ML20205B116

1998 Annual Rept of Afrri Triga Reactor. with

ML20205B116
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	12/31/1998
From:	Miller S ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE
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NUDOCS 9903310153
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l ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE 8901 WISCONSIN AVENUE BETHESDA. MARYLAND 20089-5603 5002 .

25 March 99 RSDR

SUBJECT:

Submission of Anr.ual Report U.S. Nuclear Regulatory Commission Document Control Desk Washington,DC 20555

Dear Sir:

Attached please find the 1998 Annual Report for the AFRRI TRIGA reactor facility, submitted as required by license R-84, facility docket 50-170.

Should you nee ~ .ay fmther information, please co tact the undersigned at (301) 295-1290.

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Attachment:

n Mi .ler f as stated ctor Fajility Director Cy Furn:

U.S. Nuclear Regulatory Commission ,

ATTN: Mr. Marvin Mendonca, Mail Stop 11B20 j Washington,DC 20555 l Regional Administrator U.S. Nuclear Regulatory Commission, Region I ATTN: Mr. Thomas Dragoun 475 Allendale Road I'ing of Prussia, Pa.19406 go 9C000C g

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Submission of1998 Annual Report

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1 Armed Forces Radiobiology Research Institute I l AFRRI Triga Reactor Facility l i l 1 January 1998 - 31 December 1998 To satisfy the requirements of

( U.S. Nuclear Regulatory Commission, License No. R-84 (Docket No. 50-170),  !

Technical Specification 6.6.1.b.

The Reactor Facility Director acknowledges the participation of the following personnel for their contributions to this annual report.

Prepared by Robert George Mart 6 mal Kenneth L. Wrisley, CM, USA SFC Samuel Osborne, USA ETI Steven Pierson, USN John Nguyen Graphics by Guy Bateman Submitted by Stephen Miller Reactor Facility Director Armed Forces Radiobiology Research Institute 8901 Wisconsin Avenue Bethesda, MD 20889-5603 Telephone: (301)295-1290 l Fax: (301) 295-0735 l

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Docket'50-170. , License R-84 Submitted by l Stephen Miller l Reactor Facility Director l 1

1998 ANNUAL REPORT TABLE OF CONTENTS

! Introduction <

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l l General Information f J

l Section I Changes in the Facility Design, Performance Characteristics and Operational Procedures;

and Results of Surveillance Tests and Inspections

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l Section 11 l l Energy G:nerated by the Reactor Core and the Number of Pulses $2.00 or Larger l

l Section III Unscheduled Shutdowns l

Section IV Safety-Related Corrective Maintenance Section V Facility and Precedee Changes as Described in the Safety Analysis Report. New Experiments on 'n. , Performed During the Year 1

Section VI l Summary of Radioactive Effluent Released i Section VII l Environmental Radiological Surveys  !

Section VIII l Exposures Greater Than 10% of 10 CFR 20 Limits  !

Attachment A Revised Reactor Administrative and Operational Procedures Attachment B 10 CFR 50.59 Safety Evaluations ofModifi ations, Changes, and Enhancements to Procedures or Facilities Attachment C

- Appointment Letters for Changes to the Radiation Facility Safety Committee v

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l l 1998 ANNUAL REPORT I

f INTRODUCTION  !

The AFRRI reactor facility was available for irradiation services throughout the year except for two nonoperational periods: heat exchanger replacement and annual reactor maintenance shutdown.

1 A plate and frame heat exchanger was installed in July. A bypass valve was added to the primary l side of the heat exchanger to allow primary and purification systems to continue operating when the heat exchanger is disassembled for maintenance. The new exchanger is physically smaller but matches the heat transfer specifications of the original unit. The replacement of the heat exchanger is part of a continuing effort to maintain and upgrade the reactor facility to the highest possible j standards.

l The Nuclear Regulatory Commission inspected the AFRRI TRIGA Reactor during 1998. No violations were issued.

Staff time was utilized in numerous projects throughout 1998. Acquisition and installation of a multichannel analyzer was completed to enhance the reactor staff's ability to perform neutron activation analysis. Multiple experimental arrays were constructed to meet the rigid neutron energy spectrum requirements ofone investigator. Reactor staff also participated in public relations projects in the Washington D.C. area.

Changes were made to various procedures and facilities during 1998 in accordance with the provisions of 10 CFR 50.59. Summaries of modifications are found in Sections I and V.

The reactor staff personnel were provided to conduct a peer review of the reactor facility at Cornell-University in Ithaca, New York.

The remainder of this report is written in the format designated in AFRRI's TRIGA Reactor Technical Specifications. Items not specifically required are presented in the General Information section. The following sections correspond to the required items listed in Section 6.6.1.b of the specifications.

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O Key Personnel O Reactor and Radiation Facility Committee

l GENERAL INFORMATION All personnel held the listed positions throughout the year unless othenvise specified.

Key AFRRI administration personnel (as of 31 December 1998) are as follows:

1. Director: COL Robert R. Eng, MS, USA Chairman, Radiation Sciences Department: CAPT James Malinoski, MSC, USN l

Radiation Protection Officer: Maj Bruce White, USAF  !

2. Reactor Facility Director and Senior Rcactor Operator (SRO): Stephen Miller j

3. Reactor Operations Personnel:

l Reactor Operations Supervisor: Robert Marts (SRO) ,

l Training Coordinator: Robert Mart 6 (SRO)

Maintenance: John Nguyen (SRO)

Records Administration: SFC Samuel Osborne, USA (SRO)

Senior Staff Engineer: MAJ Kenneth L. Wrisley, CM, US A (SRO)

4. Other Senior Reactor Operators: CPT Michael Ortelli, FA, USA (3 September 1998)

SFC William Baxter, USA (3 September 1998)

5. Operator Candidates: ETl Steven Pierson, USN (24 August 1998)

HM1 Deborah Gilchrist, USN (18 July 1997)

6. Newly Licensed Operators: MAJ Kenneth L. Wrisley, CM, USA (3 September 1998)

SFC Samuel Osborne, USA (3 September 1998)

CPT Michael Ortelli, FA, USA (3 September 1998)

SFC William Baxter, USA (3 September 1998)

7. Additions to staff during 1998: ET) Steven Pierson, USN (24 August 1998)

8. Departures during 1998: None

9. There was one staff change and one substitution to the Reactor and Radiation Facility Safety Committee (RRFSC) during 1998. Dr. Leslie Mckinney was removed as a nonvoting member from j the committee. Mr. Marts acted as the recorder for tiie RRFSC for the December meeting.

In accordance with the requirements set forth in section 6.2.1.1. of the AFRRI Reactor Technical Specifications, tne 1998 RRFSC consisted of the following voting members as of 31 December 1998.

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Regular Members:

Maj Bruce White (Radiation Protection Officer)

Stephen Miller (Reactor Facility Director)

Marcus Voth (Reactor Operations Specialist) .

William Powers (Health Physics Specialist) I l

Chairman:

Col Curtis Pearson, USAF, MSC (Director's Representative)

. Special Member:

CAPT James Malinoski, MSC, USN (Chairman, Radiation Sciences Department, AFRRI)

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Additional Nonvoting Member:

Edward Herbert, Montgomery County Government (Environmental Protection Agency)

Recorder:

SFC Samuel Osborne, USA As required by the Reactor Technical Specifications, four meetings of the RRFSC were held: I 13 April 1998, Full Committee Meeting, 13 June 1998, Full Committee Meeting, 15 October 1998, Full Committee Meeting, and l 4 December 1998, Subcommittee Meeting. I i

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O ChangesitoltheFa~cility be' sign,JPerformance Charactenstics and O erational Procedures O Results of Surveillance Tests and Inspections

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l SECTION I Changes in the Facility Design, Performance Characteristics, Administrative Procedures, Operational Procedures, and Results of Surveillance Test and Inspections.

A summary of changes to the facility design, performance characteristics, administrative procedures, and operational procedures, and the results from surveillance testing are provided in this I section. Revised reactor administrative and operational procedures are in attachment A, and the 10 CFR 50.59 reviews are in attachment B.

I A. DESIGN CHANGES:

There were six design changes in the facility during 1998.

1. A voltmeter was added to the stack gas monitor (SGM) to continuously measure the high voltage to the SGM detector. This meter allows easier verification of the correct SGM operating voltage. j

2. The reactor distillation unit was removed from the water makeup system and replaced with the AFRRI water purification system. The AFRR1 system can provide a larger volume of water at 9 faster rate than the existing reactor distillation unit could provide.

The water reservoir remains. This change improves the capabilities of the water makeup system.

3. Radiation Area Monitors (RAM) R1 and R5 were relocated from over the reactor tank to locations on the east wall of the reactor room. This change resulted from an inspector's comments regarding the adjustment of the RAM set points for high power reactor operations. The new locations were chosen based on the areas where people are most likely to be working in the reactor room.

4. A water spigot was added inside the reactor cooling tower to allow for a hose hookup.

Cooling fins in the tower nearly reach the bottom of the tower, making it difficult to brush calcium deposits from under the fins. The hose allows deposits to be easily removed from under the fins.

5. Check valves were added to the air system for the lead shield door bearing. The check valves will prevent the backflow of water into the bearing cup should air pressure be lost.

In addition, a pressure sensor was added to the reactor air system to notify the front desk in the event that air pressure is lost. Thee changes,in conjunction with the bearing cup design, will ensure that the air bearings are kept dry.

6. The reactor tube and shell heat exchanger was replaced with a plate and frame heat exchanger. The new heat exchanger was installed in room 2158. This location is above

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the old unit and above the level of the core. The new exchanger provides the same l thermal transfer capacities as the original unit but occupies a smaller area. Some of the l aluminum piping in the primary system was replaced with stainless steel piping.

Analysis of the seinless steel piping and stainless steel plates in the heat exchanger showed that the replacement would not create an activation problem from ions dissolving j into the primary water. A bypass valve was added to the primary side of the exchanger  ;

to allow the primary and purification systems to continue operating while the heat I exchanger is disassembled during maintenance. This upgrade to the facility will prevent future problems with the aging exchanger and allow for easier maintenance. ,

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B. PERFORMANCE CHARACTERISTICS:

No changes to the core occurred during 1998. All fuel, chambers, and the core experiment tube (CET) remained in place for operations throughout the year. The performance characteristics of the core did not change.

C. ADMINISTRATIVE PROCEDURES:

Four modifications to the Safety Analysis Report (SAR) were made in 1998.

1. All references to the criticality monitor, RAM R5, were removed from the SAR. This change coincides with the movement of RAMS R1 and R5 as described in part A of this section. Discussions with the NRC inspector and research in Title 10 CFR showed that a criticality . monitor is not required for an operating reactor facility.

2. A reference to a patch panel, which had been removed from the facility, was removed from the SAR. A panel for coax cables had been attached to a wall outside a reactor exposure room for connecting the dosimetry readout room with chambers inside the exposure rooms.

The patch panel was removed when new cables were run directly from the readout room to each exposure room. The reference in the SAR was removed afler the panel was removed.

3. The accidental criticality monitors were removed from the reactor facility as well as all references to them in the SAR. This type of criticality monitor is used to detect accidental criticality at fuel fabrication facilities and are not required in this type of facility.

4. The SAR was changed to reflect the plate and frame heat exchanger installation. The description of the tube and shell exchanger was removed, and a description of the plate and frame exchanger was added. Drawings of the coolant water system were also updated.

D. OPERATIONAL PROCEDURES:

1. Procedure C006, Stack Gas Monitor Calibration, was changed to add the calibration of the voltmeter that continuously measures the detector high voltage power supply.

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2. The instructions on how to replace the resin beds in procedure M042, Change Resin Beds for Water Makeup System, were changed from the still resin beds to the resin beds for the l water makeup system. The reactor now receives purified water from the AFRRI water I system. The water then runs through two additional resin beds before being adding to the reactor holdup tank. Procedure M042 provides instructions on how to change the two additional resin beds.

3. Startup and safety checklists were revised twice during 1998. The alarm set points were changed to 10 mrem for RAMS R1 and R5 when the RAMS were relocated. The second revision involved the accepted pressure range at the output of the primary pump, because the new exchanger presents less resistance to the flow of water, the output pressure from i the water pump dropped from 21 psi to 13 psi. Wording changes in the procedures involved modifying Section VI, Line 8(b) where " Alarm check" was changed to "SGM High Indicator Check",Section VI, Line 8(d)"High alann set to" was changed to "High alarm point set to", and line 12 was clarified as "Demineralizer Inlet Temperature." The stanup checklist had one additional change to line 15: " Time Delay Operative" was moved below line 17,"Prestart operability checks performed."

4. Two modifications were made to the Shutdown Checklist during 1998. The alarm set points were changed to 10 mrem for RAMS R1 and R5 when the RAMS were relocated.

The second change involved the accepted pressure range at the output of the primary pump.

Because the new heat exchanger presents less resistance to the flow of water, the output pressure from the water pump dropped from 21 psi to 13 psi.

5. The term " Criticality Monitor" and its set points were removed from procedure 8, Tab C, Nuclear Instrumentation Set Points, in response to moving the RAM as discussed in part A of this section.

6. Procedure 8 TAB G1 was changed to eliminate adjusting the RAM alarm points during high power operations. This change was part of the RAM movement as discussed in part A of this section.

7. Procedure 8, Tab G2 was modified twice in 1998. The first change was to eliminate

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adjusting the RAM alarm points due to the movement of the RAMS. The second was to clarify from what power level a subcritical pulse may be fired.

8. The word " criticality" was removed from Procedure 8, TAB H, Weekly Operational Instrumentation Checklist, as part of the elimination of the criticality monitor.

9. Procedure 8, Tab F1 (Suberitical Square Wave Operations) was modified to clarify the equation for calculating the transient rod position. The equation did not change. Only the format in which the equaNn appears was changed for clarification.

10. Fitness for Duty Procedure, A1, was updated to remove references to employee termination and to allow prescription medication usage as long as the medication does not impair the performance of the operator. The previous version stated that " drug" users would be

r temiinated. Reactor management may relieve an operator from licensed duties but does not have the authority to terminate an employee. The current version reflects this position.

11. A line in Procedure 6, Emergency Procedures, was expanded to notify both the Reactor Facility Director and Emergency Response Team commander of the emergency situation.

12. Reactor Operations Procedure 8A was updated to remove references and recording requirements for the Senior Reactor Operator (SRO) on call, Health Physicist (HP) on call, and Person In Charge (PIC). The positions and recording of personnel fdling the positions were moved to Procedure 8, Tab A. This change was implemented due to the use of a new set oflogbook stamps that record this information for each reactor operation.

13, Procedure 8, TAB A, Logbook Entry Checklist, was updated in several places. Many of the changes were due to new logbook stamps. The stamps were updated to include blanks for the four positions required by Technical Specifications. When filled in, the blanks prove compliance to the Technical Specifications. Changes to the procedure include how to use the new stamps when filling out the operational logbook, who can be designated in each of the four positions on the stamp, and sample usage of the stamps for a typical day's operations. Under the green entries section, reactor calibrations and data were added for any data that the operator wishes to enter into the operations logbook. The color blue-black was removed as an acceptable color for use in the operational logbook. Various redundant statements were removed from this procedure.

14. In Procedure 11, Air Particulate Monitor (also called Continuous Air Monitor, CAM), the specification that the secondary chan recorder will be tumed on when the primary CAM is bypassed was removed because the secondary CAM chart recorder operates continuously.

E. RESULTS OF SURVEILLANCE TESTd AND INSPECTIONS All required maintenance and surveillance tasks during 1998 were accomplished.

Malfunctions are detailed in section IV, Safety-Related Corrective Maintenance..

The Nuclear Regulatory Commission inspected the reactor filcility during 1998. AFRRI's programs were found to be in compliance with NRC requirements. No safety concerns or violations were identified. No noncompliance or significant issues were identified.

The inspector commented that two of the four technical specification positions required for operations were explicitly noted in the logbook but the other two were not. The reactor .

administrative staff agreed to change logbook entries to include all four positions, which were always filled but had not been explicitly noted in the logbook. This change was implemented with the use of new logbook stamps and various procedural changes previously described in Parts A and D of this section.

The inspector discussed year-2000 issues relating to the reactor console and other systems. The reactor facility is in the process of procuring an upgrade to the reactor console to make it fully year-2000 compliant. Tests have shown that the console will continue to operate properly when 1 January 2000 arrives.

The inspector noted reactor staff members adjusting the RAM set points several times a day to allow for various high-power reactor operations. The administration agreed to change the RAM system to eliminate the need to change set points. This change involved procedure and SAR l changes as well as relocating the RAMS. These changes have been discussed in Parts A, C, and l D of this section.

l The inspector stated that facility changes were thorough and well documented, that the Radiaticn Protection Program was well maintained, that personnel in key positions were knowledgeable and had sufficient background to do their jobs, and that logs and records were maintained as required.

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4 SECTION II Energy Generated by the Reactor Core and the Number of Pulses $2.00 or Larger Month Kilowatt-hours JAN 11,099.0 FEB 654.5  !

MAR 1,757.7 l APR 647.6 MAY 1,293.9 JUN 2,436.9 JUL 35.4 AUG 81.9 SEP 1,538.3 OCT 3,565.3 NOV 275.8 DEC' 4,775.1 TOTAL 28,161.4 Total energy generated in 1997: 28,161.4 kwhr Total energy on fuel elements: 945,405.6 kwhr Total energy on FFCRs*: 212,607.5 kwhr Total pulses this year 2 $2.00: 11 Total pulses on fuel elements 2 $2.00: 4,206 Total pulses on FFCRs* 2 $2.00: 94 Total pulses this year: 167 Total pulses on fuel elements: 11,451 Total pulses on FFCRs*: 1,686

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SECTION III Unscheduled Shutdowns There were no unscheduled shutdowns in 1998.

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O Sa"ety-Related Corrective Maintenance 1

7 SECTION IV Safety-Related Corrective Maintenance The following are excerpts from the malfunction logbook during the reporting period. The reason I for the corrective action taken, in all cases, was to return the failed equipment to its proper operational status.

l 26 January 1998 A daily test of the fuel temperature scram points showed a faster than normal i ramp rate during the automated prestart tests. Manual tests of the fuel temperature scram circuits passed. During the automated scram test, a signal l from the fuel temperature test action pack is ramped into the fuel temperature l circuit to check the scram point of each fuel temperature channel. Because the fuel temperature test action pack supplies the ramp signal for both fuel temperature channels, the unit was replaced with a new calibrated unit. The 1 new unit provided the proper ramp rate and allowed the prestart tests to pass. j 05 February 1998 The stack gas monitor air pump was found not operating during the daily instrumentation startup checklist. Diagnosis found the fuse holder for the pump motor had broken. A new fuse holder was installed, and the pump operated properly. The stack gas monitor passed the daily tests and was l placed back on line, i 27 May 1998 The float in the cooling tower that controls the addition of makeup water into 4 the cooling tower was found broken offits stem. This makeup water float works like a toilet bowl float. The broken float allowed a continuous stream ,

ofwater to flow into the cooling tower sump. When the water added filled the cooling tower sump, the water flowed over a stand pipe and down the drain. The secondary system is isolated from the primary water system, and consists of normal tap water. A new float was ordered, and the make up water system was repaired. During the time the water in the cooling tower was shut off, the secondary system, which uses the cooling tower, was also shut off.

22 June 1998 The water temperature at the core outlet was discovered reading -25 C during the moming instrumentation checkout. The Resistance Temperature Device (RTD) probe above the core that provides the temperature indication to the console had failed. A new probe was installed in its holder, tested, and calibrated. The holder with the probe was re-positioned above the reactor core, an ' the console indicated the correct pool temperature.

10 August 1998 During the daily startup checklist, the water temperature at the inlet to the demineralizer was found reading -25 C. Investigation found that contractors working on the new heat exchanger had broken the RTD probe where it enters the water monitor box. A new probe was installed, tested, and

E calibrated. The nonnal water temperature reading registered on the reactor ,

console. l 19 August 1998 The console was found locked up with the message " network looks dead." l Diagnosis found the network board in the Data Acquisition and Control unit )

(DAC) had failed. A new network board was installed and tested. The I console booted up properly, and all tests passed. j 02 October 1998 The reactor core was moved into region 1, but the region I lamp did not illuminate, and the lead shield doors would not close. The lever arm on the switch that detects the core in region 1 was bent. The switch was replaced and adjusted to operate properly. All other switches were checked and found i to be operational. )

13 November 1998 Prior to an operation, the console showed 3% power on the NP channel l (Safety Channel 1), and the NPP channel (Safety Channel 2) was less than i 1% but greater than zero. Test signals inserted into the NP channel showed l

the entire span of the channel was 3% high. This error was a conservative '

error. A test of the system determined that the analog input board (AI0l6),

which measures the signal from the NP and NPP units, was bleeding over from channel to channel. A new A1016 board was installed and calibrated.

The new board passed all tests, and the bleed-over problem was corrected.

The A1016 board was tested to verify the proper operation.

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i O Facility Changes and Changes to Procedures as Described in the Safety Analysis Report l

0 New Experiments or Tests During the Year

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'SECTION V Facility Changes and Procedure Changes as Described in the Safety Analysis l Report (SAR). New Experiments or Tests Performed During the Year i l

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A. Changes to the SAR

1. All references to the criticality monitor, RAM R5, were removed from the SAR.

Operating reactors are not required to have a criticality monitor.

2. The locations of RAMS R1 and R5 were changed.  ;

The RAMS were relocated from over the reactor pool to areas in the reactor deck where people are likely to be during normal reactor operations.  ;

3. A reference to a patch panel was removed from the SAR.

A panel for coaxial cables had been attached to the wall outside exposure room 2 for connecting the dosimetry readout room with chambers inside both exposure rooms. The patch panel was removed when new cables were run directly from the readout room to each exposure room.

4. The accidental criticality monitors were removed from the reactor facility.

The criticality monitors in use at AFRRI were intended for use at fuel fabrication facilities. Since the reactor core is shielded, there is little value for this type of detector at AFRRI.

5. The SAR was changed to reflect use of a plate and frame heat exchanger.

A description of the plate and frame heat exchanger replaced the description of the tube and shell unit. Drawings of the water-cooling system were also updated.

B. There were no changes to procedures described in the SAR. Changes to the operational procedures are covered in Section I.

C. There were no new experiments or tests performed during the reporting period that were not encompassed by the S AR.

Attachment B contains the safety evaluations made for changes not submitted to the NRC, pursuant to the provisions of 10 CFR 50.59. Each modification was described and qualified using Administrative Procedure A3, Facility Modification. This procedure utilizes a step-by-step process to document that there were no unreviewed safety questions, and no changes were required to the Technical Specifications.

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O Summary of RadioactiveLE ffluent Released O Environmental Radiological Surveys O Exposures Greater than 10% of 10 CFR Limits n

1 SECTION VI Summary of Radioactive Effluent Released A. Liquid Waste: The reactor produced no liquid waste during 1998.

B. Gaseous Waste: There were no paniculate discharges in 1998.

The total activity of Ar-41 discharged in 1998 was 17.80 curies. The estimated activity from the release of Argon-41 was below the constraint lirnit for unrestricted areas (Table 2 of Appendix B to 10 CFR 20).

Quarterly: Jan - Mar 1998 5.74 Ci Apr - Jun 1998 0.94 Ci Jul - Sep 1998 0.83 Ci Oct - Dec 1998 10.29 Ci j l

C. Solid Waste: All solid radioactive waste material was transferred to the AFRRI byproduct license; none was disposed of under the R-84 License.

1 SECTION VII '

Environmental Radiological Surveys A. Environmental sampling of soil and vegetation reponed no radionuclide levels above the normal range. The radionuclides that were detected were those expected from natural background and from long-term fallout from nuclear weapons testing.

