ML20205G312

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Summary of 860718 Meeting W/Util,Cygna Energy Svcs,Static O- Ring,Inc,Gpu & Sargent & Lundy to Discuss Util Test Results of Static O-Ring Switches.List of Meeting Attendees & Viewgraphs Encl
ML20205G312
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 08/04/1986
From: Bournia A
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8608190459
Download: ML20205G312 (67)
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Text

E Docket No. 50-374 LICENSEE: Commonwealth Edison Company (CECO)

FACILITY: La Salle County Station, Unit 2

SUBJECT:

SUMMARY

OF MEETING ON JULY 18, 1986 ith CECO and their contractors, CYGNA ENERGY SERVICES The NRC held a meeting and Static-0-Ring Inc. w(SOR), to discuss CECO's test results of SOR switches.

On July 1, 1986, La Salle County Station, Unit 2 had a reactor feedwater system transient that caused the reactor protection system to drop below the setpoint of the low water level (level 3). Following the observed anomalous operation, CECO initiated an investigation and determined that SOR switches used to per-form this function were the cause of the setpoint to be exceeded. As a result, CECO instigated a more detailed test program to further investigate the cause of this malfunction. The purpose of this meeting was for CECO to present to the staff its findings relative to this test program. A list of attendees is provided in Enclosure 1 and copies of the viewgraphs used by CECO and their representatives during the meeting are presented in Enclosure 2.

In its presentation, Ceco indicated that as a result of the investigation it has determined that these SOR switches malfunctioned because of three effects:

(1) setpoint shift with static pressure up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (these switches are calibrated at atmospheric pressure); (2) setpoint shift with cyclic effect; and (3) due to surface finish and corrosion of cross shaft a repeatability problem occurred. Consequently, CECO in its presentation presented a program at la Salle whereby the shift points for static pressure and cycle effect up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> would be accounted for in its calibration setpoint; for the surface finish of cross shaft which caused repeatability problems, the accountability of this problem would be to test switches numerous times and allowing a band of acceptable repeatability would choose only those switches which fell within this band to be used at the plants; and for the corrosion problem, increase surveil-lances of these switches.

In addition, in the existing calibration procedure after operation, the recorded "as found" calibration was performed after the switch was cycled 2 to 3 cycles.

From this investigation, it was determined that cycling the switches did correct the offset; and therefore, the error when the calibration was performed was more or less wiped out. The revised calibration procedure would only record the "first hit" as "as found" value, thus alleviating the problem of correcting the error.

Alta, an analysis was performed using these new setpoints in the Chapter 15 Analysis, and it was determined that these changes would have minimal effect on the results. The analyses showed that there were large unused margins between the analyzed limit for the parameter and the technical specifications limit.

8608190459 860804 PDR ADOCK 05000374 P PDR

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Consequently, the licensee indicated for the short-term action, that it would:

(1) submit its final report of the SOR switch investigation; (2) complete set-point revision; (3) complete calibrations procedure revisions; and (4) increase surveillance frequency (initial 2-week calibration of level 3 switches) for the corrosion problem. For its long-term actions, it would: (1) determine a SOR switch long-term test; (2) recomend and evaluate SOR switch improvements; (3) decide whether or not alternate level sensing equipment would be use; (4) install improved SOR switches or install alternate level sensing equipment; and (5) evaluate calibrating switches at operating conditions. Consequently, the licensee stated that it believed that it characterized the deviation for its existing switches at site and defined the corrective actions to alleviate the malfunction; it was requesting the staff to allow it to proceed to startup.

CECO specified that it will be ready by July 29, 1986.

The staff indicated that it could not proceed to issue its findings until a formal submittal of a draft report dated July 18, 1986, was submitted. The licensee agreed to supercede this report with a letter by July 24, 1986, addressing all the pertinent i,nformation in order for the staff to make its findings, since it will take sometime before the final report will be issued.

Also, the licensee agreed to respond to the Bulletin on SOR switches issued on July 18, 1986. Finally, the licensee agreed to submit to the staff some tests whereby the switches were held for 2 weeks duration at pressure that were being performed on these switches by SOR, Inc., by July 22, 1986.

Anthony Bournia, Project Manager BWR Pro,iect Directorate No. 3 Division of BWR Licensing l

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Mr. Dennis L. Farrar la Salle County Nuclear Power Station Comonwealth Edison Company Units 1 & 2 cc:

Philip P. Sf5ptoe, Esquire John W. McCaffrey Suite 4200 - Chief, Public Utilities Division One First National Plaza 160 North La Salle Street, Room 900 Chicaao, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatorv Comission Rural Route No.1 P.O. Box 224 Marseilles, Illinois 6134)

Chairman La Salle County Roard of Supervisors la Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 627!;1 Chairman Illinois Comerce Commission Leland Buildina 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Gary N. Wright, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Sprinafield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Reaulatory Comission 799 Rossevelt Road i Glen Ellyn, Illinois 60137

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ENCLOSURE 1

. MEETING ATTENDEES 7/18/86 NAME AFFILIATION Anthony Bournia NRR/ DBL /PD-3 J. T. Beard NRC/NRR/0 RAS R. C. Engel SOR Jim Johnson SOR Roy R. Dunlap SOR Wayne Hodges NRC/NRR/DRL Cordell Reed CECO Kenneth L. Grasser CECO Michael Turbak Ceco Jim Abel CECn Dick Givan Sargent A Lundy Everett Spitzner CECO Martin G. Santic CECO Edward L. Seckinger Ceco Roger Woodruff IE/EAB J. L. Knox NRR/ DBL G. C. Wright NRC/RIII G. C. Lainas NRC/ DBL Ray Ramirez NRC/ DBL Joe Kowalski GPU Nuclear - Dyster Creek R. L. Humphreys Sargent & Lundy E. C. Marinos NRR/ DBL T. Collins NRR/ DBL /FOR N. Trehan NRR/ DBL /EICSB R. Bernero NRR/ DBL R. F. Janecek CECO David L. Rahn CYGNA ENERGY SERVICES E. G. Adensam NRR/ DBL /RWD-3 D. P. Allison IE/ EAR J. N. Donohew NRR/ DBL /BWD-1 George W. Busch GPUN Licensing I

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ENCLOSURE 2

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AGENDA NRC MEETING JULY 18, 1986 LASALLE COUNTY STATION SOR DIFF. PRESSURE SWITCH INVESTIGATION INTRODUCTION CORDELL REED

