Text

Forwards Matls for Afrri Rrfsc Meeting on 880526,per Request
	ML20196D244
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	07/05/1988
From:	Evans D; ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE
To:	Alexander Adams; NRC
Shared Package
ML20196D251	List: ML20196D244; ML20196D253; ML20196D262; ML20196D273; ML20196D282;
References
	NUDOCS 8812090007
	Download: ML20196D244 (18)
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(0-170 5 JULY 1988 Mr. Alexander Adams U. S. Nuclear Regulatory Commission OWFN-11-ii3 Wnahington, DC 20555 Mr. Adams:

Enclosed are materiala requested by you.

1 Deborah Evans Secretary i

Radiation Sources Department 1

ao l N$ $ E p Da *ADOCK 05000170 FDC

DEFENSE NUCLEAR AGENCY ARVE0 FORCES R ADICBloLOGY RESE ARCH INSTITUTE BETHESD A. M ARYLAND 20414 5145 12 MAY 1988

Dear Gentlemen:

Encloses please find the package for the upcoming AFRRI RRFSC meeting on the 26th of May 1988 at 0930 in the Board Room. For this meating, we will have parking spaces reserved. We also agree that i'; will be simpler to issue V-Badges rather than issuing picture badger,. Our staff will have the necessary paperwork ready upon your arrival to make your access to AFRRI as efficient as possible. The truet of this meeting is directed primarily at obtaining your approval for the installation of our New Reactor Digital Console.

Items left open at the last meeting will be addressed i n t4 future meeting. This meeting's purpose is to antwer any questions you may have regarding the new console and its instaliation. Furthermore, we will present for your review and approval the "Installation and Checkout Plan" and the "10 CFR 50.59 New Console Safety Evaluation".

In addition to these, several other documents have been provided for informational purposes. These include:

1. Console Installation Schedub

2. Briefing given to the NRC on 3 February 1988.

3. New Console User / Buyers Group Meeting Hinutes and Response.

4 Training Plan

5. Descriptions of the old and New Consoles

6. Quality Assurance Plan

7. ANSI /ANS Standard 15.15-1978.

After the meeting, should you desire, there will be an opportunity to examine the new console and to answer any further questions you may have.

Please read the material carefully and call me or Capt Hodgdon at 295-1290 should you have any questions while you are reviewing the material. Also, if there are any specific items that you wish further information on, please call us in advance of the meeting to allow us time to prepare the appropriate material to

$P provide an answer to your questions.

Thank you for your consideration.

Mark Moore Chairman Radiation Sources Department

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t ORI, Inc.

6295 A Eduff Road 5 Atexandria, VA 22312 ,

y Telephone: UO3) 823-8100 :

REF: SEPD-1711.-88 l j May 23, 1988 Armed Forces Radlobiology Research institute !

Building 42 Bethesda, MD ?00 4-f445 Attention: Mr. Mark Moore ,

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Reference:

(1) 10 CFR 50.59 Safety Evaluation Report of the New Reactor i l Instrumentation and Control System at the Armed Forces Radiobiology Research Institute

[ (2) Contract DNA004-87-C-0008 i 4

Enclosure:

(1) Specific Review Comments on AFRR1 10 CFR 50.59 Safety j Evaluation Report a

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Dear Mr. Moore:

1 3, A review of Reference (1) was conducted under the Reference (2)

contract. We concur with the conclusions of Reference (1) that the l installation of 6 new reactor control console at AFRRI will result in no unreviewed safety questions. Three copies of our specific comments are j included as Enclosure (2). The review was conducted by John E. Miesner.

l If you have any questions concerning this report, please contact me I

or John E. Miesner at (703) 823-8506.

Sincerely, SYSTEMS ENGINEERING A PERFORMANCE DIVISION f *

) William R. Steele '

Director JEM:kt Enclosure (3) om m aeouAnu as . im nccano omo . mm u a w mm . om m mn

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@ W.:== g l Specific Review Comments on AFRR1 10 CFR 50.59 Safety Evaluation Report The Armed Forces Radiobiology Research Institute (AFRRI) is planning to install a new reactor control and instrumentation system. As required by the Code of Federal Regulations (Title 10, Part 50.59), AFRRI has written a safety evaluation report to provide +.he basis for determining the change does not involve an unreviewed safety question. According to 10 CFR 50.59(2), an unreviewed safety question exists if (1) the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or (3) the margin of safety as defined in the basis for any technical specification is reduced. The AFRR1 safety evaluation report concludes that no unreviewed safety questions exist. After performing an independent review of the safety evaluatioa report. -

we concur with this finding.

j lt should be noted that a change in the automatic operating mode will result 1

in a possibility of increased positive rer.ctivity insertion rate in the case of a I continuous rod withdrawal accident due to a computer malfunction ana rod with-drawal interlock malfunction while in this mode. The new servo controller can drive all three standard control rods simultaneous in the automatic mode while the old system could only drive one rod. This was recognized and evaluated in the AFRRl safety evaluation report and it was shown that no reactor technical .

