ML20197F169

Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors

ML20197F169
Person / Time
Site:	Millstone, Hatch, Peach Bottom, Salem, Mcguire, Perry, Kewaunee, Oyster Creek, Pilgrim, Arkansas Nuclear, Braidwood, River Bend, Haddam Neck, San Onofre, McGuire, 05000000, Fort Saint Vrain, Crane
Issue date:	05/08/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8605150462
Download: ML20197F169 (17)

Text

r-MAY 0 8115 MEMORANDUM FOR:

Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON APRIL 28, 1986 - MEETING 86-14 On April 28, 1986, an Operating Reactor Events meeting (86-14) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on April 21, 1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2.

In addition, the assignment of follow-up review responsibility was also discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard to their respective responsibilities.

Note that several assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, x27864) if the target completion date cannot be met.

AS/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

i As stated cc w/ enc 1*

See next page DISTRIBUTION Central Filesv/

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Harold R. Denton.

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D. Eisenhut M. Wegner J. Taylor P. Leech C. Heltemes J. Zwolinski T. Murley, Reg. I S. Stern J. Nelson Grace, Reg. II W. Butler J. Keppler, Reg. III H. Rood R. D. Martin, Reg. IV G. Knighton.

J. B. Martin, Reg. V J. Stefano R. Starostecki, Reg. I H. Bailey R. Walker, Reg. II J. Shea C. Norelius, Reg. III C. Grimes E. Johnson. Reg.-IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russeil T. Novak F. ' Schroeder W. Houston

~

B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin

=

54Y 0 81986 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-14)

April 28,1986 NAME DIVISION NAME DIVISION H. Denton NRR M. Wegner 0IE:DEPER J. Stefano NRR/ DBL

0. Gormley IE:VPB H. Rood NRR/PBD#7 D. Allison IE:EAB R. Perfetti NRR/PBD#8 D. Vassallo NRR/ DBL /F0B W. Regan NRR/PWR-B D. Crutchfield NRR/PWR-B l

C. Miller NRR/PWR-B R. Jones NRR/PWR-B i

E. Weinkam NRR/PWR-A S. Newberry NRR/0 RAS G. Murphy ORNL/N0AC D. Ziemann NRR/DHFT R. Baer IE/DEPER/EGCB E. Weiss IE/DEPER/EAB H. Bailey IE/DEPER/EAB A. Howell IE/DI/0RPB

~

G. Klingler IE/DI/0RPB V. Benaroya NRR/F08-A J. Ridgely NRR/PSB W. Minners NRR/DSR0 L. Solander NRR/ PRAE R. Auluck NRR/ DBL J. T. Beard NRR/0 RAS G. Holahan NRR/0 RAS M. Virgilio NRR/0 RAS R. Gallo NRC/ REGION I F. Miraglia NRR/PWR-B R. Houston NRR/ DBL F. Schroeder NRR/PWR-B E. Rossi NRR/PWR-A B. Sheron NRR/DSR0 T. Speis NRR/DSR0 R. Bernero NRR/ DBL N. Trehan NRR/ DBL j

W. Swenson NRR/0 RAS D. Tarnoff NRR/0 RAS S. Black NRR/TOSB i

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l

ENCLOSURE 2 f

l OPERATING REACTORS EVENTS BRIEFING 86-14

. APRIL 28, 1986 L

CHERN0BYL MAJOR ACCIDENT l

SAN ONOFRE UNIT 3 UNEXPECTED CRITICALITY AND REACTOR TRIP PILGRIM FAILURE TO ISOLATE RCS FROM RHR A.I.T FOLLOW-UP OTHER EVENTS OF INTEREST PERRY UNIT 1 CONTINUING PROBLEMS WITH SPIKES ON NUCLEAR INSTRUMENTATION MILLSTONE UNIT 1 PARTICLES CAUSE NON-CONSERVATIVE SHIFT OF APRM FLOW BIASING i

l-CHERN0BYL' - NUCLEAR REACTOR ACCIDENT (W. SWENSON, NRR)

PROBLEM:

NUCLEAR REACTOR ACCIDENT AT S0VIET PLANT NEAR KIEV l

SIGNIFICANCE:

POTENTIAL WIDE CONTAMINATION l

BACKGROUND:

! ~

- PLANT CONSISTS OF 4-1000 MWE RBMK-1000 GRAPHITE MODERATED PRESSURE-TUBE REACTORS

- COOLING WATER CIRCULATES THROUGH 1690 ZIRCONIUM PRESSURE TUBES

- 190 TONS OF 2% ENRICHED URANIUM-0XIDE FUEL PRESENT IN REACTOR

- REACTOR HOUSED IN STANDARD INDUSTRIAL STYLE BUILDING DISCUSSION:

4

- SWEDISH MONITORING STATIONS REPORTING INCREASED AIRBORNE RADI0 ACTIVITY

- NUCLEAR-WEAPON-TESTING-RELATED-RADI0 ACTIVITY RULED OUT AFTER ANALYSIS OF COMPONENTS

- UNCONFIRMED REPORTS OF INJURY AND/0R CONTAMINATION J

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Figure 1.