SUMMARY

JIM ABEL BACKGROUND JIM ABEL SETPOINT CHARACTERIZATION TESTING DAVE RAHN DISASSEMBLY OF SWITCH 2B21-N038B BOB JANECEK JUSTIFICATION FOR OPERATION B0B JANECEK CONCLUSIONS JIM ABEL

INTRODUCTION

1. PREVIOUS t'EETINGS MEETING IN BETHESDA JUNE 12, 1985 DISCUSSED INITIAL SOR TEST PROGRAM MEETING AT LASALLE, JUNE 24, 1986 REVIEW SOR TEST PLAN AND APPARATUS MEETING WITH REGIONAL ADMINISTRATOR JULY 9, 1986 DISCUSSED COMPLIANCE WITH CAL PERSONNEL PERFORMANCE FEEDWATER TRANSIENT INVESTIGATI0fl
2. THIS MEETING WILL ADDRESS HARDWARE WHAT HAPPENED SETPOINT CHARACTERIZATION TESTING JUSTIFICATION FOR UNIT RESTART 4

i 3. LONG TERM ACTIONS e

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OF SOR INVESTIGATION INITIAL INVESTIGATION RESULTS - SWITCH THE SOURCE OF SETPOINT VARIABILITY OBSERVED JUNE 1, 1986 CONCLUSIONS - TESTING REQUIRED TO FULLY CHARACTERIZE SETPOINT VARIABILITY I

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SUMMARY

OF SOR INVESTIGATION SETPOINT CHARACTERIZATION TEST (125 TESTS PERFORMED WITH 8200 MAN-HOURS)

RESULTS - SUBSTANTIAL SETPOINT SHIFT FROM 0 TO 1000 PSI

- SETPOINT REPEATABILITY QUANTIFIED

- DIFFERENCE BETWEEN CALIBRATION CYCLING AND FIRST ACTUATION OBSERVED CONCLUSIONS - RESULTS USED TO REVISE SETPOINTS AND CALIBRATION PROCEDURES SETPOINT CHARACTERIZATION RESULTS VS. LEVFL DROP TEST RESULTS RESULTS - L-3 SCRAM SWITCH RESULTS MATCHED FOR 24 !'0UR TEST AT 1000 PSI VS. LEVEL DROP CONCLUSION - SETPOINT CHARACTERIZATION TESTS ARE ADEQUATE l

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SUMMARY

OF SOR INVESTIGATION DISASSEMBLY AND INSPECTION OF SWITCH 2B21-NO38B RESULT - LARGE SETPOINT VARIATION OBSERVED DURING CALIBRATION CAUSED BY RUSTED CROSS SHAFT BEARING CONCLUSION - SURVEILLANCE PROGRAM WILL DETECT DEGRADED SWITCH PERFORMANCE AND THE SURVEILLANCE PROGRAM HAS BEEN AUGMENTED.

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SUMMARY

OF SOR INVESTIGATION JUSTIFICATION FOR OPERATION ACTIONS -

SWITCH SETPOINTS REVISED TO COMPENSATE FOR STATIC PRESSURE SHIFT  ;

CALIBRATION PROCEDURES IMPROVED TO CLARIFY "AS-FOUND" AND " CYCLING".

SURVEILLANCE FREQUENCY INCREASED SURVEILLANCE REJECTION CRITERIA EXTABLISHED CONCLUSION -

OPERATION JUSTIFIED

- NEW SETPOINTS, CALIBRATION PROCEDURES AND SURVEILLANCE REQUIREMENTS ENSURE SWITCHES FUNCTION AND WILL CONTINUE TO FUNCTION IN ACCORDANCE WITH '

l TECHNICAL SPECIAFICATIONS.

DOCUMENT 40431

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BACKGROUND f

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BACKGROUND A. ON JUNE 1, 1986, THE REACTOR WATER LEVEL DROPPED TO ABOUT 6 INCHES.

B. TECH. SPEC. ALLOWABLE LIMIT FOR OPERATION: 2 11.0" AB0VE INSTRUMENT ZERO C. ONLY ONE OUT OF THE FOUR RPS LEVEL SWITCHES TRIPPED.

1. SWITCHES ARE NORMALLY SET AT 13.4".
2. THEY ARE ARRANGED IN A "0NE OUT OF TWO TAKEN TWICE" LOGIC.

D. LEVEL SWITCHES ARE SOR SERIES 103 DIFF. PRES. SWITCHES, MODEL NO. 103AS-B212-NX-C1A-JJTTX6.

E. 59 SOR DP SWITCHES WERE INSTALLED ON UNIT 2 IN SPRING, 1985, TO REPLACE THE ORIGINALLY INSTALLED BARTON SWITCHES.

1. SERVICE APPLICATIONS:

REACTOR WATER LEVEL ............ 23 ECCS MINIMUM FLOW ............... 8 LINE BREAK DETECTION ........... 28 F. TABLE 11-1 IDENTIFIES ALL SOR DP SWITCHES INSTALLED ON UNIT 2.

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DESCRIPTION OF RPS LEVEL SWITCHES STATIC-0-RING MODEL 103-AS-B212-NX-C1A-JJ-TTX6 NOMINAL PRESSURE -

1000 PSI SETPOINT INST. ZER0 ACTUAL COLUMN DP CALIBRATION 13.4 INCH 63.15" WC NOMINAL SETPOINT 12.5 INCH 63.78" WC TECH SPEC LIMIT 11.0 INCH 64.84" WC REFERENCE WATER COLUMN HIGHER THAN VARIABLE WC (DECREASING LEVEL CAUSES INCREASING DP)

DIAGRAM 0F SWITCH t .

INCHES TECH. SPEC . INSTR.

ABOVE- SET POINT 6P VESSEL INCHES INCHES ZERO ABOVE WATER INSTR.