B. The calculated annual dose, due to Argon-41 release to the environment for 1998, was 0.6 mrem at the location of maximum exposure. The maximum exposure is calculated at a location 91 meters from the release point. Exposure to the general population at the boundary of the National Naval Medical Center is significantly less due to the diffusion of Argon-41 in the atmosphere. The constraint limit for exposure to the public is 10 millirem per year. The exposure dose was calculated using COMPLY code, level 2, which is the most conservative level of COMPLY. Emissions due to reactor operations were 6% of the 10 millirem constraint limit, or 0.6 millirem for the entire year.

C. The reactor in-plant surveys, specified in HPP 3-2, did not exceed any of the action levels specified in HPP 0-2.

SECTION VIII

- Exposures Greater than 10% of 10 CFR 20 Limits There were no doses to reactor staff personnel or reactor visitors greater than 10% of 10 CFR 20

. occupational and public radiation dose limits.

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1 ATTACHMENT A l l

Revised Reactor Administrative and Operational Procedures Procedure C006, Stack Gas Monitor Procedure M042, Change Resin Beds For Water Makeup System Procedure A1, Fitness For Duty Procedure 6, Emergency Procedures l Procedure 8, Reactor Operations Procedure 8, Tab A, Logbook Entry Checklist Procedure 8, Tab B, Daily Operational Startup Checklist Procedure 8, Tab B1, Daily Safety Checklist Procedure 8, Tab C, Nuclear Instrumentation Set Points Procedure 8, Tab F1, Square Wave Operation (Subcritical) j Procedure 8, Tab G1, Pulse Operation (Critical)

Procedure 8, Tab G2, Pulse Operation (Suberitical)

Procedure 8, Tab H, Weekly Operational Instrumentation Checklist l Procedure 8, Tab 1, Daily Operational Shutdown Checklist Procedure 11, Air Particulate Monitor (CAM) Procedure j l

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STACK GAS MONITOR CAllBRATION

1. General:

1.

Reference:

Tech Specs 4.5; HPP 7.3; NMC Stack Monitor Electronic Test and Calibration Procedure P/N 0001020-1.

2. Requirement: The air particulate monitoring system (SGM) shall be calibrated annually, not to exceed 15 months. (HPP 7.3) l

3. Tools: Crescent wrench, screwdriver, special calibration connectors.

4. Equipment: Oscilloscope w/ leads, valtmeter, pulse generator, pulse counter, plastic Ar-41 sample beaker w/ tubing provided by SHD

5. Coordination: With SHD to set a date for isotopic calibration and with the ROS/RFD to arrange a date on operations schedule with no other reactor operations.

6. Estimated time: One day

7. Safety precautions: Use caution when working around high voltage sources and .

minimize exposure to Ar-41 or Na-22 calibration sources.

8. General:

Turn off high voltage and main power before plugginr, or unplugging any of the circuit boards.

The " unit" refers to the rack mountable electronics se : tion of the SGM.

11. Procedural Sequence:

1. Schedule date for calibration with RFD/ROS and br1D.

2. Assemble required tools and equipment

3. Produce Argon-41 (for argon calibration) with reactor.

Suggest: 2 syringes,50-60 cc P-10 gas irradiated for 5 min at 100 Kw.

Revised: 25 Aug 97 Page 1 i

ELECTRONIC CAllBRATION

- 4. Tum off the power. Adjust the front panel meter to 10 cpm.

5. Remove the CRA-14B/91 card and ensure switches SW1, SW2, and SW3 are open.

6. Remove the IC-13 card and set the dip switches into the following configuration:

S1 Closed SS Open (10%

Window)

S2 Open S6 Closed (20%

Window)

S3 Open S7 N/C S4 Open (5% Window) S8 N/C

{ Gross counting mode S1 Closed, S2 Open, S3 Open.}

{ Spectrometer mode S1 Open, S2 Open, S3 Closed.}

Replace the IC-13 Card.

Place the card extension card into the CRA-14B/91 slot and attach the CRA-14B/91 card to the extension card.

7. Disconnect the detector cable from the back of the SGM unit and attach the test cable to the SGM unit.

Power up the unit.

8. Verify 24 i 4 VDC between pins 19 and 20 on the terminal block inside the back of the unit. If the voltage is outside this range, replace or repair the power supply.

9. Connect a pulse generator to the detector test cable.

10. Attach a test cable from the jack on the face of the AA-13A/91 plastic face mask to a volt meter. The access hole is just below the red high alarm button.

11 Set the pulse generator to create 16,666 cps (1x108 cpm).

12. Adjust R33 on the CRA-14B/91 card to give -5.00 t 0.01 VDC.

13. Set the pulse generator to create 166.6 cps (1x10' cpm).

14. Adjust R32 such that the analog meter reads 10,000 cpm.

15. Set the pulse generator to create 16.66 cps (1000 cpm).

l Revised: 25 Aug 97 Page 2 I i

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16. Verify 1000 cpm on the local analog meter.

17. Adjust the potentiometer on the 0-1 mA card such that the remote analog meter in the reactor control room reads 1000 cpm.

18. Adjust the potentiometer on the 0-10 VDC card to give 1000 cpm on the remote chart recorder in the control room.

19. Monitor the voltage through the AA-13A/91 mask test Jack, step through the following inputs, and verify the following outputs.

Pulse Generator Voltage @ AA-13A/91 10 cpm 0.00 i 0.15 VDC

.100 cpm - 1.00 t 0.15 VDC 1000 cpm 2.00 i 0.15 VDC 10,000 cpm 3.0010.15 VDC 100,000 cpm 4.00 t 0.15 VDC 1,000,000 cpm 5.00

• 0.15 VDC

20. Adjust the potentiometer, located above the yellow fail button, while pressing the I yellow fail button such that the analog meter reads about 12-15 cpm. Set the pulse generator to 10 cpm. Verify that the fail alarm lamp illuminates when the analog meter needle drops below 12-15 cpm.

21. Press the meter reset and alarm reset buttons.

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22. Press the alert and high alarm buttons to note the settings. Increase the count output of the pulse generator to cross each of these alarm points and verify that the respective lamps on top of the stack gas monitor illuminate at their set points and that the sonalert alarms at the high alarm point.

23. Power off the unit. Remove the test cables from the front and back of the unit.

Set toggle switches to the following configurations: SW1 - Closed, SW2 -Open, SW3

- Open. Replace the CRA-14B/91 card back into its slot. Attach the detector cable to the back of the unit.

24. Remove the IC-13 card and set the dip switches into the following configuration for spectrometer mode:

S1 Open S5 Open (1r!%

Window)

S2 Open S6 Closed (20%

Revised: 25 Aug 97 Page 3

Window)

S3 Closed S7 N/C S4 Open (5% Window) S8 N/C ,

Replace the IC-13 card.

25. Power the unit back on. Tum on the high voltage. Press the meter reset button.

26. Insert the Sodium-22 source slowly into the chamber and verify operability of the unit.

27. Determine the proper high voltage and adjust as necessary to find the peak l counts for the argon / sodium peak.  !

A. This is done with the sodium source or a sample of argon in the detector chamber B. Slowly adjust the voltage. Set the voltage such that the maximum counts are read from the analog meter. Be sure that the peck selected is the Argon 41 (1293 Kev) or the Sodium 22 ((1274 Kev) peak and not the sodium 22 (511 Kev) peak. graph the output vrs voltage if necessary to find the proper peak.

28. Assist SHD, as needed, in the isotopic calibration using HPP 7-3.

29. After SHD provides the new alarm point numbers, adjust the alarm points.

A. The high alarm point is adjusted by pressing the high alarm button and adjusting the poteritiometer located directly above the button to give the proper alarm point reading on the analog meter.

B. The alert alarm point is adjusted by pressing the alert alarm button and adjusting the potentiometer located directly above the buttcn to give the proper alarm point read:ng on the analog meter.

30. See that a new calibration sticker is placed on the SGM. Change the written alarm points at the appropriate locations (At SGM and Control Room Meter).

31. Obtain and file isotopic calibration report required by HPP 7-3 from SHD.

32. Create decay curve for Sodium-22 source to be used for semiannual source test.

33. Update TRIGA Tracker.

l Revised: 25 Aug 97 Page 4 i

c.

MEMORANDUM TO FILES 1 I

Re: Calibration of SGM l The SGM was calibrated on . The results are as follows.

\

Step Point Expected As Left

8. Voltage TB19-20 24 i 4 VDC

12. AA-13A/91 Jack -5.00 i 0.01 VDC

17. Control Room Meter 1000

18. _ Control Room Chart 1000 l l

19. Inject Signals '

Pulse Generator Voltage AA-13A/91 Meter Reading 0 cpm (0 cps) .V cpm 100 cpm (1.666 cps) V. cpm 1000 cpm (16.66 cps) V cpm 10,000 cpm (166.6 cps) V cpm 100,000 cpm (1,666 cps) V cpm 1,00,000 cpm (16,666 cps) V cpm  !

Fail Lamp Operates YES/NO Warning Lamp Operates YES/NO High Lamp Operates YES/NO Audible Alarm Operates YES/NO High Voltage Set Point VDC Alert Alarm Set Point cpm High Alarm Set Point cpm Counts Generated From Sodium-22 Source cpm Revised: 25 Aug 97 Page 5

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MAINTENAti.CE 'P.ROCEDURE. ..

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-.- - --.w.8. - M ".7_II.Ea .I --M. 042 Change Resin Beds For Water Makeup System

1. General

1.

Reference:

Manufacturers Literature

2. Requirements: As needed

3. Tools: None

4. Equipment: None

5. Coordination: None

6. Estimated Time: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ll. Procedural Sequence: ,

i

1. Determine that a demineralizer needs to be changed. There is a lamp on top  !

of the demineralizer which will go out when the resins need changing. The lamp may come on if there has been no flow of water through the unit. To ensure the resins have been exhausted, open sample port and run water ,

through the resins beds for one to two minutes.

2. Close the water supply valve to the resin bed housings.

3. Unscrew the housing and lower carefully so es not to damage the distributor tube. Remove the o-ring, dump out the resin and clean out the housing.

The exhausted resin can be disposed of into any waste container as there is no danger of any hazard. l

4. Before loading, make sure the bottom strainer of the distributor tube is inserted into the socket'at the bottom of the housing. Cr.refully pourin the resin from one jar of resin. After loading, clean the threads, o-ring groove and the top surface of the housing of all resin beads. Wipe the o-ring dry and place into the groove in the housing. Lightly lubricate the top surface of the o-ring.

5. Replace the housing, hand tighten, and reapply the water supply. i I

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lADMINISTRhiM5 PROCEDUR5j]EQ$@(( ~.yrocedisr5 M FITNESS FOR DUTY REQUIREMENT:

To meet the specifications as defined in the AFRRl plan.10 CFR does not require a fitness for duty precedure for training reactors.

GENERAL The AFRRI Reactor Facility is a drug-free work-place. The use of illicit drugs by any RSDR staff member is prohibited. Personnel using over-the-counter or i prescription drugs which cause drowsiness or otherwise alter one's state of l consciousness will not be permitted to operate the AFRRI TRIGA reactor. In addition, reactor operators, operators-in-training, and management will be monitored for attitude and behavioral changes that may impact an individual's reliability.

SPECIFIC

1. RSDR staff members shall participate in drug-free awareness programs sponsoreo by AFRRI. Military and civilian staff membe.c shall submit to drug screening programs conducted by their respective services. If a staff member's drug screening test yields an unexplained positive result, that staff member shall not be permitted to operate the reactor pending verification of the test. ,

Acceptable positive results may occur following use of certain prescription drugs.

The Reactor Facility Director (RFD) is required to ensure that the cutoff levels for alcohol or controlled substances as established in 10 CFR 26 are not exceeded by NRC licensed personnel. Any staff member determined to be a drug user will be temporarily assigned non operational duties pending administrative procedures.

Revised: 14 July 98 I:\PROCEDWP\OP_A1.WP6 Page 1 l l

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2. Personnel are instructed to inform their physician of theirjob description and requirements prior to being issued a piescription medication. They are instructed to inquire about any medication side effects expected and the physician's opinion regarding interference with safe job performance. This

'nformation shall be relayed to RFD as soon as possible.

Personnel are encouraged to minimize their use of non-prescription over-the-counter drugs for self-medication purposes. Specifically, sedatives, cough and cold preparations, appetite suppressants, and pain relievers have central nervous system side effects. If these medications are used in any quantity, an operator must inform the RFD or ROS and be relieved from operating on that day or until any side effects have resolved once the medication has been discontinued.

Personnel are instructed to read the information in the Physician's Desk Reference (PDR) conceming medication they are taking. If the medication is unlisted in the PDR or the instructions are not understood, the staff physician will be consulted for information on how the drug may affect performance. If there are indwations that the medication will adversely affect an operator's ability to safely perform his/her duties, he/she must inform the RFD or Reactor Operations  ;

l Supervisor (ROS) that he/she must be relieved from operating on that day.

3. The RFD shall continuously monitor the reliability of individuals under his/her command by the following criteria:

. Any court-martial or civil conviction of a serious nature. Minor traffic violations are not a consideration. 1 i

. Negligence or delinquency in duty performance. J

= Significant mental or character traits, or aberrant behavior, sustained by medical aJthority, that might affect the reliable performance of duties.

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. Behavior pattems that show or suggest a contemptuous attitude toward Revised: 14 July 98 1:\PROCEDWP\0P_A1.WP6 Fage 2

the law or regulations

- Drug abuse or alcohol misuse.

. Poor attitude, lack of motivation toward assigned duties, or financial irresponsibility.

The RFD will be observed by his superiors to ensure his/her adherence to reliability criteria. Individuals who exhibit any of the listed behaviors or actions will be removed from licensed activities.

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' OPERATIONAL PROCEDURE '

' ' N][E]^_ " Procedure 6 EMERGENCY PROCEDURES i

GENERAL The reactor emergency organization, emergency classes, and emergency action levels are set forth in the AFRRI Reactor Facility Emergency Plan and its Implementing Procedures.

SPECIFIC Perform the following, as appropriate (need not be done in order).

1. Reactor Emergency:

a. SCRAM reactor,

b. Check rad.'ation monitors; use portable survey instruments to assess situation,if necessary.

c. Notify the RFD/ERT Commander of the situation.

d. Activate the emergency response team.

2. AFRRI Complex Emergency Evacuation:

a. SCRAM reactor,

b. Secure any exposure facilities which are in use so that personnel access to >

that facility is not possible.

c. Remove logbook, emergency guide, radios, te,lotector, tool kit, and keys; report to ERT.

d. Ensure reactor area doors are secured upon departure.

3 Proper classification of emergency situation: All SROs must revi-v the referenced Emergency Plan documents and be able to properly classify the events as they occur. Below is a tabulation of emergency classification to be used as guidance.

Revised: 4 June 98 I:\PROCEDWP\0P_6.WP6 Page 1

EMERGENCY Radiation Activate AFRRI Complex Activate Emergency CLASS Alarms F ergency Evacuation Response Team (Unanticipated)

Class 0 Fire Alarm (non-reactor) Yes Yes I

Class 1 R1 >> 1 min. Yes R2>> 1 min. Yes R3 No No R5 >> 1 min. Yes R6 No No E3 >> 1 min. Yes E6 >>1 min. Yes SGM>> 1 min. Yes l Reactor Stack Fan l l

Monitor No No  ;

Fire Alarm (reactor) Yes Yes Class 2 CAM >> 1 min.

concurrent with R1, R2, R5, and/or SGM

• Yes I

NOTE:

• A decision to evacuate the Institute will be made by the ECP Commander based on input fron. 'he ERT Commander.

Revised: 4 June 98 1:\PROCEDWP\OP_6.WP6 Page 2

l IOPERATIO5 [5i66E695E' ~~1;M((][ proce'd558 REACTOR OPERATIONS GENERAL l Logbook entries will be made in accordance with the Logbook Entry Checklist (Tab A). i l

SPECIFIC

1. The names of the individuals who supervised and performed the daily and weekly checklists will be shown at the top of the checklist. Check marks or numbers, as appropriate, will then be entered on each checklist line as that item is performed.

2. Perform reactor Daily Operational Startup Checklist (Tab B), utilizing appropriate i nuclear instrumentation set points (Tab C). In the case of no planned operations, a Daily Safety Checklist (Tab B1) may be performed.

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3. Perform K-excess measurement (Tab D)if the startup is not a safety startup.

4. Perform operations in accordance with the following:

a. Steady state operation (Tab E).

b. Square wave operation (Tab F).

c. Pulse operation (Tab G).

d. CET operations (Procedure 1, Tab B).

e. Pneumatic Transfer System (Procedure 1. Tab D). -

f. In-pool /in-core experiment (Procedure 1, Tab E)

5. Perform Weekly Operational Instrument Checklist once during each calendar week (Tab H).

6. At the end of each day in which a Daily Operationa! Startup Checklist or Daily Safety Checklist has been completed, perform a Daily Operational Shutdown Checklist (Tab I).

Revised: 1 May 98 1:\PROCEDWP\0P_8.WP6 Page 1 l

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7. Complate the monthly summary .

8. Respirator equipment will not be used on a routine basis. Respirator equipment is provided for use during emergency conditions only.

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l OPEFiATIONdi_YN6dNDUR$ ~~~~FQ{.[53c'edijii5[t lih LOGBOOK ENTRY CHECKLIST I

1. Operational Logbook

1. The reactor operations logbook is a "before-the-fact" record, that is, entries will be logged whenever possible before the operator actually performs the operation. i I

Events, such as scrams, which may not be planned ahead of time, will be entered at the time of occurrence. Any late entries will be so noted. Entries about what you plan to do are not necessary, only actual events need to be logged in the logbook.  ;

2. The operations logbook will have a hardbound cover and will be sequentially numbered by volume. The pages will be dated at the top of each page and each page will be sequentially numbered.

3. The Reactor Facility Director (RFO) will review each logbor' upon its complet he will make an approprict,5: try in the back of the logbook and sign the entry. Tht operator who makes the final entry at the end of a logbook is responsible for ensuring that the ROS is notified that the logbook is ready for RFD review.

4. All items in GREEN (see below) that are not closed out during the working day will be carried in GREEN at the end of the day and again at the beginning of the next operational day.

5. Each of the logbook stamps has space for SRO ON CALL, SRO IN CHARGE (supervising) of the operation, the HP ON CALL, and a second person who is in AFRRI who could help in emergency situations. The individual at the console will enter data into the stamp to designate who is filling these 4 positions. The persons who are on console will have their names entered on the CONSOLE UNLOCKED Byline and will be considered as RO's for the operation. For subsequent stamps Revised:4 May 98 1:\PROCEDWP\0P_8A.WP6 Page 1

when the console is already unlocked, lining out the time for the corisole unlocked entry is appropriate.

One SRO can fill the positions of SRO ON CALL, SRO IN CHARGE and RO on console in CONSOLE UNLOCKED BY.

The HP on call cannot be on call and on the console at the same time.

6. The entries will be made in ink and in accordance with the following designated color code:

a. BLACK: Most Operational Activities.

(1) Console Unlocked By stamp.

(2) Completion of the daily startup, shutdown, and weekly checklists.

(3) Mode of operations. Use appropriate stamp or entry to designate the operation:

(a) Steady State.

(b) Square Wave (c) Pulse (4) Subsequent power level changes.

(5) Operation of reactor associated facilities such as lead shield doors, t pneumatic tube systems, etc., unless such operations cause a change of reactivity (see 5.b.(2) below).

(6) Change of personnel at the console stamp. If hand written, the persons l name replacing the person on console should be entered first as "on console" before the person logging off of the console is entered as *off" (7) All changes to logbook entries (including line outs, error corrections, changes to operations mode stamp lines, and end-of-page line outs) will be initialed or signed by the operator.

(8) Console locked (9) Signature of reactor operator to close out the log for the day.

Revised:4 May 98 1:\PROCEDWP\OP_8A.WP6 Page 2

1

b. RED: For items Which Change or Measure Reactivity (1) K-excess measurements, to include experiment worth determinations. l (2) Actions which affect reactivity:

(a) Core movement.

-(b) Fuel movement.

(c) Control rod physical removal for maintenance.  ;

(d) Experiment loading and removal from the CET, PTS, pool, or core.

(e) Removal or insertion of CET into core. j

c. GREEN: For Maintenance or Malfunctions (1) Any reactor malfunctions noted upon discovery / occurrence with a second entry noting corrective action has been completed.

(2) Additionalitems entered at the discretion of the operator such as addition of l

make-up water to the reactor pool, etc.

- (3) Any Technical Specification required equipment taken out of service for any reason. A second entry is made when the uni' is returned to service.

l (4) Movement of detectors or chambers 1 om above core. )

(5) Reactor calibrations and data. I

6. When an operation requiring entry into the logbook falls under more than one color j code, the color to be used will be determined via the following order of precedence: l RED - GREEN - BLACK.  !

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Sample Logbook Entries for a Typical Operational Day {

Startup Checklist Begun BLACK SRO ON CALL SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY (BLACK)

Startup Checklist #**" Complete BLACK SRO ON CALL SRO IN CdARGE HP ON CALL OTHER '/ERSON ONSITE

)

CONSOLE UNLOCKED BY ,

CRITICAL AT _ , WATTS FOR K-EXCESS TRANS $ SHIM $

SAFE $ REG $

1 SCRAM, CORE POSITION K-EXCESS $

I (RED)

Console locked by *""" BLACK SGM out of service for maintenance. No operations GREEN '

SGM Back in service GREEN l SRO ON CALL _ _ SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY (BLACK)

Revised: 4 May 98 1:\PROCEDWP\0P_8A.WP6 Page 4

z=-

Opening Pb Doors BLACK Moving Core to *" RED Closing PB Doors BLACK Rabbit (containing "") inserted into CET RED SRO ON CALL SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY l

RAISING RODS TO GO CRITICAL TRANS SHIM SAFE REG Tl MAX C T2 MAX ,C RUR#

CRITICAL AT WATTS SCRAM, TOTAL TIME ' " KWHRS (BLACK) 4

. Rabbit removed from CET RED Console locked by *"*" BLACK Shutdown Checklist Begun BLACK Shutdown Checklist #"" Complete BLACK Page lined out, Page signed by SRO BLACK Revised: 4 May 98 1:\PROCEDWP\OP_8A.WP6 Page 5

ll. Malfunction Logbook All entries in the malfunction logbook should include the following information. For consistency, the bold words should be copied into the malfunction log prior to the information.

DATE, TIME, SIGNATURE OF PERSON DISCOVERINc '%LFUNCTION SYMPTOM:

This section describes how the system is acting or r, %ning, i.e., channel went full scale, pump failed, keyboard stopped responding ,e keystrokes etc.

IMMEDIATE ACTION TAKEN: .

1 This section is for denoting such things as Reactor Secured, SHD notified.

RFD NOTIFIED: )

A remark should be made that the RFD or acting RFD was notified.

DIAGNOSIS : of problem l A narrative description of what was discovered to be causing the problem, i.e.,

Which system was malfunctioning or which component failed.

SOLUTION: / repair A narrative description of what was done to correct the problem This could include both physical changes or administrative changes, i.e., a component was replaced and the unit was recalibrated, an additional backup system installed, an administrative prohibit on ... was initiated.

OPERATIONAL VERIFICATION AND/OR CALIBRATION:

A de scription of what actions were taken to verify that the new unit / repair would indeed pmform the function for which it was intended, i.e., a calibration signal, system ectuated multiple times, system tested, system calibrated with a source.

Indicate whether the change will require staff training.

SIGNATURE RFD Revised:4 May 98 I:\PROCEDWP\OP_8A.WP6 Page 6

. - ~. - _ . ._ _ -, _ _ ,m.. , _ - .. e ,-.m, 7 m. _

s OPERATIONAL PROCEDURE . m OgMMEm;h.uw.u MP r.o_ced .

re .;..

