio of notco and chotches mado during tho =coting, thic design has been drawn apprc::imately ac dicpinyed in our Skotch-2, Attach =cnt-2 The wcicht of the valve was given as 950 lb. without the stack and 1300 lb. with the stack.

Its general arrangement with rocpect to the stcas line in chown on Sketch-1, Attachment-1 There in no external

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cupport to oither the valvo body or the olbow-stack accc=bly.

Tho heador and valvo acccmbly was hydro-tested at 1356 poi during a 4b hour proscurization cycle according to Mr. R. Pulito of Ebasco..This particular

't valvo did not weep during hydro.

(Valve presumably blocked shut at test pressuro.)

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continued (While this report in primarily concerned with the design revicw aspects of the failure, diccuccion of the transient will be reported and obccrvations made to the degrco that the writer participated in thic discussion.)

In discussion of the progrecc of tho test of the valvo in cucation, it was cctablished that the pncu=atic lift device was being used and they woro ctarting to go up in proscuro.

It was the reported opinion of test crew mc=bero that the valvo did not " pop".

!!owcycr, thoro cocco to be conflicting opinion in thic rocpect. Obocrverc report hearing two distinct counds - one could be the valvo popping, the cccond could be the cocape of etcan upon rupture of the noccio.

On the other hand, the first cound could have been accociated with the break in the noccio l

followed by the dicchargo report of cteam.

It was -

l ctated by Mr. Cunningham of Woctinghouco that examia nation of the valvo showed groaco in the arca of tho

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valvo cton and paint in the exhaust ccction which did.

t not appear to havo bocn cerubbed away by exhausting e

steam. (This valvo was reported not to havo cin=ored during previous tests.)

Thuc the fooling that tho valve did not pop.

Mr. Cunningham did point out however, that the crease was not in the direct patn of the stcan and the concral appearanco was not a great deal unlike that of other valvoc which had popped.

3 It is the writer's opinion that, at best, this cvidence as procented is inconclusivo.

If tho

'valvo popped and failed soon afterwards, it would not have experienced a great deal of steam flow.

If conclusions aro nado on the basis of those indications in the future, they should bo developed from a moro thorough ctudy of tho history of operation of thio valvo and comparicon with other valves of known ucago, and confir=cd poccibly with tects under controlled conditions.

Whether or not the valvo popped is of courco an important concideration in analycic of the cause of failure, particularly if predominantly stress I\\

related. Conclusions as to this probability can be drawn from the trial analysis presented in s

Attachment No. 4

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Discussion of Inspection Items:

continued The header and transition picco (no==1o) woro designed by Ebasco Servicca and fabricated by B. F. Shaw Co.

The no: lo was cado from A105 Gr. B Schedulo 80 scamicas pipe. Tho wold between the valvo body and the nozzlo in the reduccd section (Schedulo #40) was made with the aid of a backing ring Icft in place.

This wold was made by field personnel under Ebacco's construction contract.

The field wold was not stress relieved.

Note:

While Ref. 1 reports stress relieving in accordanco with code requirc=ents, this scetion, being under 3/4" wall thickness, would not requiro stress relief.

It is difficult to predict the magnitudo of residual stresses due to welding in a caso liko this. An observation can to mado however that tho hoop restraint or pinching offect of the residual stresses in the wold tends to add to

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the pressuro and thermal discontinuity strccces aircady procent at scvoro changes in scotion in the failure area.

The backing ring, which is assumed fused to the wold providca even further restraint under pressuro and temperature.

Mr. Cunningham of Westinghouco went on to report tho' results of their metallurgical investigation to dato.

Ito explained that h'o had been enlled in from the Westinghouco Roccarch organization to work with the project group as a noro or icos independent consultant..

The charactor of the failure was described by Mr. Cunningham at the board essentially as reconstruc-tcd on our Sketch-3, Attachment-3.

From a design-analysis point of view, it cuffices to say that ho described the failure as a typically tensile break, and reported that no abnormalitics woro yet found in the physical proporties of the material.

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III. Discussion of Inspcction Items:

continued 9

They believe that a crack ctarted from the insida (not confirmed) at initiation of failuro from the west cdge which progressed symetrically about the E-W 3

center line to the cast cdoc.