ZERO DRYER MAIN - 648 STEAM k-- - ,,,

,7 {T,{,{," ,, LEVEL 8- 583 55.5 33.5 LEVEL 3- 540 12.5 63.8 kR

- - - - - - - 527.5 O INSTRUMENT -

ZERO LEVEL 2- 477.5 -50 14 5.6 LEVEL 1- 398.5 -129 202.2

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VESSEL LEVEL

SUMMARY

(SOR APPLICATIONS ONLY)

I I I i I I 8 1 55.5 l_B21-N101A(1. B(2) l SHUTS DOWN RCIC TURBINE I I I I B21-N100A(1). B(1) i CLOSES HPC5 INJECTION I l i I I I 3 l 12.5" l B21-N024A-D l PCIS GR, 6 & 7 I I

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l l l B21-N038A, B l ADS LOW LEVEL CONFIRMATION l I I I I I l l -50" l B21-N026AB BB, CB. DB. I PCIS GR. 1, 2. 3, 4 &5 I I 2 l l B21-N031A-D l INITIATE HPCS I I I I I START DIV. 3 D/G l 1 l l B21-N037AB, BB, CB, DB l INITIATE RCIC i i l l l I I I I I I i 1 1 -129" i B21-N037AA, CA I INITIATE LPCS I I I I I INITIATE "A" RHR I I I I I INITIATE "A" ADS I I l l l START DIV. 1 D/G l i I I B21-N037BA, DA 1 INITIATE "B" & "C" RHR 1 l l l l INITIATE "B" ADS I I I I I START DIV. 2 D/G I I I I I I

(1) THESE INSTRUMENTS ARE BARTONS ON BOTH UNIT 1 AND UNIT 2 (2) SOR ON UNIT 2: BARTON ON UNIT 1 9

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l SOR DIFFERENTIAL PRESSURE SWITCH A. SWITCH OPERATION l

o THE SOR DP SWITCH IS A DIAPHRAGM-0PERATED MECHANICAL-LINKAGE-ACTUATED SWITCHING DEVICE.

o THE FORCE ON THE HIGH PRESSURE SIDE OF THE DIAPHRAGM IS OPPOSED BY THE FORCE OF AN ADJUSTABLE RANGE SPRING.

o WHEN THE RESULTANT FORCE ON THE DIAPHRAGM DUE TO THE DIFFERENTIAL PRESSURE EXCEEDS THE RANGE SPRING FORCE, THE DIAPHRAGM MOVES THE CROSS SHAFT TO OPERATE A SWITCH.

B. REACTOR VESSEL LEVEL APPLICATION o TRIPS ON DECREASING LEVEL o HIGH PRESSURE SIDE IS AT CONSTANT PRESSURE o LOW PRESSURE SIDE IS CONNECTED TO THE COOLANT REGION OF THE VESSEL o DECREASING LEVEL RESULTS IN INCREASING DP C. LINE BREAK APPLICATION .

o TRIPS ON INCREASING FLOW TO ISOLATE LINE o CONNECTED ACROSS A FLOW-SENSING ELEMENT o A LINE BREAK WILL CAUSE DP ACROSS THE FLOW ELEMENT TO AT LEAST DOUBLE THAT FOR NORMAL FLOW.

D. ECCS MINIMUM FLOW APPLICATION

o TRIPS ON DECREASING FLOW TO OPEN MINIMUM FLOW VALVE o CONNECTED ACROSS A FLOW-SENSING ELEMENT o AT NORMAL ECCS FLOW THE DP GREATLY EXCEEDS THE RANGE OF THE SWITCH i

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SOR DIFFERENTIAL PRESSURE SWITCH (CONT'D)

E. CALIBRATION METHOD o ISOLATE SWITCH, EQUALIZE DP, AND REDUCE STATIC PRESSURE TO ZERO ,

o CONNECT PRESSURE SOURCE TO HIGH PRESSURE SIDE AND VENT LOW PRESSURE SIDE T0. ATMOSPHERE o INCREASE PRESSURE UNTIL SWITCH TRIPS. THEN REDUCE PRESSURE UNTIL IT RESETS o ADJUST SETPOINT AS NECESSARY AND REPEAT PROCESS

o RECORD AS FOUND AND AS LEFT SETPOINTS I

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INITIAL INVESTIGATIONS

1. INSTRUMENT PIPING AND INSTRUMENT RACKS INSPECTED.
2. SWITCH INSTALLATION REVIEWED.
3. CALIBRATION METHOD EXAMINED.
4. CALIBRATION DATA REVIEWED.
5. SOR PERFORMANCE AND CONSTRUCTION TEST DATA REVIEWED.
6. REACTOR LEVEL DROP TESTS PERFORMED.

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REACTOR LEVEL DROP TESTS A. PURPOSE: REPRODUCE THE ANOMALOUS SWITCH OPERATION B. TEST DESCRIPTION:

1. RPV WATER LEVEL WAS LOWERED UNTIL ALL FOUR RPS SWITCHES TRIPPED.
2. A RECORDER MONITORED THE OUTPUT OF EACH LEVEL SWITCH AND RPV WATER LEVEL. THE RPV LEVEL WAS MONITORED ON FOUR ROSEM0UNT DP TRANSMITTERS, ONE AT EACH RACK.
3. AS EACH SWITCH TRIPPED, THE LEVEL READINGS AT EACH RACK WERE RECORDED.
4. BETWEEN JUNE 2 AND 5, 1986, SIX LEVEL DROP TESTS WERE PERFORMED - TWO EACH AT REACTOR PRESSURES OF 950,500, AND 0 PSIG.

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INITIAL CONCLUSIONS THE LOW WATER LEVEL SCRAM SWITCHES DID NOT TRIP ON JUN 1 BECAUSE THE SETPOINTS OF THE SWITCHES CHANGE BETWEEN CALIBRATION AND OPERATING CONDITIONS.

o NO SIGNIFICANT PROBLEMS WERE IDENTIFIED WITH THE INSTRUMENT PIPING, SWITCH INSTALLATION, OR CALIBRATION PROCEDURE.

o A SMALL DIFFERENCE IN THE CONDENSING CHAMBER ELEVATIONS WAS FOUND.

o LEVEL READINGS DURING THE LEVEL DROP TESTS WERE NOT THE SAME BETWEEN THE RACKS AT THE SAME TIME (SEE TABLES IV-1 THRU IV-6) o A DRYWELL SURVEY FOUND A 1.8" DIFFERENCE BETWEEN THE HIGH AND LOW CHAMBERS (SEE TABLE IV-9) o THE SWITCH SETPOINTS INCREASE AS STATIC PRESSURE INCREASES.

o IN THE LEVEL DROP TESTS, THE AVERAGE TRIP POINT OF THE SWITCHES WAS ABOUT 3" W.C. HIGHER AT 950 PSIG THAN AT

0. (SEE TABLE IV-7) o SOR FACTORY . TEST DATA ALSO SHOWS THIS EFFECT (SEE TABLE IV-8) o THE CALIBRATION DATA SHOWS THAT THE SETPOINT DECREASES BY 0.5 TO 1.5" W.C. DURING CYCLING FROM THE "AS 'FOUND" VALUE.