8,TA. B. Oc - -

6l DAILY OPERATIONAL. STARTUP CHECKLIST l i

l Checklist No. Date Time Completed Supervised by l Assisted by l

l I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) ....... *

2. Water drained from air compressor . . . . . . . . ..... .............. ...

3. Air dryer operating .. .. . . . .. . ................... ..... ... l

4. Doors 231,231 A, and roof hatch SECURED . . . . .. .. ............... '

'!. LOBBY AREA Lobby alarm turned o ff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....

Ill. EQUIPMENT ROOM (Room 2158)

1. PrefiP.er differential pressure (< 8 psid) ... ...... .. ...............

2. Primary discharge pressure (11 - 16 psig) ............................. *

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) .. .................

4. Stack roughing filter (notify supervisor if > 1.0" of water) *

5. Stack absolute filter (notify supervisor if > 1.35" of water) *

6. Visualinspection of area ............... .......................... I

7. Door 2158 SECURED ........ ....... .......... ................

IV. PREPARATION AREA Visual inspection of area ...... .. .... ..... ...................... i V. REACTOR ROOM (Room 3161) j

1. Transient rod air pressure (78 - 82 psig) .. ... . .. .......... .

2. Shield door bearing air pressure (8.5 - 11 psig) ................... ...

3. Visual inspection of core and tank ....... . ........ ...............

4. Number of fuel elements and Fuel elements control rods in tank storage Control rods

5. Air particulate monitor (CAM)

(a) Primary operating and tracing . .......... ...... ..... ..

(b) Backup operating . . . . . . . . . . . . . . . . . ........ ........... .

(c) Channel test completed, damper closure verified ......... .....

6. Channel test completed on SGM . ...... ... .. . ... .... .....

7. Door 3162 SECUP '- - <

\

l l

• Numerical Entry AF RRI Form 62a (R) Revised: 27 November 98 I:\PROCEDWP\OP_88.WP6 Page 1  ;

i 4

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2. Console recorders dated ...........................................

3. Stack flow and fuel temperature recorders dated ........................

4. Logbook dated and reviewed .......................................

5. Water monitor box (a) Background activity (10 - 60 cpm) . . . . . . . . . . . . . . . . . . . . . . . . . . . .

(b) Water monitor box resistivity (> 0.2 Mohm-cm) .................

(c) DMI resistivity (> 0.5 Mohm-cm) ............................

(d) DM2 resistivity (> 0.5 Mohm-cm) ............................

6. Stack gas flow rate (15 - 35 Kefm) .............................. . .

7. Stack linear flow rate (1.0 - 2.0 Kft/ min) ..............................

8. Gas stack monitor (a) Background (2 - 20 cpm) ... ............ ...................

(b) SGM High Indicator Check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

(c) High alarm point set to 3.2 E-5 microCi/cc at stack top ............

(d) SGM chart recorder operating and tracing . . . . . . . . . . . . . . . . . . . . . . .

9. Radiation monitors f

Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr)

(a) R-1 (< 10) 10

• l (b) R-2 (< 10) 10 (c) R-3 ,_ (< 10) 10 (d) R-5 (< 10) 10 j (e) E-3 (<10) 10 (f) E-6 (< 10) 10

10. TV monitors on ................... .............................

I1. CAM high level audible alarm eneck ....... ........................

12. Demineralizerinlet temperature (5 '!3 *C) ........................... .

13. Water level log completed ..... ...............................

14. Console lamp test completed ..... .... ..........................

15. Source level power greater / equal to 0.5 cps ...........................  !

16. Prestart operability checks performed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l

17. Time delay operative . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

18. Interlock Tests (a) Rod raising, SS mode (e) I kW/ Pulse mode  !

(b) Rod raising, Pulse mode (f) NM-1000 HV l (c) Source RWP __

(g) Inlet Temp I (d) Period RWP

19. SCRAM checks (at least one per rod) i (a) % Power 1 (h) Reactor key (b) % Power 2 (i) Manual (c) Fuel temp 1 (j) Emergency Stop (d) Fuel temp 2 (k) Timer (c) HV loss 1 (1) CSC Watchdog (f) HV loss 2 (m) DAC Watchdog (g) Poollevel 2 0. Zero po wer pulse . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .

• Numerical Entry AFRR1 Form 62a (R) Revised: 27 November 98 1:\PROCEDWP\OP,_8B.WP6 Page 2

1 kfR TIONA5 PROC 55U5$h)$IMM5Mhhhhhd11BJ l

DAILY SAFETY CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by

1. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) ... . .. ... .....

2. Water drained from air compressor .. ....... .. ...... .. ... ..

3. Air dryer operating . ....... ............... . .. ... ... . . .

4. Doors 231, 231 A, and roof hatch SECURED . . . . . . . . . . . . . . . . . . . . . . . . .

II. EQUIPMENT ROOM (Room 2158)

1. Prefilter differential pressure (< 8 psid) ....... ................ . ....

2. Primary discharge pressure (11 - 16 psig) ............. ............ .

3. Demineralizer flow rates set to 6 gom (5.5 - 6.5 gpm) ....................

4. Stack roughing filter (notify supervisor if > 1.0" of water) ................

5. Stack absolute filter (notify supervisor if > 1.35" of water) ............. .

6. Visualinspection ofnea ................................... .......

7. Door 2158 SECURED ...... ...... ......... ....................

Ill. PREPARATION AREA Visual inspection of area ........... .... ... . ... ................

IV. REACTOR ROOM (Room 3161)

1. Transient rod air pressure (78 - 82 psig) ........ ....... ..............

2. Shield door bearing air pressure (8.5 - 11 psig) .. ... ......... .. .

3. Visual inspection of core and tank ........ .................. .....

4. Number of fuel elements and Fuel elements control rods in tank storage Control rods

5. Air particulate monitor (CAM)

(a) Primary operating and tracing ................ ...............

(b) Backup operating . . . . . . . . . ... ....... . .. ..... .

(c) Channel test completed, damper closure verified ................

6. Channel test completed on SGM ........... ... ...................

7. Door 3162 SECURED . .......... ...... .. ............ .......

• Numerical Entry AFRRI Form 62b (R) Revised: 27 November 98 1:\PROCEDWP\OP._8Bl.WP6 Page1

V. LOBBY AREA Lobby audio alarm turned o ff . .. . ........ ... ..... .. .. .. . .. ... .. .. . .. .. .... .... . . . .. . . .. . .. . . . . . . . . . . . .. . . . ... ...

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .

2. Console recorders dated .................... .......................

3. Stack flow and fuel temperature recorders dated ........................

4. Logbook dated and reviewed .......................................

5. Water monitor box (a) Background activity (10 - 60 cpm) ............................

(b) Water monitor box resistivity (> 0.2 Mohm-cm) .................

(c) DMI resistivity (> 0.5 Mohm-cm) ............................

(d) DM2 resistivity (> 0.5 Mohm-cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6 Stack gas flow rate (15 - 35 Kcfm) ...................................

7. Stack linear flow rate (1.0 - 2.0 Kfl/ min) ..............................

8. Gas stack monitor (a) Background (2 - 20 cpm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

(b) SGM High Indicator Check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

(c) High alarm point set to 3.2 E-5 microCi/cc at stack top . . . . . . . . . . . . .

(d) SGM chart recorder operating and tracing . . . . . . . . . . . . . . . . . . . . . . . .

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr)

(a) R-1 (< 10) 10 (b) R-2 (< 10) 10 (c) R-3 (< 10) 10 (d) R-5 (< 10) 10 (e) E-3 (< 10) _

10 (f) E.6 (< 10) 10

10. TV monitors on ................ .................. .............

I1. CAM high level audible alarm check ....... ........................

12. Demineralizer inlet temperature (5 - 35 *C) ...........................

13. Water levellog completed ........................................

14. Source level power greater / equal to 0.5 cps ...........................

i'

• Numerical Entry AFRRI Form 62b (R) Revised: 27 November 98 I:\PROCEDWP\0P_8Bl.WP6 Page 2 1

1

]

, OPERATIONAL _ PROCEDURE dj((d[j}$((P[rS[c[eif[re 8MC l

j NUCLEAR INSTRUMENTATION SET POINTS 1

l GENERAL:

These set points may be adjusted for a specific operation by of the RFD or ROS but in no case may they be set at a point non-conservative to the technical specifications.

SPECIFIC The following are channel or monitor set points (alarm, scram, rod withdrawal l i

prevent). j

1. Scrams: I

a. Fuel Temperature 1 & 2: 575 C

b. High Flux 1 & 2: 110% (1.1 MW) {

c. Safe Chambers 1 & 2 HV Loss: 20% 1

d. Pulse Timer: Less than 15 seconds

e. Steady State Timer: as necessary

2. Rod Withdrawal Prevents:

a. Period: 3 seconds b.1 KW (Pulse Mode): 1KW l

c. Source: 0.5 CPS

d. Water inlet Temperature: 50 degrees C

e. Fission Chamber HV Loss: 20%

3. Alarms:

a. RAMS: As directed in procedures

b. CAMS: 10,000 CPM

c. Stack Gas: 3.2E-5 microCi/cc at stack top

d. Water Monitor Box Gamma: 7000 CPM i

Revised: 18 March 98 D:\RDRIVE\PROCEDWP\OP_8C.WP6 Page 1

• u r -

a e- +.

SQUARE WAVE OPERATION (Subcritical)

GENERAL The sc;uare wave mode will not be used above a demand power of 250 KW.

SPECIFIC

1. Determine the transient rod critical position using the core position, the final transient I rod position, the rod curves and the equation below. Note that a square wave insertion I

can not exceed 75 cents. I l

TOTAL WORTH TRANSIENT ROD ($)(to 100% or mechanical stop)

- DESIRED INSERTION ($) *

= TRANSIENT ROD IN!TIAL POSITION ($)

• For demand powers up to 25 KW, insert $0.70

• For demand powers greater than 25 KW, insert $0.75

2. Apply air to the transient rod and raise the anvil to the critical position that was  ;

calculated above.

3. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with the core position and experimental requirements. If Auto Mode is used, select the rods to be used. Ensure that these rods have been raised at least 5% before entering Auto Mode. Set the cold critical power level on the Power Demand thumb wheels and enter Auto Mode.

4. Stabilize the reactor in Manual Mode.

5. Set power demand thumb wheels to desired power level.

6. Select the standard control rods to be servoed. Make sure that all control rods to be servoed have been raised at least 5%

7. Scram the transient rod.

Revised: 29 April 98 1:\PROCEDWP\0P_8F1.WP6 Page 1

1 f

8. Raise the anvil to the desired final position.

9. Allow the power level to fall below 1 watt. l

10. Switch into Square Wave mode.

11. Depress Fire button.

12. As the power level approaches the power demand level, the console will switch into Auto Mode. If power can not reach the demand power, it will automatically change i to manual mode. At this time, either switch to Auto Mode or bring the reactor to the desired power level manually.

13. Scram the reactor at the end of the run using the manual or timer scram.  ;

14. Ensure all pertinent information has been entered in the reactor operations logbook.

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Revised: 29 April 98 1:\PROCEDWP\OP_8F1.WP6 Page 2

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" OPERATIONAL PROCEDURE "][E[2]386$3ilr$'8, TAB _G1 PULSE OPERATION (CRITICAL)

GENERAL Pulses above $2.00 must be verbally approved by the RFD (prior to pulse initiation) or specified on the RUR, signed by the RFD. I SPECIFIC i

l

1. Bring the reactor critical at less than 1000 watts using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements.

)

2. Stabilize in the manual mode.

3. Raise the transient rod anvil to the desired pulse position. (This position is obtained from the control rod worth curves for the appropriate core operating position)

4. Select the proper pulse detector according to the table below, if the Cerenkov I detector is selected, turn off the reactor room and tank lights.

Detector 1 = Pulse ion (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = $4.00) l l

5. Adjust Pulse Mode Scram Timer if necessary. l

6. Enter Pulse Mode and select high or low resolution pulse display. High resolution displays 1200 MW full scale and should be used for pulses of $2.00 or smaller.

Enter the pulse number at the next prompt. Remember, the power level must be l below the 1 kW Technical Specification limit to enter Pulse Mode.

7. Fire the pulse by depressing the " Fire" button on the reactor console.

8. Record the appropriate data in the reactor operations logbook from the pulse display.

Revised: 16 March 98 1:\PROCEDWP\OP_8G1.WP6 Page 1

))7((.jc'eddr's 8, FAB'G2

~

OPERATIONAL ERO'CEDURE PULSE OPERATION (SUBCRITICAL)

GENERAL Pulses above $2.00 must be verbally approved by the RFD (prior to pulse initiation) or specified on the RUR, signed by the RFD.

SPECIFIC

1. Given a core position, set the transient rod at a position corresponding to the dollar value determined by the following equation:

$ Value = Total worth (S) Transient rod (to 100% or mechanical stop) -

Desired pulse (S) Value

2. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements.

Do not use Automatic Mode until the three standard rods have been raised at least 5%

Note: If a series of repetitive pulses are to be fired, it is not necessary to bring the reactor to cold critical for each pulse. Consecutive pulses may be fired using the same rod positions on the same day as long as the reactor power is not increasing and is less than 1 kW.

3. Stabilize in the manual mode.

4. Select the proper pulse detector according to the table below. If the Cerenkov detector is selected, turn off the reactor room and tank lights.

Detector 1 = Pulse lon (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = S4.00)

5. Adjust Pulse Mode Scram Timer if necessary.

6. Scram the Transient rod.

7. Raise the Transient rod anvil to 100% or the mechanical stop if installed.

8. Let the power decay to approximately 1 watt or less unless otherwise dictated by Revised: 16 March 98 1:\PROCEDWP\OP_8G2.WP6 Page 1

l j

experimental constraints. Pulses may not be initiated above the Technical Specification ikW limit. ,

9. Enter Pulse Mode and select high or low resolution pulse display. High resolution displays 1200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulse number at the next prompt.

10. Fire th~ pulse by depressing the " Fire" button on the reactor console.

11. Record the appropriate data in the reactor operations logbook from the pulse display.

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Revised: 16 March 98 1:\PROCEDWP\0P_8G2.WP6 Page 2

r

~~

OPERATIO'NALYRO.CEDUREf[ [ ))jjliTQr$e[d[urj5, TAB h WEEKLY OPERATIONAL INSTRUMENT CHECKLIST CHECKLIST # DATE SUPERVISED BY ASSISTED BY REVIEWED BY

1. WATER LEVEL INDICATOR A. In pool, east side, depress float on water level indicator . . . . . . . . . . . .

B. Observe scram on console . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

II. WATER RESISTIVITY List resistivity readings for previous calendar week from daily startup checklists. Determine the average at each point is >0.5 Mohm-cm. l MON TUE WED THU FRI AVG .

Monitor Box DM1 DM2 i

lli. RADIATION ALARMS I A. Test alarm functions for high level and failure Monitor Failure alarm functional HIGH Level alarm functional l R-1 i R-2 R-5 E-3 E-6 Reactor Room CAM Gas Stack Monitor B . R e s e t a l a rm s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

l IV.OTHER A. Top lock key seals at Security Desk and at LOG verified intact . . . . . '

B. Change Filter in the Stack Gas Monitor . . . . ....... ...... .

Revised: 27 April 98 1.\PROCEDWP\OP_8H.WP6

., - n . ..n.m mmymw , ..,.n w gm,pfrgyrocedur,e,8, TAB Ihf

!_OPERATI0NAL PROCEDURE

,ggggg DAILY OPERATIONAL SHUTDOWN CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by

1. REACTOR ROOM (Room 3161)

1. All rod drives DOWN . . . . . . . . . . . . . . ...... .. ..... ........... . I

2. Carriage lights OFF . . . . . . . . . . . . . . . . . . . . . . . . .... ........... .

3. Door 3162 S ECURED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l

4. Channel test completed on both CAM's . . . . . .. .

. ............. _ l

5. Door 3161 locked with key . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

II. EQUIPMENT ROOM (Room 3152) i

1. Distillation unit discharge valve CLOSED . . ... ... .. .. . .......

2. Air dryer OPERATIONAL . . . . . . . . . . . . . . . .... .. .. ... .......

3. Doors 231,231 A, and roof hatch SECURED . . . . . . . . . . . . . . . . . . . . . . . . .

III. EQUIPMENT ROOM (Room 2158)

1. Primary discharge pressure (ll - 16 psig) . . . ....... .... ...........

2. Demineralizer flow rates set to (5.5 - 6.5 gpm) . . . . . . . . ... ... ... ..

3. Visual inspection for leaks . . . . . . . . ... .... .. . . .. ........ ...

4. Door 215 8 and 2164 SECURED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

IV. PREPARATION AREA

1. ER2 plug door CONTROL LOCKED . . . . . .. ..... . . .. . ......

Door closed; and handwheel PADLOCKED . ..... .. . .. ... ...

2. ER2 lights ON and rheostat at 10% ... .. . .. .. ......... ...

3. ERI plug door CONTROL LOCKED ....... ... .. .. ...

Door closed; and handwheel PADLOCKED . . ...... ..

4. ERI lights ON and rheostat at 10% . .......... . . .. . .... .

5. Visualinspection of area ..... ......... .. ..... ..... .. .....

6. Warm storage doors closed . . . . . ... .. . .. . . .... . .....

V. LOBBY ALARM AFRRI Form 62(R) Revised: 27 November 98 I:\PROCEDWP\OP_8I.WP6 Page 1

e i

Lobby alarm audio ON ..............................................

VI. REACTOR CONTROL ROOM (Room ?160)

1. Reactor tank lights OFF ...........................................

2. Console chart recorder pens raised ................................... 1 I

3. Steady-state timer OFF .................................. .........

4. Console LOCKED, and all required keys returned to lock box ............. l

5. Diffuser pumps OFF .............................................. l

6. Purification, secondary and primary pumpt ON . . . . . . . . . . . . . . . . . . . . . . . .

7. Reactor monthly usage summary completed ..... .....................

8. Auxiliary chart recorders operating and tracing . . . . . . . . . . . . . . . . . . . . . . . . . .

9. Radiation monitors ...............................................

MONITOR READING HIGH LEVEL ALARM SETTING )

(mrem /hr) a.R-1 (<10) 10

b. R-2 (<10) 10

c. R-3 (<10) 10

d. R-5 (<10) 10 e.E-3 (<10) 10

f. E-6 (<10) 10

g. R-6 (<10)

• Numerical Entry 1

i

. AFRRI FoInn 62(R) Revised: 27 November 98 I:\PROCEDWP\OP__8I.WP6 Page 2

e

.OP,ERATip,NASPROCEDdRE_ _,((![I97$35Ilkcddure11 l AIR PARTICULATE MONITOR (CAM) PROCEDURE GENERAL This procedure specifies how to test the CAM to ensure proper operation of this monitoring ,

device. A channel test will be performed on both reactor room CAMS at the beginning and end of each day.

SPECIFIC

1. TEST FREQUENCY This entire procedure will be performed in conjunction with the daily startup or safety checklist. Items 2,3a and 3d will be performed again as part of the daily shutdown checklist.

2. OPERATING and TRACING Check that the primary CAM is operating and tracing with the correct time indicated on the chart and check that the secondary CAM is operating. Ensure the flow rate is >6 cfm and not off scale.

3. CHANNEL TEST WITH SOURCE

a. Place the switch on the front of the CAM to " test" and verify a reading of 1000 cpm

+/-20%. Reset the switch,

b. Open shield door and change the detector filter if the filter appears excessively dirty or the flow rate has dropped below 6 cfm (with the door closed). Place the used litter in the radioactive waste box in each CAM drawer.

c. Slowly bring a radioactive source near the detector. Observe the meter on the front of the CAM. The yellow light will activate at approximately 4,000 counts per minute.

The red light will activate at approximately 10,000 counts per minute; the alarm will sound and the dampers will close. Reset the alarm, close the chamber door and return the source to the CAM drawer.

d. Annotate completion of the channel test on chart paper with initials, time, and date performed for primary CAM.

Revised: 1 May 98 1:\PROCEDWP\OP_11.WP6 Page 1

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1 Revised: 1 May 98 1:\PROCEDWP\0P_,11.WP6 Page 2

ATTACHMENT B 10 CFR 50.59 Safety Evaluations of ,

Modifications, Changes, and Enhancements

.to Procedures or Facilities Voltmeter Added To Stack Gas Monitor Replacement Water Distillation Unit Replaced References To Criticality Monitor R5 Removed From SAR Sub-Critical Pulse Mode Operation Procedure Updated )

The Word " Criticality" Removed From Weekly Checklist Patch Panel Removed From SAR Equation in Sub-Critical Square Wave Procedure Clarified Accidental Criticality Monitors Removed From SAR Water Spigot Added To Cooling Tower ,

Update of Procedures A1,6,8,8 Tab A, and 11 Air Pressure Loss Switch For Compressor Tank & Check Valves in Air Lines Replacement of Heat Exchanger With Stainless Steel Pipe Startup Procedure Updated Safety Procedure Updated Shutdown Checklist Updated

1 l

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Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: ADD VOLT METER TO STACK GAS MONITOR POWER SUPPLY Modification to: Procedure Facility XX Experiteent Submitted by: Osborne & Georae Date 11 Feb 1998

1. Description of change: .

Add a volt meter to the stack gas monitor (SGM)high voltage power I cupply.

The addition of a panel volt meter allows for easier verification of the SGM operating voltage. Currently to check the SGM operating voltage the power supply must be turned off and a po'; tab 1? volt meter installed. The panel volt meter will provide us with a continous raadout for calibration purposes.

The operating current for the detector and panel voltmeter was dotermined to be <104A and 504A respectively. This well below the j 10mA provided by the H.V. power supply.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or  ;

procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a) (2) .

NONE

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, forward a copy of changes necessary to Facilities.

NONE

4. Determine what other procedures, logs, or training material may be '

affected and record below.

Calibration Procedure C006, Stack Gas Monitor Calibration (attached)

5. List of associated drawings, procedures, logs, or other materials to be changed:

Manufacturer's drawings have been updated

6. Create an Action Sheet containing the ist of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Submitted Not Required XX If ,

Reviewed and approved by RFD .

' ~

$. Date - /t' /*9

\

RRFSC Notified Jeo, \ Date APR I 3 mG8

CAUBR5TidNYRMip0REQt " E 5 9 - d j M 2 M P EC006]

STACK GAS MONITOR CALIBRATION

1. General:

1.

Reference:

Tech Specs 4.5; HPP 7.3; NMC Stack Monitor Electronic Test and Calibration Procedure P/N 0001020-1.

l

2. Requirement: The air particulate monitoring system (SGM) shall be calibrated j annually, not to exceed 15 months. (HPP 7.3)

3. Tools: Crescent wrench, screwdriver, special calibration connectors.

4. Equipment: Oscilloscope w/ leads, voltmeter, pulse generator, pulse counter, plastic Ar-41 sample beaker w/ tubing provided by SHD I l

5. Coordination: With SHD to set a date for isotopic calibration and with the i ROS/RFD to arrange a date on operations schedule with no other reactor operations.

6. Estimated time: One day

7. Safety precautions: Use caution when working around high voltage sources and l minimize exposure to Ar-41 or Na-22 calibration sources.

8. General:

Turn off high voltage and main power before plugging or unplugging any of the circuit boards.

The " unit" refers to the rack mountable electronics section of the SGM.

II. Procedural Sequence:

1. Schedule date for calibration with RFD/ROS and SHD.

2. Assemble required tools and equipment

3. Produce Argon-41 (for argon calibration) with reactor.

Revised: 12 Feb 98 Page 1 j

Suggest: 2 syringes, 50-60 cc P-10 gas irradiated for 5 min at 100 Kw.

ELECTRONIC CAllBRATION

4. Turn off the power. Adjust the kont panel meter to 10 cpm.

5. Remove the CRA-14B/91 card and ensure switches SW1, SW2, and SW3 are open.

I

6. Remove the IC-13 card and set the dip switches into the following configuration:

S1 Closed SS Open (10% Window)

S2 Open S6 Closed (20% Window)

S3 Open S7 N/C S4 Open (5% Window) S8 N/C

{ Gross counting mode S1 Closed, S2 Open, S3 Open.}

{ Spectrometer mode S1 Open, S2 Open, S3 Closed.}

Replace the IC-13 Card.

