ML20045H089

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Provides Generic Assessment of plant-specific Compensatory Actions Implemented by Plant Prior to Startup of Either Unit
ML20045H089
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/02/1993
From: Newton R
WESTINGHOUSE OPERATING PLANTS OWNERS GROUP
To:
WESTINGHOUSE OPERATING PLANTS OWNERS GROUP
References
GL-93-04, GL-93-4, OG-93-42, NUDOCS 9307190042
Download: ML20045H089 (11)


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OG 93-42 . , .s July 2,1993 *l'-> -

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To: Westinghouse Ownem Group Pnmary Rwhidives (IL,1A)

Subject:

Westinghouse' Owners Group REGULATORY RESPONSE GROUP Generic Assessment of the Plant-Soecific Compensatory Actions Retarding Salem Rod Control System Event 2 - , . , . s ,

The purpose of this lener is to provide a generic assessment of the plant-specific compensatory actions implemented by Public Service Electric & Gas Salem Station prior to the startup of either unit. Each .

compensatory action is identified, reviewed, and a position taken as to whether or not the action should be implemented by the remainder of Westinghouse plants. In addition,informadon regarding ,

the conupted rod control signals (including a copy of typical normal and corrupted Rod Control System cunent trams), the three types of postulated movements, and the proposed test program is included. A copy of the Salem Justification of Continued Operation (JCO)is also attached (Attachment I).

This letter completes Action 5 of 00 93-39 " Westinghouse Owners Group Regulatory Response Group WOG Effort Related to Salem Rod Control System Event (GL 93&) Update", dated June 25, 1993.

DISCUSSION OF COMPENSATORY ACTIONS .

Pursuant to the requirements of 10 CFR 50.54 (f), the NRC issued Generic Letter 93@, " Rod Control System Failure and. Withdrawal of Rod Control Cluster Assemblies" on Monday, June 21,1993 and was addressed to all licensees with the Westinghouse Rod Control System (except Haddam Neck) for action and to all other licensees for information.

The generic letter listed six compensatory actions that the Salem licensee was implementing prior to startup of either unit. Applicability of each of the actions to other WOO members is discussed below.

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Action 1.

%hmed rod contml system surveillances prior to startup and during operation"W. - .

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Action 2.

"More frequent periodic surveillances of the rod contml system" .

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salem Unit 2 experienced multiple failures in the rod comrol system in addition to -

failures that contributed to the single md withdrawal. The more frequent and enhanced surveillances specifically address the need to re-establish confidence in the Salem 4 Unit 2

,y contml system. The mom frequent surveillances apply at Salem for appmximately ~ a th month period. If rod control system operation is found to be reliable during this tim the utility will remm to their normal frequency. The enhanced surveillances and at-power will continue to be perfonned at both units.

nd The increased surveillance frequency should not be required by member utilities if th Control System is operating in an acceptable manner. Utilities should review their surve!' lances to ensure that they adequately 1) include the steps necessary to ensu system operability and 2) incorporate maintenaxe trouble shooting, if required.

Action 3. -

" Modification of the startup procedure to preclude an asymmetric rod withdraw the suberitical condition by ,

first then, pulling control rods while highly borated to the estimated cridcal pos deboranng to cnticality" . '

Discussion PSE&G prepared a JCO for both Salem Units. The basis of the JCO was .,

plant both units would meet Condition II acceptance criteria T

_s Jin ~~j tod withdrawal at power. The analyses showed, however, that Condition II criteria might not be met in all cases for an asymmetric md withdrawal fmm the subcritical c The JCO assumed that as the rod control system would be in manual, the only ,y time would be withdrawn would be under control of the operator. Credit for operator attent dg ~

during the withdrawal was taken to terminate the event prior to exceedmg Conditio ' '

The typical accident analysis limitation of ten minute operator action was not con applicable. . The operator would be manually conttolling the rod widdrawal such that th detection of md misteppmg in less than one minute would be reasonable. ,

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' During the-r= view of the Salem 3COs/ the,N5tC expressed their concem over crediting the

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operster during a rod withdrawal from the suberitical condition to meet Condition U criteria. . . .