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SETPOINT CHARACTERIZATION TESTING e

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SETPOINT CHARACTERIZATION TESTING

1. HYP0 THESES TESTED A. SETPOINT SHIFT WITH STATIC PRESSURE AND TIME B. CALIBRATION "AS-FOUND" VS. "AS-LEFT" DUE TO CYCLING
2. DESCRIPTION OF TESTING PROCEDURES
3. DESCRIPTION OF TESTING APPARATUS
4. TEST RESULTS A. RESULTS PER SOR APPLICATION LEVEL 1, LEVEL 2, LEVEL 3, ETC.

B. COMPARIS0N OF SETPOINT CHARACTERIZATION TESTING RESULTS AND SYSTEM TEST RESULTS

1) LEVEL DROP TESTS
2) MINIMUM FLOW TESTS .
5. TEST CONCLUSIONS A. STATIC PRESSURE SHIFT QUANTIFIED AND REVISED SETPOINTS DETERMINED B. CYCLING UNDERSTOOD AND CALIBRATION PROCEDdRE CHANGES WILL ADDRESS IT C. SETPOINT REPEATABILITY ENVELOPED AND INCLUDED IN REVISED SETP0 INT REJECTION CRITERIA D

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TESTING PROCEDURE l

TEST 1 - STATIC PRESSURE EFFECT TEST 2 - COMBINED STATIC PRESSURE AND CYCLING EFFECT TEST 3 - SLOW APPROACH TO SETPOINT TEST 4 - TIME RELATED EFFECTS 7-MINUTE STABILIZATION AT ELEVATED PRESSURE 30-MINUTE STABILIZATION AT ELEVATED PRESSURE 4-HOURSTABILIZATIONATELEVATEDPR$$SURE 24-H00R STABILIZATION AT ELEVATED PRESSURE j 48-HOUR AND 72-HOUR AT ELEVATED PRESSURE e

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Test 1: Static Pressure Effect Figure V.2 (Combined with Cycling) n First actuation Ortt actuation static pressure l o ~. '

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Test 2: Cycling Effect at Elevated Static Pressure Figure V-3 d

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Deerene - snere.,e DP p

DP Deadweight l II II l l I 1I II 1

6959-3 07 86 - 395 V-13

- @a_amm _8aanat

SETPOINT CHARACTERIZATION TESTING RESULTS S.0.R. A SWITCH APPLICATIONS AT LASALLE STATION PARAMETER S.O.R. MODEL ADJ. RANGE QUANTITY OF SWITCHFS

. REACTOR LEVEL 3 103-B212 7-100" W.C. 4 RPS -- SCRAM

_2 ECCS -- ADS PERMISSIVE 6 TOTAL

. REACTOR LEVEL 2 103-B203 20-200" W.C. 4 RCIC -- INITIATION 4 HPCS -- INITIATION 103-BB203 20-200" W.C. _a MSIV/ CONTAINMENT ISOLATION 12 TOTAL

, REACTOR LEVEL 1 103-BB205 40-300" W.C. 2 ADS,LPCS,LPCI A DIV. 1 NIT.

_2 ADS,LPCI B,C DIV. 2 INIT.

4 TOTAL

. REACTOR LEVEL 8 103-B212 7-100" W.C. _1 RCIC TURBINE TRIP (HIGH LEV.)

1 TOTAL

. RHR/RCIC STEAM 103-B203 20-200" W.C. 4 LINE BREAK RCIC STEAM LINE 103-B203 20-200" W.C. 4 BREAK RHR-SHUTDOWN 103-B203 20-200" W.C. _a COOLING LINE 12 BREAK

i. ECCS MINIMUN 103-B202 5-35" W.C. 5 VALVE CONTROL FLOW VALVE _I ALARM 8 TOTAL

. MAIN STEAM LINE 102-B305 100-500 PSID 16 TOTAL (PISTON)

BREAK GRAND TOTAL 59 l

g;a;10-0 .331Il7 ll;:erelLlal reSSure u e n . ,

n awi;01 v,) era)i.i;y les; ,Ja;a ..

60-M-1-32M ; Spare 1203'i 3 '2n '83 j Test #4e (Full Operational Test) m 61 4 O b2 ! -

Existing Allowable Tolerance

.  : , Lower Lusit (b2.51) 3 E

~

b3-5, ............... ...........................................e D e s i y e d S e t P o i n t ( b 3 . 151 o  : - Existing At tomble Tolerance a b 4 2' ' IJppu Luai t (b 3. 761 11. T. 5. P.

Y $ $

-- 65=

o 2 O_ E 66 5 -

+' =

CLI  : .

a-) 671 # ~7=b # ~-

,3-%g=

g e= -

=.,a w-I I I I I I I I I 68 i 2 3 4 5 6 7 8 9 10 Actuation l_ c,.i . 7 a ,. >> h-- ci i 5 "*** e >> H vc i a a >> I - - ' i " "**a e i>> l l _._ c,. i. i a ,. .. H c,.i. 1 e u.. ,.i - p c, .i . : <. , .: . l -,- c, . i. . u o ,.. . . p c,.i. s a ,. .. p o.. . t 3

a... ,.. .. l

. k, a a.c - 0 h.ng i. ..erenaa ,ressure .

Swi:ci 0) era)ility Tes; Da a >

q'10 - n 9 .; , c.

na 4 Jh.

~

(! W U ] Op u h6 Ud -

60- -

E Test #1 (Static Pressure Effect) 5 m bi ~

(_.) 625  : Existing Allowable Tolerance -

e  :

, Lower Lt. net (62.51) 3 E b3-5p........................... ........ ....................'s D e s i r e d Se t Po i n t ( 6 3.15 )

  • Existing Allowable Tolarance

[. --

  • 64 : _g ~ _ _ .:d

~_,.4 - _ _ _ ,

- -,.  ; Upper Litait (63.70) I. 1. S. P.

__ _ -,,g

, ..cq,s 4=5 g

- 659 [

p- ----

o E ct E 66 i e E .