Place the card extension card into the CRA-14B/91 slot and attach the CRA- ,

14B/91 card to the extension card.

7. Disconnect the detector cable from the back of the SGM unit and attach the test cable to the SGM unit.

Power up the unit.

8. Verify 24 i 4 VDC between pins 19 and 20 on the terminal block inside the back of the unit. If the voltage is outside this range, replace or repair the power supply.

9. Connect a pulse generator to the detector test cable.

10. Attach a test cable from the jack on the face of the AA-13A/91 plastic face mask to a volt meter. The access hole is just below the red high alarm button.

11 Set the pulse generator to create 16,666 cps (1x10' cpm).

12. Adjust R33 on the CRA-14B/91 card to give -5.00 i 0.01 VDC.

13. Set the pulse generator to create 166.6 cps (1x10' cpm).

14. Adjust R32 such that the analog meter reads 10,000 cpm.

Revised: 12 Feb 98 Page 2

[

15. Set the pulse generator to create 16.66 cps (1000 cpm).

16. Verify 1000 cpm on the local analog meter.

17. Adjust the potentiometer on the 0-1 mA card such that the remote analog meter in the reactor control room reads 1000 cpm.

18. Adjust the potentiometer on the 0-10 VDC card to give 1000 cpm on the remote ,

chart recorder in the control room. I

19. Monitor the voltage through the AA-13A/91 mask test jack, step through the following inputs, and verify the following outputs.

Pulse Ge:1erator Voltage @ AA-13A/91 10 cpm - 0.00

• 0.15 VDC 100 cpm 1.00 i 0.15 VDC 1000 cpm 2.00

• 0.15 VDC 10,000 cpm 3.00 i 0.15 VDC 1

100,000 cpm 4.00 i 0.15 VDC l 1,000,000 cpm 5.0010.15 VDC

20. Adjust the potentiometer, located above the yellow fail button, white pressing the yellow fail button such that the analog meter reads about 12-15 cpm. Set the pulse generator to 10 cpm. Verify that the fail alarm lamp illuminates when the analog meter needle drops below 12-15 cpm.

21. Press the meter reset and alarm reset buttons.

22. Press the alert and high alarm buttons to note the setting;. Increase the count output of the pulse generator to cross each of these alarm pc:nts and verify that the ,

respective lamps on top of the stack gas monitor illuminate at their set points and that the sonalert alarms at the high alarm point.

23. Power off the unit. Remove the test cables from the front ar d back of the unit.

Set toggle switches to the following configurt.tions: SW1 - Closed, SW2 -Open, SW3 - Open. Replace the CRA-14B/91 card back into its slot. Attach the detector cable to the back of the unit.

24. Remove the IC-13 card and set the dip switches into the following configuration for spectrometer mode:

Revised: 12 Feb 98 Page 3

l 1

S1 Open SS Open (10% Window)  ;

S2 Open S6 Closed (20% Window) i S3 Closed S7 N/C S4 Open (5% Window) S8 N/C Replace the IC-13 card.

25. Power the unit back on. Turn on the high voltage. Press the meter reset button.

26. Insert the Sodium-22 source slowly into the chamber and verify operability of the unit.

27. Determine the proper high voltage and adjust as necessary to find the peak counts for the argon / sodium peak.

A. This is done with the sodium source or a sample of argon in the detector chamber B. Slowly adjust the voltage. Set the voltage such that the maximum counts are read from the analog meter. Be sure that the peak selected is the Argon 41 (1293 Kev) or the Sodium 22 ((1274 Kev) peak and not the sodium 22 (511 Kev) peak. graph the output vrs. voltage if necessary to find the proper peak.

28. Verify that the panel voltmeter displays the high voltage set point i 1 VDC. If the vnitage falls outside this range follow these steps to calibrate the panel .

meter:

A. Verify the 5 volt power supply voltage is within

• 0.1 volt. Adjust if necessary.

B. Turn off the power and disconnect the SGM high voltage supply to the panel meter.

C. Connect a precision DC power supply, turn on the unit, and allow the unit to warm up for 5 minutes.

D. Apply 900 VOC with the precision power supply, adjust the potentiometer on the rear of the panel meter until the readout displays 900.

E. Turn off power reconnect the SGM high voltage supply, turn on the unit and verify that the panel meter displays the high voltage setpoint i 1 VDC.

29. Assist SHD, as needed, in the isotopic calibration using HPP 7-3.

30. After SHD provides the new alarm point numbers, adjust the alarm points.

A. The high alarm point is adjusted by pressing the high alarm button and adjusting the potentiometer located directly above the button to give the proper alarm point reading on the analog meter.

B. The alert alarm point is adjusted by pressing the alert alarm button and Revised: 12 Feb 98 Page 4

l adjusting the potentiometer located directly above the button to give the proper alarm point reading on the analog meter.  !

31. See that a new calibration sticker is placed on the SGM. ' Change the written alarm points at the appropriate locations (At SGM and Control Room Meter).

32. Obtain and file isotopic calibration report required by HPP 7-3 from SHD.

33. Create decay curve for Sodium-22 source to be used for semiannual source  !

test. ,

34. Update TRIGA Tracker.

I Revised: 12 Feb 98 Page5

MEMORANDUM TO FILES Re: Calibration of SGM The SGM was calibrated on . The results are as follows.

Step Point Expected As Left

8. Voltage TB19-20 24

• 4 VDC

12. AA-13A/91 Jack -5.0010.01 VDC

17. Control Room Meter 1000

18. Control Room Chart 1000

19. Inject Signals Pulse Generator Voltage AA-13A/91 Meter Reading 1 0 cpm (O cps) V cpm j 100 cpm (1.666 cps) V cpm 1000 cpm (16.66 cps) V cpm 10,000 cpm (166.6 cps) V cpm  ;

100,000 cpm (1,666 cps) V cpm i 1,00,000 cpm (16,666 cps) V cpm i 1

28. Panel Voltmeter H.V. Sctpoint i I

Fail Lamp Operates YES/NO j Warning Lamp Operates YES/NO High Lamp Operates YES/NO Audible Alarm Operates YES/NO High Voltage Set Point VDC Alert Alarm Set Point epm High Alarm Set Point cpm Counts Generated From Sodium-22 Source cpm Revised: 12 Feb 98 Page 6

d Facility Modification Work Sheet 1 10 CFR 50.59 Analysis Proposed change: Replacement of Reactor Distillation Unit with AFRRI water purification system.

Submitted by: George Date _6 March 98_

1. Description of change:

R;moval of the reactor distillation unit as the primary source of make up wat'.. and replace with the AFRRI water purification system.

The water will be run through two demineralizer beds before being added to the reactor water holdup tank to ensure purity. The UV lamp will remain in the hold up tank to sterilize the water in the tank.

2. Reason for change:

The ag i ng reactor still needs to be repaired and replumbed. The reactor j still rakes about 6-8 gallons of water per hour where over 100 gallons of water can be drawn per hour from the AFRRI system. With the hold up tank from the still remaining in place, the system could supply 4 times the makeup capability of the current system.

3. Verify that the proposed change does not involve a change to the Tschnical Specifications or produce an unresolved safety issue as epecified in 10 CFR 50.59(a) (2) . Attach an analysis to show this.

Analysis attached? Yes _XX_

4. The proposed modification constitutes a changes in the facility or an operational procedure as described in the SAR. Describe which (check all that apply)

Procedure _XX_ Facility _XX_ Experiment i

)

l I

Facility Modification Work Shtet 1

(

5. Specify what sections of the SAR are applicable. In general terms )

describe the necessary updates to the SAR. Note that this description need not contain the final SAR wording.

In Section 3.3.4, the AFRRI water purification system will replace the reactor still.

Drawing 3-6 on page 3-44, change still water tank to water tank See attached for SAR wording.

)

6. For facility modifications, specify what testing is to be performed to assure that the systems involved operato in accordance with their design intent.

Flow rate will be measured from the output of the demineralizer resins,  !

upon installation, to verify that the flow rate of water added to the i water tank is comparable to the current flow rate.

l i.____._.._.

1 l

k Facility Modification Werk Sheet 1 )

i

7. Specify associated information.

New drawings are: Attached -XX~

Not required Does a drawing need to be sent to Logistics? Yes _XX_ No Are training materials effected? Yes _XX_ No Will any Logs have to be changed? Yes No _XX_

Are other procedures effected? Yes _XX_ No List of items effected:

Annual maintenance procedure for the reactor still will be eliminated.

Question bank to be searched and updated for questions on the make up water system i The operations manual will be updated.

I

8. Create an Action Sheet containing a list of associated work specified in items #7, attach a copy, and submit another to the RFD. 1 Action Sheet: Submitted._XX_ Not Required i

Rsviewed and approved by RFD IYI Date hL3 ]M

~ ,v fpO 0 ) APR I 31998

.RRFSC Concurrence Date I

I ACTION SHEET

/ Remove procedure M027 (Still Cleaning and Inspection) from triga tracker and procedure book.

J Replace procedure M042 (Change Resin Beds for Water Makeup System) with procedure for new demineralizer beds.

/

Verify Technical Specifications do not need changed.

J

_ Verify that an unresolved safety issue is not created.

/ Update section 3.3.4 of the SAR. i

/ Update drawing 3-6 in SAR.

/ nstall I new water system.

'. /

v Verify flow rate of > 8 gallons per hour from new system. '

j V Remove existing still unit from service.

1 Update as built drawings )

/ Update operations manual (training document).

/ Search question bank for questions on still and remove. Add questions for the new 3- system. (training document).

1

)

I 1

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. 7.,,.g.,g.cg., mg ,g.mg,, , . , , . , . ~ . .. f (MAINTENANCERRO.CED.URE-- i 1., 1.m 1 * . m,,_ LM0421 i l

Change Resin Beds For Water Makeup System I. General

1.

Reference:

Manufacturers Literature

2. Requirements: As needed

3. Tools: None

4. Equipment: None

5. Coordination: None

6. Estimated Time: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> l

11. Procedural Sequence:

1. Determine that a demineralizer needs to be changed. There is a lamp on top of the demineralizer which will go out when the resins need changing.

The lamp may come on if there has been no flow of water through the unit.

To ensure the resins have been exhausted, open sample port and run water  ;

through the resins beds for one to two minutes.

2. Close the water supply valve to the resin bed hous'ags. .

3. Unscrew the housing and lower carefully so as not ,'o damage the distributor tube. Remove the o-ring, dump out the resin and cleen out the housing.

The exhausted resin can be disposed of into any waste container as there is no danger of any hazard.

4. Before loading, make sure the bottom strainer of the distributor tube is inserted into the socket at the bottom of the housing. Carefully pour in the resin from one jar of resin. After loading, clean the threads, o-ring groove and the top surface of the housing of all resin beads. Wipe the 0-ring dry and place into the groove in the housing. Lightly lubricate the top surface l of the o-ring.

5. Replace the housing, hand tighten, and reapply the water supply. l

, -vow 1

i l

l

' Analysis for reactor water purification system replacement project:

Technical Specificalons:

• The pool water makeup system is not specifically mentioned in the Tech Specs. The requirement is that the conductivity of the bulk pool water be maintained at 200,000 ohms or greater.

Safety Analysis Report:

The water purification system is designed to replace water due to normal evaporation.

Water loss beyond the capability of the water purification system is addressed by other systems covered elsewhere in the S AR, and remains unchanged.

- The replacement system meets or exceeds the makeup system currently being used.

A backup for the primary water purification exists, and remains unchanged.

Other Items Considered:

Failure of the primary water makeup system does not affect the pool water level, or the ability to add water due to loss from normal operations.

The limiting conditions for operations (conductivity of the bulk pool water) does not change as a result of the replacement

• The conductivity of the bulk pool water will be maintained at or above the Technical Spt:cification requirement at all times.

i

)

i

EXISTING VERSION 3.3.4 Primary Water Makeup System The primary water makeup system replaces any primary coolant water lost due to evaporation from the pool surface. The evaporation of 66 gallons of primary water results in an approximate one inch decrease in the pool water level. During normal operations, approximately 80 gallons of primary water are lost each week due to evaporation, depending on the season of the year The primary water makeup system consists of a 100 gallon holding tank and distillation unit (still) connected via valving and piping to the primary water makeup line. This system is capable of using raw industrial water as feed water. In the event of a primary makeup water system failure, the replenishing of the evaporated reactor pool water is achieved via a straight-feed system (with valving and coupling) which contains a mixed-bed demineralizer and filter system. This system is also capable of using raw industrial water as feed water. The discharge line from the holdup tank is several feet above the reactor pool, which allows the makeup water to be gravity-fed to the reactor pool. This makeup water line is located along the east wall of the reactor pool and discharges the makeup water above the surface of the pool.

PROPOSED VERSION 3.3.4 Primary Water Makeuo System The primary water makeup system replac'es any primary coolant water lost due to evaporation from the pool surface. The evaporation of 67 gallons of primary water results in an approximate one inch decrease in the pool water level. Depending on the season of the year, up to 80 gallons of primary water are lost each week due to evaporation. The primary water makeup system consists of a water feed line from the AFRR1 water purification system and a 100 gallon holding tank connected via vahing and piping to the primary water makeup line. In the event of a primary makeup water system failure, the replenishing of the evaporated reactor pool water is achieved via a straight-feed system (with valving and coupling) which contains a mixed-bed demineralizer and filter system This system is also capable of using raw industrial. water as feed water. The discharge line from the holdup tank is sbove the reactor pool, which allows the ,

makeup water to be gravity-fed to the reactor pool. This makeup water line is located along the l east wall of the reactor pool and discharges the makeup water above the surface of the pool.

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Facility Modification Work Shsat 1 10 CFR 50.59 Analysis Proposed Change: Remove all References to Criticality Monitor R5 from SAR Submitted by: George Date 13 March 1998

1. Description of change:

This change is to remove all references to the Radiation Area Monitor (RAM) R5 from the SAR. RAM R1 will be moved from above the reactor pool to the east wall of the reactor room over the hot table, and RAM R5 will be moved to another location in the reactor room and be used as a spare RAM. Both RAMS will have a designated alarm point set to alert personnel of radiation in the area of the detector.

An additional radiation monitor will be added around the reactor dolly to inform operators working over the core when radiation levels are above come predetermined setpoint.

Various procedures (attached) will be updated to reflect this change.

2. Reason for change:

i Radiation levels above the reactor pool for typical operations, are above l the 20 millirem night time setpoint for RAMS R1 and R5. Typical )

operations require changing these set points to prevent alarms. An NRC l inspector recommended changing the RAM locations so that alarm points ]

would not have to be changed prior to high power runs or pulses. '

10 CFR 70.24 specifies that an accident criticality monitor is required for storage of nuclear material. Because the nuclear material is in a reactor core and not in storage, an accidental criticality monitor is not )

applicable. .

l

3. Verify that the proposed change does not involve a change to the Technical Specifications or produce an unresolved safety issue as cpecified in 10 CFR 50.59(a) (2) . Attach an analysis to show this.

Analysis attached? Yes XX

4. The proposed modification constitutes a changes in the facility or an operational procedure as described in the SAR. Describe which (check all that apply).

Procedure _XX_ Facility _XX_ Experiment

Facility Modification Work Shsst 1

5. Specify what sections of the SAR are applicable. In general terms describe the necessary updates to the SAR. Note that this description ,

need not contain the final SAR wording. l 1

Section 3.6.5. Remove reference to R5 being criticality monitor.

Table 3-1. Change location of RAM R1 l Figure 3-13 RAM locations and names. 1 l

l l

l i

6. For facility modifications, specify what testing is to be performed I to assure that the systems involved operate in accordance with their I design intent.

Channel test to be preformed. Unit will not be altered. Only the location of the detector head will be moved.

i Facility Modification Work Sheet 1

7. Specify associated information.

New drawings are: Attached Not required _XX_

Does a drawing need to be sent to Logistics? Yes No _XX_ i Are training materials effected? Yes ~

No l Will,any Logs have to be changed? Yes -XX No _XX_

Are other procedures effected? Yes _XX_ No List of items effected:

As built drawings, Location of RAMS Startup Checklist Shutdown Checklist Pulse procedures (critical and subcritical)

Nuclear Instrumentation Setpoint Check sheet SAR sections 3.6.5 SAR Table 3-1 (Page 3-26) Figure 3-13 (page 3-51)

8. Create an Action Sheet containing a list of associated work specified in items #7, attach a copy, and submit another to the RFD.

Action Sheet: Submitted _XX_ Not Required l

/

Reviewed and approved by RFD .( < Date ~$ /h./ c * ;.!

/

('

1 I

RRFSC Concurrence b Date c:spt$059cnt. anach: cntana entaar, critsar2.cntygl/op8clopbl/ophilop8b, h:rdrivebpBg2ch2,

ACTION SHEET: Criticality Monitor t/ Change startup checklist to leave R1 and R5 set points unchanged

./ Change shutdown checklist to leave R1 and R5 set points unchanged V Change alarm points on safety checklist for RAM's R1 and R5 Change Nuclear Instrumentation set point check sheet to reflect current set points for R1 and R5.

l

-/ Remove RAM adjustments from subcritical pulse procedure i

V Remove RAM adjustments from critical pulse procedure  ;

1. Change SAR section 3.6.5 to remove reference about RAM R5 as criticality monitor

1. Change SAR Table 3-1, location of RAM R1

1. Change Figure 3-13 l 1

v' Move RAM R1 and R5 to new location in reactor deck l Search and update question bank for R1 and R5 questions Update Chapter 6 of operations training manual on RAM locations and alarms.

Search training program for data on RAMS

/ Replace procedures in procedure books Update procedure files on R: drive

=====,

s

Analysis for moving RAM R1 and R5 Technical Specifications: The Effect of Moving RAMS R1 and R5 The Technical Specifications does not specify where in the reactor room RAM R1 will be located. RAM R5 is not required by the Technical Specifications.

Safety Analysis Report: Effect on SAR for fuel cladding failure accident.

The SAR states that the maximum inventory of fission products released from a single TRIGA fuel element operating at full power would produce an exposure rate in the reactor room of about .2 Rem / hon: from the noble gas mixture. The movement of the Radiation Area Monitor (RAM) detectors within the reactor room will not effect in the readings because the radioactive gas would distribute equally throughout the room Safety Analysis Report: Effect on SAR loss of shielding water accident.

The SAR states that a loss of shielding water would produce a predicted gamma dose rate of approximately 300 mrem /hr 10 feet from the pool due to skyshine. Dose readings directly over the reactor core are expected to be approximately 3.2 Rem /r. The location of the detector would be moved from over the pool to a location on the wall approximately 10 feet from the edge of the pool. The alarm point for Ram R1 will be 10 millirem and would alarm in either location. The movement of the ram would not change its ability to alarm in a loss of shielding water accident.

Ability for RAM R1 to detect fuel being removed from the pool A fuel element emitting a dose rate as little as 4 Rem at one foot, would alarm any RAM unit that is within 20 feet of the source. Each of the RAMS will be approximately 10 feet from the edge of the reactor pool. Fuel removed from the reactor deck would have to pass within 20 feet of one or more RAMS. Removal of fuel from the reactor pool would therefor be detected by the RAMS.

EXISTING VERSION 3.6.5 critiatiev unnienre Criticality monitors are used to detect and measure acute radiation dose levels, in excess of those measurable with personnel monitors, in the event of a criticality accident occurring in an inhabited work  !'

area. Here are two types of criticality monitors used at AFRRI.

he reactor room criticality monitor is mounted at the end of the trail cable boom directly above the core carriage. There is only one of these units associated with the reactor. This unit monitors gamma radiation emitted by fuel elements stored in the reactor pool as well as the reactor core itself when the reactor is secured. The unit is attached to an uninterruptible power supply which can provide continuous power in the event of an electrical power outage at the facility. His criticality monitor consists of a scintillation detector and is capable of measuring gamma radiation with energies great:r than 80 kev. The reactor room criticality monitor has a range of I mrem /hr to 10' mrem /hr, and a nominal accuracy of il5 percent at all levels. He unit is designed to activate a radiation alarm, both audible and visual, at an adjustable, preset level. The unit's readout meter and radiation alarms are located in the reactor control room. He reactor room criticality monitor also activates a visual alarm in the reactor control room when a toss of high voltage to the detector or a foss of signal occurs. The alarm setpoint is given in the appropriate AFRRI internal documents' and conforms to 10 CFR 70.24.

"The second type of criticality monitor at AFRRI is the criticality accident dosimeter which contains l i

various metal foils and other materials which are activated when exposed to large neutron and gamma radiation fields. In case of a criticality accident, the activated materials can be analyzed and the total integrated dose calculated. These dosimeters measure neutron exposures above I rem deep-dose equivalent (H 4) and gamma exposures above 50 rems H . The dosimeters are also capable of measuring exposures within discrete energy levels of the neutron specuum. The foils and materials utilized in these dosimeters are contained in vials and the units are mounted on red plaques in the following locations:

o North wall of the reactor room o East wall of the reactor room (2) o South wall of the reactor room o Ceiling of the reactor room o East wall of the reactor control room o West wall of Hallway 3106 o North wall of room 3152 o in room i120 by the heat exchanger

1 i

PROPOSED VERSION 3.6.5 criticaliev Mnniinrs he accidental criticality monitor is a dosimeter which contains various metal foils and other inaterids which are activated when exposed to large neutron and gamma radiation fields. In case of a criticality accident, the activated materials can be analyzed and the total integrated dose calculated. Rese dosimeters measure neutron exposures above I rem deep-dose equivalent (HJ and gamma exposures above 50 rems H,. The dosimeters are also capable of measuring exposures within discrete energy levels of the neutron spectrum. The foils and materials utilized in these dosimeters are contained in vials and the units are mounted on red plaques in the following locations:

o North wall of the reactor room o East wall of the reactor room (2) o South wall of the reactor room )

o Ceiling of the reactor room o East wall of the reactor control room o West wall of Hallway 3106 o North wall of room 3152 o in room i120 i

i l

4

EXISTING VERSION TABLE 3-1 REACTOR REMOTE AREA MONITORS RAM LOCATION READOUT RADIATION ALARM R-1 Approximately 2 feet Meter in reactor control Activates audible and visual above the reactor room and Emergency alarm in the reactor room and in tool surface on the Response Center (Room the reactor control room; cast side c< tne 34?O) activates visual alarm in the reactor pool Emergency Response Center (Room 3430); activates visual and optional audible alarm on annunciator panel in Hallw2y 3101 R-2 Approximately 7 feet Same as R-1 Activates visual alarm in the atuve the floor on reactor control room and in the the reactor room Emergency Response Center west wall (Roam 3430)

E-3 6 feet above the floor Same as R-1 Same as R-2. In addition, a on the west wall prep visual and audible local alarm area opposite ER #1 exists in the prep area near ER #1 plug door and a red light ai the front desk E-6 6 feet above the floor Same as R-1 Same as E-3 except the visual and on the west wall prep audible local alarm exists in the area opiusite ER #2 prep area near ER #2 plug door ER' #2 l

1

i PROPOSED VERSION TAPLE 3-1 i l

REACTOR REMOTE AREA MONITORS RAM LOCATION READOUT RADIATION ALARM l l

'l R-1 Approximately 7 feet Meter in reactor control Activates audible and visual above the floor on room and Emergency alarm in the reactor room and in the reactor room east Response Center (Room the reactor control room; j wall 3430) activates visual alarm in the Emergency Response Center l (Room 3430); activates visual and optional audible alarm on annunciator panel in Hallway 3101 R2 Approximately 7 feet Same as R-1 Activates visual alarm in the above the floor on reactor control room and in the the reactor room Emergency Response Center west wall (Room 3430)

E3 6 feet above the floor Same as R-1 Same as R-2. In addition, a on the west wall prep visual and audible local alarm area opposite ER #1 exists in the prep area near ER #1 plug door and a red light at the front desk E-6 6 feet above the floor Same as R-1 Same as E-3 except the visual and on the west wall prep audible local alarm exists in the area opposite ER #2 prep area near ER #2 plug door ER #2 l

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1 b!h h)I$NNNhNbkMMN hh DAILY OPERATIONAL STARTUP CHECKLIST l Checklist No. Date Time Completed Supervised by Assisted by

/

I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) . .

