ML20030D603

Minutes of ACRS Subcommittee on Electrical Sys 810528 Meeting Re Inadequate Core Cooling Instrumentation Sys. Supporting Documentation & Viewgraphs Encl

ML20030D603
Person / Time
Issue date:	07/15/1981
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-1863, NUDOCS 8109100239
Download: ML20030D603 (37)

Text

{{#Wiki_filter:4 % 'S hh. &m fAl/A [' ' /, q SUBCOMMITTEE MEETING ON ELECTR [A1. SYSTEM $h 'I.Q JUL 151991 MAY 28, 1981 g7 g,% 4dge [,\\ p WASHINGTON, DC // jg gg,/pg b f-Q ~ %}s,+hq9 p y. y ,n y /. The ACRS Subcommittee on Electrical Systems heldia-meeti,ngTn May 28, 1981 y f u> at 1717 H.-Street, N.W., Washington, D.C. The purpose of this meeting was to discuss inadequate core cooling instrumentation systems. The specific objectives were to discuss the status of the development work, the liceasee plans for implementation of the NRC requirements, and the adequacy of the various proposed systems. The Subcomittee met with representatives of NRR and RES Staff, Combustion Engineering, Westinghouse, EPRI and Northeast Utilities. ' General Electric and Babcock and Wilcox were also invited but. declined. Notice of this meeting was published in the Federal Register on May 12, 1981. A copy of this notice is included as Attachment A. A list of attachments is included as Attachment B. The schedule for this meeting is included as Attachment C. Selected portions of the handouts for this meeting are included as Attachment D. A complete set of handouts is in the ACRS files. The meeting was begun at 8:30 a.m. with a short executive session in which W. Kerr, Subcommittee Chairman, sumarized the objectives of the meeting. The meeting was adjourned at 5:00 p.m. It was conducted in open session with the exception of approximately 2 hours which was closed to discuss proprietary information presented by Westinghouse representatives. The meeting was attended by W. Kerr, Subcommittee Chairman, J. Ebersole, Subcommittee Member, Richard Savio, ACRS Staf f and the ACRS Consultants I. Catton, W. Lipinski and Z. Zudans. The Designated Federal Employee for this meeting was R. Savio. 1 l 009 IO o2 39 n U

Electrical Systems Mtg May 28, 1981 INTRODUCTION There was a short executive session at which W. Kerr discussed the purpose of the day's ' meeting. He asked tne Staff to address the priority being assigned the requirements relative to other post-TMI requirements and the way in which they reach the reliability requirements for the proposed systems. STATUS OF LICENSEE PLAN AND THE STATUS OF NRR REVIEW - L. PHILLIPS, NRC AND J. ANDERSON, ORNL L. Phillips of the NRC Staff presented the current schedule for the implemen-tation of the core liquid level measurement requirements (NUREG-0737, Section II.F.2). Proposals were to be submitted by the licensees by January 1,1981. Generic (pertaining to proposed instrument systems rather than to plant specific aspects of the system installation and use) comments and information requests are to be issued by the NRC Staff by July 1,1981. Generic SERs are to be issued by December 1, 1981. The instruments are to be installed in the-licensee's plants by January 1,1982. Plant specific SERs are to be installed by July 1,1982. This schedule requires that the licensee select and install instrument systems before the completion of the NRC Staff review and efore the completion of the develcpment and testing of the instrument systems. A summary of the licensee commitments and schedules is given on pages 1-4 of Attachment D. Questions were raised by members of the Subcommittee as to whether this schedule should be extended to allow the completion of the testing and devel-opment before requiring licensee commitments and installation in the plant of a particular system. The Subcommittee noted that the requirements for core liquid level measurement instruments are ambiguous.