1 specifir,ation would be violated. The safety margin in the ramp reactivity !

I insertion accident evaluated in the new console safety evaluation report would be i

considarably more than exists with the step reectivity insertion accident I evaluated in the existing f acility safety analysis report. In addition, the maximum reactivity insertion rate due to a rod withdrawal accident on the new system in the automatic mode is no greater than a simila' accident on the old system in the square wave mode. T! erefore this is not considered an unreviewed safety question.

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Page 1 of 2 Enclosure (1) to 3EF: SEPD-171L-88

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in all other areas of modification, the new reactor control and instrumentation system will either improve or rot change the reactor safety characteristics. All safety circuits will still be hardwired in the new system and will not be affected by computer malfunction. All technical specifications for the AFRRI reactor facility will continue to be met.

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i Page 2 of 2 Enclosure (1) to REF: SEPD-l?1L-88

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CURRENT CONSOLE SCHEDULE 5/11/88 1985 -

New Console Technical Specifications Produced 198Q - Contract Bids and Review

- Contract Award to General Atomics MAY 1987 26 May - Console Upgrade Plan / Console Schedule JUNE 2 Jun - Produced Training Plan 3 Jun - RRFSC Meeting

- Review Specs for Compliance 17 Jun - Produced Wiring Document

- Electronics Class 24 Jun -

Produced Checkout Plan

- SRO Requal - New Console Preview 29 Jun - 2 Jul - Reactor Operator Training at AFRRI JULY 8 Jul - Review GA maintenance manuals for compliance

- Electronics Class 9 - 26 Jul -

Resotor Operators' Training at GA 29 Jul - Electronics Class AUGUST 14 Aug - RRFSC Subcommittee Maeting 24 Aug - Annual Shutdown

^EPTEMBER 11 Sept - Resume Reactor Operations

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l OCTOBER

- GA Performing Timing Analysis NOVEMBER

- GA making Hardware / Software changes based on Timing Analysis results

! DECEMBER i i 8- 16 Dec - Program Status Review at GA l - Revised Console Installation, Checkout and Test Plan j (Tech Spec Reg'd Item). Note: The plan was modified t to provide for "parallel" Old/New Console Hook-up as a result os the 9 month contract extension, i l 18 Dec - RRFSC Meeting i

JANUARY 1988 l

20 - 22 Jan - GA Console Buyers / Users Group meeting at GA ,

FEBRUARY ;

- Program Status Review and System Checkout at GA

- Operator Retraining at GA l

"'RCH

- Console Delivery '

- Parallel Console Hook-up i

APRIL i

- lith Biennial International TRIGA conference ;

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10 CFR 50.59 Safety Evaluation Report Completed

- RRFSC Meeting (26 May 1988)

- Console Review and Demonstration Installation Decision f

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e JUNE or DECE!!BER/ JANUARY 1989

- Console Installation, Checkout and Operational Testing

- Operator Training at AFRRI on New System

- Operator Requalification Exams

- RRFSC Review and Acceptance of New System r

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ERG - DIGITAL CONSOLE OVERVIEW BRIEFING 3 Feb 1988

- ORIGINAL CONSOLE - 1962

- NEXT CONSOLE - 1968

- CURRENT CONSOLE - 1978 1972 vintage unit salvaged from 1977 decommissioning of DORF reactor facility and installed at AFRRI in 1978.

- The design life of this unit is 10 years.

- Because the current console is 16 years old, maintenance down time has and is expected to increase exponentially over the next five years.

- The console's functional utility is now continuously diminishing due to the progressive obsolescence of many of its critical i electronic components.

- These electronic components and systems are constantly becoming obsolete and are no longer manufacturedi consequently, replacements are unobtainable.

- Redesign of selected circuits to use currently available electronic :

comuonents would require, in each case, a safety review by the reactor safety committee and possible review and approval by the NRC.