2. Water drained from air compressor . .. . . .

3. Air dryer operating .

4. Doors 231,231 A, and roof hatch SECURED ... . ..

II. LOBBY AREA Lobby alarm turned off . . . .  ;

III. EQUIPMENT ROOM (Room 2158) 1 Prefilter differential pressure (< 8 psid) 2 Primary discharge pressure (15 - 25 psig) . . .

3. Demineralizer flow rates set tc,6 gpm (5.5 - 6.5 gpm)

4. Stack roughing filter (notify supervisor if > 1.0" of water) .

5. Stack absolute filter (notify supersisor if > 1.35" ofwater)

6. Visualinspection of area .. . .

7, Door 2158 SECURED . . ..

IV PREPARATION AREA Visual inspection of area V REACTOR ROOM (Room 3161) 1 Transient rod air pressure (78 - 82 psig) 2 Shield door bearing air pressure (8 5 - 11 psig)

3. Visual inspection of core and tank 4 Number of fuel elements and Fuel elemerts control rods in tank storage Control rods

5. Air particulate monitor (CAM)

(a) Primary operating and tracing (b) Backup operating (c) Channel test completed, damper closure verified

6. Channel test completed on SGM ,

7. Door 3162 SECURED .

• Numerical Entry AFRR1 Form 62a (R) Revised: 24 Nov 97 R:\PROCEDWP\0P_8B.WP6 Page 1

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset . .. ... .. .. . ...........

2. Console recorders dated . .. . .... . .. .. ...., . .

3. Stack flow and fuel temperature recorders dated ..... .. ......... .

4. Logbook dated and reviewed .......... . . . . . . . . . . . . . . . . . . . . . _ _

5. Water monitor box (a) Background activity (10 - 60 cpm) . . . . . . .... ... ..

(b) Water monitor box resistivity (> 0.2 Mohm-cm) .. ..... .....

(c) DM1 resistivity (> 0.5 Mohm-cm) . ... .. ................ .

(d) DM2 resistivity (> 0.5 Mohm-cm) . . ... .... . .......

6. Stack gas flow rate (15 - 35 Kcfm) ..... . ......

7 Stack linear flow rate (1.0 - 2.0 KfVmin) . . . .. . . . ... ....

8. Gas stack monitor (a) Background (2 - 20 cpm) . .... .. .. . . .. .. ..

(b) Alarm check . . . ....... ........ . ... .

(c) High alarm set to 3.2 E-5 microCi/cc at stack top ... . .. . . .

(d) .SGM chart recorder operating and tracing . .. . .. . .... .

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr)

(a) R-1 (< 20) 500 (b) R-2 (< 10) 10 (c) R-3 (< 10) 10

• 500 (d) R-5 (< 20)

(e) E-3 (< 10) 10 (f) E-6 (< 10) 10

10. TV monitors on .. . . . ..... .... ..... . ..  !

11. CAM high level audible alarm check . ........... . . ..... ..

12. Water temperature (inlet)(5 - 35 *C) . .. . . .. . ..

l

13. Water level log completed .. ... .... ..... . .  ;

14. Console lamp test completed . . .. ... .

15 Time delay operative . . .. . .

i 16 Source level power greater / equal io 0 5 cps . . ... .

17. Prestart operabili' checks performed . . . .. . .

1

18. Interlock Tests (a) Rod raising. SS mode (e) I kW/ Pulse mode j (b) Rod raising, Pulse mode (f) NM-1000 HV i (c) Source RWP (g) Inlet Temp (d) Period RWP 19 SCRAM checks (at least one per rod)

(a) % Power I (h) Reactor key (b) % Power 2 (i) Manual (c) Fuel temp 1 (j) Emergency Stop (d) Fuel temp 2 (k) Timer (e) HVloss 1 (1) CSC Watchdog (f) HV loss 2 (m) DAC Watchdog (g) Poollevel

20. Zero power pulse . .. . . .. . .. ..

• Numerical Entry AFRRI Form 62a (R) Revised: 24 Nov 97 R:\PROCEDWP\0P,_8B.WP6 Page 2

M C M fI2 @ IkhIAN$EMBE #NMkN hh DAILY OPERATIONAL STARTUP CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) . . . .

2. Water drained from air compressor . ...

3. Air dryer operating . . . . . . . . ,

4. Doors 231,231 A, and roof hatch SECURED ... . . . .. . . . ..

11 LOBBY AREA Lobby alarm turned off .. . . . .

111. EQUIPMEh ROOM (Room 2158)

1. Prefilter difTerential pressure (< 8 psid)

2. Primary discharge pressure (15 - 25 psig) . . . .

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) . . .

4. Stack roughing filter (notify supenisor if > 1.0" of water) .

5. Stack absolute filter (notify supenisor if > 1.35" ofwater) .....

6. Visualinspection of area .. . . .

7. Door 2158 SECURED . .

IV. PREPARATION AREA Visual inspection of area .

V. REACTOR ROOM (Room 3161)

1. Transient rod air pressure (78 - 82 psig) 2 Shield door bearing air pressure (8 5 - 1 I psig) 3 Visual inspection of core and tank 4 Number of fuel elements and Fuel elements

• control rods in tank storage Control rods

5. Air particulate monitor (CAM)

(a) Primary operating and tracing (b) Backup operating (c) Channel test completed, damper closure verified

6. Channel test completed on SGM .

7. Door 3162 SECURED .

• Numerical Entry AFRRI Form 62a (R) Revised: 18 March 98 C:\WP\CRITOP8B.WP6 Page1

o VI. REACTOR CONTROL ROOM (Room 3160)

. l. Emergency air dampers reset - . .. .. ............. ...... ...

2. Console recordera dated ... ........ . ........... ............. .

3. Stack flow and fuel temperature recorders dated ........... ...........

4. Logbook dated and reviewed .. ...... ............ ............. .

5. Water monitor box (a) Background activity (10 - 60 cpm) . . . . . . . . . . . . . . . . . . . . . . . . . 4 (b) Water monitor box resistivity (> 0.2 Mohm-cm) ............ I (c) DMi resistivity (> 0.5 Mohm-cm) . .............. ... .. .

)

1 (d) DM2 resistivity (> 0.5 Mohm-cm) ... .... ... ...... .... ..

6. Stack gas flow rate (15 - 35 Kcfm) . . ... . . . . . . . . . . . . .

I l

7. Stack linear flow rate (1.0 - 2.0 KfVmin) . . . . . . .. . .......... . .

8. Gas stack monitor (a) Background (2 - 20 cpm) .. ... ......... .. ........ . ...

(b) Alarm check . . . . . . . . ...... . . ... .......... ...

(c) High alarm set to 3.2 E-5 microCi/cc at stack top ..... ... ..

(d) SGM chart recorder operating and tracing ... ... .. .

9, indiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrern/hr)

(a) R-1 (< 10) 10 l_

(b) R-2 (< 10) 10 (c) R-3 (< 10)

, 10 (d) R-5 (< 10) 10 l (e) E-3 (< 10) 10 (f) E-6 (< 10) 10

10. TV monitors on. .. . . . .. .. j

11. CAM high level audible alarm check . . ...... ..  !

12. Water temperature (inlet)(5 - 35 *C) . . . . .

13. Water levellog completed . . .. . .

14. Console lamp test completed . . . . ... ... .. .... . l

15. Time delay operative .. . . .

16 Source level power greater / equal to 0.5 cps . . .. .

17. Prestart operability checks performed .. . . . . . . . ..

18. Interlock Tests (a) Rod raising, SS mode (e) I kW/ Pulse mode (b) Rod raising, Pulse mode (f) NM-1000 HV (c) Source RWP (g) Inlet Temp ,

l (d) Period RWP

19. SCRAM checks (at least one per rod)

(a) % Power 1 (h) Reactor key (b) % Power 2 (i) Manual (c) Fuel temp 1 (j) Emergency Stop (d) Fuel temp 2 (k) Timer (e) HV loss I (1) CSC Watchdog (f) HV loss 2 (m) DAC Watchdog (g) Poollevel

20. Zero power pulse . . .. .

• Numerical Entry AFRRI Form 62a (R) Revised: 18 March 98 C:WMCRITOP8B.WP6 Page 2

mawemmm, . . -, - .~ . s-~~w m OPERATIONARPROCEDU_RE ; n S/t  :'M 's F [; g.;.,m Pawce,, dure 8. TAB I' iQ DAILY OPERATIONAL SHUTDOWN CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by

1. REACTOR ROOM (Room 3161)

1. All rod drives DOWN . . . ... . .

2. Carriage lights OFF . .

3. Door 3162 SECURED .

4. Channel test completed on both CAM's ..

5. Door 3161 locked with key . . . . . . . .

II. EQUIPMENT ROOM (Room 3152)

1. Distillation unit discharge valve CLOSED

2. Air dryer OPERATIONAL . . . .

3. Doors 231,231 A, and roof hatch SECURED . .

111. EQUIPMENT ROOM (Room 2158)

1. Primary discharge pressure (15 - 25 psig) 2 Demineralizer flow rates set to (5 5 - 6.5 gpm)

• 3 Visual inspection for leaks

4. Door 2158 and 2164 SECURED IV PREPARATION AREA

1. ER2 plug door CONTROL LOCKED Door closed; and handwheel PADLOCKED ..

2. ER2 lights ON and rheostat at 10*. .

3. ERI plug door CONTROL LOCKED . ..

Door closed; and handwheel PADLOCKED

4. ERI lights ON and rheostat at 10% .

5. Visualinspection of area .

6. Warm storage doors closed .

AFRR1 Form 62(R) Revised: 1I Feb 97 R:\PROCEDWP\0P_81.WP6 Page 1

V. LOBBY ALARM Lobby alarm audio ON .. . . ... .......... . . .... ..

VI. REACTOR CONTROL ROOM (Room 3160)

1. Reactor tank lights OFF .. ............. ...... . . . . .. . .

2. Console chart recorder pens raised .. ..... ... ... .. . . ..

3. Steady-state timer OFF , .. . ............. ..... .. . . . .

4. Console LOCKED, and all required keys returned to lock box . . ..

5. Diffuser pumps OFF , .. . . . ... . ....... .. . . .

6. Purification, secondary and primary pumps ON . . . ... . ... . .

7. Reactor monthly usage summary completed ... . ... . . . ..

8. Auxiliary chart recorders operating and tracing . .. ...... .. .. .

9. Radiation monitors .... . . . . . . . .. . . . . . . . .

MONITOR READING HIGH LEVEL ALARM SETTING i (mrem /hr) a.R-l (<20) 20

b. R-2

• 10

(<!O)

c. R-3 (<10) 10

d. R-5 (<20) 20 e.E-3 (<10) 10 f E-6

• 10

(<10)

g. R-6 *

(<10)

• Numerical Entry l

i

~

AFRRI Form 62(R) Revised: 1I Feb 97 R:\PROCEDWP\0P_81.WP6 Page 2 1 i

A69McM4WPmMMWX99NMMSM 4%3aW3M' mm.v. :s n ne. Nur}5;. ..m M..,..n-,.hww r,. ..

Q .Ifa%2ROCEDUREQfy%d@M65$@[fd@@y.measud, NiTABl@n,.vfA DAILY OPERATIONAL SHUTDOWN CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by

l. REACTOR ROOM (Room 3161)

1. All rod drives DOWN . . . . . ... . .

2. Carriage lights OFF . . . .

3. Door 3162 SECURED . . .

4. Channel test completed on both CAM's . .

5. Door 3161 locked with key . . .

11 EQUIPMENT ROOM (Room 3152)

1. Distillation unit discharge valve CLOSED .

2. Air dryer OPERATIONAL ,. .

3. Doors 231,231 A, and roof hatch SECURED . . . .

111. EQUIPMENT ROOM (Room 2158) 1 Primary discharge pressure (15 - 25 psig) .

2 Demineralizer flow rates set to (5 5 - 6.5 gptr) 3 Visual inspection for leaks 4 Door 2158 and 2164 SECURED .

IV PREPARATION AREA I ER2 plug door CONTROL LOCKED Door closed; and handwheel PADLOCKED .

2 ER2 lights ON and rheostat at 10% .

3. ERI plug door CONTROL LOCKED .

Door closed; and handwheel PADLOCKED

4. ERI lights ON and rheostat at 10% .

5. Visualinspection of area . .

6. Warm storage doors closed . . .

AFRRI Form 62(R) Revised: 18 March 98 C:\WP\CRITOP8I.WP6 Page 1

V. LOBBY ALARM Lobby alarm audio ON- .. . . ....... .. ........ .......... .

VI. REACTOR CONTROL ROOM (Room 3160)

1. Reactor tank lights OFF .. . . . ... .. .... . ....... ..

2. Console chart recorder pens raised . . .. .. . . . .

3. Steady-state timer OFF .. . . ..... ... .. ... ... .... ..

4. Console LOCKED, and all required keys returned to lock box .., .... .

5. Diffuser pumps OFF .. .. . . .. . ... . ..... ....... . .

6. Purification, secondary and primary pumps ON . . . . . . . ... .. . ..

7. Reactor monthly usage summary completed ... ... .... ..... ..... .

8. Auxiliary chart recorders operating and tracing .. ,... .. .. ..

9. Radiation monitors . .. .. ..... . .... ... ..... . .. I MONITOR READING HIGH LEVEL ALARM SETTING j (mrem /hr)

{

l a.R-1 (<10) 10 l

b. R-2 (<10) 10

c. R-3 (<10) 10

d. R-5 (<10) 10 I e.E-3 (<10) 10

f. E-6 (<l0)

• 10

g. R-6 (<10) 1 1

• Numerical Entry AFRRI Form 62(R) Revised: 18 March 98 C:\WP\CRITOP81.WP6 Page 2 L

TRP54biH#dIEWMifHi@ #TR$%#@@$hfMIM43GliW!if5Bli3fdl DAILY SAFETY CHECKLIST Checklist No. Date I

Time Completed ._

Supervised by Assisted by l

I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) . .. . ... . .

2. Water drained from air compressor .. . . . ... . .

3. Air dryer operating .. . . . .

l

4. Doors 231,231 A and roof hatch SECURED .

II. EQUIPMENT ROOM (Room 2158)

1. Prefilter differential pressure (< 8 psid) .

• i

2. Primary discharge pressure (15 - 25 psig) .

j

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) . .. .

l

4. Stact: roughing filter (notify supenisor if > 1.0" of water) . . .

5. Stack absolute filter (notify supenisor if > 1.35" ofwater)

6. Visualinspection of area . . . . . I

7. Door 2158 SECURED .

111. PREPARATION AREA Visualinspection of area . .

IV. REACTOR ROOM (Room 3161) 1 Transient rod air pressure (78 - 82 psig) 2 Shield door bearing air pressure (8 5 - 11 psig)

3. Visual inspection of core and tank .

4. Number of fuel elements and Fuel elements control rods in tank storage Control rods

5. Air particulate monitor (CAM)

(a) Primary operating and tracing . .

-(b) Backup operating . .

(c) Channel test completed, damper closure verified . .

6. Channel test completed on SGM . . .

7. Door 3162 SECURED -

• Numerical Entry AFRRI Form 62b (R) Revised: 26 APR 96 R:\PROCEDWP\0P_8Bl.WP6 Page 1

l i

V. LOBBY AREA l Lobby audio alarm turned off' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .

1 i

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset .. ... .. . .... ...... . .. .

2. Console recorders dated . . . . . . . . ........ .... ............ ..

3. Stack flow and fuel temperature recorders dated . . . . . . . . . . . . ..... ...

4. Logbook dated and reviewed . . . . .. . . . . . . . .. ..

5. Water monitor box (a) Background activity (10 - 60 cpm) . . . . . . . . . . ... . .. . ..

(b) Water monitor box resistisity (> 0.2 Mohm-cm) *

(c) DMI resistivity (> 0.5 Mohm-cm) . . . . .... ....... ....

(d) DM2 resistivity (> 0.5 Mohm-cm) . . ...... . . . ..

6. - Stack gas flow rate (15 - 35 Kcfm) .. . .... . .. .. .

7. Stack linear flow rate (1.0 - 2.0 KfVmin) . ... .. .. .. . ,.

8. Gas stack monitor (a) Background (2 - 20 cpm) . . ...... . ...... .

(b) Alarm check . .. . .. . ........ .

(c) High alarm set to 3.2 E-5 microCi/cc at stack top .. .. .. .

'(d) SGM chart recorder operating and tracing . . ... . .. . .

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr) .

(a) R-1 (< 20) 20' )

(b) R-2 (< 10) 10 (c) R-3 (< 10) 10 (d) R-5 (< 20) 20 (e) E-3 (< 10) 10 (f) E (< 10) 10 10 TV monitors on .. . . . . . .

I 1. CAM high level audible alarm check ... .

12. Water temperature (inlet)(5 - 35 *C) . .

13. Water levellog completed . . .. . . .. . .. . _

14 Source level power greater / equal to 0.5 cps .

• Numerical Entry AFRRI Form 62b (R) Revised: 26 APR 96 R:\PROCEDWP\OP_8Bl.WP6 Page 2

d kN3h[fNDCNN N IEN DEN $$$N$Ni$NI[$$$' M [NY NN!

DAILY SAFETY CHECKLIST i Checklist No. Date Time Completed Supervised by Assisted by

)

1. EQUIPhiENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) . . . . . .. .

2. Water drained from air compressor . . . . . .... .

3. Air dryer operating .

Doors 231,231 A, and roof hatch SECURED l

11. EQUIPMENT ROOM (Room 2158) l 1

1. Prefilter difTerential pressure (< 8 psid)

2. Primary discharge pressure (15 - 25 psig)

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) ... .. .. .

4. Stack roughing filter (notify supersisor if > 1.0" of water)

5. Stack absolute filter (notify supervisor if > 1.35" of water) ....

6. Visualinspection of area .

7. Door 2158 SECURED .

Ill. PREPARATION AREA Visual inspection of area IV. REACTOR ROOM (Room 3161) i Transient rod air pressure (78 - 82 psig) 2 Shield door bearing air pressure (8 5 - l 1 psig) .

3. Visual inspection of core and tank 4 Number of fuel elements and Fuel elements control rods in tank storage Control rods

5. Air particulate monitor (CAM)

(a) Primary operating and tracing . .

(b) Backup operating .

(c) Channel test completed, damper closure verified .. .

6. Channel test completed on SGM .

7. Door 3162 SECURED . .

• Numerical Entry AFRR1 Form 62b (R) Revised: 18 March 98 C:\WP\CRITOPBl.WP6 Page 1

V. LOBBY AREA i l

Lobby audio alarm turned off . . . . . . . ... . . . . . . . . . . . . . . . .

l VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset . . .. .. . ......

2. Console recorders dated .. . .. .. .. . ..

3. Stack flow and fuel temperature recorders dated . . . . .

4. Logbook dated and reviewed ,. . .. .. ...

5. Water monitorbox (a) Background activity (10 - 60 cpm) .... . .... ...... . .

(b) Water monitor box resistivity (> 0.2 Mohm-cm) . .. .. . . .

(c) DMI resistivity (> 0.5 Mohm-cm) . .

(d) DM2 resistivity (> 0.5 Mohm-cm) . . . . .

6. Stack gas flow rate (15 - 35 Kcfm) . . .. . ... .

7. Stack linear flow rate (1.0 - 2 0 KfVmin) ... . . . . .

8. Gas stack monitor (a) Background (2 - 20 cpm) .. .. . . .

(b) Alarm check . .

(c) High alarm set to 3.2 E-5 microCi/cc at stack top . . .. .

(d) SGM chart recorder operating and tracing

9. Radiation monitors )

Monitor Alarm Point Reading Alarm Setting { l Functional (mrem /hr) (mrem /hr)

(a) R-1 (< 10) 10 l

• 10 (b) R-2 (< 10)

(c) R-3 (< 10) 10 10 I (d) R-5 (< 10)

(e) E-3 (< 10) 10 (f) E-6 (< 10) 10 10 TV monitors on . .

I1 CAM high level audible alarm check . .

12 Water temperature (inlet)(5 - 35 "C) 13 Water level log completed . . .

14. Source level power greater / equal to 0.5 cps . .. .  ;

I l

l i

• Numerical Entry AFRRI Form 62b (R) Revised: 18 March 98 C:\WP\CRITOPB1.WP6 Page 2

i f6P5R iiONdi?pR6CEDUREl (((([]Q][I@l[ lid 5IIIdureij B[d l

NUCLEAR INSTRUMENTATION SET POINTS l GENERAL:

These set points may be adjusted for a specific operation by of the RFD or ROS l but in no case may they be set at a point non-conservative to the technical specifications.

SPECIFIC The following are channel or monitor set points (alarm, scram, rod withdrawal prevent).

1. Scrams:

a. Fuel Temperature 1 & 2: 575 C

b. High Flux 1 & 2: 110% (1.1 MW)

c. Safe Chambers 1 & 2 HV Loss: 20%

d. Pulse Timer: Less than 15 seconds

e. Steady State Timer: as necessary

2. Rod Withdrawal Prevents:

a. Period: 3 seconds b.1 KW (Pulse Mode): 1KW

c. Source: 0.5 CPS d Water Inlet Temperature: 50 degrees C

e. Fission Chamber HV Loss- 20%  !

3. Alarms: l

a. RAMS: As directed in procedures

b. CAMS: 10,000 CPM

c. Stack Gas: 3.2E-5 microCi/cc at stack top

d. Water Mon; tor Box Gamma: 7000 CPM

e. Criticality Monitor (RS): 500 mrem day 20 mrem night  ;

l I

Revised: 24 Nov 97 R:\PROCEDWP\OP_8C.WP6 Page 1

F

[655 Efi6 IEFRUC56URE.! 3 ["%@ @@%lik((@ [ % If5[iN$y NUCLEAR INSTRUMENTATION SET POINTS GENERAL:

These set points may be adjusted for a specific operation by of the RFD or ROS but in no case may they be set at a point non-conservative to the technical specifications.

SPECIFIC The following are channel or monitor set points (alarm, scram, rod withdrawal I prevent).

1. Scrams:  !

a. Fuel Temperature 1 & 2: 575 C

b. High Flux 1 & 2: 110% (1.1 MW)

c. Safe Chambers 1 & 2 HV Loss: 20%

d. Pulse Timer: Less than 15 seconds

e. Steady State Timer: as necessary

2. Rod Withdrawal Prevents:

a. Period: 3 seconds b.1 KW (Pulse Mode): 1KW

c. Source: 0.5 CPS

d. Water inlet Temperature: 50 degrees C

e. Fission Chamber HV Loss: 20%

3. Alarms:

a. RAMS: As directed in procedures

b. CAMS: 10,000 CPM

c. Stack Gas: 3.2E-5 microCi/cc at stack top

d. Water Monitor Box Gamina: 7000 CPM Revised: 18 March 98 C:\WPiCRITOP8C.WPS Page 1

1 1

[OPERhTIONAllPROlCEDUREj ,

d[dih Mg@ooedure 8,"T B G2 l

PULSE OPERATION (SUBCRITICAL) j GENERAL Pulses above $2.00 must be approved by the RFD (prior to pulse initiation). Specification on the RUR may be used to meet this requirement.

SPECIFIC

1. Set the alarm points on R-1 and R-5 (criticality monitor) to full scale. Tum over the RAM indicator sign to denote that the RAMS are tumed up.

