ML20214P636

Forwards Draft Charter for Augmented Investigation Team for LaSalle to Investigate Failure to Scram When Reactor Water Level Decreased Below Scram Settings

ML20214P636
Person / Time
Site:	LaSalle
Issue date:	06/10/1986
From:	Wright G NRC
To:	Norelius C NRC
Shared Package
ML20214P629	List: IR 05000374/1986023 ML20214P625 ML20214P636 ML20214P639 ML20214P643
References
NUDOCS 8609230330
Download: ML20214P636 (28)

Text

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9 Attachment 2 d-4 JUN 30 I!B6 MEMORANDUM FOR: Charles E. Morelius, Director, Division of Reactor Projects FRON: G. C. Wright, Team Leader LaSalle Augmented Investigation Team (AIT)

Subject:

AIT CHARTER Attached for your infonnation is a charter we have drafted for the Augmented Investigation Team for LaSalle to investigate the recent failure to scram when reactor wcter level decreased below the scrar. settings. Attached to the charter is a list of questier.s which we believe should be answered. These c;uesticr.s obvicusly are not all-inclusive but should help us to gain ir. sight ii.tc the event. The charter and the list of questions can be sumarized into five basic problem areas:

1. Feedwater Control

2. Reactor Protection; Syster.

3. Rcactor Operator Response A. Event Reporting

5. Precursor Events Our investigation will focus or these areas.

onto:NAL sIGNI:D BY W C F "'~'"3 G. C. Wright, Team Leader LaSalle Augment Investigation Tean-cc w/ attachment:

J. G. Keppler A. B. Davis C. J. Paperiello J. A. Hind H. R. Denton, NRR E. J. Jordan, SRI C. J. Heltenes, Jr. ,AE0D D. P. Allison, IE J. T. Beard, NRR

6. Holahan, NRR J. h. Taylor, IE

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8609230330 860917 PDR ADOCK 05000374 O PDR

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I Ch6rter for Augmented Investigation Team (AIT) for LaSalle '

Investigate:

1. Feedwater Transient

2. Reactor Water Level Switch Problems (Static-0-Ring)

a. Erratic Setpoint Behavior

b. RPS response

c. Vendor-Branch Review

3. ATWS Considerations

4. Operater Performance during and Following the Transient

5. History of any previous problems

6. Broader Ibplicatier.s

a. Unit 1

b. Other Static-0-Ring applications (e.g. LaSalle SRV problems)

7. Safety Significance, Root Cause(s)

C. Event Reporting

9. Conclusions / Recommendations Corrective Actions, and affect on startup

4 l Starter Questions for LaSalle Ali ,

1. Feedwater Transient 1.1 Whet was the sequence of events?

1.2 Why did_the pump on 3-element control increase speed ano lock up?

1.3 Why did flow go to zero after the reset of the lockup?

1.4 how fast was the transient?

1.5 How low did the Rx water level actually get?

1.6 How high did the Rx water level actually get?

1.7 Is there any history of previous problems (e.g. scram of May 9, 1986) with the feedwater contrcl syster.i?

1.8 Why was one pump on manual control; is that normal operating procedure?

2. Rx hater Level Switch Problems 2.1 Switch drift .

2.1.1 What are the calibration requirements?

2.1.2 When were switches last calibrated? How frequer.tly have calibrations been required?

[ 2.1.3 Are switches checked in "as found" condition prior to recelibration? If not, why not?

2.1.4 Does calibration procedure take into account entire logic or does it soniehow bypass part of the logic?

2.1.5 Any previous history of probler.si i

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2 2.1.6 How many switches actually failed?

2.1.7 What were "as found" switch scram settings? Subsequent settings?

2.1.8 How were switches checked following the event?

2.1.9 Did the low level alarm annunciate?

2.1.10 Did the high level alana annunciate?

2.1.11 What is ver.dcr's explanation?

2.1.12 How many cther in plant applications in safety sys,tems and systems important to safety?

2.2 RPS Response 2.2.1 Was a scram signal received by the RPS system?

2.2.2 How many level detectors generated the signal?

2.2.3 How many leve'. cetectors worked?

2.2.4 Was scran, logic satisfied? If so, why did reactor not scram?

2.2.5 If detectors cid not receive a scram signal, should they have?

2.2.6 Wes the response by the recorders correct? (e.g. was the narrow range low level signal a rec 1 signal?)

2.2.7 K' hat pust event RPS testing was completed to establish RPS operability?

2.3 Vendor-Branch Review 2.3.1 Have any inspections ever been conducted at Statis-0-Ring'r

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3 If so, were results tetisfactory or were there problems?