Electrical Systems Mtg May 28, 1981 The reliability requirements for the liquid level instruments were discussed. It appears that the requirements will be that the instruments be designd to the reliability required for reactor safety grade instrumentation. Questions were raised as to the range of transients that NRC had considered and the degree to which A had assessed the information and use thereof that core water level would provide. Phillips noted that the instrumentation was intended for the range of small to intennediate size LOCAs and that it was not expected to provide significant information during a large LOCA. The effects of instrument failure on operator actions has not been assessed. Lipinski recommended that failure mode and effects or other equivalent analyses be performed on these instrument systems. He suggested thorough evaluation of the potential of the instrument system for providing false information to the reactor operators and of the potential for causing operator actions which might increase the severity of the consequences of the accident. ORNL is assisting the NRC in developing a position on liquid level instruments and inevaluating licensee proposals. Draft evaluations have been prepared for the Westinghouse differential pressure system and the CE heated junction thermcouple system (HJTC). An evaluation will also be prepared for the DAVC0 microwave level system and for the National Nuclear Corporation excore neutron detection system. ORNL will assist in the review of the plant specific installations and of operating procedures. The ORNL representative indicated f that they were not prepared to express an opinion as to which was the best system.

Electrical Systems Mtg May 28, 1981 PRESENTATION BY NORTHEAST UTILITIES - A. PURI, NORTHEAST UTILITIES Mr. A. Puri, representing Northeast Utilities, stated that the use of liquid level instruments could provide benefits. He noted that the current schedule ~ would not allow for the systematic development, testing, selection, and installation of such systems. Northeast Utilities currently plans to install HJTC systems. He estimates that the instruments could be installed by 1984 on a well planned systematic schedule. PRESENTATIONS BY J. LONGO, G. MENZEL, AND C. NEUSCHAEFER, COMBUSTION ENGINEERING The CE representatives discussed the work being carried out on the Combustion Engineering heated junction thennocouple system. All operating CE plants, with the exception of AN0-2, have committed to the installation of some form of heated junction thennocouple system. The ANO-2 licensee has taken the position that additional instrumentation is not needed to detect inadeouate core cooling. The CE system for the detection of inadequate core cooling involves the use of the HJTC, core exit thennocouples, incore thermocouples, hot leg RTDs, and a saturation meter. The HJTC system proposed by CE is a two-channel system. The output is displayed on the equipment display readouts and on CRTs for the comp'uterized Critical Function Monitoring System. The sensor utilizes an -unheated and a heated chrome 1/alumel thermocouple and measures heat transfer away from the heated junction. Tests and analyses performed by CE indicate that the device has a limited capatility for distin-I 1 guishing between a heated junction which is wetted with water and one which is l submerged in water. A splash shield is provided to assist in the distinction. l The device has been tested in laboratory experiments but has not yet been j tested in an operating reactor the status of the activities associated with l

mu t 4 Elec. Systems Mtg May 28, 1981 on page 5 of Attachment D. The inadequate core cooling instrumentation systems provided by CE are intended to provide an unamb'iguous easy-to-interpret indication of inadequate core cooling, and are intended to provide an indication of in-adequate cooling rather than to give specific water level indication. Different instruments will be used to cover the range from normal operation to complete core uncovery. The WTC system can provide an indication of core water level from normal operating level to the top of the reactor fuel. Figures 6-8 Attachment D, sumarizes CE's assessment of existing anc plannea instrumentation for the detection of inadequate core cooling. Figure 6 of Attachment D sumarizes the proposed accident monitoring system. Figure 9-14 in Attachm6nt D give details of the NTC system proposed by CE. The CE test program was discussed. Autoclave tests, atmospheric air / water tests and tests in TFTF have been completed. CE considers that these tests verify the principle design and deaonstrate the soundness of the design. The tests performed are sumarized on page 15 of Attachment D. Ad'ditional tests on a prototype instrument are p anned. The completion of these l tests is scheduled for the end of 1981. There will be a series of system tests witn a prototype instrument under simulated acci # nt conditions. WESTINGHOUSE PRESENTATIONS (The following material was presented during a proprietary session and should be treated as containing proprietary material). i ~ i 1 ~ DRUl00 ~ ~ r

Elec. Systems Mtg May 28, 1981 DELEil0ii9 i I i EPRI PRESENTATION EPRI is currently sponsoring testing of the National Nuclear Corporation ex-core neutron detectors. Preliminary tests have been perfomed in the Trojan and Rancho Seco reactors and advanced tests are being conducted on the Farley The tests appear to demonstrate the ability of t'he device to i l Unit I reactor. follow the raising and lowering of the water in the reactor vessel. The i i results are being analyzed and documented, and will be submitted to the NRC l l