Reactor RMBK-lOOO General Arrangement 1-reactor; 2-main circulation pianp; 3-feed piping; 4-lower support p) ate; 5-upper protective plate; 6-loading-unloading machir.e; 7-steamwater piping 8-separator drums.

1. -

Table 2.

Basic Characteristics of RMBK-Type Channel Reactors Characteristic Reaction i

RMBK-1000 RMBK-1500 i

I Electric power, MWe 1000 1500 Core dimension, m height 7

l diameter 11.8 Number of evaporative channels 1693 1661 Uranium charge, T 192 189 Enrichment, %

1.8 Average Uranium burning, MWt day /kg 18.1 Fuel element dimensions (diameter x casing thickness)mm 13.5 x 0.9 2

Pressure in separators, kgf/cm 70 Steam parameters before turbine pressure, kgf/cm2 65

temp,

• C 280 i

SAN ONOFRE UNIT 3 - UNEXPECTED CRITICALITY AND REACTOR TRIP APRIL 13, 1986 (H. BAILEY, IE)

PROBLEM:

REACTOR BECAME CRITICAL UNEXPECTEDLY, THEN AUTOMATICALLY TRIPPED BY PROTECTION SYSTEM.

SIGNIFICANCE:

INADEQUATE CONTROL OF PROCEDURES (XENON TABLES).

FAILURE TO FOLLOW APPROACH-T0-CRITICAL PROCEDURES.

FAILURE TO MAINTAIN ADEQUATE SHUTDOWN MARGIN.

DISCUSSION:

APPROACH TO CRITICALITY AFTER BEING SHUTDOWN FOR ONLY 16 HOURS; XENON CHANGING RAPIDLY; BEHIND SCHEDULE ON REACHING CRITICALITY; TRAINEE ON CONTROL RODS.

DUE TO INADEQUATE ADMINISTRATIVE CONTROL, THE XENON TABLES FOR CYCLE 1 WERE BEING USED INSTEAD OF CYCLE 2.

SLIGHT MISALIGNMENT OF FULL-0VT CONTROL RODS GENERATED CPC PENALTY POINTS.

ECP WAS 60 INCHES OUT ON GROUP 6; WENT CRITICAL AT 80 INCHES OUT ON GROUP 4; NOT RECOGNIZED BY TRAINEE OR LICENSED OPERATOR.

RODS PULLED FURTHER TO 114 INCHES OUT (STABLE PERIOD OF 1.7 DPM).

LICENSED OPERATOR RECOGNIZED CRITICALITY HAD OCCURRED BELOW ZER0 POWER INSERTION LIMIT; STARTED INSERTING RODS PER TECH SPECS, CPC ACTIVATED AT 10-4 PERCENT POWER; AUTO TRIP ; PEAK POWER WAS 10-2 PERCENT.

IT APPEARS THAT ADEQUATE SHUTDOWN MARGIN WAS NOT MAINTAINED.

FOLLOWUP:

INVESTIGATION BY REGION AND IE IN PROGRESS, i

INFORMATION NOTICE BEING CONSIDERED.

PILGRIM - FAILURE TO ISOLATE RCS FROM RHR A.I.T. FOLLOW-UP (M. WEGNER, IE)

PROBLEM:

CONCURRENT FAILURE OF ALL THREE ISOLATION VALVES ON "B" RHR/LPCI LINE MODE SWITCH CONTACTS NOT MAKING UP PROPERLY FAILURE OF MSIVs TO RE-0 PEN SIGNIFICANCE:

P0TENTIAL FOR INTER-SYSTEM LOCA OUTSIDE OF CONTAINMENT INADEQUATE CORRECTIVE ACTION FOR PRECURSOR EVENTS IN EACH PROBLEM AREA UNNECESSARY CHALLENGES TO SAFETY SYSTEMS (PCIS, RPS)