GI E US 67 E -

E 5 ' ' ' ' ' ' ' ' '

68

. 1 2 3 4 5 6 7 8 9 10 HC Illa I I Ori -

j _c,.i. , a .... p c,.i. u... ,... p cy.. .c. ,. ,,l_.-c,.. . a u... ,. ,il y c,..i a ,.. p c,a.2 a... ,... p cya.: a , .. ., p cy a . u u. ,.. . p cr a. s a ,. ., p c,a. . u... ,. . l .

e

S;alic-0-i(ina, Ji:"eren:.ial 'ressure .

  • q =a ,

b1 r)es; Ja a ..

WliC.1 oo n o.n n n Nu U) ,

f.era')llliy

.0 w 'o

  • 'or/ .

58-Test #2 (Hysteresis,1000 psig) 592

, ' * -+- b+-e __,__ o __ g 8 O 602 w -

2 bil

"' 62 2

) o - Existing Allowable Tolerance q -,....................................... .................................y L ou e r L i .To t ( 6 2. 51 )

P g3 - Desired Set Point (63.15) g  %...................................._..........._............._..-o 4 ~~'"-'

< Existing Allowable Tolerance

~

.h,- -

...................................g Up p e r L un i t ( b3. 7 0 ) N. T. S. P.

.... g ., , , ,

~

O_ .

e 65:

rn i W 662 1 I I I l l l l l l l  ! l I I I -l I l i i l l 1  ! l l l l h7 1 3 5 7 9 11 13 15 17 19 Cycles 1 & 3 exercise switch s starting from 0 " AP HCIUaI.I O Tl Cycles 2 L 4 exercise snitch startiog from 200 " sP l .+ cy.i . l _,_ cy.i. l + cy.i. x l + cy.i. 4 l

TEST RESULTS REACTOR WATER LEVEL 3 SWITCHES (100% SAMPLING) i (STATIC-0-RING MODEL B212 - 7" - 100" W.C. ADJUSTABLE RANGE)

SWITCH TRIP P0INTS SHIFTED NON-CONSERVATIVELY FROM AS-LEFT CONDITION BY A RANGE OF 2.2" TO 6.1" W.C.

NEW SETPOINTS WERE CALCULATED USING MAXIMUM ACCEPTABLE STATIC PRESSURE SHIFT OF 3.0" W.C.

SWITCHES WITH MORE THAN 3.0" W.C. -

STATIC PRESSURE SHIFT WERE REPLACED WITH ACCEPTABLE NEW SWITCHES.

9 9

COMPARISON OF LEVEL DROP TEST DATA WITH SETPOINT CHARACTERIZATION TEST PROGRAM DATA FOR REACTOR WATER LEVEL 3 SWITCHES

(" W.C. AT SWITCH)

SWITCH NUMBER 2B21-N024A 2B21-N024B 2B21-N024C 2B21-N024D LEVEL DROP 66.1 69.7 67.6 65.3 TEST 1 (1000 PSIG)

TEST PROGRAM 66.0 69.2 68.3 65.6 STATIC SHIFT (TIME T = 24 HOURS)

DESIRED TRIP POINT WAS 63.1" W.C.

I l

1 l

1 1

DOCUMENT 4043I

~. . _. _

TEST RESULTS REACTOR WATER LEVEL 2 AND 1 SWITCHES (STATIC-0-RING MODELS B203 200" W.C. ADJUSTABLE RANGE B205 300" W.C. ADJUSTABLE RANGE)

- 24-HOUR TESTING WAS PERFORMED ON A SAMPLE OF SWITCHES, BASED ON WORST AND BEST PERFORMERS ON OPERATIONAL TESTS (TESTS 1 AND 2)

(44% SAMPLING)

WORST PERFORMERS SHOWED LARGEST SHIFT IN 24-HOUR TESTS

~

24-HOUR TEST SWITCHES EXHIBITED NON-CONSERVATIVE STATIC PRESSURE SHIFT IN TRIP POINT (RANGE 2.5 - 6.0" W.C.)

- NEW SWITCH SETPOINTS WERE CALCULATED, USING 8.0" MAXIMUM ACCEPTABLE STATIC PRESSURE SHIFT e

l

[._

TEST RESULTS REACTOR WATER LEVEL 8 SWITCH (STATIC-0-RING MODEL B212 - 7" - 100" W.C. ADJUSTABLE RANGE)

ONLY ONE SOR SWITCH IS USED AT LASALLE FOR THIS APPLICATION STATIC PRESSURE SHIFT FOUND TO BE 3.4" (NON-CONSERVATIVE) ,

NEW SETPOINT CALCULATED FOR 2B21-N101B USING STATIC PRESSURE OFFSET 9

TEST RESULTS RHR/RCIC PROCESS LINE BREAK DETECTION SWITCHES STATIC-0-RING MODEL B203 - 20" - 200" W.C. ADJUSTABLE RANGE)

ALL SWITCHES PERFORMED WELL DURING OPERATIONAL TESTS (ONLY 1.5 -

2" W.C. STATIC PRESSURE SHIFT)

TIME TEST PERFORMED ON ONE SWITCH (8.3% SAMPLE)

SWITCH EXHIBITED SLIGHT CONSERVATIVE TRIP POINT SHIFT (APPR0XIMATELY 6" W.C.)

NEW SWITCH SETPOINT WAS CALCULATED USING 8" NON-CONSERVATIVE STATIC PRESSURE SHIFT FOUND IN REACTOR WATER LEVELS 2 AND 1 SWITCH TESTS

TEST RESULTS MAIN STEAM LINE BREAK DETECTION SWITCHES (STATIC-0-RING MODEL 102 SERIES SWITCH - 100 PSID - 500 PSID ADJUSTABLE RANGE)

- ALL SWITCHES PERFORMED WELL DURING TESTS 1 AND 2: HOWEVER, SOME SWITCHES WERE FOUND TO BE LESS REPEATABLE THAN OTHERS SWITCHES WITH WORST REPEATABILITY PERFORMED WORST WITH RESPECT TO STATIC SHIFT ERROR. NON-CONSERVATIVE STATIC PRESSURE SHIFTS FROM 2 TO 10 PSID WERE OBSERVED.

NEW SWITCH SETPOINTS WERE CALCUALTED USING MAXIMUM ACCEPTABLE STATIC PRESSURE SHIFT OF 6 PSID.

SWITCHES WITH MORE THAN 6 PSID STATIC SHIFT ERROR WERE REPLACED.