Elec. Systems Mtg May 28, 1981 1 in June 1981. Future testing is planned in the LOFT L3-5 and L8-1 tests and in the Farley reactor. Mr. Bailey of EPRI noted that there had been failures of thermocouples in the heated junction thermocouple tests and that the environmental qualification of the thermocouples may be in question. In discussion on this topic, it was noted that thermocouple failures from improper degassing are relatively common, and that better QA and construction procedures can eliminate these failures. RE3 SPONSORED RESEARCH RES is sponsoring the testing of heat junction thermocouples systems (ORNL, CE. IDEL, and Navy systems), the ORNL ultrasonic device, of a heated RTD system, of the National Nuclear Corooration excore neutron detector, and of the Westinghouse 3P system. A sunmary of the results obtained to date is giver. on pages 20-21 of Attachment D. An evaluation of the tested instruments, based on the results obtained to date, is given on page 23 of Attachment D. Time limitations prevented the completion of the prepared RES presentation. It is expected that this will be completed in a Subcommittee meeting in the near future. NOTE: ADDITIONAL DETAILS CAN BE OBTAINED FROM THE TRANSCRIPT LOCATED IN THE PUBLIC DOCUMENT ROOM, 1717 H STREET, N.W., WASHINGTON,D.C. 20555 OR FROM ALDERSON REPORTING, INC., 400 VIRGINIA AVENUE, S.W., WASHINGTON, D.C.

l o 2G412 Federal Register / Vol. 4G. No. 92 / Tuesdny. May 12. 1981 / Notices .'p a d clude:nnme and address of appbcnnt, practicable, these closed sessions will water storace tanks to the steam bject of presentation. relation to be held so as to minimize inconvenience generaturs. a genda, amount of time needed, to members of the public in attendance. The opp!ication for the amendment 4 individual's quahfications to speak on The agenda for subject meeting shall complies with the standards and I the subject and a statement justifyt:g be as follows: requirements of the Atomic Energy Act of 19M. as amended (the Act), and the the need for an oral rather than wrtten Thursday. May:8.121. s x o.m. untilthe Commission's rules and regulations.The i m presentation. conclusen ofbusines, Commission has made appropriate i The Commission Chairman has se themjc findings as required by the Act and the D na in ial o l right to decide to what extent pubLc oral g Commii,sion's rules and regulations in to presentations may be permitted atthe consultants who may be Fr:sent. may meeting. Oral presentations will be eachange prehrninary views regardmg CFR Chapter 1. which are set forth in the hmited to statements of facts and siews tnatters to be considered during the balance license amendment. Prior public notice and shall not include any questioning of of the meetmg-of this amendment was not required Commission members or other The Subcommittee will then hear since this amendment does not involve a particf.. ants unless these questionshave presentations by and hold dtscussions with significant hr.zards consideration, been specifically approved by the representatises of the NRC Staff, memers of The Commission has determined that industry. their consuhants, and other the issuance of this amendment will not Chairman Mmuteshi the meeting and materials interested persons regardmg this review. prepared for it will be available for,s Further information regardmg topics $'p c "an h p u oC public inspection at the Commission to be discussed. whether the meeting 51.5(d)[4) on environmentalimpact i acadquarter's.1522 K Street NW., Suite has been cancelled or rescheduled the staternent c,r negative declaration and 300, Washington. D.C. Chairman's ruling on requests for the environmentalimpact apprals.1 need [ Signed in Washington.D.C this tkh day of opportunity to present oral statements not be prepared in connection with and the time allotted therefor can be issuance of this amendment. May 193t. 5 Daniel 11. Saks. obtained by a prepaid telephone call t F f Director.NatwnalCom*nissionfor the Co8nizant Designated Federal dMls,e wd M G a o tye ap a go g Employrnent rohey. Employee, Dr. Richard Snvio (telephone y 202/634-3267) between 8:15 a.m. and Amendment No. 55 to Ucense No. DPR- [ P * "" " *-"*