(Sec Attachment-3).

The inner edge of the break followed the transition line between the Schedulo #40 diamotor and the tapered section, and thus thoro was no opportunity to cStablish the tool radius of this corner.

However, Westinghouse plans to concuro a tool radius for tho-1 adjacent machined surfaces which might be an indica-tor to that vthich existed at the transition line.

Some necking-down of the failed section was observed.

Westinghouse reported that single wall radiographs showed no rejectablo defcets.

Meta 11ographic examina-tion showed only como normal longitudinal stringcro in the pipe.

7 The preliminary conclusion by Westinghouse is that there are no materials prob 1 cms and that an overload

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type of failure is indicated. The final metalluroi-cal report was expected to be issued within a few weeks of the mcoting dato.

Qucations and answers during the discussion of the failure revealed a consensus that the nozzles cr transition pieces were machined as detail parts in a lathe (vs. boring after assembly to the header) and that the Schedulo #40 counter-boro and transition taper were made in the enmo setup.

If this is the caso, as would be expected, wo should not find any offcot or cecontricity betwoon the counterbore and taper which could act.

as an additional strcos condentration factor and discontinuity.

It was asked whether other noz=les could be inspected to verify this fact.

Mr. Banhs (C. P. & L.) said it was not.possible to view this area adequately with the valves wolded in placc. However, it.does coom possible to the writor that some in-situ inspection could be performed by removing the valvo' mochanisms and viewing with a boroscopo or similar device.

If it is decided to leave the other valves in placo, (S)

. such an inspection to reveal any incipient flawr 4

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might be well warranted.

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Discussion of Inspection Items:

continued During the afternoon coscion, Ebaccc stroco analycis perconnel procented the results of their design-analysis as recorded on Exhibit-A attached. Tho strocccc ac dicplayed initially on the board by it. S. Boonc arc chown in the original columns.

Revisions to theco numbers,ac cvolved from modification of the nosump-tions upon vihich the analycis was based by Mr. Pulito and Mr. Labriola are offcot and chown in parentheses.

The meaning and applicability of both the original and reviced numbers can best bc explained by summari-zing the results of somewhat probing inquires by the writer and recponcco obtained as follows.

As the modo of failure appeared to be related to longitudinal loadings, Ebasco tabulated only longitu-dinal strccces at 900 psig,1140 poig and 1356 psig.

The 900 psig valvo was the approximato prcosure at the time of failure, 1140 psig was relief setting of the valvo and 1356 psig the previonc hydro-test temperaturo. The strcases at 900 psig and 532 F

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operating precouro are of greatest interest to us in this ovaluation. The primary longitudinal stresses woro due to internal proscuro, weight of the valvo, and a wind loading of 30 mph. cotimated at the time of failure. The primary axial otroso is tensilo and ito constituento colf explanatory. Two cocondary ctreccco (bonding through the wall thickness) woro calculated:

1)

" Bonding Stress Due to Eccentricity" (offset of mean diamotors of walls at chango in section) and 2)

" Bonding Stress Due to Step in Thickness" (this is a pressuro discontinuity stress at i

the change in section of tPo wall).

Tho mathematical model for the " original" strccces is chown on Exhibit-A and depicto an abrupt change from the Schedulo #40 (.28") wall ccction of the 6" diamotor nozzio to a wall section of approximately 1%" in the valvo. This treatment with a 900 step at the change

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III.

Diccuccion of Inspection Items:- continued

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in ccction in harch and the analycic chould be concor-vativo.

Cond$ng Otrocccc arc added arithmotically and c"- cd with axial tencile strcccco to arrivo at a concervativo maxi =um stroca of 34,070 poi (the original caco).

i As the opposing effect (oppocito sign) of tho bonding strccccc due to cccontricity and chango in ccction are nogiccted and the maximum cccen-s tricity at an abrupt change in ccction accumed, this value of strocc might be expected to bo concorvatively high. Yet the value is suffici.

cntly below the Mill Test Yiold and ultimato 4

valuco of the matorial (48,500 poi and 75,700 poi recpectively) that a failuro of tho type obccrved would not be expected to arico from J

theco axial otrecc Icvolo.