PSE&G resolved this by agreeing to dilute'ta criticality. It.is believed that analyses, using,  ;', R w illde-mtnte that Condition H . . . . , . M 559.S

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J more sophiitti ter+ codes;as' proposed'by the WOGa a v w ud'cribria can'be met <for;allvestinghouse plams.for both the,-at.

  • power cases.l Dihit!'orito criticality lijudged not to be.a necessary action to preclude unacceptable.

consequences sliculd.this event securf This position will be further discussed at a July 9, ,j%M .

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e 1993, x:.w.r meeting;with aun- a the NRC. n M . hip,y, 4.; 4 ' Q . ,,

Action 4. W" Classroom and simulator training. add:essmg;the effects of potential single failures-iny d]8$'

the rod control system"

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Action 5. '" Issuance of standing oniers to heighten operator awareness of potential rod control. ggy system malfunctions" <.

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Acti3n 6. Review of cvent regense procedures to assure adequate guidance to operators in the event of a rod control system malfunction" , . . . . . . -

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Discussion . .M M -

These actions were irdtiated while Unit I was still operating and the investigations were , .p ongoing in Unit 2. The investigations were aimed at determining the root cause of the frequent falhues in the Unit 2 rod control system as well as the single rod withdrawal event ,m,.

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that had occurred. The ardons were pmdent and consistent with the overall plant review being*

performed.

Following completion of the ' 1 7 program to address Generic Leuer 93 04, recommendations for dmoorn and simulator m , mi event isi~nse procedures may be issued for utility ._ , g;.,

guidance. Until this program o e gettd, following the twm a* ions in the Westmghouse Nuclear Safety Advisory Letter 93-007 dated June 11,1993 is considered "_ > y* * , &@

sufficient to meet the intent of increased operator awartness for the potentir.1 of rod control system malfwniuus. This increased awareness was the purpose of these three actions for the ,.

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_ ADDITIONAL INFORMATION .

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.In their presentadon to the NRC on June 18 in King of Prussia, one of the findings reported by the PSE&O Significant Event Review Team (SERT) was." Pin Connections / contacts pmblem three (3) other Westinghouse sites." (Slide 93MM3-16). _ . +

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This finding was the: result of an infnemi survey conducted.by the PSE&O SERTof the u.r

'e apr escately 25 plants where Westinghouse had performed.the same preventative maintenance p.y ,

pmgram that was performed:st Sidem Unit 2* Slavey responses indicated that the only significant-problems following;the. extensive printed circuit _(PC) carti.Temoval., testing:and upgrading.d;$ werei.wittr.

f further noted in thesame slide. that**PM;(Pferentative ~

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contribute to the-FLRCS (Full Length Rod Contml Sy, stem) pmblem." Based on the above. m 41 Wesunghouse/WOG~noterthat normal cars and ' attention to detail should be exercised when kh @k kNSN*N -

PSE&G also implemented.the;followingppm+mMWadon programr.,1) installation ofi suppresslortdiodes across the-steprcounter colls for both.unitrand 2) static charge PC cani .. hand guidance. West +nghrmadWOG*irev' aluating the gerielic~ applicability of these corrective modifican as part of our review activities. " '

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  • c 'qC l'URTHER DESCRIPTION OFTHE SALEM UNIT 2 ROD CONTROL SIGNALS Y .ma

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"N Effect of the Failures on the Slave Owler Current Orders

.. . .; ..- ..<.a -1 > .s The two PC card failures that caused corrupted cur.,ent ortiers to be applied to the stmtdown bank

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m A mds were both located in the Logic Cabmet slave cycler c signal to a' ways remain selected; Tids signal nonnally ca ircuits. One failure caused .