2.3.2 Did the Oyster Creek problem involve the same type of switches?

2.3.3 Has an Information Notice /IEB ever been published on this subject?

3. ATWS Considerations 3.1 Was this an ATWS?

3.2 Does licensee have an ATW5 procedure?

3.3 Is it adequate?

3.4 Have personnel beer. trained on it?

3.5 Was ATWS considered by licensee?

4. Operator Performance 4.1 What actions did the co-duty operations staff take inr.eciately during and following the event?

4.2 Was this action proper?

4.3 When and by whom was the apparent failurt to scram first identified?

4.4 If answer to 4.3 is not the on duty crew, what actions did the licensee then 16kei 4.5 Was the event identified durir.c a deliberate action (e.g., was it identified by the on-coming crew while performing a walkdown) or was it found by a happenstance?

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4.0 Why did the classification /notificatior,take about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />? Was the delay and classification proper or was evidence available such that it should have been sooner?

4.7 Did any shift crew member ever get out the ATWS procedure, or consider an ATWS?

4.8 Was any of this information recordcd ir. the RO's log book? Was this satisfactory?

5. History of any previous problems 5.1 Has there been any previous event similar to this (specifically, in hindsight does the May 9,1986 scram appear to have similar symptoms?)

5.2 If there were previous ever.ts, was the licensee aware of ther?

5.3 If not, why not?

5.4 Other thar. Oyster Creek, is there any informatior, available on other similar events?

5.5 Have there ever been any IEIN's or IEB's issued on similar subjects?

5.6 Did NRR require Oyster Creek to remove similar switches (assun.ing Oyster Creek had such switches)?

5.7 Does hRR have a mechanisn. for notifying other licensees or LPV's if l modifications are ordered, or does it rely on the IEB system?

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6 5

6. Generic Implications 6.1 Determine if similar switches are installed on Unit 1 6.2 Determine other Static-0-Ring applications at LaSalle and what affect this may have on these applications.

0.4 Review NRC policy on calibration of detectors, and determine its adequacy; specifically, does KRC have a definition or policy on "as .

found" (e.g., do we allow switches / detectors to be " cycled" prior te making"asfound" measurements)?

6.5 Did NRC/licerisec's do a satisfactory analysis cr. all EQ considerations?

6.6 Should NRC revisit other EQ modifications?

7. Safety significance.

7.1 In hindsight, was there any immediate safety significance from this event? If sc, what was significant?

7.2 has there been too much/too little attention given to the switch problem and not enough on the initiating event (e.g., the feedwater pump problem by LaSalle? By the NkC?

7.3 What was the root cause of all of the significant events especially; l

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7.3.1 Feedwater Control problems

, 7.3.2 RP5 problems 7.3.3 Reactor Operator response 7.3.4 Event Reporting (if it was determined to be late) 7.3.5 Precursor events (if there were any)

6. Co'nclusions/Recommendaticns 8.1 What corrective actions are proposed (by the licensee and by AIT),

and are they adequate?

8.2 What should be the af fect on startup of LaScllt Ur.its I and 2?

8.3 What shculd be the affect on all operatir.5 plarts with similar switches?

8.3.1. Should they be ordered to shut down immediatcly and repair / change switches?

8.3.2 Can modification wait until next refueling outage?

8.4 Should the hRC reevaluate its policy regarding surveillance requirements? (NRR,IE,AEOD,Regionsatalaterdate).

8.4.1 Do we have available, or can we get, a history of problces caused during required surveillance tests?

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7 S.4.2 Are the numbers of such probler.s excessive?

8.4.3. Should more surveillances be conducted during shutdowns rather than during operatior.5, and the number of such surveillances be reduced?