It ic pointed out however that a third contributor to the axial-bending ctrecccc will be the thermal disconti-nuity stroco due to bhlk tc=porsture gradient

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along the noccio and valvo body wallc. Thic gradient resulto from the termination of incula-tion at tho valvo and the grcator heat dicsipa-tion capability of the valvo volume and curfacco.

r, After the original strccccc as described abovo woro precented, Mr. Pulito ctated that ho thought the ctrccccc duo to ctop in thicknecc woro unrealistically high ac far as the conditions at the point of failuro woro concerned.

Becauco the failure occurred at the trancition betwcon the Schedulo #40 (.28") and Schedulo /180 (.43") occtionc of the nozzlo,'it was felt that only thic chango in thicknocs chould be concidered for the " Bonding stroco duo to stop in 4

thicknecc." By clido rule cniculations they deter-mined that this stroca (the proccuro diccontinuity) chould be approximately 44% of tho value given in tho original precentation. Thuc, bending ctreocco duo to etcp in thicknoco woro reduced to 443 of their original valuc for all thrco proccuro cacco and new totalc cero substituted. Theco reviced nu= boro are chown in i~'

parenthocos on the chart of Exhibit-A. The derivation of tho.44 factor.was not explained.

In any caso tho.

(7) roviced chart ic now inconcistant and incomplote

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III.

Discuccion of Inspection Itenc:

continacd 9

1)

Bending strcccco due to cccontricity betrcen the Schedulo #40 (.20'!) and the valvo (1.5")

walls added to 2)

Bending ctrocccc duo to step in thickncos (prcccuro diccontinuity) between the Schedulo

40 (.23") and Schedulo #80 (.43") wallc 3 t

but niccing are:

3)

Bending strocccc duo to cccontricity betwoon the Schedulo #40 and Schedulo #D0 ccctionc,

and 4)

Bending ctrecccc due to stop in thicknoco betwcen tho Schedulo #40 and valvo wall.

Ebacco otrccc perconnel agreed with the writor's connonto that the otroccco at tho two changen in ccotion could not be coparated duo to their axial proxinity (about b") and.that a nearly completo inter-action of the stroco componento licted abovo nuct bo Q

expected to exist.

Becauco the eccentricity stroco is not largo; however, the analyccc are not entirely neaning-1ccc for comparicon purpocos. The original numbero can be taken to reprocent a harch analy-cis or/and upper limit of cccondary ctrecccc.

l On the othorhand, the reviced nunbora could be taken as a lower non-concorvativo limit thus brackoting the probablo actual caco.

In ncither caso are thornal otrocccc conciderod.

Tho writor asked Ebacco porconnel rihother they had considered thornal strccccc.

It was stated by Mr. Labriola that thornal strccccc woro not expected to bo hiCh and were not calculated. The point nac nado by tho writer that even though thornal ctrccccc were predicted to bo low, they woro precent and

, s becauco thic wac a failuro analysis chould be concia derod.

In thic caco cotabliching that tho design not' o

t codo requiremento and allowablo stroco levolo might not be enough to catablich the contribution of real strocccc to the failure.

t

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_ _ _ ~ _ _____--

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III. Diccuccion of Inspection Itens:

continued

^

s

+

l It wac reported that no ctrcco concentration factorc -

were uced in the Ebacco analyccc.

,.lMN In vicw of the charp corncro apparent at tho changcc in ccction, copecially at the point of 4

{g failuro, eniccion of SCF'c in analycing for tho cauco of failuro doco not ccen realictic.

From the diccuccion of the cubject, the writor drew 3

the conclucion that only a Codo proccuro analycic had been perforned in the original design.

In addition, s

)

Ebacco ctated that an analycic had alco been nado for.

f, ccicnic conditions.

It was cicar' cotabliched, in s

recponce to questions by the writo.:.tnd Mr. Potapovo, s

that tho joint nocelo connection wac not analyzed for tho blow down caco.

Mr. Pulito caid they woro conci4 3'

do-ing cupports for the valvec, but it wac not cicar,

whother theco woro contc@ lated beforo the failuro or'.

s after-tho-fact finco.

!!o ctated that in any caco the final installation would noot all requirc=cnto.

p Tho onniccion of tho bonding co=cnt duo to valvo

['

n blow-off has to be considered a corious defici

?

cncy in tho design-analycio. The jot reaction

~

foreco during blowdown aro largo and in the daco' of thic docign, acting on a fairly 2.cng IcVer arm.