2. Given a core position, set the transient rod at a position corresponding to the dollar value determined by the following equation:  ;

l

$ Value = Total worth ($) Transient rod (to 100% or mechanical stop) -

l Desired pulse ($) Value 1

3. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements. l Do not use Automatic Mode until the three standard rods have been raised at least 5%

Note: A series of repetitive pulses may be fired using the same rod positions on the same day as long as the reactor power is not increasing and is less than 1 kW.

4 Stabilize in the manual mode.

5. Select the proper pulse detector according to the table below. If the Cerenkov detector is selected, tum off the reactor room and tank lights.

Detector 1 = Pulse ton (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = $4.00) 6 Adjust Pulse Mode Scram Timer if necessary. ,

7. Scram the Transient rod.

8. Raise the Transient rod anvil to 100% or the mechanical stop if installed.

Revised: 24 Nov 97 R:\PROCEDWP\0P_8G2.WP6 Page 1

9. Let the power decay to approximately 1 watt or less.

10. Enter Pulse Mode and select high or low resolution pulse display. High resolution displays 1200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulse number at the next prompt.

11. Fire the pulse by der essing the " Fire" button on the reactor console.

12. Record the appropriate data in the reactor operations logbook from the pulse display.

13. Reset R-1 and R-5 to their normal alarm points when pulsing operations are complete and tum over the RAM indicator sign to denote that the RAMS are set back to normal.

l I

l i

Revised: 24 Nov 97 R:\PROCEDWP\0P_8G2.WP6 Pags 2

[dN55 ii6s INN dEdUFEEf ~ K T " P ' '# $ k IDEA d d 5 5 d d 2 PULSE OPERATION (SUBCRITICAL)

GENERAL Pulses above $2.00 must be verbally approved by the RFD (prior to pulse initiation) or specified on the RUR, signed by the RFD.

SPECIFIC l

1. Given a core position, set the transient rod at a position corresponding to the dollar value determined by the following equation:

$ Value = Total worth ($) Transient rod (to 100% or mechanical stop) -

Desired pulse ($) Value

2. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements.

Do not use Automatic Mode until the three standard rods have been raised at least 5%

Note: If a series of repetitive pulses are to be fired, it is not necessary to bring the reactor to cold critical for each pulse. Consecutive pulses may be fired using the same rod positions on the same day as long as the reactor power is not increasing and is less than 1 kW.

3. Stabilize in the manual mode.

4. Select the proper pulse detector according to the table below, if the Cerenkov l

detector is selected, turn off the reactor room and tank lights.

Detector 1 = Pulse ion (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = $4.00)

~

5. Adjust Pulse Mode Scram Timer if necessary.

6. Scram the Transient rod. '

i

7. Raise the Transient rod anvil to 100% or the mechanical stop if installed. '

Revised: 16 March 98 H:\ USERS \EVERYONE\RDRIVE\0P8G2CH2.WBgb 1 i

8. Let the power decay to approximately 1 watt or less unless otherwise dictated by experimental constraints. Pulses may not be initiated above the Technical Specification ikW limit.

9. Enter Pulse Mode and select high or low resolution pulse display. High resolution  ;

displays 1200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulse number at the next prompt.

10. Fire the pulse by depressing the " Fire" button on the reactor console. )

l

11. Record the appropriate data in the reactor operations logbook from the pulse display. q l

{

l 1

l l

Revised: 16 March 98 H:\ USERS \EVERf5sE\RDRIVE\OP8G2CH2.WB@e 2

$PERATI .NAll!ROCEDURE [ [I Cd$ foe 8, TAB G1 PULSE OPERATION (CRITICAL)

GENERAL Pulses above $2.00 must be approved by the RFD (prior to pulse initiation). Specification on the RUR may be used to meet this requirement.

SPECIFIC

1. Set the alarm points on R-1 and R-5 (criticality monitor) to full scale. Tum over the RAM indicator sign to denote that the RAMS are tumed up.

2. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements. Note:

A series of repetitive pulses may be fired using the same rod positions on the same day as long as the reactor power is not increasing and is less than 1 kW.

3. Stabilize in the manual mode.

4. Raise the transient rod anvil to the desired pulse position. (This position is obtained from the control rod worth curves for the appropriate core operating position)

5. Select the proper pulse detector according to the table below, if the Cerenkov detector is selected, turn off the reactor room and tank lights.

Detector 1 = Pulse ion (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = $4.00)

6. Adjust Pulse Mode Scram Timer if necessary.

7. Enter Pulse Mode and select high or low resolution pulse display. High resolution displays 1200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulse number at the next prompt. Remember, the power level must be below 1 kW to enter Pulse Mode.

8. Fire the pulse by depressing the " Fire" button on the reactor console.

9. Record the appropriate data in the reactor operations logbook from the pulse display.

10. Reset R-1 and R-5 to their normal alarm points when pulsing operations are complete Revised: 24 Nov 97 R:\PROCEDWP\OP_8G1.WP6 Page 1

and tum over the RAM indicator sign to denote that the RAMS are set normal.

l l

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i I

Revised: 24 Nov 97 R:\PROCEDWP\OP_8G1.WP6 Page 2

$5hfl6 ]fNdC.5UUNE3~ " " [ 1 7 @[ @ 13fiiT5dOkE@X(UI PULSE OPERATION (CRITICAL)

GENERAL Pulses above $2.00 must be verbally approved by the RFD (prior to pulse initiation) or specified on the RUR, signed by the RFD.

1 SPECIFIC l '

1. Bring the reactor critical at less than 1000 watts using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements.

2. Stabilize in the manual mode.

3. Raise the transient rod anvil to the desired pulse position. (This position is obtained from the control rod worth curves for the appropriate core operating position)

4. Select the proper pulse detector according to the table below. If the Cerenkov detector is selected, turn off the reactor room and tank lights. 1 Detector 1 = Pulse lon (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = $4.00)

5. Adjust Pulse Mode Scram Timer if necessary.

6. Enter Pulse Mode and select high or low resolution pulse display. High resolution displays 1200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulse number at the next prompt. Remember, the power level must be below the 1 kW Technical Specification limit to enter Pulse Mode.

7. Fire the pulse by depressing the " Fire" button on the reactor console.

8. Record the appropriate data in the reactor operations logbook from the pulse display.

l Revised: 16 March 98 C:\WP\CRITOPG1.WP6 Page 1

Facility Modification Work Shaet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Pulse Mode Operation (Sub-critical), RE: Redefining initial conditions for repetitive pulse firings Modificatio.. to: Procedure _X_ Facility Experiment Submitted by: ORTELLI, GEORGE Date

1. Description of changes: The change in paragraph #3 redefines pre-requisite conditions for the firing of each pulse in a. series of pulses. Previously, the procedure required that before firing a pulse, it was necessary to bring the reactor to cold critical, but did not define whether this was only an initial requirement, or was to be met in all conditions. It could potentially cause confusion with a following statement in the procedure that states that the reactor power must be less than 1 KW in order to fire a pulse (which is a tech spec requirement). It is now proposed that only the <1 KW requirement be required, and to state clearly that there is no requirement to attain a cold critical status subsequent to the firing of an initial pulse that is part of a repetitive series.

The change in paragraph #9 gives latitude for meeting a 1 watt power level before entering pulse mode. Previously, the paragraph stated that the power must decay to less than 1 watt before entering pulse mode, regardless of any circumstances. It is now proposed that experimental constraints may dictate whether or not the 1 watt power level requirement be met.

2. Verify that the proposed change does not involve a change to the Technical

.secifications, the facility as described in the SAR, or procedures as described 1.. the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59 (a) (2) .

The proposed change does not affect any of the above.

3. If change involves a facility modification, attach a drawing if appropriate. If '

structural facility drawings need updating, forward a copy of changes necessary to Facilities.

Change does not involve facility modification j

4. Determine what other procedures, logs, or training material may be affected and record below.

1

)

None are affected j

5. List of associated drawings, procedures, logs, or other materials to be changed:

No other changes

6. Create an Action Sheet containing the list of associated work, specified above, attach a copy, and submit it to the RFD.

l Action Sheet: Submitted Not Required X Reviewed and approved by RFD Date Mf- M RRFSC Notified Date APR I 31993 l

py. . y w . . . . .v p; ;<. . 4.u. . . 3 .w y.9 ,..s

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99p;a.;qq:g;.3..pg,.pggg 9 g.gm.g g g :ggw ,..,...._s....x.w.g...,e.,

jpfg,R6TIONAlfBpCgDUBE; _

a %gigiggocedure BlJABJ2 PULSE OPERATION (SUBCRITICAL) i l

GENERAL j Pulses above $2.00 must be verbally approved by the RFD (prior to pulse initiation) or specified on the RUR, signed by the RFD. I SPECIFIC

1. Set the alarm points on R-1 and R-5 (criticality monitor) to full scale. Tum over the i RAM indicator sign to denote that the RAMS are tumed up.

2. Given a core position, set the transient rod at a position corresponding to the dollar value determined by the following equation:

$ Value = Total worth ($) Transient rod (to 100% or mechanical stop) - l Desired pulse ($) Value

3. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with core position and experimental requirements.

Do not use Automatic Mode until the threc standard rods have been raised at least 5%

Note: If a series of repetitive pulses are to be fired, it is not necessary to bring the reactor to cold critical for each pulse. Consecutive pulses may be fired using the same rod positions on the same day as long as the reactor power is not increasing and is less than 1 kW.

4. Stabilize in the manual mode.

5. Select the proper pulse detector according to the table below. If the Cerenkov detector is selected, turn off the reactor room and tank lights.

Detector 1 = Pulse lon (Maximum insertion = $2.00)

Detector 2 = Cerenkov (Maximum insertion = $4.00)

6. Adjust Pulse Mode Scram Timer if necessary.

Revisec: 24 Nov 97 H:\ USERS \EVERYONE\RDRIVE\0P8G2CH1.WB@e 1

' 7. Scram the Transient rod.

8. Raise the Transient rod anvil to 100% or the mechanical stop if installed.

9. Let the power decay to approximately 1 watt or less unless otherwise dictated by -

experimental constraints. Pulses may not be initiated above the Technical Specification ikW limit.

10. Enter Pulse Mode and select high or low resolution pulse display. High resolution displays 1200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulse number at the next prompt.

11. Fire the pulse by depressing the " Fire" button on the reactor console.

12. Record the appropriate data in the reactor operations logbook from the pulse display.

13. Reset R-1 and R-5 to their normal alam1 points when pulsing operations are complete and tum over the RAM indicator sign to denote that the RAMS are set back to normal. l l

J i

l Revised: 24 Nov 97 H:\ USERS \EVERYONE\RDRIVE\OP8G2CH1.WB@e 2 l

l

8 Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Remove Word " Criticality" From Procedure 8, TAB H Modification to: Procedure _XX_ Facility Experiment l Submitted by: George Date _27 April 1998_

1. Description of change:

Remove the word " Criticality" from section 3 of the weekly operational instrumentation checklist. The Criticality monitor name was eliminated in the last RRFSC meeting and this name change was missed during 6e document search.

2. Verify that the proposed change des not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

NONE, SAR already changed

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and fmward a copy of changes necessary to Facilities.

No Facility change 4 Determine what other procedures, logs, or training material may be affected and record below.

None

5. List of associated drawings, procedures, Icss, or other materials to be changed: l None, l

6. Create ar. Action Sheet contain..sg the list of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Submitted / Not Required _XX_

Reviewed and approved by RFD Date V/7_7/7p Ip/g 3 RRFSC Notified Date JUL I 31998 h

iQJNt{k@(PhDDEDURE 5 ((][][7"T[6%dd@Md4M l WEEKLY OPERATIONAL INSTRUMENT CHECKLIST CHECKLIST # DATE SUPERVISED BY ASSISTED BY REVIEWED BY I. WATER LEVEL INDICATOR A. In pool, east side, depress float on water level indicator ... .... .

B. Observe scram on console . . .

II. WATER RESISTIVITY List resistivity readings for previous calendar week from daily startup {

checklists. Determine the average at each point is >0.5 Mohm-cm. '

MON TUE WED THU FRI AVG Monitor Box DM1 DM2 J 111. RADIATION ALARMS A. Test alarm functions for high level and failure Monitor Failure alarm functional HIGH Level alarm functional R-1 R-2 R-5 E-3 E-6 Reactor Room CAM Gas Stack Monitor B. Reset alarms.. . . . . . . . .. ..

IV. OTHER A. Top lock key seals at Security Desk and at LOG verified intact .

B. Change Filter in the Stack Gas Monitor . . . . ..

Revised: 27 April 98 R:\PROCEDWP\0P_8H.WP6

. . \

(R I

Facility Modification Work Slast 1 10 CFR 50.59 Analysis i

Proposed Change: __ Remove Section 5.2.4 of SAR which describes --

__ a non-existent patch panel system.  ;

i Submitted by: George Date _ 28 April 1998_

1. Description of change:

Section 5.2.4 of the SAR describes a patch panel system for both exposure rooms. The system was removed from service when it was determined that the patch panel connections were affecting the readings in the dosimetry readout room. The wires were replaced  !

with continuous uninterrupted cables that fed directly from the j exposure rooms to the dosimetry readout room. The patch panel was i then removed.

2. Reason for change:

System described no longer exists

3. Verify that the proposed change does not involve a change to the Technical Specifications or produce an unresolved safety issue as npecified in 10 CFR 50.59 (a) (2) . Attach an analysis to show this.

Analysis attached? Yes __NO, Not appropriate _

Removal of the panel will decrease the signal noise in the lines due to bad connections in the patch panel.

4. The proposed modificatien constitutes a changes in the f acility or an operational procedure as described in the SAR. Describe which (check all  !

that apply).

Procedure Facility _XX_ Experiment _

i

5. Specify what sections of the SAR are applicable. In general terms ,

d2 scribe the necessary updates to the SAR. Note that this description nted not contain the final SAR wording.  ;

Remove Section 5.2.4, Patch Panel System j

Facility Modifiestion Work Shest 1

6. For facility modifications, specify what testing is to be performed to assure that the systems involved operate in accordance with their f design intent.

The replacement wiring was tested and operated properly.

7. Specify associated information.

New drawings are: Attached Not required XX 4 Does a drawing need to be sent Logistics? Yes No XX Are training materials effected? Yes No _XX_

Will any Logs have to be changed? Yes No _XX_

Are other procedures effected? Yes No _XX_

List of items effected: )

{

NONE identified

8. Create an Action Sheet containing a list of associated work specified j in items #7, attach a copy, and submit another to the RFD.

Action Sheet: Submitted Not Required _XX_

S nu ' Date!//y/(, '

Reviewed and approved by RFD 3 w

\

JUL 131998 1 RRFSC Concurrence m m, Date

\

SECTION TO BE REMOVED FROM SAR 5.2.4 Patch Pr.el System A patch panel system exists within the AFRRI reactor building so that electrical signals from instruments in either exposure room can be transmitted to other areas inside AFRRI. The Patch Panel in ER #1 is connected to a Patch Panel in Hall 1106, and the patch panel in ER #2 is connected to a Patch Panel in the prep. area near ER #2. From here, the signals may be routed to other patch panels, as desired.

}

Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Better Define the Equation in the Suberitical Square Wave Procedure Modification to: Procedure _XX_ Facility E:.periment Submitted by: _

George _

Date _29 April 1998_

1. Description of change:

The defmition in the square wave procedure on how to set the rod position is not very clear.

This change clarifies the equation.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

No Change to the SAR. Only a procedural change

3. If change involves a facility modiGcation, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a cc,py of changes necessary to Facilities.

No Facility modification

4. Determine what other procedures, logs, or training material may be affected and record below.

None, Single procedure change only

5. List of associated drawings, procedures, logs, or other materials to be changed:

Only the suberitical square wave procedure needs changed.

6. Create an Action Sheet containing the list of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Subn.itted Not Required _XX_

Reviewed and approved by RFD Date 9/LT/T f RRFSC Notified I Date JUL 3M

~~

)

{

l

[dp5R5TidN lPFif~CEDURE: , ,

~'"IE lEdidd0regT B'F5)

[QUARE WAVE OPERATION (Subcritical) l GENERAL The square wave mode will not be used above a demand power of 250 KW.

SPECIFIC  !

1. Determine the transient rod critical position using the core position, the final transient rod position, the rod curves and the equation below. Note that a square wave insertion can not exceed 75 cents.

TOTAL WORTH TRANSIENT ROD ($)(to 100% or mechanicat stop)

DESIRED INSERTION ($) *

= TRANSIENT ROD INITl'AL POSITION ($)

• For demand powers up to 25 KW, insert $0.70

• For demand powers greater than 25 KW, insert $0.75

2. Apply air to the transient rod and raise the anvil to the critical position that was calculated above.

3. Bnng the reactor cold entical using the three standard control rods; use a rod configuration commensurate with the core position and experimental requirements. If l

Auto Mode is used, select the rods to be used. Ensure that these rods have been J raised at least 5% before entering Auto Mode. Set the cold critical power level on the Power Demand thumb wheels and enter Auto Mode.

4. Stabilize the reactor in Manual Mode.

5 Set power demand thumb wheels to desired power level.

6. Select the standard control rods to be servoed. Make sure that all control rods to be servoed have been raised at least 5%.

Revised: 29 April 98 R:\PROCEDWP\OP_8F1.WP6 Page 1 l

c

7. Scram the transient rod.

8. Raise the anvil to the desired final position.

9. Allow the power level to fall below 1 watt.

10. Switch into Square Wave mode.

11. Depress Fire button.

12. As the power level approaches the power demand level, the console will switch into Auto Mode. If power can not reach the demand power, it will automatically change to manual mode. At this time, either switch to Auto Mode or bring the reactor to the desired power level manual!y.

13. Scram the reactor at the end of the run using the manual or timer scram.

14. Ensure all pertinent information has been entered in the reactor operations logbook.

l Revised: 29 April 98 R:\PROCEDWP\OP_8F1.WP6 Page 2 I

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@@EMfiogfpW56i[NEj f"WW]@@[MpM@(?fAER SQUARE WAVE OPERATION (Subcritical)

GENERAL The square wave mode will not be used above a demand power of 250 KW.

SPECIFIC

1. Determine the transient rod critical position using the core position, the final transient rod position, the rod curves and the equation below. Note that a square wave insertion can not exceed 75 cents.

CRITICAL POSITION ($) = FINAL POSITION ($)-INSERTION ($)

• For demand powers up to 25 KW, insert $0.70

• For demand powers greater than 25 KW, insert $0.75

2. Apply r to the transient rod and raise the anvil to the citical position that was calculated above.

3. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with the core position and experimental requirements. If Auto Mode is used, select the rods to be used. Ensure that these rods have been raised at least 5% before entering Auto Mode. Set the cold critical power level on the Power Demand thumb wheels and enter Auw Mode.

4. Stabilize the reactor in Manual Mode.

5. Set power demand thumb wheels to desired power level.

6. Select the standard control rods to be servoed. Make sure that all control rods to be servoed have been raised at least 5%.

7. Scram the transient rod.

8. Raise the anvil to the desired final position.

9. Allow the power level to fall below 1 watt.

I Revised: 24 Nov 97 Page 1 j l

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10. Switch into Square Wave mode.

11. Depress Fire button.

12.- As the power level approaches the power demand level, the console will switch into Auto Mode. If power can not reach the demand power, it will automatically change to manual mode At this time, either switch to Auto Mode or bring the reactor to the desired power level manually.

13. Scram the reactor at the end of the run using the manual or timer scram.

14. Ensure all pettinent information has been entered in the reactor operations logbook.

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1 Revised: 24 Nov 97 Page 2

Facility Modification Work Shast 1 10 CFR 50 59 Analysis Proposed Change: Removal-of Accidental Criticality Monitors from SAR Submitted by: George Date _4 June 1998_

1. Description of change:

Removal of section'3.6.5, accidental criticality monitor, from the SAR.

Szction 3.6.5 specifies the location of the Accidental Criticality l Monitors in the facility.

2. Reason.for change:

Criticality monitors are not required by 10 CFR 70.24 to be in the facility, and criticality monitors which contain foils and powders such as the ones specified in section 3.6.5 of the SAR were designed and used in fuel f abrication and reprocessing plants. These criticality monitors have no purpose for the AFRRI reacfx e facility.

3. Verify that the proposed _ change does not involve a change to the Technical _ Specifications or produce an unresolved safety issue. ara specified in 10 CFR 50.59 (a) (2) . Attach an analysis.to show this.-

Analysis attached? Yes _XX_  !

<4 . The proposed modification constitutes a changes in the facility or an 1 operational procedure as described in the SAR. Describe which (check all that apply).

Procedure Facility Experiment NONE, Removal of monitors from facility.

Facility Modification Work Shnet 1

5. Specify what sections of the SAR are applicable. In general terms describe the neceusary updates to the SAR. Note that this description need not contain the fin &l SAR wording.

Removal of section 3.6.5 of the SAR l

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6. For facility modifications, specify what testing is to be performed to assure that the systems involved operate in accordance with their design intent.

No Facility Modification

1 Fscility Modification Work Shost 1

7. Specify associated information.

l New drawings are: Attached Not required _XX_

Does a drawing need to be sent Logistics? Yes No -

Are training materials effected? Yes No ~XX~

XX~

Will any Logs have to be changed? Yes No [XX_

Are other procedures effected? Yes No _XX_  ;

l List of items effected:

SAR change only l l

9

8. Create ar. Action Sheet containing a. list of associated work specified in items #7, attach a copy, and submit another to the RFD.

Action Sheet: Submitted _XX_ Not Required Rsviewed and approved by RFD Date Ih4 )M C/ I RRFSC Concurrence _

Date JUL i 31998 msm ,

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ANALYSIS ON TECENICAL SPECIFICATIONS  !

FOR REMOVAL OF ACCIDENTAL CRITICALITY MONITORS The technical specifications stato nothing about criticality monitors and therefore no change is required.

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ACTION SHEET REMOVAL OF ACCIDENTAL CRITICALITY MONITORS Remove section 3.6.5 of SAR from electronic copy.

/ Update file copy of SAR Remove diamond plaques 1

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l Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required l Proposed Change: ADD WATER SPIGOT TO REACTOR COOLING TOWER Modification to: Procedure Facility XX Experiment ,

Submitted by: Osborne & George Date 5 June 1998 '

i

1. ' Description of change:

Add a water spigot to the reactor cooling tower.

The addition of a water spigot allows for easier monthly cleaning of the reactor cooling tower.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a) (2) .

NONE

3. If change involves a facility modification, attach a drawing if t appropriate. If structural facility drawings need updating, forward a copy of changes necessary to Facilities.

NONE  !

I

4. Determine what other procedures, logs, or training material may be affected and record below.

NONE

5. List of associated drawings, procedures, logs, or other materials to be changed:

NONE

6. Create an Action Sheet containing the list of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Submitted Not Required XX Reviewed and approved by RFD /( I Date d/l/79

/

RRFSC Notified IM Date J' l 3 1998 i

io Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Update of various operational procedures Modification to: Procedure _XX_ Facility Experiment Submitted by: George Date _4 June 98_

1. Description of change:

Review and update of various operational procedures. See attached for changes to the following procedures.

Fitness for Duty Procedure Al Emergency Procedures Procedure 6 Reactor Operations Procedure 8 Logbook Entry Checklist Procedure 8, Tab A Air Particulate Monitor (CAM) Procedure 11

2. Verify that the proposed change does not involve a change to the Technical Specifications, j the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

No change to T.S. or SAR

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Facilities.

No drawing changes

4. Determine what other procedures, logs, or training material may be affected and record below.

No oth:r logs

5. List of associated drawings, procedures, logs, or other materials to be changed:

l Listed in #1 above

6. Create an Action Sheet containing the list of associated work, specified above, attach a copy, !

and submit it to the RFD.