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' - Estimated hardware costs to entirely redesign, replace, and upgrade l

AFRRI's existing console exceed the cost of buying a new '

instrumentation system.

Failure analyses of current console components indicate that, under

! normal circumstances. AFRRI has sufficient spare parts to sustain

, its present operational capability for less than 2 years. Then l i

it is expected that AFRRI would become involved in serious down '

I time problems.

l - AFRRI's control rod drive systen also suffers from the same l progressive obsolescence, increasing maintenance down time, and spare parts unavailability as the control console.

- Acquiring a new state-of-the-art console and control rod drive system using integrated circuits and microprocessor technology will i resolve these problems and provide for reliable operation of the :

AFRRI Reactor Facility through the year 2000.

- CURRENT CONSOLE AUXILIARY PANELS

- Coolant temperature, activity, and conductivity.

- RAMS, CAMS, SOM, SpM.

l - Reactor ventilation and fuel temperature chart recorders.

- Reactivity Computer. i l

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- TRAINING & DOCUMENTATION (t : Completod)

Performed 40' hours of in-house (9 AFRRI) classroom instruction by AFRRI staff over the last year.

Received 35' hours of in-house classroom and seminar instruction by GA 6taff in June 87.

Received 60' hours of classroom, seminar, simulator and reactor operations training by GA staff at GA in July 87. This included 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of maintenance instruction. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of simulator time, and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of reactor time.

4 SRO's will attend 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of refresher training at GA within the next four to six weeks. These SRO's will instruct. the remainder of the AFRRI staff during the console installation. GA will also aid in training the AFRRI staff during the console installation on facility specific items.

GA will deliver a minimum of 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months of "hands on experience" in the operation and maintenance of the new Reactor Instrumenation and Control System at AFRRI. after instellation. '

Produced Training Plan in June 1987.

Installation. Checkout and Test Plan completed and awaiting GA

- $0bFR50.59SafetyEvaluationinprogress. .

Facility Safety Analysis revision in progress.

Facilty Annual Report due March of 1989.

- GA SIMULATOR A simulator console was hooked-up for over a year and was bei.ma used for hardware / software development and validation, and for training SROs. AFRRI's console has been hooked-up in the simulator mode and is undergoing system checkout.

- CLOSE-UP OF CONSOLE CRT'S ,

Reactor Control CRT Reactor Status CRT Rod Control Panel

- System Keyboard

- GA INSTALLED CONSOLE Six Phase Development. Test and Checkout Program has been in progress for over a year. Currently in Phase III. Proceeding to Phase IV within two weeks. See Test Phase Handout

- GA INSTALLED CONSOLE

- Another view

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CONSOLE NODE CONTROL PANEL 4

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- This Servoslide shownSwitch.

Selector the added Calibration Switch and the Rod Drive NM-1000'S

- This is the heart and brains of the reactor control system. A l fission chamber feeds the Pre Aap Unit which includes power ;

e supplies, a pre-amp, count rate and cambelling circuitry, and an i 4 analos to digital converter. The signal is then routed to the I 1

Microprocessor Unit which includes power supplies, the computer, and relay and communications boards. The outputs are to the l hardwired bararaphs and to the DAC. ,

PREAMP AND MICRO '

. - Open view. I I

i PREAMP CLOSE-UP I

- Close-up.

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MICR0 CLOSE-UP

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i - Close-up. !

t DAC IN CHECKOUT

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- Picture of the DAC in the bench-top test mode. I j

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DAC CLOSE-UP . i i

i j - Close-up Front View.

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- DAC BACK

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) - Close-up Back View.

- AFRRI DAC f

j - Starting from the top shelf and working down:

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POWER SUPPLIES (2) (Power Conditioning Shelf) i

- Power Supply Drawer.

I ROD DRIVE SHELF (2) (AC Digital Shelf) l - Rod Drive Drawer - drive relays and optically isolated limit switch I

inputs. l l

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TESTING OF I&C SYSTEM ON TRIGA MARK I i

e TEST PROGRAM BEING CARRIED DUT UNDER 10CFR50.59 APPLICATION

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o PHASED APPROACH BEING UTILIZED PHASEI SETUP IN READ ONLY MODE l

PHASEIA DEMONSTRATE INDIVIDUAL CONTROL ROD DRIVE OPERATl0N WITH REACTOR IN SUSCRITICAL CONDITION ,

PHASE 11 - DEMONSTRATE FULL MECHANICAL / ELECTRICAL OPERATION OF ALL R00 DRIVE SYSTEMS IN SUSC#1 TEAL CONDITION.