8.5 Do NRC reporting requirements adequately address this type of event?

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'" Ib2 04:22:29 B09 fl 0612 LP HIR 24C EX STft 21. VLV OPEti 152 04:22:40

. . 499 A 0400 HP HTR 261 LEVEL RIGH

? "h42 /A*049C LP HlR 2CC LEVEL HIGH

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901 il 1020 E.JAE. 2!1D S1 AGE f1 M PREE A . tiORM AL 152 04: 22:45

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- 4 11:2 04: 2 3.!,4 E ' -

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/ 9t!B A 0491 HP lttR 2!D DRtl VALVE F CLOSED ,

~/ 152;o4: 22:5U 444.A 042& ttSR DRtl Ti; 2P SPILL V ALVE OPEt1 6

152 04:24:&2 x Yu4,i 0409"In !!YR 26A SPILL VALVE OPEll 152 C4: 24:04 l

501#A'0502 LP H13 24C LEVEL HIGH I i b',' . 0 4 : 2 4 : O/ #

l H 14 A'0209 LP H1R 22C LEVEL HIGH -

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• 046 tl 042 6 ME,f: Phil !!: 21 SPIL! Vhl')E CLOSED

,*i 152 04:24:14 702 A 020Y Lf' H1R 22C LEVEL HIGH .

102 04: 24:1E

~'B2 ?! 0209 L P I!1 R 22C LEVEL IIDF.t1 A'. .

It2 04:24:1Y

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i r. t. . C L aeu r. .n 152 04:24:3'/

227 A 0423 !!EP likfi Tr. 2A DRti VA!"E A CLDEED

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. . c...: L o. L r. . u. t. I. .n. c-i E n. r . .

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056 !! 050E L P IM P 24C LEVEL fl0F. MAL 16o il 0490 Ht' Hli 26P EPILL VAL 8)E CL O E Eli 11:2 04: 2 4 : 4

105 ?! 0489 HP H1 f: 2LL t.EVEL t!ORMAL

• lb2 04: 24:42 721 A 050Y L.P H1R 24A EPILL VAL '!!: OF Eti 152 04:24:44

/2b A 0500 LP HlR ?4C LEVEL HIGH 2.' t;Pli L "!.9 GPEtt v2e .T 6423 1 E '- r :D l tlr 1..,*,

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2

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lb2 04:24:59 7S7 A 0269 LP Hl R 25L LEVEL H I C-H l'i2 04 : 25:00 121! fl 0422 t'.UR PRt! TK 20 DRtl V AL')E E OPErl 278 A 0510 tP liik 24P EPILL VALVL DPEN 821 11 02G9 LP HTR 22C LEVEL !!OR M A! ,

IU2 04:25:01 762 ?! 0422 115f: DR!! It: 2AiDRtl VALVE fi OPEtl

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215 tl 0424 MSP DRt! T r. 2 A PRfl VALVE D GPEN

".' 1 1 A 0424 Mf:i: DR!l T!: 2A !!Rtl V At VE F CLGEED 24L fl 0424 t1CR DPH 19 2 A DRil "(.! VF F 6PFfJ lb2 04 : .!b :01,

'c ik.! v4: 4 ti t W

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, . 'e /. ^7Si Crb WA1Eh I !! I'I F F F RFSS HIGl! e

( l' . "4 : 4t!! 21 ,

'g /.*!! 07bt t:PD UA1LR IIL li1F F F LEEE tl0MMAL 152 04:49:09 ^

' V t. A 07S6 Ckb UATEf? Fil 11F! IhEEE HIGH 152 04:4? 17 ,

'J f 2 .ti 0 7 5 4 C R16 UATER I 11 FIFF -\ SREhE ilDEMAL -

152 04:4?:24 Pi4 A 07S6 CI:!' UATEli fit I'l F i iRESE HIGH e

lb2 04:49:25 -

44L tl O !b e. CPD UA1ER FIL D1FF PRESE IIDRt1 AL S S U f. 07 L t. C R I- L' A1 ER F l! PIFF FREES H!bil .

Ib2 04:49:29 -

251 il 0754 CI:P U A'I EP F!i blFF PRESE t10hMAL

.-e; .., n. ri.. 4 o. . ..a. .

555 A 0756 CRD UATLF. FIL PIFF PREEE HIGH b25 H 0756 CR15 UATER F1L DIFF FRESE tt0RMAL -c 152 04:49:3t:

122 A 0756 Cl<D UATER FIL DIFF PhtEE HIGH 640 !! 07bf CEO UATER FIL DIFi F'RE E E !40Rh AL' 642 A 0706 CRb UA!ER FIL PIFF PRESS HIG:

711 N 0756 FRP UATt:R FIL PIT f PREES 140 RNAI '

r fi91 A 075 EPP UATER Fil L l ! !- EPEbb H ! Gl!