1 Action Sheet: Submitted /\ Not Required _XX_

Reviewed and approved by RFD Date YUAE*) 7 RRFSC Notified IPC y, Date !4M 10%=== my i

Fitness for Duty Procedure Al Slight changes were made to this procedure to account for positive drug test results due to prescription medications. The statement that drug users would be terminated was changed to " assigned non operational duties pending administrative procedures".

Emergency Procedures Procedure 6 The line " Notify ERT commander..." was changed to " Notify the RFD/ERT commander of the situation".

3 Reactor Operations Procedure 8 The new reactor logbook stamps now contain spaces for who is SRO on call, HP on call. j and Operator in Charge, so the section in the procedure on entering that information at j the top of each logbook page was removed from the procedure. l l

Logbook Entry Checklist Procedure 8, Tab A Changes were made to this procedure to account for the new console stamps. Also several redundant items were removed from the procedure.

Specifications were added (new item #5) on how to fill out the new stamps Under black entries, the stamps are specified as options for unlocking the console, and for change of operators during operations. Added to the list were the console locked and signature at end of day.

Under green entries, Reactor Calibrations and Data was added for any data that the  ;

operator wishes to enter into the operations logbook.

The color BLUE-BLACK was removed as no one ever uses it.

The sample logbook entries page was redone to show the new console stamps in an example of how they might appear in a logbook.

Air Particulate Monitor (CAM) Procedure 11 The specification that the secondary chart recorder will be turned on when the primary CAM is by-passed was removed because the secondary CAM chart recorder operates continuously.

IX6siik-w-. . I5f.t.ii TiVEDR CEDUREI. n E I N 7 " ~_ 5 .v I#Eod35EEEI.i

~ ~ -- - ,

FITNESS FOR DUTY REQUIREMENT:

To meet the specifications as defined in the AFRRI plan.10 CFR does not require a fitness for duty procedure for training reactors.

GENERAL The AFRRI Reactor Facility is a drug-free work-place. The use of illicit drugs by )

any RSDR staff member is prohibited. Personnel using over-the-counter or prescription drugs which cause drowsiness or otherwise alter one's state of l

consciousness will not be permitted to operate the AFRRI TRIGA reactor. In l addition, reactor operators, operators-in-training, and . ~.anagement will be monitcred for attitude and behavioral changes that may impact an individual's reliability.

SPECIFIC

1. RSDR staff members shall participate in drug-free awareness programs sponsored by AFRRI. Military and civilian staff members shall submit to drug ,

1 screening programs conducted by their respective services. If a staff member's  ;

drug screening test yields an unexplained positive result, that staff member shall l not be permitted to operate the reactor pending verification of the test.

Acceptable positive results may occur following use of certain prescription drugs. l The Reactor Facility Director (RFD) is required to ensure that the cutoff levels for alcohol or controlled substances as established in 10 CFR 26 are not exceeded by NRC licensed personr.el. Any staff member determined to be a drug user will be temporarily assigned non operational duties pending l Revised: 1 June 98 R:\PROCEDWP\0P__A1.WP6 Page 1

4 administrative procedures.

2. Personnel are instructed to inform their physician of theirjob description and requirements prior to being issued a prescription medication. They are instructed to inquire about any medication side effects expected and the physician's opinion regarding interference with safe job performance. This.

information shall be relayed to RFD as soon as possible.

Personnel are encouraged to minimize their use of non-prescription over-the-counter drugs for self-medication purposes. Specifically, sedatives, cough and cold preparations, appetite suppressants, and pain relievers have central nervous system side effects. If these medications are used in any quantity, an operator must inform the RFD or ROS and be relieved from operating on that day or until any side effects have resolved once the medication has been discontinued.

Personnel are instructed to read the information in the Physician's Desk Reference (PDR) concerning medication they are taking. If the PDR indicates that the medication will adversely affect an operator's ability to safely perform his/her duties, he/she must inform the RFD or Reactor Operations Supervisor (ROS) that he/she must be relieved from operating on that day.

3. The RFD shall continuously monitor the reliability of individuals under his/her command by the following criteria:

. Any court-martial or civil conviction of a serious nature. Minor traffic violations are not a consideration.

• Negligence or delinquency in duty perfo,mance.

• Significant mental or character traits, or aberrant behavior, sustained by medical authority, that might affect the reliable performance of duties.

Revised: 1 June 98 R:\PROCEDWP\OP_A1.WP6 Page 2 i

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. Behavior patterns that show or suggest a contemptuous attitude toward the law or regulations

. Drug abuse or alcohol misuse.

. Poor attitude, lack of motivation toward assigned duties, or financial irresponsibility.

The RFD will be observed by his superiors to ensure his/her adherence to reliability criteria. Individuals who exhibit any of the listed behaviors or actions will be removed from licensed activities.

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Revised: 1 June 98 R:\PROCEDWP\OP_A1.WP6 Page 3 l

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IhDUI liiTRATIVE P'ROCEDUREl }[ ~ *((

, ' [Piocedure A1 FITNESS FOR DUTY REQUIREMENT:

To meet the specifications as defined in the AFRRI plan.10 CFR does not require a fitness for duty procedure for training reactors.

GENERAL The AFRRI Reactor Facility is a drug-free work-place. The use of illicit drugs by any RSDR staff member is prohibited. Personnel using over-the-counter or prescription drugs which cause drowsiness or otherwise alter one's state of consciousness will not be permitted to operate the AFRRI TRIGA reactor. In addition, reactor operators, operators-in-training, and management will be monitored for attitude and behavioral changes that may impact an individual's reliability.

SPECIFIC

1. RSDR staff members shall participate in drug-free awareness programs sponsored by AFRRI. Military and civilian staff members shall submit to drug screening programs conducted by their respective services. If a staff member's drug screening test yields an unexplained positive result, that staff member shall 1

not be permitted to operate the reactor pending verification of the test.

Acceptable positive results ma) occur following use of certain prescription drugs.

The Reactor Facility Director (RFD) is required to ensure that the cutoff levels for alcohol or controlled substances as established in 10 CFR 26 are not exceeded by NRC licensed personnel. Any staff member determined to be a drug user will be temporarily assigned non operational duties pending Revised: 14 July 98 R:\PROCEDWP\0P_A1.WP6 Page 1

1 administrative procedures.

2. Personnel are instructed to inform their physician of theirjob description and requirements prior to being issued a prescription medication. They are instructed L inquire about any medication side effects expected and the physician's opinion regarding interference with safe job performance. This information ; hall be relayed to RFD as soon as possible.

Personnel are encouraged to minimize their use of non-prescription over-the-counter drugs for self-medication purposes. Specifically, sedatives, cough and cold preparations, appetite suppressants, and pain relievers have central nervous system side effects. If these medications are used in any quantity, an operator must inform the RFD or ROS and be relieved from operating on that day or until any side effects have resolved once the medication has been

' discontinued.

Personnel are instructed to read the information in the Physician's Desk Reference (PDR) concerning medication they are taking. If the medication is unlisted in the PDR or the instructions are not understood, see the staff physician for information on how the drug may affect performance. if there are indications that the medication will adversely affect an operator's ability to safely

' perform his/her duties, he/she must inform the RFD or Reactor Operations Supervisor (ROS) that he/she must be relieved from operating on that day.

3.- .The RFD shall continuously monitor the reliabinty of individuals under his/her command by the following criteria: y e '. Any court-martial or civil conviction of a serious nature. Minor traffic violations are not a consideration.

. Negligence or delinquency in duty performance.

Revised: 14 July 98 R:\PROCEDWP\0P _A1.WP6 Page 2 1

Significant mental or character traits, or aberrant behavior, sustained by medical authority, that might affect the reliable performance of duties.

. Behavior patterns that show or suggest a contemptuous attitude toward the law or regulations

. Drug abuse or alcohol misuse.

Poor attitude, lack of motivation toward assigned duties, or financial irresponsibility.

The RFD will be observed by his superiors to ensure his/her adherence to reliability criteria. Individuals who exhibit any of the listed behaviors or actions will be removed from licensed activities.

Revised: 14 July 98 R:\PROCEDWP\OP_A1.WP6 Page 3

@h5@hyhM NOCEDORE. ['[ (( ] [][ "" j @ id[5 EMERGENCY PROCEDURES )

GENERAL The reactor emergency organization, emergency classes, and emergency action levels are set forth in the AFRRI Reactor Facility Emergency Plan and its implementing Procedures.

SPECIFIC Perform the following, as appropriate (need not be done in order).

1. Reactor Emergency:

a. SCRAM reactor. .

b. Check radiation monitors; use portable survey instruments to assess I situation, if necessary. 1

c. Notify the RFD/ERT Commander of the situation.

d. Activate the emergency response team.

2. AFRRI Complex Emergency Evacuation: ,

a. SCRAM reactor.

b. Secure any exposure facilities which are in use so that personnel access to that facility is not possible.

c. Remove logbook, emergency guide, radios, teletector, tool kit, and keys; l report to ERT. l

d. Ensure reactor area doors are secured upon departure.

3 Proper classification of emergency situation: All SROs must review the referenced Emergency Plan documents and be able to properly classify the events as they occur. Below is a tabulation of emergency classification to be used as guidance.

Revised: 4 June 98 R:\PROCEDWP\0P_6.WP6 Page 1

EMERGENCY Radiation Activate AFRRl Complex Activate Emergency CLASS Alarms Emergency Evacuation Response Team (Unanticipated) .

Class 0 Fire Alarm (non-reactor) Yes Yes Class 1 R1 >> 1 min. Yes R2>> 1 min. Yes R3 No No R5 >> 1 min. Yes R6 No No E3 >> 1 min. Yes E6 >>1 min. Yes SGM>> 1 min. Yes Reactor Stack Fan Monitor No No Fire Alarm (reactor) Yes Yes Class 2 CAM >> 1 min.

concurrent with R1, R2, R5, and/or SGM Yes NOTE:

• A decision to evacuate the Institute will be made by the ECP Commander based on input from the ERT Commander.

l Revised: 1 May 98 R:\PROCEDWP\OP_6.WP6 Page 2 1

1 can.n~.vr,..,,..,.~,.,mx......-...m.r..,... . ,, g.,p y gy.g, , ng, gggygrm.,,_wmmmgg. g ,,,yg.g , m gy ,

T ~ ~;2h, RrocedureL6

[ OPE, RAT.lONAlf.R.O_CEDUREi Ja EMERGENCY PROCEDURES l I

GENERAL The reactor emergency organization, emergency classes, and emergency action levels are set forth in the AFRRI Reactor Facility Emergency Plan and its Implementing Procedures. j l

SPECIFIC Perform the following, as appropriate (need not be done in order).

1. Reactor Emergency:

a. SCRAM reactor. l l

b. Check radiation monitors; use portable survey instruments to assess l situation, if necessary. l

c. Notify ERT Commander of situation. l

d. Activate emergency organization.

2. AFRRI Complex Emergency Evacuation:

a. SCRAM reactor. l

b. Secure any exposure facilities which are in use so that personne' access to that facility is not possible.

c. Remove logbook, emergency guide, radios, teletector, tool kit, and keys; report to ERT.

d. Ensure reactor area doors are secured upon departure. I 3 Proper classification of emergency situation: All SROs must review the referenced Emergency Plan documents and be able to properly classify the events as they occur. Below is a tabulation of emergency classification to be used as guidance.

Revised: 15 May 91 R:\PROCEDWP\OP_6.WP6 Page 1

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EMERGENCY Radiation Activate AFRRI Complex Activate Emergency CLASS Alarms Emergency Evacuation Response Team (Unanticipated)

Class 0 Fire Alarm (non-reactor) Yes Yes Class 1

• I R1 >> 1 min. Yes R2>> 1 min. Yes R3 No No R5 >> 1 min. Yes R6 No No i E3 >> 1 min. Yes E6 >>1 min. Yes SGM>> 1 min. Yes Reactor Stack Fan i Monitor No No Fire Alarm (reactor) Yes Yes Class 2 CAM >> 1 min.

concurrent with R1, R2, RS, and/or SGM Yes NOTE:

• A decision to evacuate the Institute will be made by the ECP Commander based on input from the ERT Commander.

I 1

Revised: 15 May 91 R:\PROCEDWF\0P_6.WP6 Page 2

e

" ' ~ "

$hhh5f[S12[ROCE'DOREL ,, 7 [3][oddir(E REACTOR OPERATIONS GENERAL Logbook entries will be made in accoroance with the Lo0 book Entry Checklist (Tab A).

SPECIFIC

1. The names of the Mdividuals who supervised and performed the daily and weekly checklists will be shown at the top of the checklist. Check marks or numbers, as appropriate, will then be entered on each checklist line as that item is performed.

2. Perform reactor Daily Operational Startup Checklist (Tab B), utilizing appropriate nuclear instrumentation set points (Tab C). In the case of no planned operations, l a Daily Safety Checklist (Tab B1) may be performed.

3. Perform K-excess measurement (Tab D)if the startup is not a safety startup.

4. Perform operations in accordance with the following:

a. Steady state operation (Tab E).

b. Square wave operation (Tab F).

c. Pulse operation (Tab G).

d. CET operations (Proceduro 1, Tab B).

e. Pneumatic Transfer System (Procedure 1, Tab D).

f. In-poollin-core experiment (Procedure 1, Tab E) l

5. Perform Weekly Operational Instrument Checklist once during each calendar week (Tab H).

6. At the end of each day in which a Daily Operational Startup Checklist or Daily Safety Checklist has been completed, perform a Daily Operational Shutdown Checklist (Tab I).

Revised: 1 May 98 R:\PROCEDWP\0P,_8.WPii" Page 1 l

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7. Complete'the monthly summary .

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8. Respirator equipment will not be used on a routine basis. Respirator )

! equipment is provided for use during emergency conditions only.

4

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Revised: 1 May 95 R:\PROCEDWP\OP_8.WP6 Page 2 l

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@f[kIphfiPNCEDUR( ,,

_[2i]$$(([jb.[Pgdeilire5 REACTOR OPERATIONS GENERAL Logbook entries will be made in accordance with the Logboo: Entry Checklist (Tab A).

SPECIFIC

1. The names of the individuals who supervised and performed the daily and weekly checklists will be shown at the top of the checklist. Checkmarks or numbers, as appropriate, will then be entered on each checklist line as that item is performed.

2. Perform reactor Daily Operational Startup Checklist (Tab B), utilizing appropriate nuclear instrumentation set points (Tab C). In the case of no planned operations, a Daily Safety Checklist (Tab B1) may be performed.

3. Record at the beginning of each day in the reactor operations logbook the SRO on-call for that date.

4. At the top of each logbook page also record the name of the senior person in charge, noted as physicist in charge (PIC). present in the reactor facility and the name of the HP on-call. If the PIC, SRO on-call, or HP on-call changes during the day, an updated entry will be made in the body of the logbook at the time of occurrence.

5. Perform K-excess measurement (Tab D).

6. Perform operations in accordance with the following:

a. Steady state operation (Tab E).

b. Square wave operation (Tab F).

c. Pulse operation (Tab G).

d. CET operations (Procedure 1, Tab B).

e. Pneumatic Transfer System (Procedure 1, Tab D).

f. In-poollin-core experiment (Procedure 1, Tab E)

Revised: 18 Feb 93 Page 1 l

l

7. Perform Weekly Operational Instrument Checklist once during each calendar week (Tab H).

8. At the end of each day in which a Daily Operational Startup Checklist or Daily Safety Checklist has been completed, perform a Daily Operational Shutdown Checklist (TabI).

9. Complete the monthly summary .

10. Respirator equipment will nct be used on a routine basis. Respirator equipment is provided for use during emergency conditions only.

4 Revised: 18 Feb 93 Page 2

IO_ 5.. 5.i. .. .f. i. .I.f_dE,pii.6.

6. EDOREi " . m T

"477", m.m .rnure.8hT.A_ B..A i

LOGBOOK ENTRY CHECKLIST

l. Operational Logbook i

1. The reactor operations logbook is a "before-the-fact" record, that is, entries will be )

i logged whenever possible before the operator actually performs the operation. '

i Events, such as scrams, which may not be planned ahead of time, will be entered at the time of occurrence. Any late entries will be so noted. Entries about what you plan to do are not necessary, only actual events need to be legged in the logbook.

2. The operations logbook will have a hardbound cover and will be sequentially numbered by volume. The pages will be dated at the top of each page and each page will be sequentially numbered.

3. The Reactor Facility Director (RFD) will review each logbook upon its completion; he will make an appropriate entry in the back of the logbook and sign the entry. The operator who makes the final entry at the end of a logbook is responsible for ensuring that the ROS is notified that the logbook is ready for RFD review.

4. All items in GREEN (see below) that are not closed cut during the working day will be carried in GREEN at the end of the day and again at the beginr.nig of the next

]

operational day. l l

5. Each of the logbook stamps has space for SRO ON CALL, SRO IN CHARGE (supervising) of the operation, the HP ON CALL, and a second person who is in ,

t AFRRI who could help in emergency situations. The individual at the console will

]

enter data into the stamp to designate who is filling these 4 positions. The persons who are on console will have their names entered on the CONSOLE UNLOCKED I Revised: 4 May 98 R:\PROCEDWP\0P_8A.WP6 Page 1 1

1 l

l Byline and will be considered as RO's for the operation. For subsequent stamps when the console is already unlocked, lining out the tima for the console unlocked entry is appropriate.

One SRO can fill the positions of SRO ON CA .L, SRO IN CHARGE and RO on console in CONSOLE UNLOCKED BY The HP on call cannot be on call and on the te nsole at the same time.

i

6. The entries will be made in ink and in accordance with the following designated ,

color code:

f

a. BLACK: Most Operational Activities.

(1) Console Unlocked By stamp.

Completion of the daily startup, shutdown, and weekly checklists.

)

(2) l (3) Mode of operations. Use appropriate stamp or entry to designate the operation:

(a) Steady State.

(b) Square Wave ,

1 (c) Pulse (4) Subsequent power level changes.

(5) Operation of reactor associated facilities such as lead shield doors, pneumatic tube systems, etc., unless such operations cause a change of reactivity (see 5.b.(2) below). .

(6) Change of personnel at the console stamp. If hand written, the persons name replacing the person on console should be entered first as "on console" before the person logging off of the console is entered as "off" (7) All changes to logbook entries (including line outs, error corrections, changes to operations mode stamp lines, and end-of-page line outs) will be initiated or signed by the operator.

(8) Console locked (9) Signature of reactor operator to close out the log for the day.

Revised: 4 May 98 R:\PROCEDWP\0P_8A.WP6 Page 2

b. RED: For items Which Change or Measure Reactivity (1) K-excess measurements, to include experiment worth determinations.

(2) Actions which affect reactivity:

(a) Core movement.

(b) Fue. ,~.iovement.

(c) Control rod physical removal for maintenance.

(d) Experiment loading and removal from the CET, PTS, pool, or core.

(e) Removal or insertion of CET into core.

c. GREEN: For Maintenance or Malfunctions (1) Any reactor malfunctions noted upon discovery / occurrence with a second entry noting corrective action has been completed.

(2) Additional items entered at the discretion of the operator such as addition of make-up water to the reactor pool, etc.

(3) Any Technical Specification required equipment taken out of service for any reason. A second entry is made when the unit is returned to service.

(4) Movement of detectors or chambers from above core.

(5) Reactor calibrations and data.

6. When an operation requiring entry into the logbook falls under more than one color

' code, the color to be used will be determined via the following order of precedence:

RED - GREEN - BLACK.

Revised: 4 May 98 R:\PROCEDWP\OP._8A.WP6 Page 3 i

Sample Logbook Entries for a Typical Operational Day Startup Checklist Begun BLACK SRO ON CALL SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY I

(BLACK)

I Startup Checklist #"" Complete BLACK I

I SRO ON CALL SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY CRITICAL AT WATTS FOR K EXCESS TRANS $ SHIM $

SAFE $ REG $

SCRAM, CORE POSITION K-EXCESS $

'(RED) 1 Console locked by "*""

BLACK SGM out of service for maintenance.No operations GREEN i l

SGM Back in service GREEN l SRO ON CALL SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY (BLACK)

Revised: 4 May 98 R:\PROCEDWP\0P_8A.WP6 Page 4

Opening Pb Doors BLACK Moving Core to *" RED Closing PB Doors BLACK Rabbit (containing "") inserted into CET RED SRO ON CALL SRO IN CHARGE HP ON CALL OTHER PERSON ONSITE CONSOLE UNLOCKED BY RAISING RODS TO GO CRITICAL TRANS SHIM SAFE REG T1 MAX "C T2 MAX C RUR#

CRITICAL AT WATTS SCRAM, TOTAL TIME ' " KWHRS (BLACK)

Rabbit removed from CET RED Console locked by """" BLACK Shutdown Checklist Begun BLACK Shutdown Checklist #"" Complete BLACK Page lined out, Page signed by SRO BLACK Revised: 4 May 98 R:\PROCEDWP\OP_8A.WPS Page 5

l-

'll. Malfunction Logbook All entries in the malfunction logbook should include the following information. For consistency, the bold words should be copied into the malfunction log prior to the information.

DATE, TIME, SIGNATURE OF PERSON DISCOVERING MALFUNCTION SYMPTOM:

This section describes how the system is acting or malfunctioning, i.e., channel went full scale, pump failed, keyboard stopped responding to keystrokes etc.

IMMEDIATE ACTION TAKEN:

This section is for denoting such things as Reactor Secured, SHD notified.

RFD NOTIFIED:

A remark should be made that the RFD or acting RFD was notified.

DIAGNOSIS : of problem A narrative description of what was discovered to be causing the problem, i.e.,

Which system was malfunctioning or which component failed.

SOLUTION: / repair i A narrative description of what was done to correct the problem This could include both physical changes or administrative changes, i.e., a component was replaced and the unit was recalibrated, an additional backup system installed, an administrative prohibit on . . was initiated.

OPERATIONAL VERIFICATION AND/OR CALIBRATION:

A description of what actions were taken to verify that the new unit / repair would indeed perform the function for which it was intended, i.e., a calibration signal, system actuated multiple times, system tested, system calibrated with a source.

Indicate whether the change will require staff training.

SIGNATURE RFD Revised: 4 May 98 R:\PROCEDWP\0P_8A.WP6 Page 6  ;

[@DJ PJOCEDyREjs[2@%#deM7lj]((~@[8]Nf .

LOGBOOK ENTRY CHECKLIST

l. Operational Logbook

1. The reactor operations logbook is a "before-the-fact" record, that is, entries will be logged whenever possible before the operator actually performs the operation.

Events, such as scrams, which may not be planned ahead of time, will be entered at the time of occurrence. Any late entries will be so noted. Entries about what you plan to do are not necessary, only actual events need to be logged in the logbook.

2. The operations logbook will have a hardbound cover and will be sequentially numbered by volume. The pages will be dated at the top of each page and each page will be sequentially numbered. -

3. The Reactor Facility Director (RFD) will review each logbook upon its completion; he will make an appropriate entry in the back of the logbook and sign the entry. The operator who makes the final entry at the end of a logbook is responsible for ensuring that the ROS is notified that the logbook is ready for RFD review.

4. All items in GREEN (see below) that are not closed out during the working day will be carried in GREEN at the end of the day and again at the beginning of the next operational day.

5. The entries will be made in ink and in accordance with the following designated color code:

a. BLACK and BLUE-BLACK Most Operational Activities.

(1) Console locked and unlocked. The individual at the console will enter his/her name and the supervisory licensed operator's name, if necessary.

Revised: 31 Jan 96 R:\PROCEDWP\0P_8A.WP6 Page 1

(2) Checklist number and completion time.

(3) Power level at criticality and subsequent power level changes.

(4) Reactor SCRAM This entry to be added when the operational stamp does not contain the SCRAM word in the last line. The K-Excess stamp does not specify SCRAM time. Also any time the operator deviates from ,

normal stamps for multiple power changes for short periods of time, the final line should be SCRAM Console locked does not ful6ll this requirement even though the reactor scrams. ,

(5) Mode of operations. Use appropriate stamp or entry to designate the operation: {

(a) Steady State.