FOLLOW-UP:

AUGMENTED INSPECTION TEAM DISPATCHED TO SITE SUNDAY, APRIL 13, 1986 LICENSEE PREPARING REPORT ADDRESSING CORRECTIVE ACTIONS ON LEAKING RHR VALVES ADDITIONAL INSTRUMENTS ON LOW PRESSURE LINES LEAK TO TORUS THROUGH PUMP CHECK VALVE BYPASS LEAK TESTING CHECK VALVE CHECKING MODE SWITCH CONTACTS /PCIS INITIATION CIRCUITS LOOKING FOR LOOSE WIRES SIMULAT$ EVENTS CONSIDERING REPLACING MODE SWITCH DETERMINATION MADE THAT SEPARATION OF THE PILOT POPPET FROM ITS STEM WAS THE CAUSE OF THE FAILURE OF MSIVs TO RE-0 PEN RESULTS OF EXAMINATIONS A-0UTB0ARD DISCONNECTED FROM STEM B-INBOARD COULD MOVE ON STEM 1/8^

B-0UTBOARD BACKED OFF C-INBOARD DISCONNECTED, THREAD DAMAGE D-0UTBOARD BACKED OFF 3/8" A AND D OUTBOARD PILOT SPRINGS HAVE I.NDICATIONS OF CRACKS METALLURGICAL EXAMS TO BE DONE PILOT POPPET DESIGN THOUGHT TO BE UNIQUE TO PILGRIM MSIVs MODIFICATION TO IMPROVE LEAK RATES A.I.T. HAD EXIT-MEETING ON APRIL 24, 1986 A.I.T. REPORT SCHEDULED FOR RELEASE IN LATE MAY

OTHER EVENTS OF INTEREST PERRY UNIT 1-CONTINUING PROBLEMS WITH SPIKES ON NUCLEAR INSTRUMENTATION APRIL 25, 1986 - (E. WEISS, IE)

PROBLEMS:

NOISE SPIKES ON IRMs 0F UNKNOWN ORIGIN NOISE SPIKE ON APRM DID NOT GIVE FULL SCRAM WITH SHORTING LINKS REMOVED SIGNIFICANCE:

UNKNOWN SPURIOUS INTERFERENCE WITH NUCLEAR INSTRUMENTATION AFFECTING PROTECTION SYSTEM RELIABILITY ACCEPTABILITY OF RESPONSE TIME FOR NON-COINCIDENCE APRM TRIP IN QUESTION DISCUSSION:

DURING FUEL LOAD OPERATIONS, REACTOR PROTECTION SYSTEM (RPS)

GENERATED FIVE SCRAMS ON IRMs SENSING UPSCALE CONDITION; NOISE SUSPECTED, NO SPIKES ON SRMs LICENSEE HAS INITIATED A PROGRAM FOR IDENTIFYING AND CORRECTING SUSPECTED IRM NOISE PROBLEM WHICH INCLUDES:

1. WALKDOWN CABLING FOR IRMs

2. SHIELD CABLING NEAR CONTAINMENT PENETRATION

3. CHANGE IRM PREAMPLIFIER CABINET GROUND TO QUIET INSTRUMENT GROUND

4. LOOK FOR SOURCES OF NON-PERIODIC NOISE DURING FUEL LOAD OPERATIONS, RPS GENERATED ONE HALF SCRAM IN LIEU OF FULL SCRAM ON APRM SIGNAL APRM NON-C0 INCIDENT SCRAM USES RELAYS IN MANUAL SCRAM CIRCUIT NO RESPONSE TIME REQUIREMENTS ON MANUAL SCRAM CIRCUITRY ONE RELAY IN MANUAL SCRAM CIRCUITRY HAS LENGTHENING RESPONSE TIME; DEFEATED NON-COINCIDENT TRIP LOGIC FOR SPIKES-APRM NON-COINCIDENT SCRAM IS A BACKUP SCRAM WITH NO CREDIT TAKEN IN SAFETY ANALYSIS FOLLOWUP:

REGION FOLLOWING LICENSEE PERFORMANCE AND RESULTS OF PROGRAMS TO CORRECT PROBLEMS

MILLSTONE UNIT 1-PARTICLES CAUSE NON-CONSERVATIVE SHIFT OF APRM FLOW BIASING JANUARY 14, 1985 - (E. WEISS, IE)

PROBLEMS:

RUST PARTICLES CAUSE CHANGE IN RECIRC-FLOW / CORE-FLOW AT MILLSTONE UNIT 1 - JANUARY 14, 1985 RESIN PARTICLES CAUSE CHANGE IN RECIRC-FLOW / CORE-FLOW AT PILGRIM - AUGUST 20, 1982 SIGNIFICANCE:

APRM FLOW BIAS FOR SCRAM AND R0D BLOCK SHIFTED IN NON-CONSERVATIVE DIRECTION DISCUSSION:

REGION I IDENTIFIED AS POTENTIALLY GENERIC ITEM 4

STUDIES SHOW POLYMER PARTICLE INJECTION IN TURBULENT WATER FLOW REDUCES DRAG BY UP TO 70%

- HIGHLY DEPENDENT ON CONCENTRATION, SIZE, AND TYPE (SLIPPERY-WATER).

RECOGNIZED AT PILGRIM BY ANALYSIS OF COMPUTER PROGRAM P-1 SHIFT OF APRM FLOW-BIAS 3% AT PILGRIM 5% AT MILLSTONE APRM FLOW-BIASED SETPOINT IS CLAMPED AT 100% FLOW T0:

108% POWER FOR R0D BLOCK 120% POWER FOR SCRAM SEPARATE FIXED HI-FLUX SETPOINT (120%) NOT AFFECTED SOME NEW BWRs TAKE CREDIT FOR APRM FLOW-BIASED TRIP

'l FOLLOWUP:

IE INFORMATION NOTICE IN PREPARATION

REACTOR SCRAM

SUMMARY

WEEK ENDING 04/27/86 I.

PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL 04/21/86 ARKANSAS 2

100 A PERSONNEL NO 2

04/21/96 ARKANSAS 2

OA EQUIP /ELECTRICL NO 3

04/21/86 ARKANSAS 2

OA EQUIP / NOISE NO 4

04/23/86 TMI 1

10 A PERSONNEL NO 3

04/23/06 MILLSTONE 3

6A EQUIP /FD CNTL NO 8

04/23/86 RIVER BEND, 1

70 A PERSONNEL NO 5

04/23/06 PEACH BOTTOM 2

100 A PERSONNEL NO 3

04/24/86 KEWAUNEE 1

63 A EQUIP /FD CONTL NO 3

04/25/86 HATCH 2

85 A EQUIP /STM LEAK NO 3

04/26/96 PEACH BOTTOM 3

79 A PERSONNEL /SURV NO 3

04/26/86 RIVER BEND 1

68 A PERSONNEL / TEST NO 6

04/26/86 ARKANSAS 1

100 A EQUIP /RCP TRIP NO 2

04/27/86 FORT ST. VRAIN 1

34 A PERSONNEL NO 2

~

O

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING

~

04/27/86 SCRAM CAUSE POWER NUMBER NUMBER 1985 OF NORMALIZED (6)

WEEKLY SCRAMS (5)

TO 1985 AVERAGE (3) (4)

• • POWER >15%

EQUIP. RELATED

>15%

3 3.0 5.4 (68%)

PERS. RELATED(7) >15%

6 6.0 2.0 (25%)

OTHER(8)

>15%

0 0.0 0.6 ( 7%)

• • Subtotal **

9 9.0 8.0

• • POWER <15%

EQUIP. RELATED

<15%

3 3.0 1.3 (54%)

PERS. RELATED

<15%

1 1.0 0.9 (38%)

OTHER

<15%

O O.0 0.2 ( 8%)

• • Subtotal **

4 4.0 2.4

• • • Total ***

13 13.0 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER NUMBER 1985 OF NORMALIZED WEEKLY SCRAMS TO 1985 AVERAGE MANUAL SCRAMS O

O.0 1.0 AUTOMATIC SCRAMS 13 13.0 9.4

NOTES 1.

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST.

PERIOD IS MIDNIGHT SUN, THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE, 2.

REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAU.SE OF SCRAM 3.

1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF

, UNPLANNED REACTOR TRIPS IN 1985.

WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY & DIVIDING BY 52 WEEKS / YEAR 4.

IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC 8 MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES).

THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR 8 AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

5.

BASED ON 93 REACTORS HOLDING A FULL POWER LICENSE, AS OF 2/1/86 6.

NORMALIZED VALUES ALLOW COMPARISON TO 1985 DATA BY MULTIPLYING ACTUAL 1986 VALUE BY:

93 REACTORS IN 1985 NUMBER OF REACTORS REPORTING 7.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS 8.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

ENCLOSURE 3 Page No.