If the valvo popped prior to failuro, the no=cnt cuperpoced on the proccuro loado would 'av-cw havo to be concidered as a likely cajor contribu-tor to the failure.

Conversely the fact of i,

failuro and relativo otroco Icvolo exicting under e'^

etcady ctato conditions vc. blow-off nicht bc decicivo in concluding whether tho valvo. popped' i

s or not.

Further evidence to cupport oither caco s_

will be cocential to final conclusionc.

i A design fix for the valvo connection is being conci-l dered by Ebacco and Wootinghouco.

They indicated that,

,47 a number of different approaches woro being studied 1 7 ~ *'

and they woro not yot ready to discuco theco in y5-dotail.

From the convorcation, it was obvious that '

one nodification would involvo removing the chort 6"'

~ $6 b

Schedulo #00 pipo noz:So and welding the valvo D.'

3 directlytothecteamlino(andreinforcement~glato)'-

s with a heavy ocction wold in tho area of the 45

>% 5 taper

't

-on the bottom of the valvo.

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III.

Discussion of Inspection Itens:

continued Mr. Erion stated that they hoped to decido on the design nodification within the next ucck. They are trying to have field work completed by June 7.

Their position is that a design r_cdification can bc developed and work proceed without having conclusively learned the cauco of the original failuro.

One cannot arguo that a new design can be devo-loped without learning why the original failed, but fron an AEC-Complianco point of vicw, the caunc would remain important. Thoro are many other connections of this typo in this plant and possibly nore in other plants designed by Ebasco or other A/E's.

In any event, a revised dccign or any nodifica-tion to the c::icting design chould be cubjected to a rigorous design-analysis.

Ecofing up tho connection night not colve all conditions of overstress c:<porienced and night further intro *

('1 duce new factors.

It would be appropriato that the AEC-Complianco rovicu tho new design and 6

andlysis both to confirn its adequacy and to provido a further referenco for evaluation of' the original failuro.

Mr. Siedic cnphasimod the need to know the cauco of failure even if the fix involves a najor change to the design.

He c=phasized the offects on primary cystens as being of real concern as a result of this type of failure.

Mr. Pulito described Ebasco's progran to rovicw all cafoty valvo and piping connections that night bo considered similar to the safety valvo nozclo in tho.

Y Robinson-2 plant. The following quantitics of connec tions had been identified for review:

s a) 24 wold connections sinilar to tho safoty valvo (all with reduced thickncss coctions),',-

~

b) 18 flanged connections, z

f~s 4

and c) 40 other flanged, cercwed cr cockot-wolded connections.

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(~)

III.

Diccussion of Inspection Ite=c:

continued I

?:

?

Ho caid they woro 1 coking at all reduccd ccctions to deterninc if they nect decign criteria.

Mr. Pulito ctated that they were not in a position to discuco other planto at thic tiro.

i The writor would like to point out the evalua-,

tion of pipe or valvo connectionc to noot Cod 2 r

4 precouro and temperaturo critoria night not bo good enough to catablich reliability. The failed.

cafoty valvo connection is an c::collont caso in point. The joint was apparently ciccd for obvious * ' "'

precouro and weight, and poccibly coicnic and wind Icadings, but the rost ccvoro loading condi--

tion of valvo popping rac not considered in the total analycis. The codoc, whilo provid.ing cpecific rulec and for=ulac for precouro design, generally leave the evaluation of inposed loads to the designer and define the requironento for their evaluation only in concral ter=c.

It is cncunbont upon the designor to ovaluats cach

(~)

caco individually and provido accurance tl.at the design ncots its functional requirements whether the critoria thoroford are cpecifically provided by the applicabic codes or not. A further revicw' (

of Ebacco's work in their evaluation of other connecticac chould provido the AEC-Complianco -- ' p-with tho type of infornation necoccary to cctab-lich a Ocvol of confidenco in the critical plant

^

cyctenc.

Sono discuccion was centered about the fact that no one in the group, particularly the Ebacco perconnel with both nuclear and foccil ctcan plant background,;.

had experiencc[l or knowledge of a cimilar plant o_,

failure.