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5:00 p.m., EDT. 36 and (3) the Commission's related ouseo coes assos as I have determined. In accordance with Safety Evaluation'. All of thes'e itr ms are _ Subsection 10(d) of the Federal available f r public inspection at the NUCLEAR REGut.ATORY Advisory Committee Act. that it may be Commission s Public Document Room, COMMIS3iOH necessary la close portions of thia 1717 H Street NW, Washgton K meetir:g to public attendance to protect and at the Wiscasset Public Ubrary Advisory Comm?ttee on Reactor proprietary information. The authority Assoc!ad n. High Street. Wiscasset. j Safeguards, Subcommittee on for such closure is Exemption (4) to the Maine. A copy of items (2) and (3) may .4 Eiectrical Power Systems; Meeting Sunshine Act. 5 U.S C. 552b(c)(4). be obtained upon re<;uest addressed to i %e ACRS Subcommittee on Electn. cal Dated; May 7,1981. the U.S. Nuclear Regulatcry Power Systems will hold a meeting at W C. Hoyle, Commission. Washington. D.C. 20555,' 1 Attention: Director. Division of A drisory Committee Maxgement Officer. 7I Street h ash n ton, Ucensing. I" E" """*d "ne eu discuss inadequ' ate core cooling aum coot rssom Dated at Be:hesda. Marytsnd. this 30th day Instrumentation with the emphasis on - of April 193L core water level instrumentation. Notice Fonhe Nu&ar Regulatory Commission. [ of this meeting was oublished April 21. f Oocket N$. 50-3091 In accordance with the procedures Robsrt A.C1s4k, 8 f outlined in the Federal Register on Maino Yankee Atomic Povver Co.1 Chi.f. Opemtir:g /teoctors Bmoch No. A October 7.1980. (45 FR f4535), oral or issuance of Amendme.nt to Facility Dimion ofLicensing. written statements may be presented by Operating Ucense p w m.i u n;,a s.ne su am! members of the public, recordings wil! aum coot rse-m [ be permitted only dupng those portions ne U.S. Nuclear Regulatory of the meeting when a transcriptis being Commission (the Commission) has kept, and questions may be asked only issued Amendment No. 55 to Facility [ Docket No. 50-2861 by members of the c.bcommittee,its Operating Ucente No. DPR-36. Issued to consultants, and Stati. Persons desiring Maine Yankee Atomic Power Company, Power AuthorI!y of the Stato of New to make oral statements should notJy. which revised Technical Specifications Yor'4 Ireuance of Amendment to i j the Designated Federal Employee as far for operation of the Maine Yankee Facility Operating Ucense in advance es practicable so that Atomic Power Station (the facility) appropriate arrangements can be made located in uncoln County, Maine.%e %e U.S. Nuclear Regulatory i to allow the necessary time during he amendment is effective as of the date of Commission (the Commission) has meeting for such statements. issuance. . Issued Amendment No.35 to Facility k The entire meeting will be open to %e amendment adds a flow test Operating I.icense No. DPR-64, issued to public attendance except for those . requirement to verify the normal the Power Authority of the State of New aassions which will be closed to protect Auxiliary Feeiwater Flow System flow York (the licensee), which revised I proprietary information (Sunshbe Act path and adds monthly inspections to Environmental Technical Specifications i Exemption 4) One or more closed verify that manual valves in the AFWs for operation of the Indian Foint Nuclear sessions may be necessary to discuss are locked in their proper positions to Generating Unit No. 3 (tha facility) auch irdormation.To the extent ensure flow from the deminershzed located in Buchanan, Westches'er i ~ i 1

MEETING ON THE ELECTRICAL SYSTEMS SUBC0!<QTTEE ON CORE WATER LEVEL MEASUREMENT DEVICES 1. EXECUTIVE SESSION 15 min 8:30 - 8:45 am 2. INTRODUCTION - NRR/0RNL 60 min 8:45 - 9:45 am Status of license plans for fulfilling requirements for inadequate core cooling instruments and the status of the NRR's review, with the emphasis on core water level measurement devices 3. PRESENTATION BY NORTHEAST UTILITICS 15 min 9:45 - 10:00 am 4. STATUS OF THE DEVELOPMENT EFFORT Descriptions of the core water level measurement devices status of the development work, and status of the list program a) Combustion Engineering 90 min 10:00 - 11:30 am b) Westinghouse (Part of this 90 min 11:30 - 1:00 pm discussion will be closed to discuss proprietary material) LUNCH 60 min 1:00 - 2:00 pm c) EPRI 30 min 2:00 - 2:30 pm ~ d) NRC-RES/ORNL 60 min 2:30 - 3:30 pm e) General Discussion 90 min 3:30 - 5:00 pm 5. CONCLUDING REMARKS - ACRS 15 min 5:00 - 5:15 pm i i r.. 5 he i l f