DOCUMENT 4043I

TEST RESULTS E:CS MINIMUM FLOW VALVE CONTROL SWITCHES (STATIC-0-RING MODEL B202 SWITCHES - 5" - 35" ADJUSTABLE RANGE)

SWITCH SETPOINT WAS FIRST REVISED VERY CONSERVATIVELY TO ENSURE ACHIEVEMENT OF VALVE OPENING SWITCHES WERE TESTED MULTIPLE TIMES IN SYSTEM OPERATIONAL TEST USING NEW SETPOINTS AND PERFORMED WELL SAMPLE OF SWITCHES (20%) WERE TESTED FOR TIME / STATIC PRESSURE EFFECTS TO VERIFY THAT AMOUNT OF STATIC SHIFT IS SMALL WHEN COMPARED TO MARGIN ACHIEVED BY RAISING SETPOINT MAXIMUM STATIC 0FFSET OF 1.5" WAS FOUND (ACCEPTABLE)

- REJECT LIMIT OF 4" WAS ESTABLISHED, BASED ON SWITCH REPEATABILITY DATA J

DOCUMENT ID 4044I/

ECCS MINIMUM FLOW VALVE CONTROL SYSTEM PERFORMANCE TEST RESULTS LOWEST TESTED SYSTEM / SWITCH OLD SETPOINTS NEW SETPOINTS NOMINAL TECH SPEC TRIP POINT

("W.C./GPM) ("W.C./GPM) (GPM) (GPM)

LPCS/2E21-N004 .11.0/1189 23.0/1719 640 1414 HPCS/2E22-N006 10.0/1015 23.0/1540 900 1296 LPCI-A/

,2E12-N010AA 6.2/1026 23.0/1977 550 1785 LPCI-B/

2E12-N010BA 6.2/1026 23.0/1977 550 1658 LPCI-C/

2E12-N010CB 6.2/1026 23.0/1977 550 1695 l

9 DOCUMENT ID 4044I/

l l

SETPOINT METHODOLOGY CALIBRATION SETPOINT EW CALIBRATION ~

(CALIBRATION CONDITIONS) ROCEDURE SETPOINT MARGIN FOR REPEATABILITY (CilARACTERIZAlION 1EST #1)

NOMINAL SETPOINT J l' (CALIBRATION CONDITIONS) ) t

( MARGIN FOR DRIFT

) (EXISTING TECH. SPEC.)

ALLOWABLE VALUE J NEW CALIBRATION TECH. SPEC. LCO PROCEDURE

! (CALIBRATION CONDITIONS) 3 .

MARGIN FOR STATIC REJECTION LIMIT PRESSURE SHIFT ALLOWABLE VALUE J -

TECH.' SPEC. LCO (OPERATING CONDITIONS) MARGIN FOR PROCESS, INSTRUMENT LOOP, AND

, CAllBRA110N INACCURACIES s

ANALYTICAL LIMIT

SETPOINT CHARACTFRI7ATION TFSTIM[i .

EDNCIUSIONS SWITCH APPIICATION I MARGIN FROM iCo i l l EXIS11NG TECH I '

I STATIC SHIFT l REPEATABil ITY I SPEC. DRIFT I TOTAL 1 I I I

-REACTOR VESSEL LEVEL 3 1 4.2" RWL I 2.6" RWL i 1.5" RWL I 8.4" RWL i F l 1

-REACTOR VESSEL LEVEL 2 l 11.2" RWL i 5.0" RWL I 7.0" RWL I 23.2" RWL

. I I l l I 25.5" RWL

-REACTOR VESSEL LEVEL 1 1 11.2" RWL I 7.3" RWL I 7.0" RWL I I I i

-REACTOR VESSEL LEVEL 8 I 5.0" RWL i 2.6" RWL I 0.5" RWL l 8.1" RWL I l l 1

-RHR/RCIC STEAMLINE BREAK I 8.0" RWL I 3.6" RWL I 5.0" RWL i 16.6" RWL i l I i

-RHR SHUTDOWN COOLING LINE I 8.0" RWL i 3.6" RWL I 6.0" RW1. I 17.6" RWL l l I I

-RCIC STEAM LINE BREAK I 7.2% RA1ED FLOWI 3.0% RATED FLOW l 5.0% RATED FLOW l 15.2% RATED I I l l FLOW l I I I

. -RHR LPCIeA,B,C MIN. FLOW I 187 GPM i 42 GPM l 450 GPM i 1427 GPM I I I I

-LPCS MIN. FLOW I 233 GPM i 39 GPM I 110 GPM i 1079 GPM' -

I I I I

-HPCS MIN. FLOW l 151 GPM i 27 GPM i 100 GPM i 640 GPM" l I l I

-MAIN STEAM LINE HI FLOW I 5.5 PSID I 3.0 PSID l 5.0 PSID 1 13.5 PSID j l I I I NOTES: INCLUDES ADDITIONAL MARGIN OF 1) 748 GPM FOR LPCI 2) 697 GPM FOR LPCS AND 3) 362 GPM FOR HPCS DOCUMENT 40431

i .

  • e 8 8

4 i

n DISASSEMBLY AND INSPECTION OF SWITCH 2B21-N038B t

2B21-N038B CALIBRATION HISTORY APRIL 18, 1985 INITIAL 63.4/57.4 IN W.C.

JUNE 17, 1986 A.M. AS FOUND 88.0/56.9 AS LEFT 63.1/56.7 JUNE 17, 1986 P.M. AS FOUND 67.4/58.5 AS LEFT 63.1/50.7 ,

[

e 5

DOCUMENT ID 40441/

L _

2B21-N038B DISASSEMBLY AND INSPECTION LASAltF LASAlLE o CALIBRATION CHECK o CROSS SHAFT TRAVEL CHECK o DISASSEMBLY AND VISUAL INSPECTION 10R o, OPTICAL INSTRUMENT INSPECTION o DETAILED MEASUREMENTS o QUALITATIVE AND QUANTITIVE ANALYSIS o REASSEMBLY o HELIUM LEAK TEST l

l l

DOCDENT ID 40321 - .