5Y4 the nses the slave cyclers to produce outwant motion cunent orders when rod motion is demanded. The other fallute caused the DNSPX signa always remain selected. The DNSPX signal normally causes the slave cyclers to pmduce inwani motion current orders when rod motion is demanded. With both of these failures present, the slave .

cyclers (specifically, the slave cyrler decoderPC cards) produced the.following curtmt orders vdien: y either inwartl or cutwant motion was. demanded:

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The current oniers wpplied to the CRDM stationary an.d movable coils were identical to the normal outward motion current onlers 2, . v The current 0'rderrsupplied to the CRDM lift coil was a corrupted combination of the inward ..

and outwant motion current orders "

d Note that with these failures, rod motion does not occur until a demand signal is present (i.e., j spontancous rod motion does not occur). Also, since slave cycler current orders contml rod group motion. failures such as these produce corrupted current orders that are applied to rod gmups, .c,not individual CRDMs. ; *-~ ' -

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Figures 1,2; and3 show CRDM curnmt traces taken at the Pacific Gas & Electric Diablo Canyon. .yP-.

training facilityr Pigure:1.ls a normal outward motion current tracc. Figum 2'is a normal inward-7' motion trace. Figure.3 is a trace taken with a failum of the UPSPX signal installed in the Ixgic "

Cabmet. This causes the conupted curmnt orders to be produced when inward.md motion is . pg, demaaded. Each figure captures sygv&ately two rod motion cycles of lift, movable (MOV), and fM stationary (STA) cunent. A rod motion cycle takes.780 milHenmds. The cycle begins.when - yde stationary coil currentrises fmm reduced to '~full cunent and mot when stationary coil current falls W fmm Mi to reduced _ current. _ . , . _ . . .i ^' x. . < - .

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With the slave cycler failures present (Figure 3), the following sequence of' current orders is applied to 'pW'.

the CRDMs: ;. , . g .e . , _ a l Appmximately 6 milliseconds after rod motion is demanded, the Ps-fy coil current is $

pmgrammed to rise from reduced to full cunent. while at the same time, movable coil current is programmed to. rise from zem to full cunent (the normal outward motion sequence).

2. Appmximately 30 mi!Ilseconds into the cycle, the' lift coil cunent is programmed to rise from zero to full current (the normal inward motion sequence, but note that the stationary gripper is still pogrammed for full current).

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3. 133 mHHwnnan into tiie cycle, the stationary coil current is pup-ued from full to zem ' N'~

current (the nonnal outward motion sequence).

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At hyrvAntely 213 milliseconds, tic Ilft mil cunent is programmed to Induced cuntnt (the

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y.a 5; At ppv&ately 23I milliseconds or only118 milliseconds later, the lift coil cuntnt is switched back to full cunent (the normal'outwant motion sequence takes control and demands full current at this point).

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At oppswy,378 milliseconds, t1Wmij coil current is pmgrammed fmm zem to full- "l@

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'7. At ser vaely 390 milliseconds, the lift coil current is ruitched fmmfull to zero cunent. 1.,,;b (The r-mi inward. motion sequence; takes: control and requires lift current to switch fmm- y reduced to zero current at this point.) ~ . .

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8. . At approximately-499 milliseconds, the movable coil current is programmed from full to zcm cunent (the nonnal outmotion sequence)..

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9. At 780 mi!!Lwnn*, the end of the cycle, the stationary coil current is programmed from full j.