TIME __D f 3 O MEETING ROOM _ /O DATE N A I 2 8 Mikm ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 7 Eb4 W C y-* b' l MEETING ,7 M s. y s m'< & EC TKICAL SYS TEMS Ksm ATTENDEES PLEASE SIGN BELOW (PLEASE PRINT) NAME , BADGE NO. AFFILIATION kCl !f O,I .8 1 /[,,lt K-2 Arolrpa L. 54 }lod

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TIME 2 MEETING ROOM PATE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MEETING ATTENDEES Pl. EASE SIGN BELOW (PLEASE PRINT) NAME BADGE NO. AFFILIATION 1 CArk U. N(utchebt C6 2 K.R. h ee 'Co A L Cut 3 A M-Ku no um s. 1% w ag u E w:a Pows % Co 4 I ~;v N To i R I h':'RTo iFI', T Uruirisc* 5 l /: / n-6 0'M Bmw CE ' Q uu WL"J ~ r-,,

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SUMMARY

OF OPERATING PLANTS RESPONSE TO NUREG-0737 SECTION II.F.2 REQUIREMENTS REACTOR LEVEL MEASUREMENT B&W Installation Schedule Detector No Plants Type On-time Delay tchedule AND 1 Not Needed Crystal River 3 AP Hot Leg Level No schedule' Inst. specified Davis Besse 1 Review of No commitment current available system Oconee 1, 2 & 3 aP Hot Leg Level Inst. Rancho Seco AP Hot Leg Level Inst. Three Mile Not needed Island 1 Summary 2 not needed no commitment 8 6 still 1 coking all plants { l l l l l t I l t l. ~ 1

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SUMMARY

OF OPERATING PLANTS RESPONSE TO NUREG-0737 SECTION II.F.2 REQUIREMENTS REACTOR LEVEL MEASUREMENT CE Installation Schedule Detector No Plants Type ' On-time Delay Schedule ANO 2 Not Needed . Calvert Cliffs Based on HJTC 1983 142 results i Ft. Calhoun HJTC's Fall 1982 Maine Yankee HJTC Probable Millstons-2 CE KJTC 4 Palisades Support HJTC St. Lucie 1 Per C-E OG will provide after completion of CE program

Sumary 1 Not Needed 4 no 4 still looking commitment 3 HJTC l

l I I I I l

,/ 6 /

SUMMARY

OF OPERATING PLANTS RESPONSE TO ,/. NUREG-0737 SECTION II.F.2 REQUIREMENTS REACTOR LEVEL MEASUREMENT W Installation Schedule Detector Plants Type On-tine Delay Schedule i No i Beavar Valley aP 1/1/82 Cook 1 & 2 aP 1/1/82 Farley 1 & 2 Neutronic Complete Deve. ' Refueling (EPRI? 1/1/82 GInna outage 1982 No Selection Haddam Neck Prefer CE HJTC will provide after completion of CE program Indian Point 2 aP Indian Point 3 AP 1/1/81 Kewaunee No Selection

North Anna 1 & 2 a P, Per }[

1/1/82

Point Beach 1 & 2 A P, Per }[

\\ t Prairie Island No Selection 1&2 Robinson 2 aP, Per _W_ ) Salem 1&2 6P, Per W 1/1/82 -dan unotre i No Selection Surry 1 & 2 AP, Per }[ 1/1/82 l 1 1 e

. _ _ _ _ - _... _ _. - ~.. / * /. J (Continued) j 4-4 W Installation Schedule j_ Detector Plants Type On-time Dely Schedule No i Trojan 3P, Pere 1/1/82 Turkey Point HJTC, Per CE 384 will provide i s on. completion. '~ of CE program. Yankee Rowe No Selection Zion 1 & 2 3 P, Per,W. Installed 1 Sequoyah 1 3 P, Per i 1/1/82 Sumary 2 per CE 16 3 10 2 per NNC 7 no comitment IB Mr g i I 1 l 1-i e 1 b .m...e,-r.._ ~... _m._.#,,_.