1 05/06/86 0FERATING REACTORS EVENTS MEETINS FULLOWUP ITEMS AS OF MEETINS 86-14 DN AFRIL 28,1986 (INASCEhDINGMEETINSDATE,NSSSVENDOR,FACILl!YORDER)

MEETING FACILITY RESF0NSIPLE TASKIESCRIPT10N SCHEDULE CLOSED DATE COMMENTS NUM6ER/

NSSS VENIOR/

DIVISION /

COMPLET. BY DOCUMENT, MEET!:')

EVENT DESCRIP.

INDIVIDUAL CATE(S)

MEETING,ETC.

DATE B6-03 MC6UIRE DHFS/ZIEMANN s REVIEW NOVEMBER 1, 1985 Mc6UIRE 04/30/86 CLOSED 04/28/86 01/27/86 W / SIMT-UP

/

EVENT AND DETERMINE IF FAILURE

//

APRll 28, 1986 WITH DEGRiitED TO REFAIR VALVE MOTOR OPERATOR

//

MEMO W.- RUSSELL HPSI SYSTEM PRIOR TO START-UP WAS IN TO 6. HOLAMAN VIOLATION OF TECH SPECS REQUIREMENT B6-10 OYSTER CREEK NRR IMIRABLIA F CHECK ON TMI FOR USE OF SIMILAR 05/01/86 CLOSED 04/28/86 03/31/86 SE / LEVEL

/

SWITCHES

//

AFRIL 16, 19S6 SWITCH SETPOINT

//

MEMD F.

DRIFT MIRA6LIA TO 6.

HOLAHAN 86 OYSTER CREEK NCR / HOUSTON N RESOLVE THE QUESTION OF THE 06/30/86 CPEN

/ /

REVIEW BEING 03!31/86 BE'/ LEVEL

/

ACCEPTASILITY.0F BLIND SWITCHES

//

ACCOMPLISHED UNDER SulTCH SETPOINT AND DELETION OF DAILY CHANNEL

//

TAC NO 61203 DRIFT CHECK B6-10 BRAIDWOOD 1 NRR /N00 NAN V REQUEST REPORT OF EVENT FROM 05/!0/B6 DPEN

/ /

03/31/86 W / WATER

/

LICENSEE 05/01/86 HAMMER IN MAIN

//

STEAM LINE B6-10 BRAIDWOOD 1 IE / JORDAN E EVALUATE NEED FOR IE NOTICE 05/01/B6 CLOSED 04/28/86 03/31/86 W / WATER

/

//

IE NOTICE WILL HAMMER IN MAIN

//

NOT BE ISSUED STEAM LINE 96-10 HADDAM NECK NRR /SPEIS T ASSESS THE POTENTIAL FOR 05/30/B6 OPEN

/ /

03/31/86 W / NEW SMALL

/

SENERICAPPLICABILITY

/ /

BREAK LOCA

//

RESULTS E6-10 HADDAM NECK NRR /6 RIMES C ASSURE THAT THE CORRECTIVE 05/01/86 CLOSED 04/28/86 03/31/86 W / NEW SMALL

/

ACTIONS ARE ADEQUATE PRIOR TD

//

APRIL 28, 1996 BREAK LOCA RESTART

/ /

LETTER F.

RESULTS MIRA6LIA TO J.

OPEKA B6-13 PEACH BOTTOM IE / JORDAN E EVALUATE NEED FOR IE NOTICE 05/30/86 DPEN

/ /

04/21/B6 SE / LDSS OF

/

//

OFFSITEPOWER

//

SOURCE DUE TO A TRANSFORMER FIRE AND ED6 FAILURE

Page D.

2 05/C/96 DPERATINS REACTORS EVENTS MEETING FOLLON'JP ITEMS AS OF MEETING B6-14 ON APRIL 2B,1986 (INASCENDIN6MEETINGDATE,NSSSVENDOR,FACILITYORDER)

LEET!3 FACILITY RESFCNSIBLE TASKDESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUMBER /

MSSS VE00Rt DIVISION /

COMPLET. BY DOCUMENT, MEEll3 EVENT DESCRIP.

INDIVIDUAL DATE(S)

MEETING,ETC.

DATE B6-13 RIVER BEC IE / JORDAN E DETERMINE NEED FOR VENDOR 05/30/B6 OPEN

/ /

04/21/B6 W / 94 CONCERNS

/

INSPECTION

//

INVOLVING

/ /

ARCHITECT EhBINEER rer

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