Mr. Siedlo asked whether safety valvcc in 3

foccil fucidd plants woro cinilar.

Ebacco perconnel'a

!.6,

explained that, while generally cinilar in counting:

arrangement on stian druno or lines, becauco the

.5-foccil plants operato at a higher temperaturo and

-(

precouro the pipo connections woro generally of heavier; 3

wall and/or in higher strength alloy natorialc.

Frona the diccuccion, it could be concluded that thets parti-O cular paranotors of thic design and its configuration.,*

woro probably unique to a nuclear plant.

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III.

Discussion of Inspection Items:

continued The above comments arc important in categorizing the failure or assessing its probability of occurrence on basis of other plant experience.

~~

Sa no::lo connection designed for higher steam pressures and temperatures would have a greator wall thickness, and/or use higher strength alloy materials. Thus, it t;ould inherently possess a greator margin of strength to resist externally imposed loads - such as the steam discharge reaction.

Conversely, when designing for comparatively low steam saturated steam pressures and temperaturcs in nuclear plants, relatively thin walls can be used in low alloy materials.

Thoroforo, com-parably high reaction loads will cause a much higher stress and larger percentage of the total stress in the lighter sections.

We think that this relationship might have been an important fac tor which resulted in the subject design being

(~%

marginal for largo discharge loads.

The analycos of Attachment #4 show how the dischargo forccs are predominant in the total stress picturo.

As the last agenda item of the mooting, Mr. Erion of Westinghouse explained their approach to reviewing the effect of the transient which resulted from the valve nozzle failure on the primary system.

lie expaiced that the pressure and temperature history during the transient woro very well documented by facility recorder charts and data taking which was started by operating personnel soon after the start of the transient.

The primary system experienced a 0

213 F temperature drop during a period of 63 minutos.

The writor asked whether this was the actuni transient

. g, experienced by all primary system components or an average coolant temperature chango.

Mr. Erion said that for all practical purposes this temperature cycle was representative of all parts of the system.

!!c said they had good natural circulation after the pumps were stopped - bottor than expected.

IIe stated g

further that the temperature response of the system correlated well with that predicted in earlier theoro-1 tical computer analyses.

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5 (4

III.

Discussion of Inspection Items:

continued i

i They had initiated a program to determine the offect of the transient on all major componcnts.

Designers of the vessel, pressurizer, stcan generators, pumps, etc. were given the transient data and asked to respond as to its offect on their components.

Mr. Erion reported that most of the groups contacted had respon-dod and no problems woro identified.

The report of the transient effect on the primary system referred to above was brief and more in the form of a progress report than a technical account.

It is of course undesircabic to experience transi-ents in components which will reduce their remaining usage, particularly early in the life of a plant. The effect of the transient on usage is not obvious nor can one categorically define its offect on all system components.

Each arca of high stress and thermal related usage must be

(?)

looked at individually.

It is - understood that the AEC-Division of Reactor Licensing will be reviewing the applicants evaluation of the transient offect on the entire primary system.

The writor:. wishes here merely to endorse the ABC position in assuring that the system has not

~

suffered severo damage by making a thorough review l

cf the reported transient offects.

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2-g IV.

References:

0 1

Inquiry Memorandun - Carolin-Power and Light Co.

(II. B. Robincen No. 2) Licence No. CPPR-26 Docket No. 50-261, W. C. Scidle, SRI, CO-II to J. P. O'Reilly, Chief, Inspection and Enforec=cnt Branch, CO-lfg dated April 29, 1970 2.

Inquiry Memorandu

- Carolina Power and Light Co.

(II. B. Robincon No. 2) Licence No. CPPR-26 Docket No. 50-261, W. C. Seidle, SRI, CO-II to J... O'Reilly, Chief, Inspection and Enforec=cnt Branch, CO-IIq dated April 30, 1970 b

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11. B. Rcbincon No. 3 Carolina ?c :cr and Licht.Co. -

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Attachr ent r.?.o. 4 T. -

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f:29 23, 1970 '.

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U.S. Atonic Enorcy Conninnica c

Divicion of Complinnec 9!!C Contract AT(11-1).1653 Task A J

Paracotor No. 60-70 A.-

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