c , ,

2B21-N038B FINDINGS o SPRING-END BEARING - CORRODED o SWITCH-END BEARING - GOOD o CROSS SHAFT - DEPOSITS

- SCRATCHES o "0" RINGS - GOOD

- DEPOSITS o LOWER SPRING SEAT - NO ABNORMAL WEAR

- LOOSE SPRING FIT o SPRING RETAINER /ADJ. CAP - DEPOSITS

~

o ADJUSTMENT SCREW - BURR

- DEPOSITS o LOW - PRESSURE BODY BORE - GOOD o SPRING - GOOD l

DOCWHWT ID 40321 l

l CONCLUSIONS o ERRATIC BEHAVIOR CAUSED BY CORRODED BEARING o SOURCE OF M0ISTURE CAUSING CORROSION NOT IDENTIFIED DISTRIBUTION OF RUST. SUGGESTS INTERNAL SOURCE o SUBSTANTIATED BY DAMAGE INSPECTION REASSEMBLED SWITCH PASSED HELIUM LEAK TEST FOREIGN MATERIAL MAY HAVE BEEN DISLODGED NOT EFFECT OPERABILITY ONLY EFFECT EASE OF ADJUSTNENT o OTHER CONCERNS AFFECTING ADJUSTMENT o C0 ARSE THREAD / LOOSE FIT - ADJUSTMENT SCREW / RETAINER o SPRING / WASHER LOOSE FIT COULD BE EFFECTED BY VIBRATION ~

MAY CAUSE SOME DRIFT o SURVEILLANCE TESTING WILL DETECT l

s e

DOCUMENT 4043I

  • e
  • e . .
  • e e

1 l

l l

JUSTIFICATION FOR OPERATION e

a e

4

X-1 CAtIPRATION PROCEDURES

. EXISTING PROCEDURES ,

, RECORDED "AS FOUND" AFTER 2-3 CYCLES

. CYCLED AROUND TRIP / RESET POINTS

. "AS FOUND" VALUE INACCURATE BY 1-2" WC

. REVISIONS -

. RECORD "FIRST HIT" AS "AS FOUND" VALUE

. ALL ACTUATIONS CYCLED FROM ZERO (OR FULL SCALE) DP

. PREVENT UNNECESSARY OVER/UNDER RANGING

. NEW SETPOINTS

. ACCEPTABLE BAND DEFINED .

. WORST ACCEPTABLE SHIFT i 2 a - BAND LIMIT

. BAND LIMIT BASED ON AVAILABLE MARGIN l

l  :

\

l DOCUMENT ID 4007i/ .

X-3 SURVEILLANCE FREQUENCY

. PRIOR TO STARTUP

. ESTABLISH ACTION LIMITS

. ESTABLISH REJECT LIMIT

. TWO WEEKS AFTER STARTUP

. CALIBRATE ALL LEVEL III

. CALIBRATE SAMPLES OTHER MODELS

. INCREASE INTERVAL BY MONTHLY INCREMENTS (INTERVAL NOT GREATER THAN 3 MONTHS)

. DECREASE INTERVAL

. WHEN DRIFT GREATER THAN ACTION LIMIT

. REPLACE SWITCH

. DRIFT BEYOND REJECT LIMIT

. TWO SUCCESSIVE DRIFTS BEYOND ACTION LIMIT O

e DOCUMENT 40431

, \

X-2 REVISED SETPOINTS

. ACCEPTABLE BAND ON CONSERVATIVE SIDE OF NTSP

. ASSURES ACTUATION POINT CONSERVATIVE

. RETAINS EXISTING DRIFT ALLOWANCE BETWEEN NTSP AND LC0

. NEEDED FOR:

. LEVELS 3, 2, 1, AND 8

. ECCS MINIMUM FLOW VALVES

. :4SL HIGH FLOW ISOLATION

. RHR HIGH SUCTION FLOW ISOLATION

. RHR/RCIC HIGH STEAM FLOW ISOLATION (1)

. RCIC HIGH STEAM FLOW ISOLATION

. NO TECH SPEC CHANGES REQUIRED AT THIS TIME r

i l

  • DOCUMENT 4043I

X-4 ACCEPTANCE CRITERIA

. DERIVED AS SHOWN IN FIGURE X-1

. STATIC 0FFSET BAND

. REPEATABILITY

. ABOUT STATIC SHIFT

. ABOUT 0 PSIG CALIBRATION POINT

. NEW SWITCHES

. TESTED BY VENDOR PRIOR TO SHIPMENT

. STATIC SHIFT

. REPEATABILITY

. RECALIBRATION AFTER INSTALLATION - REPEATABILITY

. EXISTING SWITCHES

. TEST PROGRAM RESULTS

. STATIC SHIFT f . REPEATABILITY

. RECALIBRATION - REPEATABILITY (AS REQUIRED) e DOCUMENT ID 4044I/

X-5 ACCEPTANCE CRITERIA (CONT'D)

. SURVEILLANCE TESTING

. O PSIG CALIBRATION

. CALIBRATION ACTION LIMIT

. EXCEED ONCE - TREND

. EXCEED TWO CONSECUTIVE TESTS - REJECT

. REPLACE

. DISASSEMBLE / INSPECT

. CALIBRATION REJECTION LIMIT

. EXCEED ONCE - REJECT

. REPLACE

. DISASSEMBLE / INSPECT

. PRELIMINARY VALUES (TABLE X-4) e e

DOCUMENT 4043I

SETPOINT METil0DOLOGY ,'

CALIBRATION SETPOINT NEW CALIBRATION '

(CALIBRATION CONDITIONS) PROCEDURE SETPOINT MARGIN FOR REPEATABILITY a (CilARACTERIZATION lEST #1)

NOMINAL SETPOINT J (CALIBRATION CONDITIONS) )

( MARGIN FOR DRIFT

) (EXISTING TECil. SPEC.)

ALLOWABLE VALUE J NEW CALIBRATION TECil. SPEC. LC0 PROCEDURE (CALIBRATION CONDITIONS)

D MARGIN FOR STATIC REJECTION LIMIT PRESSURE SHIFT

! ALLOWABLE VALUE  ;

, TECil. SPEC. LCO 3 l (OPERATING CONDITIONS) l MARGIN FOR PROCESS, d

INSTRUMENT LOOP, AND i k CALIBRA110N INACCURACIES s

ANALYTICAL LIMIT

e a a G.E. SETPOINT LIMIT EVALUATION

. DETERMINE BOUNDING ANALYTICAL LIMITS

. DETERMINE OPERATIONAL LIMITS

. ANALYTICAL LIMITS

. DERIVED FROM FSAR ACCIDENTS / TRANSIENTS

. PART OF SAFETY ANALYSIS

. PREVENT EXCEEDING SAFETY LIMITS

. OPERATIONAL LIMITS

. CONSIDER PLANT AVAILABILITY

. PROVIDE MANEUVERING RANGE TO AVOID SCRAMS

. EVALUATION BASIS

. LIMITING LOCA (DBA).- RECIRC SUCTION BREAK

. LIMITING SMALL BREAK LOCA APPROVED MODELS - SAFE /REFLOOD, CHASTE APPROX.

