ML20198H369

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Ro:On 831003,results of as-found Tests Indicated Crosby Main Steam Relief Valves Had Lift Points Exceeding Tech Spec Limits.Valves Disassembled & Rebuilt by Mfg
ML20198H369
Person / Time
Site: Palisades, 05000000
Issue date: 11/14/1983
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20198H325 List:
References
FOIA-86-266 NUDOCS 8605300294
Download: ML20198H369 (11)
v • d • e


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' IIENTIFICATIM AM IUctlPTIO1;

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PART 1 y ratta Valves Failed to Meet the ' As Found' AcqcatiaDee Cri$grjJL Eglutd in Tecnnical.

Anen i f f cat i nn n._Te st__IN-29 BJ etar sesneuro n' allo reuirom. uaisw,o 13107 _._

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On 10-3-8hS2Oct_,.b_.egan tes_t.inp J_glilades main steam.. relief b"

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g ives at the BC cobb_PTant.

Eetween 4 and Oct. *I4, Die 'as found' tests vere en pl etaA nn MV 0701 thrnech v1V_I)72js.. RLil715 *ina fnnnd within the tent et-it avi'*_

The vominine 9'4 v-al i ef vnl ype

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When these vQyes were4 td:lted in 1981. the testing had an under designed accurrnilator.

As. m vaen1t _ the ntem lift height (in discharste cauacity) was adMusted to limit; dineknem va+

Thie une Anna a ftar caMultine with the Crosby Valve _ Co. represen-tative vhn ass tred the test ensineer that this tsdjustment would not effect the valve u n ess,v.

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!f Part_10,_D_escription of_ Occurrence or Con _dit_ ion:

(cont.)

e fnund to be lenking badly nnd required resettine to meet the acceptence criteria.

That adjustment may be the reason for the high lift ogints

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hma anvine la Part 9B EVALUATION _ANQ_ DISP _OSITION ROOT CAUSE (ennt_)

After reviewing the test data. I disagree with the Crosby representative. The valve dincha-c.

mainnt.',-t aia arr.ct li ft nrannuren.

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T heli ve that tha en11nvine s cena ri n

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The valve discharge heights were adjusted in 1901.

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i The valves were then tested and consistent 1v found to lift at a lower uressure thnn renuired.

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The valves were t' hen readiusted to a higher lift Dressure.

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They were retested with the adjust 2 discharge hei ghts and tested good.

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The val vo a i e-hn,-e. hatchtm ver, rendinnted tn nri cinn1 danien and +he vo l ven

'l reinstalled.

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In 1983 the valves were retested without ad.iustment using a test rig with a large accumulator. The valves consistently lifted at a Ice:A, pressure than

'l regnived.

Met 2 I t A91 i!

Theradinstment to the valve discharge heights caused all the valves to lift at a inu?.r nrocenv. uun h et.a

% valv. l i ft naiuntmanta nna. in loa 1 nn1v enmn.nen*,a for thi. discha*ge height ad justrants. When teited in 1981 the valves nei fonn' d e

j as they vanla in s ervi c e _

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j All the Main Steam RV's have been rebuilt and tested, without discharge height ad.iustment, using a test rig that simulates actual plant conditiens.

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FORWARD ALL CORRECTIVE ACTION DOCL*.'ENTS THROL'GH YOUR CORRECTIVE ACTION COORDINATOR!

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. The main steam relier valves (RV-0]Ol thru RV-072h) are capable of performing their

]i.e_s_i2n function.

The result _s_.frpm 198T DJ!-29 testing indicated extrem_;1v lov' 'as found' set points. These valu_es vere obtained after the nozzle ring was adjusted from predescribed factory settings. The nozzle ring adjustment was necessary to de,

Jrgase blovdown due to test _JyAtgq JJmitations, ie the' test system did nok hqyg._the u

desired steam 6eneration capacity.. The valve manufacturer was consulted; they indi-

[ cated that set point was not affecEd by nozzle. ring adjustment. The valves were

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inspected, cleaned and retested. The spring tension was adjusted (increased) to ach_igye or_op_er_ lift.

Repetitiye lifts were nerformed to demonstrate _ reliability. -

Upon comoletion the nozzle ring was returned to the factory setting and lock vired.

~The 1989_RM-29 testine indicated _extremelv high 'as found' set noints. These values

_. yare obtained witho.ut prior a.djyntmentsde 1983 test system steam capacity was

_improyed__bety_een 1981 and 1989. Therefore, the_nq2 Ale rinc adjustment was not nec-

__gaggry.

The valves were inspected. cleaned.- repaired and/or relapped under the direct

._._supervis_i_p_n_of the manufaqturer's fie_ld, service._ representative. The val _ves were re-l tested with the spring tension adjp_sted (decreasedl to achieve proper lift.

Repetitive

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_ lifts were performed to demonstrate, reliability. With the valves still hot, discharge

_p.ipe v_a_g_ removed _and at 905_of_ Set P0 int._ pressure the valves were visually instsected for._1eah t.ightness.

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In recent_ telephone conversations yith D. A. Desnoyer (CPCo - Trail Street) and D.

Tuttle (Crosby Company - engineering) the Crosby oosition on the nozzle ring and set point relationshin was clarifieddrmally,_the nozzle ring is not adjusted.