V 'l C-E ICC ACTIVITY MATRIX M SAFETY CRITICAL SUBC00 LED CORE PARAMETER FUNCTION MARGIN RVUiS EXIT DISPLAY MONITOR MONITOR (HJTC) TC'S SYSTEM SYSTEM HARDWARE ~ X X X X X DESIGN X FIRST-ONE IN '82 HARDWARE X 11 2 IN JN QUALIFICATIbN X PROGRESS PROGRESS IN PR,0GRESS CUMENTATION OPERATOR GUIDELINES TO BE MODIFIED TRAINING TO BE MODIFIED r ~,

se INSTRUMENTS INCLUDED IN EVALUATIONS i FOR ICC INSTRUMENTATION SYSTEM CLARITY DEVELOPMENT iiENSORS INDICATION PROVIDED BY SENSOR OF SIGNAL STATUS ( IEATED JUNCTION

1) LIQUID INVENTORY IN UPPER HEAD /

GOOD DEVELOPMENT JIFFEREi1TIAL UPPER PLENUM COMPLETE lIllERM0 COUPLES /

2) AXIAL TEMPERATURE DISTRIBUTION IN GOOD IllERM0 COUPLES OF UPPER HEAD / PLENUM 1VLMS CORE EXIT

1) FLUID TEMPERATURE AT CORE EXIT GOOD EXIST

filERM0 COUPLES

2) INFER CLAD TEMPERATURE FAIR IN-CORE

1) METAL TEMPERATURE INSIDE GUIDE TUBE '

GOOD CONCEPT TilERM0 COUPLES

2) INFER CLAD TEMPERATURE UNDETERMINED SELF-POWERED INDIRECT MEASURE OF MIXTURE LEVEL 4"9 P00R EXIST NEUTRON EP"

DETECTORS u,r J J ' S ; j /

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f. ~ CLARITY VELOPMENT i e SENSORS INDICATION PROVIDED BY SENSOR OF SIGNAL STATUS I HOT LEG RTD

1) FLUID TEMPERATURE IN HOT LEG GOOD EXIST (5 EACH)

2) INFER CLAD TEMPERATURE POOR i

EX-CORE. INDIRECT MEASURE OF GROSS V0IDING'. FAIR EXIST NEUTRON INDIRECT INDICATION OF MIXTURE FAIR DETECTOR LEVEL IN CORE. (ONE, SOURCE RANGE) EX-CORE SAME AS ONE EX-CORE DETECTOR, BUT FAIR CONCEPT NEUTRON MORE AXIAL RESOLUTION DETECTOR (STACK OF 5, SOURCE RANGE) O d 9 9 g

0-ICC INSTRUMENTATION SENSORS INFORMATION PROVIDED PRIMARY INDICATORS DURING 1. RTDs 0F SMM, lA. STATE OF COOLANT APPROACH T0/ RETURN FROM = PZR PRESSURE IN REACTOR VESSEL HOT LEG ICC 19. STATE OF COOLANT UNDER SUBC00 LED CONDITIONS,. IN REACTOR VESSEL AB0VE FUEL ALIGNMENT PLATE 2A. ICs 0F RVU1S, PZR PRESSURE 28.-HEATED JUNCTION DIF-2. IIATER INVENTORY IN REACTOR APPROACH T0/ RETURN FROM FERENTIAL TCs 0F RVU4S VESSEL AB0VE FUEL ALIGNMENT ICC, CORE COVERED PLATE i 3. CORE EXIT TCs 3. FLUID TEMPERATURE WHICH GIVES APPROACH T0/ RETURN FROM ICC< INDICATION OF CLADDING HEATUP CORE UNC0VERED. EXISTENCE OF ICC