. STANDARD LSCS INST.. DELAY TIMES

. NEW INSTRUMENT ANALYTICAL LIMITS

. LEVEL SETP0INTS

. ECCS PUMPS MIN. FLOW VALVES DOCUMENT ID 4044I/

e " . ., ,

TABLE X-1 ANALYTICAL LIMITS ON LEVEL Level Trip Used in Used in Points Previous Analysis This Analysis L3 7.5" RWL - 10.5" RWL -

L2 -70" RWL - 97.9" RWL L1 -149.5" RWL -161.5" RWL TABLE X-2 ,

PEAK CLAD TEMPERATURES Updated New Level New Level Case FSAR Analytical Limit Analytical Limit Analyzed Analysis (current Flow) (Reduced Flow *)

No . Estimated DBA 2019'F Significant '2050*F change Worst No Small 1736*F Significant 1794*F Break Change

  • Reduced ECCS flow means that flow injected into the vessel when the minimum-flow bypass lines are fully open; i.e., the rated ECCS pump flow minus the full capacity of the minimum flow line. ,

1

TABLE X-3 POTENTIAL RANGES WITH REVISED ANALYTICAL LIMITS POTENTIAL RANGES POTENTIAL RANGES WITH EXISTING WITH REVISED ANALYTICAL LIMITS ANALYTICAL LIMITS REACTOR LEVEL LEVEL 3 7.5" TO 29.5" RWL -10. 5 (1) " TO 29.5" RWL LEVEL 2 -70.5" TO -10.5" RWL -97.9" To -10.5" RWL LEVEL 1 -149" To -114.7" RWL -161.5" To -111.7" RWL RCIC/RHR STEAM FLOW ISOLATION 114" W.C. TO 88.1" W.C. 200" W.C. (2) TO 88.1" W.C.

MSL HIGH FLOW ISOLATION 123.5 PSID TO 99 PSID 178 PSID TO 99 PSID RHR SUCTION HIGH FLOW ISOLATION 121.5" W.C. TO 82.6" W.C. 200" W.C. (2) TO 82.6" W.C.

RCIC HIGH FLOW ISOLATION 200" W.C. (2) TO 200" k.C. (2) TO 170.5" W.C. 170.5" W.C.

'HPCS/RCIC HIGH REACTOR ,

WATER LEVEL 60" TO 42.5" RWL 71.5" TO 42.5" RWL MIN. FLOW VALVE OPERATION RHR OPEN
< SPECIFIED FLOW OPEN: < SPECIFIED FL0t-LPCS HPCS CLOSE: WHEN FULL FLOW CLOSE: NOT REQUIRED INJECTION RE0'D l

l

"> ELEVATION OF LOWER INSTRUMENT TAP (2) UPPER END OF RANGE LIMITED BY INSTRUMENT RANGE l

l DOCUMENT 4043I

. . ~ . \

e

  • e

~

CONCLUSIONS SOR INVESTIGATION SIGNIFICANT SETP0 INT SHIFT FROM CALIBRATION PRESSURE TO OPERATING PRESSURE l

SETPOINT SHIFT WITH PRESSURE COMPLETE AFTER 24 HOURS j

- SETPOINT SHIFT WITH PRESSURE DETERMINED FOR EACH SOR APPLICATION AND INCLUDED IN REVISED CALIBRATION PROCEDURE

- EFFECT OF CYCLING ON VALID "AS-FOUND" AND "AS-LEFT" CALIBRATION

- CALIBRATION PROCEDURES REVISED TO REQUIRE APPROPRIATE CALIBRATION CYCLING TO ACHIEVE VALID "AS-FOUND" AND "AS-LEFT" SETPOINTS-

- THESE SEiP0lNT AND CALIBRATION METHOD REVISIONS ENSURF THE SWITCHES WILL TRIP WITHIN TECHNICAL SPECIFICATION LEilTS

- THE G.E. ANALYSES SHOW LARGE UNUSED MARGIN BETWEEN THE ANALYZED LIMIT FOR THE PARAMETER AND THE TECHNICAL SPECIFICATION LIMIT o

e

o TE ~ . .

. i.

SHORT-TERM ACTIONS SUBMIT FINAL REPORT OF SOR INVESTIGATION COMPLETE SECOND FLOW TEST OF ECCS MINIMUM FLOW SWITCHES AT NEW ..'

SETPOINT.

- COMPLETE REACTOR WATER LEVEL DROP TEST OF LEVEL 3 SWITCHES

- COMPLETE SETPOINT REVISION COMPLETE CALIBRATION PROCEDURE REVISIONS INCREASE SURVEILLANCE FREQUENCY (INITIAL 2-WEEK CALIBRATION OF LEVEL 3 SWITCHES)

COMPLETE EVALUATION OF ALTERNATIVE LEVEL SENSING EQUIPMENT TO REPLACE SOR LONG-TERM ACTIONS SOR LONG-TERM TEST RECOMMEND AND EVALUATE SOR SWITCH IMPROVEMENTS '

DECISION CONCERNING ALTERNATIVE LEVEL SENSING EQUIPMENT INSTALLATION OF IMPROVED SOR SWITCHES OR INSTALLATION OF ALTERNATIVE LEVEL SENSING EQUIPMENT EVALUATE CALIBRATION AT OPERATING CONDIT0NS (VOLUMETRICS TESTING DEVICE) 4 DOCUMENT ID 40441/

3 h, , > a h August 4, 1986 MEETING

SUMMARY

DISTRIBUTION

/

' Jocket No(s): 50-374 NRC PDR Local PDR BWD #3 r/f J. Partlow E. Adensam '

Attorney, OELD E. Jordan B. Grimes ACRS (10)

Pro.iect Manager A. Bournia E. Hylton NRC PARTICIPANTS A. Bournia J. Beard W. Hodges G. Wright, RIII G. Lainas R. Ramirez J. Knox E. Marinos T. Collins N. Trehan R. Bernero E. Adensam J. Donohew bec: Applicant & Service List

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