• 1S2 04:49:41 605 fl O/56 E Rb UATEF: FIL P!FF DhEGE fl0PMAL ,.

~C7 A 075. L Pf UATFR F1L LIFF PNEGli H10l!

152 04:49:42 7 9 fi 075L FRF UATER FIL PlFi PREEE fluRMAt c.

1Sk 04*:51:29 12*.; A OB92 Clibs DEMI!I C01:1 ROL PANEL 1 ROUBLE

, v,. 4. . .e.. .. f..,. -

104 A 0504 LP H T f: 250 DR*1 A! > E :LDEED .

152 04:52:SE 707 N 0501 '. . F !!TR 259 PR!! '! AL'/E Of E!! -

152 04: 52:41 052 !? 0816 GLArik ETM EF AL HH PEE.E E tl0RM AL 15? 04:5S:01 e

!!26 A 0756 CRb UATER FI! DIFF FRECE HIGH 1o r 4 . e_ .n . A. -

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E'2 !! bk45 IST SPD 1!!!. 2 I- D R N ')L 81 O P E !!

972 A'044? 1El EMD l ti!". .: 1 D f.fi '.' L ') CLDEED ,

~ir, n 4 '. c g . ,u ,

'3P tl bEkb 191 bi:E ! NE P Ph!I 'J: '.8 OPEfi 1*:2 04:56:10

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M-LEVEL 3 INSTRUMENT TEST DATA O TEST NUMBER : 1 DATE OF TEST: 6-2-86 Q TIME OF TEST: 1500 RX PRESS  : 950 N004C N994B N004A TEST TRAN RESET O' CHANNEL SWITCH ,

Q 8. 7 26.7

6. 3 5. 7 A1 NO24A O A2 NO24C 9.33 9. O l6. 9 ] 6. O 29.O B1 NO24B 4. 2 ,3 [3. 9 [ 1. 5 9. 9 32.5 Q

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O LEVEL 3 INSTRUMENT TEST DATA TEST NUMBER : 2 DATE OF TEST: 6-2-86 O U ME F TEST: 2100 RX PRESS  : 950 N994C N004B N004A TEST TRAN RESET CHANNEL SWITCH 0 A1 NO24A 10.8 19.5 9. 0 5.1 26.6 NO24C 19.8 19.5 9. 3 5.1 29.2 A

O N324B 5. 4 5.1 3. 0 9. 6 32.5 B1 O ,, ,,,,o 13, , i g, , 11,1 , , , , , , ,

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O LEVEL 3 INSTRUMENT TEST DATA DATE OF TEST: 6-3-86 TEST NUMBER : 3 g TIME OF TEST: 1989 RX PRESS  : 500 N994A TEST TRAN RESET SWITCH NO94C N894B t CHANNEL

{} 24.8 NO24A '

9. 6 9. 0 7. 8 ---

A1 26.8 O A2 NO24C 10.2 9. 6 8. 4 ---

6. 0 4. 8

--- 31.5 B1 NO24B 6.75

") --- 23.4 NO24D 13.5 12.6 11.7 B2 O

(TEST TRANSMITTER FAILED DURING TEST)

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o LEVEL 3 INSTRUMENT TEST DATA DATE DF TEST: 6-3-86 TEST NUMBER : 4

,} TIME OF TEST: 2100 RX PRESS  : 500 CHANNEL SWITCH N004C N004B N004A TEST TRAN RESET 73 A1 NO24A

• 12.3 12.0 10.8 9.3* 23.5 r) A2 NO24C 13.1 12.5 11.4 9.49* 27.0 B1 NO24B 11.7 10.95 9. 9 8.25* 31.8

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DATE OF TEST: 6-4-86 TEST NUMBER : 5 TIME Dr TEST: e199

!O RX PRESS  : 9 CHANNEL SWITCH N994C N994B N994A TEST TRAN RESET lQ A1 NO24A ,

10.73 9.45 8. 7 8. 4 21.1

O A2 NO24C 12.9 12.0 11.4 19.8 23.9 B1 NO24B 12.6 11.7 19.8- 19.5 27.1

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d B2 NO24D 14.25 13.95 12.15 11.85 24.6

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