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ACCIDENT N0dll0RI% SYbita uvt3vits l QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM l ~ I l l l-FROMICCh [l FROM ICC SENSO4S SENSORS CLASS 1E PROCESSING CLASS 1E PROCESSING INCLUDING INADEQUATE INCLUDING INADEQUATE l 1 CORE COOLING (ICC) CORE COOLING (ICC) l l Ci:ANNEL A CllANNEL8 l l l l l l I CLASS 1E--ll > (--l1 OTHER OTHER - CLASS 1E INPUTS INPUTS 1 l l 1 o I l I .I, v DISPLAY DISPLAY 1 l FOUIPMENT EOUIPMENT gl CHANNEL A CHANNEL B I l I L._ - u v ^ CRITICAL FUNCTION MONITORING SYSTEM 4 PUTS PUTS l v v 'F CONTROL TECHNICAL EMERGENCY ROOM SUPPORT OPERATIONS DISPLAY CENTER FACILITY DISPLAY DISPLAY t

SYSTEM DESIGN HJTCS FUNCTION AL CON FIGU R ATION [( i CONTAINMENT WALL ~ ~ CHANNEL

= ALARM PRODE ge,h ASSEMBLY

'ai A > INDICATIONS i CHANNEL A > TREND RECORDING s'a sA SENSORS ) h / c B.I CHANNEL ---> ALARM l'/l CHANIJE L B B l'el > INDICATIONS B8 > TREND RECORDING e /. / l SIGNAL TOP VIEW OF . PROCESSING REACTOR VESSEL HEAD UNIT

gM 1. HJTC PROBE ASSEMBLY ~ ! ?! = - E 21 ~ ) ~ ? ~ b) = 'o l COPPER l ~ i t g (+) !; /, CHROMEL , ALUMEL 1 A N i g i k ALUMEL !/ INCONEL B i s. CHROMEL C u._- [ COPPER ) - V (A B) = ACTUAL TEMP.ERATURE, UNHEATED JUNCTION V (C - B) = ACTUAL TEMPERATURE, HEATED JUNCTION V (A C) = DIFFERENTIAL TEMPERATURE ELECTRICAL DI AGR AM OF H.J.T.C. 3 l 0 4 S O ( e 's

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l P HEATED JUNCTION THERM 0 COUPLE l ( PR03E ASSEMBLY ELECTRICAL CONNECTORS SEPARATOR TUBE) u % L E ME g (ONE PER SENSOR) e-s 1 w ^~^ __.E-

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L J Y SEAL PLUG SENSOR AND SPLASH SHIELD i e d e

SIGNAL PROCESSING / CONTROL TYPIC A L CO N FIG U R ATIO N (O N E CHANNEL SHOWN) SUGOR A1 o. p SIGNAL PROCESSOR = RECORDER LOGIC AND = PANEL INSERT SBGORAS o-CONTROLS 5 ALARM A POWER 4 .l POWER CONTROL l S!GNAL c dI hj' y v J' ) HEATER f /[# j POWER CONTROLLER o s I I POWER TO HEATERS

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e e e s O t 9 9 9

l 1F> 2. PHASE I - PROOF 0F PRINCIPLE TEST

SUMMARY

C-E HAS COMPLETED SENSOR PROOF 0F PRINCIPLE TESTING. THIS TESTING HAS DEMONSTRATED THE FEASIBILITY OF THE HJTC DESIGN TO MEASUR SIMULATED REACTOR VESSEL T/H CONDITIONS AND PROVIDED THE DESIGN / MANUFACTURING SPECIFICATIONS. TEST PERFORMED DATE RESULTS 1. AUTOCLAVE - C-E 4/80 OUTPUT DIFFERENCE FOR STEAM AND WATER, 2. TWO PHASE FLOW - ORNL 6/80 BARE SENSOR SENSITIVITY TO V0 IDS NEGLIGIBLE. ~ 3. ATMOSPHERIC AIR / WATER - C-E 7/80 SPLASH SHIELD INCREASES SENSOR SENSITIVITY TO V0!DS. 4. HIGH PRESSURE,.THTF - ORNL 9/80 CONFIRMED SENSOR SENSITIVITY JYT PRESSURE AND TEMPERATURE. 5. ATMOSPHERIC AIR / WATER - C-E 10/80 LIQUID LEVEL IS ACCOMPLISHED IN SEPARATOR TUBE. e O e e