If the nozzle ring is adjusted it _is usua_lly only one to three " notches." Crosby main-tains that norma _l._minpr_adju._sj;;;;ent_s_ vill _ngt affect set point. They added that a

lovering the nozzle ring of a safety valve could increase varn (leakage) and_ could q

cause a slight increase in popping _ pressure.

Conversely, if varn is present (as it was in 1981) raising the nozzle ring could,cause a slight decrease in popping pres-sure. During the 1981 testing the nozzle rings were adjusted as much as 12 " notches.'

In addition, the instructions bulletin for operation and maintenance of Crosby safety valve, Vendor _. File _MI-F.D_,_sta_t_e_s :

"If the valve nous too lov. the seats may have become damaged. Lov popping pr.esaure_ is seldom caused by_. spring set, although this is considered a egemon cause."

_.The_above information indicates that set points can be influenced by seat condition and nozzle ring adjustments althp

_S_uff. ice to state that the 1961 Rh-_ ugh the exact relationship can not be determined.

a 29 'as found' test results were in error, influ-enced by leaking valver and nozzle ring adjustments. The corrective action (spring tensioning) taken during the 1981 RM-29 test caused the deviations observed / recorded during the 1983 testing.

l 6

As stated above. the main steam relief valves (RV-0701 thru RV-0724) are capable of Jetforr.ing their desian __ function.

Each_. relief valve. as installed unon completion 1

. of_ the_1989 RM-29 tesL_has_the_adjystment_bpit (c.Qntrols suring tension) returned

_39._vithin_1 25 fl.at_s of the_ '_as_Cound'. position of the 1981 RM-29_ tag 1, Iq_a_ddition.

..they_haye_indiyidually bmtinspected.for lea)t11gh.tne.ss.

Non-conclusive _.but t

_supoortive evidence can be shown (see Attachment 1).

The bold line highlights the

_ nun;_erical average of the observed ___'as found ' lift point during both the 1981 and

__19h3_JU4-29 tests.

All but one valve _. falls _yithin the recommended set Doint tolerance wa _

bhe aggregate of the above informai. ion is the basis for the conclusii>ns set fcHh.

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TELEPHONE REPORT DATE II-14 -O TIME M I6[M FACILITY 6646 Roof-DOCKET NO. 60' O 3 LICENSEE'S OCCURRENCE IDENTIFICATION NO. (IF ANY)

Ogessy M5 Spry valve RIAA 5stfr>JA 'Ps Frcrency -

BRIEF

SUBJECT:

foTEOfIkL 60.66(N DESCRIPTION OF OCCURENCE, DEFICIENCY OR INCIDENT:

Al lefndit, bax Maldrand ank $~tt Chittice YA6C calicd. n'ut a. pienfrat =50.55(e ecxe,%g Mc rt,tg settig s a fAr_ Crosq wn stras sag vnhes. hec,7 yest,,

k) wu donductd e % 6'sc at 9 Labs, a 14 &se. ktt test (ut totu unts y % teas 4 So7e of % re}'Uted. trant L ri gett;n asag d.

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are. Mssa e, %. ti9 setti cn k tcady'asted. af the.sile., cetd y9s reqtaces.Teq L3tle. ti,e_t do so.

1ke. uce,tsa. is (4 % frocers cy. fady'Gy

% difernine whetket %td eenL% Wsts sf-SearwL.

NOTIFICATION RECEIVED BY hfd'5 encosue fu 9 RO:I ForTn 50 Ab idts d ['Oh8ttl)

IIc June 74 g beger tJ q (c/t,A u

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NUCLEAR REGULATORY COMMISSION y

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WASHINGTON,D.C. 20555 Ifl6/85 l

As you noted on.the incoming draf t f rom NRR, this info notice sounds fine but begs the question of fixing the problem. We do not see a need for immediate requirements because the valves are sized conservatively,100%

steam flow.

Full capacity is needed only with very low probability events.

All steam flow (turbine, turbin ags and atmospheric dumps)is s topped e scram signals f ail so that the reactor ip is delayed,and feedwater flow is lost. However, it is apparent that other valves are likely to have less than design capacity and should be fixed.

We have discussed this with NRR.

RSB personnel are trying to sell a 10 CFR 50.54 letter.

In the meantime, we should send the info notice.

Yob Baer D e p-R@

Dennib Allison

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DIVISION DIRECT;R'S OFFICE DIVISION OF EMERGENCY PREPAREDNESS AND ENGINEERING RESPONSE

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ACTION ~ NUMBER:

85-219 DEPER 2.

DATE; 8/20/85 3.

SUBJECT:

TRANSMITTAL OF PROPOSED IE INFO NOTICE RE MAIN STEAM SAFETY VALVES 4.

REQUESTOR:

ELJordan (M Memo from RBosnak to DCrutchfield, dtd 8/9/85) 5.

ACTION REQUESTED:

This looks good, but I wonder is it's enough in view of the problem and consequences I

EGC('

6.

ASSIGNED TO:

Baer (BRANCH)

(INDIVIDUAL) 7.

EXPECTED COMPLETION DATE:

S*"*^- h. p 1985 8.

EXTENDED COMPLETION DATE:

7 9.

COMPLETION DATE:

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