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TED EFFECTS dN.CRDhih O sw c.u.- hh \

At this time, there.are.three postulated. scenarios to explain why the drive rods do not always move C- out when supplied.with *- the cormpted current oniers: M. }; 7 '. @^ '

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Movab!c gripper engages the drive rod after the lift coil has raised the movable gripper im j assembly -When the CRDM is supplied with the cormpted current orders, the lift coil is W

. energized only 24 milliseconds after the movable coil. If the lift coil raises the movable _ M gdpper assembly high enotigh befo5the movable gdppers can engage the drive rod in the normal groove, the movable. grippen may engage the md on a land and then slip over into the

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next higtwrgrue, preventing outwant motion. Note that it normally takes the lift call appmrimardy 30 milliseconds to begin to raise a disengaged movable gdpper assembly* (as, ~

- ~,ag happens during normal inward motion), while it takes the movable coil appmmmarely 110 milliseconds tar fbily engage the movable gripper. M. i l

2.

Stationary grippers do not disengage the drive rod after the stationary coil is inidally deenergized -- When the CRDM is supplied with the cormpted current orden, the stadonary l coil is deenergized after the lift coil is energized. Assuming that the movable gripper engaged

  • 1 in the lower groove, the stationary gripper has been under tension applied by the lift coil
  • trying to raise the movable gripper. Even when the stadonary coil is deenergized, the stationary grippers may not disengage the drive rod, thus preventmg outward motion. # +. - .
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Stationary grippers reengage the drive md after the lift coil has lowered the movable gripper When the CRDM is supplied with the corrupted current orders, the stationary coil is I reenergized at 378 milliseconds into the cycle. The lift coilis deenergized at 390 millisemnds. Assuming that the ot.t motion sequence has occurred ammally to this point, if .Q the lift coil field m!! apses fast enough to allow the movable gripper to drop back down before 4:

the stationary grrpper engages the rod, the stationary grippers may slip back into the original V drive rod groove, resulting in no sustained outwani motion. 'Ihe md would, in effect, move i

up 5/8 inches and then dmp back down. Note that even after a lift coil is deenergized, it nonnally takes approximately 150 milliseconds before the movable gripper assembly drops down.

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In additio5 there is a question as to whether havmg the ddve rod initially disengaged lg- (i.

when the corrupted current orders are applied has an affect. At this time, there is no clear postulation of why this would effect the CRDM response.

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ROD CONTROL SYSTEM EVALUATION PROGRAM " @3 W

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'Ihe WOO Rod Contml System Evaluadon Program will run tests to detennine why the ddve rods - .

sometimes do not move out when the corrupted currerit orders are applied to the CRDMs. A Rod. " "

Contml System that is installed in a WOG utility member test facility, con Power Cabinet and more than one CRDM. will be used to run tests to help isolate the cause or mm ,,.

of inconsistent rod steppi.4 Tests will hu:!ude the following:- ~

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Baseline. cycle tests - determine how consistently the CRDMs respond to corrupted current-~ ;;;.,, ,,

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Latching tests -determine;whether the md being.initialiy nnW5dhas any effect 1m.ma

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26% *C-Vertical displacement tests - determine whether the initial position of the rod relative to the, , ,_

gdpper position has any cffect., y:-@..Q T.=,N .

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,a .2 Load tests - determim whethecthe-load.on the drive.rud.has any effect

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. . v': n Timing tests - determine whether the timing of current orders has any effect

'Ihe test team will inchule Rod Contml and CRDM design engineers as well as WOO utility 2.i Q e W" representadon.

1993.

  • ' This team will further devlelop the tests and produce a WOG report by Septemb

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'Ihe.pdmary tecimical contact at Westinghouse is Mr. Mark Pmviano (412) 374-5651. 'Ihe WOG

%%Ak7 Project Office Interface is Mr. J. David Campbell (412) 174- 6206. Additionalinfonnation will be pmvided as it becomes available.

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Very truly yours,

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Roger A. Newton Chairman Regulatory Response Group - - d* -

Westinghouse Owners Group cc: WOG Steering Committee (IL,1A)

Regulatory Response Gmup (IL,l A) -

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C.K. McCoy, Geoq;ia Power (1L,1 A)

J.P. O'Hanlon, Virginia Power (IL l A)

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NJ. Liparulo E(IL)

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