/D ~ . MEASURESWATER LEVEL IN UPPER HEAD AND UPPER PLENUf1 ~ ~ 5 pass Naad Penetration (l_ L I O$'" MEASURES WATER ) ^ LEVEL FR0f1 TOP TO r a w BOTTOM 0F VESSEL WITH PUMPS OFF eneae=(APD L 1 l Q

• • • a cae f1EASURES DIFFERENTIAL PRESSURE FROM TOP T0 goag%i,a, coaduit BOTTOM 0F VESSEL WITH PUMPS RUNNING Ted d Tem s REACTOR VESSEL WATER LEVEL MEASUREfENT SYSTEM 3

i )

V D.- \\ . rs lA -k< A U l M ,r " N TRAIN SENSOR ap, ap B i f A A SEAL TABLE i f g HOT LEG Q TRAIN 5 HOT LEO u,;.; g.,; - u I HYDRAULIC ISOLATORS s i TRAIN CONTAINMENT ' WESTINGHOUSE REACTOR VESSEL WATER LEVEL ~ MEASUREMENT SYSTEM

Pages l' and 19 This cortion of the attachment has Seen deleted as: i 4 I T5 pern, e s - n f {. hd'.k.: d bDk5 e, t l i.

/ l' i RVLIS TESTING PROGRAM i I. FOREST HILLS TEST A. STATIC TEST - FILL AND DRAIN B. VERIFY HARDWARE AND ELECTRONICS PERFORM AS DESIGNED II. SEMISCALE TEST FACILITY A. A NUMBER OF SMALL BREAK TRANSIENTS INVESTIGATED i 1. TWO 2-1/2 % COLD LEG BREAKS WITHOUT UHI 2. ONE 2-1/2 % COLD LEG BREAK WITH UHI 3. ONE 5% COLD LEG BREAK WITHOUT UH'. 4. ONE 5% COLD LEG BREAK WITH UHI l l 5. FIVE NATURAL CIRCULATION TEST WITH VARIOUS PRIMARY AND SECONDARY l CONDITIONS. 6. NATURAL CIRCULATION WITH SMALL LEAK - NO ECCS. 7. NATURAL CIRCULATION WITH SMALL LEAK - WITH ECCS. B. RVLIS OUTPUT COMPARED WITH OTHER SEMISCALE DATA.

i 9 REMARKS Electrical 4 .p Not recommended. Impedance LLD Sonic / Ultrasonic .t -f-Could be used now when Propagation calibration is available. Sonic Propagation 4 + -t A possible backup system. on Vessel 4 Sonic Pressure 4.- 4 -f-There may not be available Pulse Reflection space for wave guide. Microwave + Y f-Needs to be proven. ~ Time DomaCin + + Not recommended. Reflectometery Ultrasonic Ribbon 4 + + f 'f Needs development. Promising. l l p s

^ ^ - ~ -} l,, [ ..[ (CONTINUED) I' b D D d M O REMARKS SPND Y Not recommended. ~ ~ ~ It is still a viable j y-Beam + + alternative. May be g S1 useful af ter Rt.D. Exterior Neutron .{- -{ + 7 Top / bottom location not I proving side string Detector + promising. T}i 9 j ~ m l Not proven. i Neutron Themalization ? Moisture Gauge. t Not recommended. Y ~ ~ ~ I Weighing SEl Heated T.C. + t -f' + + A good local measurement. g i A viable method;. BWR is - f op Cell .Y Y _Y using it'. ~ ~ LOI M AUT e sud.

J / ACCIDENT EVALUATION TEST PROGRAM FOR ICC INSTRUMENTATION OVERVIEW _(LIQUIDLEVELDETECTORS) EPRI ORNL NAVY 0RNL INEL FCI CE ' NEUTRON W cilit ._ 'HTC HTC ULTRASONIC HTC HRTD HTC MONITOR D JRESSURIZER Good

• Good
• Good
• Good
• 1 i

3 TEAM-WATER Good

• TITF Shorted Good
• for During V < 10 f t/-;ec Test l

!EEMISCALE After ? After 05/81 03/81 t l 60FT Failed to I indicate 9 AUTOCLAVE Good * ~}}