R00 MAGNET CURRENT SUPPLIED FROM OLD CONSOLE i

- PHASE Ill - REPEAT PHASE II, BUT WITH FUEL LOADED. DEMONSTRATE ALL PERMITTED OPERATION MODES. i ALL SAFETY SYSTEMS REMAIN FUNCTIONAL l

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4 'l CONSOLE REACTOR SAFETY SYSTEM COMPARISON

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SAFEiY CHANNELS I SVE1Y CHANNELS i

- 2 Percent Power - 2 Percent Power l r

- 2 Fuel Temperature - 2 Fuel Temperature l !

L SCRAMS SCRAMS

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-TECH SPEC -TECH SPEC i

- 4 High level Sofety - 4 High Level Sofety f l

Trips Trip l

- Manual - Manual [>

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- 2 HV Loss % Power - 2 HV Loss % Power i j

- Pulse Timer - Pulse Timer i !

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- Emergency Stop - Emergency Stop i

- Water Level - Water Level I l

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-SAR -SAR i !

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- V., Switch - Key Switch j

- Steady State ilmer - Steady State Timor !

- Loss of AC - Loss of AC I r

- Focility Interlocks !

- Focility Interlock !

Sofety Channel Cc!ibrate

Wotchdog i i

- 2 Re!cys in both the l DAC and the CSC

- individual Rod SCRAM - Indivic'c:! Rod SCRAM {

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Reactor Operator Training plan and prograg l

l I. The Training Program will consist of instructions on the use of o the Computer, Fundamentals of Electronics, and Console Operations I and Maintenance. These subjects will be covered in a series of sessions which will be held at AFRRI and at GA as described below.

A. Preinstallation Training

1. Approximately 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months of classes held at AFRRI by AFRRI staff - mainly reviewing the information learned from trips to GA and the materials sent to AFRRI by GA.

2. Approximately 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months of classroom instruction and seminars held at AFRRI by GA staff.

3. Approximately 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months of training in the operation and maintenance of an operational prototype of the new console at GA.

B. Installation Training

1. The AFRRI reactor operational staff will assist in the installation of the new console at AFRRI. During this information the staff will receive instructions on special items which are unique to the AFRRI console.

C. Postinstallation Training

1. Apor,ximately 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months of "hands on experience" in the operation and maintenance of AFRRI'm new Reactor Instrumentation and Control System. These classen wC,1 be held at AFRRI by GA staff.

II. Computer Training

1. The Floppy Disk

a. High Density vs. 360 kbyte

b. Write Protects f c. Floppy Disk Storage

2. The Machine

a. IBM vs. Zenith

b. Configuration of the "AT" 1

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2. Data Acquisition Computer

3. Interface Lines

4. Control Console

5. Basics of Microprocessors B. Practical Electronic Techniques

1. Safety

2. Soldering i

3. Cables and Wire Tiew -

4. Switches l S. Interfacing ,

C. Exercises in Wire Tracing

1. Cables

2. Ribbon Connectors t

D. Interfacing of New Console to Facility

1. Present Cable Trays

2. Facility Interlock System E. New console Maintenance i 1. Problem Identification I 2. Trouble Areas

3. Documentation IV. Console Training

] The console portion of the Training Program will cover the new l Reactor Instrumentation and Control System Description (including I Hardware and Software), System Operations, and System '

i Maintenance. This portion of the training will be conducted in a series of sessions which will be held at AFRRI and at GA as

described reviously. .

A. System Hardware (

1. Control Console

a. Control System Computer

b. Operational Indicators and Controls l c. LED Bar Graph Indicators l d. CRTs

e. Printers i

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2. Data Acquisition Computer

a. A1016 i b. DOM 32

c. LABRASTER i

' . .o D. System Maintenance

1. System Calibrations. Tests, and Surveillance Requirements

2. Preventative Haintenance

3. System Diagnostics

4. System Maintenance

5. Documentation Maintenance Manuals and Drawings (including System Descriptions, Schematics, Calibration Guides, and Troubleshooting Guides)

V. Reactor Operator Qualification Exams These exams will be administered by the Henctor Facility Director. These exams will cover the System Description, System I Operation, and System Maintenance.

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ML20196D244

Contents

Text

Dear Gentlemen:

Reference:

Enclosure:

Dear Mr. Moore:

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ML20196D244

Text

Dear Gentlemen:

Reference:

Enclosure:

Dear Mr. Moore:

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