(b) Square Wave  !

(c) Pulse (6) Operation of reactor associated facilities such as lead shield doors, pneumatic tube systems, etc., unless such operations cause a change of reactivity (see 5.b.(2) below).

(7) Change of personnel at the console. When a change of operator is noted a

in the logbook, the name of the person replacing the person on console should be entered first as "on console" before the person logging off of the console is entered as "off".

(8) The operator in charge will be designated in the logbook whenever multiple operators are signed on the console.

(9) Completion of the daily startup and shutdown checklists and weekly checklist.

(10) Signature of reactor operator to close out the log for the day.

(11) Designation of the SRO rsn-call and physicist in charge (PIC).

(12) Reactor calibrations and data.

(13) All changes to logbook entries (including line outs, .yror corrections, changes to operations mode stamp lines, and end-of-page line outs) will Revised: 31 Jan 96 R:\PROCEDWP\0P_8A.WP6 Page 2

be initialed or signed by the operator,

b. RED: For items Which Change or Measure Reactivity (1) K-excess measurements, to include experiment worth determinations.

(2) Actions which affect reactivity; (a) Core movement.

(b) Fuel movement. l I

(c) Control rod physical removal for maintenance.

(d) Experiment loading and removal from the CET, PTS, pool, or core.

(e) Removal or insertion of CET into core. ,

c. GREEN: For Maintenance or Malfunctions (1) Any reactor malfunctions noted upon discovery / occurrence with a second entry noting corrective action has been completed.

(2) Additional items entered at the discretion of the operator such as addition of make-up wate.- to the reactor pool, etc.

(3) Any Technical Specification required equipment taken out of service for any reason. A second entry i t made when the unit is returned to service.

(4) Movement of detectors or chamt;ers from above core.

6. When an operation requiring entry into the logbook falls under more than one color code, the color to be used will be determined via the following order of precedence:

RED - GREEN - BLACK / BLUE-BLACK l

Sample Logbook Entries for a Typical Operational Day -

SRO/PIC/HP Stamp, Date Stamp BLACK Startup Checklist Begun DLACK Console unlocked by - BLACK Startup Checklist #"" Complete BLACK Revised: 31 Jan 96 R:\PROCEDWP\OP_8A.WP6 Page 3

~

1 RAISING RODS TO GO CRITICAL RED CRITICAL AT WATTS FOR K-EXCESS TRANS S SHIM $

SAFE $ REG $

CORE POSITION K-EXCESS $

Manual Scram BLACK Console locked by - BLACK SGM out of service for maintenance No operations GREEN SGM Back in service GREEN Console unlocked by =- --- BLACK Opening Pb Doors BLACK Moving Core to " RED Closing PB Doors BLACK Rabbit (containing ") inserted into CET RED RAISING RODS TO GO CRITICAL BLACK l O

TRANS T1 MAX C SHIM T2 MAX "C SAFE RUR#

REG TOTAL KWHRS CRITICAL AT WATTS SCRAM, TOTAL TIME MIN SEC Rabbit removed from CET RED Console locked by ="= BLACK 4 Shutoown Checklist Begun BLACK Shutdown Checklist #" Complete BLACK Page lined out, Page signed by SRO BLACK Revised: 31 Jan 96 R:\PROCEDWP\0P_8A.WP6 Page 4

ll. Malfunction Logbook All entries in the malfunction logbook should include the following information. For consistency, the bold words should be copied into the malfunction log prior to the information.

DATE, TIME, SIGNATURE OF PERSON DISCOVERING MALFUNCTION SYMPTOM:

This section describes how the system is acting or malfunctioning,i.e., channel went full scale, pump failed, keyboard stopped responding to keystrokes etc.

. IMMEDIATE ACTION TAKEN:

This section is for denoting such things as Reactor Secured, SHD notified.

RFD NOTIFIED:

A remark should be made that the RFD or acting RFD was notified.

DIAGNOSIS : of problem A narrative description of what was discovered to be causing the problem, i.e.,

Which system was malfunctioning or which component failed.

SOLUTION: / repair .

A narrative description of what was done to correct the problem This could in::lude both physical changes or administrative changes, i.e., a component was replaced and the unit was recalibrated, an additional backup system installed, an administrative prohibit on ... was initiated.

OPERATIONAL VERIFICATION AND/OR CALIBRATION:

A description of what actions were taken to verify that the new unit / repair would indeed perform the function for which it was intended, i.e., a calibration signal, system actuated multiple times, system tested, system calibrated with a source.

Indicate whether the change will require staff training.

SIGNATURE RFD Revised: 31 Jan 96 R:\PROCEDWP\0P,_8A.WP6 Page 5

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?EF3AJiON_ALTEtOCED'UB.E; m.,.m , g g g g e g g g ggjProcedurej.1 AIR PARTICULATE MONITOR (CAM) PROCEDURE GENERAL This procedure specifies how to test the CAM to ensure proper operation of this monitoring device. A channel test will be performed on both reactor room CAMS at the beginning and i end of each day.

SPECIFIC

1. TEST FREQUENCY This entire procedure will be performed in conjunction with the daily startup or safety checklist. Items 2,3a and 3d will be performed again as part of the daily shutdown checklist.

2. OPERATING and TRACING Check that the primary CAM is operating and tracing with the correct time indicated on the chart and check that the secondary CAM is operating. Ensure the flow rate is >6 cfm and not off scale.

3. CHANNEL TEST WITH SOURCE

a. Place the switch on the front of the CAM to " test" and verify a reading of 1000 cpm

+/-20%. Reset the switch.

b. Open shield door and change the detector filter if the filter appears excessively dirty or the flow rate has dropped below 6 cfm (with the door closed). Place the used filter in the radioactive waste box in each CAM drawer.

c. Sloavly t: ring a radioactive source near the detector. Observe the meter on the front of the CAM. The yellow light will activate at approximately 4,000 counts per minute.

The reo light will activate at approximately 10,000 counts per minute; the alarm will l sound and the dampers will close. Reset the alarm, close the chamber door and return the source to the CAM drawer.

d. Annotate completion of the channel test on chart paper with initials, time, and date Revised: 1 May 98 R:\PROCEDWP\OP 11.WP6 Page 1

i l

performed for primary CAM.

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p .w .wn, y .:<.ww+w .-ww y> -/.ww.sc- e - . ~ . ,. .~ . . . . . . . y y;p,:;gy:7 .:.gyy.p.v.yggi :gyqu.,,p. , pg.yrg:;gsw.,q. .py:g y.y.

[OggMTION.ALTRO.C..EDURE L , y g;, mm,f;;;iProcedup;;.y,y;,sw At AIR PARTICULATE MONITOR (CAM) PROCEDURE GENERAL This procedure specifies how to test the CAM to ensure proper operation of this monitoring device. A channel test will be performed on both reactor room CAMS at the beginning and end of each day.

SPECIFIC

1. TEST FREQUENCY This entire procedure will be performed in conjunction with the daily startup or safety checklist. Items 2,3a and 3d will be performed again as part of the daily shutdown checklist.

2. OPERATING and TRACING Check that the primary CAM is operating and tracing with the correct time indicated on the chart and check that the secondary CAM is operating. Ensure the flow rate is >6 I J

cfm and not off scale.

3. CHANNEL TEST WITH SOURCE

a. Place the switch on the front of the CAM to " test" and verify a reading of 1000 cpm

+/-20%. Reset the switch.

b. Open shield door and change the detector filter if the filter appears excessively dirty or the flow rate has dropped below 6 cfm (with the door closed). Place the used filter in the radioactive waste box in each CAM drawer.

t

c. Slowly bring a radioactive source near the detector. Observe the meter on the front 5

of the CAM. The yellow light will activate at approximately 4,000 counts per minute.

The red light will activate at approximately 10,000 counts per minute; the alarm will sound and the dampers will close. Reset the alarm, close the chamber door and return the source to the CAM drawer.

d. Annotate completion of the channel test on cha/t paper with initials, time, and date Revised: 04 Aug 97 R:\PROCEDWP\OP_11.WP6 Page 1

performed for primary CAM. Annotate completion of the channel test on secondary CAM chart oaoer only when primary CAM is bvoassed.

l l

4. BY-PASS of PRIMARY CAM When the primary CAM is by-passed, the secondary CAM chart recorder needs to be activated, then perform items 2,3a, and 3d.

I l

Revised: 04 Aug 97 R:\PROCEDWP\0P_11.WP6 Page 2

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\\

Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: - Air Line Check Valves and Air Pressure loss Switch Installation Modification to: Procedure Facility XX Experiment Submitted by: George. Ortelli Date 5 October 1998

1. Description of change:

. Installation of air line check valves preventing backflow of water into the lead shield door bearings in the event of loss of air pressure to the bearing compartment. Additionally, a switch will be installed on the reactor facility air compressor to provide a light signal alerting the security guards in the event of a pressure loss to the reactor air system.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

l The installation of the new components to the pressurized air system does not require i changes to be made to either the Technical Specifications or the SAR.

3. If change involves a facility modification, attach a drawing if appropriate. If stmetural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Facilities.

Not required

4. Determine what other procedures, logs, or training material may be affected and record below.

A pressure loss warning light check will be added as a step in the air compressor maintenance and will be performed during annual shutdown.

5. List of associated drawings, procedures, logs, or other materials to be changed:

Figure M-14 of the Reactor as-built drawings will be amended to include the new components.

6. Create an Action Sheet containing the list of associated work, specified above, attaca a copy, and submit it to the RFD. l Action Sheet: Submitted M Not Required _

Reviewed and approved by RFD '!

Date f Nh RRFSC Notified @ -

_ Date UCT l 41993

50.59 ACTION SHEET CHECK VALVE AND SAFETY SWITCH INSTALLATION Items Needing Attention Date Complete Add Maintenance Step to Annual Shutdown Procedures Add new components into As-built drawing M-14 1

l 1

I I

tv Facility Modification Work Sheet 1 10 CFR 50.59 Analysis i l

Proposed Change: Reolacement of Reactor Heat Exchanger and the Use of Stainless Steel ,

Pipe in Primary Water System Submitted by: George. Wrislev Date: 18 August 1998 4

1. . Description of change:

i Replacement of the tube in shell heat exchanger and the aluminum primary piping (from the isolation valve ,

on the discharge side of the primary pump to the input of the new exchanger) with a new plate and frame exchanger and stainless steel primary piping. The old heat exchanger will be disconnected and the new unit will be installed in room 2158. 1

2. Reason for change:

Preventive maintenance. The current heat exchanger is 30 years old. Replacement will prevent future problems caused by leaks.

3. Verify that the proposed change does not involve a change to the Technical Specifications or produce an i unresolved safety issue as specified in 10 CFR 50.59(a)(2). Attach an analysis to show this.

Analysis attached? Yes XXX

4. The proposed modification constitutes a changes in the facility or an operational procedure as described in the SAR. Describe which (check all that apply).

Procedure Facility XXX Experiment

Facility Modification Work Sheet 1

5. Specify what sections of the SAR are applicable. In general terms describe the necessary updates to the SAR. Note that this description need not contain the final SAR wording.

3.3.1 The primary cooling system is described an consisting "of the reactor tank, the primary pump, the tube side of the shell-and-tube heat exchanger". The shell-and-tube will be changed to plate and frame.

The primary water is later described as passing "through the tube side of the heat exchanger".

Section 3.3.1 will have to have the wording " tube side of the shell-and-tube heat exchanger" and " tube side of the heat exchanger" changed to "the primary side of the plate and frame heat exchanger" 3.3.2 The secondary cooling system is described as consisting "of an enclosed forced-airflow wet tower with sump, a secondary pump, the shell side of the six pass heat exchanger, and associated piping, valves, and fittings. The secondary pump draws raw industrial water from the sump of the cooling tower, passes the water through the shell side of the heat exchanger at a rate of about 700 gpm, and retums the water Section 3.3.2 will have to have the wording "the shell side of the six pass heat exchanger" and "the shell side of the heat exchanger" changed to " the secondary side of the plate and frame heat exchanger"

' Fig 3-6 will need slight modification. the diagram of the water purification and cooling systems currently  !

I specifies that the heat exchanger is a 1.5 Mw 6 PASS heat exchanger located IN WARM STORAGE.

this will have to be changed to reflect a PLATE AND FRAME heat exchanger in room 2158.

i

6. For facility modifications, specify what testing is to be performed to assure that the systems involved operate in accordance with their design intent. j Pressure testing will be performed to verify that there are no leaks from either the primary or secondary I sides of the exchanger.

Facility Modification Work Sheet 1

7. Specify associated information.

New drawings are: Attached Other XX Drawings to be Not required provided with new heat exchanger.

Does a drawing need to be sent Logistics? Yes _XX No Are training materials effected? Yes XX No Will any Logs have to be changed? Yes No XX Are other procedures effected? Yes No XX List ofitems effected:

SAR 3.3.1 SAR 3.3.2 SAR Figure 3-6 Operations Manual (Under revision)

Facility Training Plan As-built Drawings Question Bank

8. Create an Action Sheet containing a list of associated work specified in items #7, attach a copy, and submit another to the RFD. 1

{

Action Sheet: Submitted XXX Not Required i h I

. Reviewed and approved by RFD -

3 v Date _

)

V  !

N, OCT l 4 la l RRFSC Concurrence Date l

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50.59 ANALYSIS TECHNICAL SPECIFICATION CHANGE NOT REQUIRED FOR HEAT EXCHANGER PIPLACEMENT The Technical Specifications for the AFRRI Triga Reactor Facility does not specify the type of heat exchanger installed in the facility. The specifications for the original heat exchanger has been provided to the contractor for a system will match the current cooling capacity of the current exchanger.

The new plate and frame exchanger is designed such that any leaks which could' occur around gaskets would cause the exchanger to leak into the hot drain in room 2158 thus preventing cross contamination between the primary and secondary systems.

The new heat exchanger is composed of stainless steel plates. This is the same material as the tubes of the current heat exchanger. If any leaks were to occur through a plate in the new plate and frame heat exchanger, the heat exchanger can be easily disassembled, cleaned and new plates installed to replace bad plates. This is a great advantage over the current heat exchanger which has only 3 tubes.

The heat exchanger can later be expanded with additional plates if additional cooling is desired.

This change does not increase the consequences of, nor change the types of accidents previously evaluated in the Safety Analysis Report. This change does not reduce the margin of safety as defined in the basis for any Technical Specifications.

HE ATTM % F

L se CURRENT WORDING IN THE SAR 3.3.1 Primary Cooline System The primary cooling system consists of the reactor tank, the primary pump, the tube side of the shell-and-tube heat exchanger, and associated piping, valves, and fittings, all situated at elevations above the top of the core. The primary pump draws water from the reactor pool through the suction line, located in the reactor pool approximately 4 feet beneath the pool surface. The primary pump passes the water through the tube side of the heat exchanFer at a rate of approximately 350 gallons per minute (gpm). The water is then returned to the reactor pool through the return line, located in the reactor pool approximately 8 feet beneath the pool surface. Small holes drilled in the suction and return lines about 4 inches beneath the pool surface prevent water from being syphoned out of the reactor pool and uncovering the core in the event of a primary coolant line leak or rupture. In the event of signific. ant coolant depletion (below core height), due to a reactor tank leak or rupture, an -

emergency fill line will be connected from an outside, adjacent fire hydrant to the primary i coolant loop in order to maintain the reactor tank coolant level above the reactor core.'

3.3.2 Secondary Cooline System The secondary cooling system consists of an enclosed forced-airflow wet tower with sump, a secondary pump, the shell side of the six-pass heat exchanger, and associated piping, valves, and fittings. The secondary pump draws raw industrial water from the sump of the cooling tower, passes the water through the shell side of the heat exchanger at a rate of about 700 gpm, and retums the water to the top of the cooling tower, providing the heat sink to cool the primary water. The water cascades down through the tower, where it is cooled by direct contact with the outside air, and returns to the sump at the base of the cooling tower.

The cooling tower is heated in winter only enough to prevent freezing.

1

PROPOSED WORDING FOR THE SAR 3.3.1 Primary Cooling System The primary cooling system consists of the reactor tank, the primary pump, the primary side of the plate andframe heat exchanger, and associated piping, valves, and fittings, all situated at elevations above the top of the core The primary pump draws water from the reactor pool through the suction line, located in the reactor pool approximately 4 feet beneath the pool surface. The primary pump passes the water through the primary side of the heat exchanger at a rate of approximately 350 gallons per minute (gpm). The water is then returned to the reactor pool through the return line, located in the reactor pool approximately 8 feet beneath the pool surface. Small holes drilled in the suction and return lines about 4 inches beneath the pool surface prevent water from being syphoned out of the reactor pool and uncovering the core in the event of a primary coolant line leak or rupture.

In the event of significant coolant depletion (below core height), due to a reactor tank leak or rupture, an emergency fill line will be connected from an outside, adjacent fire hyorant to the primary coolant loop in order to maintain the reactor tank coolant level above the reactor core.

3.3.2 Secondary CoolintEnicm The secondary cochng system consists of an enclosed forced-airflow wet tower with sump, a secondary pump, the secondary side of the plate andframe heat exchanger, and associated piping, valves, and fittings. The secondary pump draws raw industrial water from the sump of the cooling tower, passes the water through the secondary side of the heat exchanger at a rate of about 700 gpm, and returns the water to the top of the cooling tower, providing the heat sink to cool the primary water. The water cascades down through the tower, where it is cooled by direct contact with the outside air, and returns to the sump at the base of the cooling tower. The cooling tower is heated in winter only enough to prevent freezing.

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50.59 ACTION SHEET HEAT EXCHANGER REPLACEMENT Item Needing Attention Date Complete Change Section 3.3.1 of the SAR Z7 Nov 9s Change Section 3.3.2 of the SAR Z7 #0U 9 7 Change Figure 3-3 of the SAR 7/7 NOV 97 ,

Change Operations Manual (under revision) 'L7 N oJ T 5 Change Facility Training Plan 27 As o u 9 g File new manufacturers literature CCr 7g Install new heat exchanger and test hwi 49 Change Asbuilt Drawings Al, A2, A6, A8, M1, M2, M3, M4, 1N Proc <sg Search Question Bank for Piping and Heat Exchanger questions _274odTi HEATACTN WP -

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SPECIFICATION SHEET tmTE: 11/10/94 CUSTOMER: AFFRI Y t PR01%>L No. sc 572258-87A RSS ITEk t, GIBER A SALas T3CH. PTC ABMI MDEL NO: UFE-25 e No. Or tatITs IN PARALLEL 8 '1 4 RUN NUMBER: 277874 ,

4

• PsRFORMANCE ROT SIDE **** COLD SIDE

• c FLUID CIRCULATED

• MATER

• WATER

• 358.80

• 705.98

• GPM TOTAL FLOW RATE

• 788.95

• GPM IntIT FLOW RATE

• 358.55

• 1.06

• 1.88

• BTU /LB *F SPECIFIC HEAT

• 1.98

• SPECIFIC GRAVITY

• .99

.36 * .35

• STD/HR FT *F THERMAL CONDUCTIVITY * .31

• CP AT AVG TEMP

• .68

• VISCOSITY

• 110.00

• 88.55 * *F INLET TEMPERATURE * * 'F OUTLET TEMPERATURE

• 90.08 89.97

• 5.57

• if.89

• psi PRESSURE DROP *

• PSIC

• IDlINOWN 1D00t0533I ,

OPERATING PRES $URE BTU /HR UNIT NEAT EXCHANGED

• • • • • • • • • 3414378.0 *********

• PA8S ARRANGEMENT $ .

• CONSTRUCTION -

DESIGN PRESSURE

• 196

• PSIG  !

• 155

• PsIG 1 x 1 TEST PRESSURE

• 158 * *F DESIGN TEMPERATURE

• UNIT NET WEIGRT 1221

• POUNDS

• UNIT DIMENSIONS

• NOSELE SPECIFICATIONS LOCATION 1 M/I- 4*-STR LOCATION 2 C/I- 4'-STR 8

• 41.31' I4 CATION 3 E/O- 4"-STR DI'S#

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• 46.94" LOCAT E 4 _C/O- 4*-ST*

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• MATERIALS PLATE 8

• 384 38 GAsEETS

• NBR NOIILEs

• HOT EA-535 COLD SA-535 (FLANGED) l yRAME

• CS EPOET PAINTED RARs ** CD/EN Cs (wzTu urPzR sTAINLass sTEst CzaD) I 30LTs FIATED

• REMARKS:

• The spPEACHANGER p*W #8'*"** k based on yo eacwooy of en dem preeereed abon, and the customere ob81 e posuci and operstmg conssene m senernense wei me above?

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Corrosion and Activation Analysis of a Stainless Steel (type 304 or equivalent) Primary Pipe and Heat Exchanger Replacement for the AFRRI TRIGA Reactor Assumptions:

1. The corrosion 2

rate for austenitic stainless steels in neutral water is ie-7 g/cm day. This is reported as the lowest measurable value by H.H. Uhlig, Corrosion Handbook,1948, p.154

2. Year 1y average reactor usage is 26.3 MWh which yields a year 1y thermal neutron fluence of 1e18 n/cm2and a fast neutron fluence of 0.5e18 n/cm2,

3. The volume of water that receives neutrons is approximately 9.25 cubic feet, which is 0.45 % of the total water volume in the core and primary coolant system.

4. The composition of the austenitic stainless steel is 18 wt% Cr and 8 wt% Ni.

5. Decay of the activation daughter products can be neglected.

6. Activation Reactions ofinterest are:

Reaction isotope Cross Section T3 Abundance (thermal / fast)

Fe54(n.p)Mn54 5.85% I (Fe) = 0/0.082 bams 312.5 d Fe54(n,y)Fe55 5.85% I.(Fe) = 2.25/1.2 bams 2.7 y NiS8(n,y)NiS9 68.08 % I. (Ni) = 4.6/2.2 bams 75000 y NiS8(n.p)CoS8 68.08 % I. (Ni) = 0/0.113 bams 70.8 d Cr50(n,y)Cr51 4.35 % I (Cr) = 15.9/7.7 bams 27.7 d Constants:

1. Surface area of primary side of heat exchanger = 300 ft2

2. Surface area of primary piping = 25 ft'.

Calculated Values:

1. Surface Area of Primary Coolant System = 3E5 cm'

2. Corrosion Rate = 11 g/yr

3. Radioactive materials produced:

Max Dose Numberof atoms Activity (mR/hr) after Isotope Tx produced per year (mci /yr) 1 year storage Mn54 312.5 d 9.47E11 8.16E-4 1.8E 3 Fe55 2.7 y 0.58E13 0.018 8.0E-7 NiS9 75000 y 1.57E14 1.56E-6 1.0E-5 CoS8 70.8 d 1.56E12 0.005 6.0E-4 Cr51 27.7 d 8.87E13 0.856 1.8E-4 Total 2.6E-3

Conclusion:

The conversion of the primary piping and heat exchanger to stainless steel will not pose an increased radiation hazard to personnel or increase our waste disposal requirements.

O Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required

- Proposed Change: Daily Shutdown Checklist Modification to: Procedure _XX_ Facility Experiment Submitted by: Marte' Date 27 Nov 1998

1. Description of change:

Section III, Line 2, Discharge pressure changed to Il-16 psig. New heat exchanger provides less resistance to primary pump.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

None, items changed are adnumstratwe changes.

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy

=

cf changes necessary to Facilities.

No change to drawings

4. Determine what other procedures, logs, or training material may be affected and record below.

None, Staff to sign of f on new procedure

5. List of associated drawings, procedures, logs, or other materials to be changed:

None 6 Create an Action Sheet containing the list of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Submitted '

Not Required _XX_

Reviewed and approved by RFDDate I

,Ff' [9We U DEC 4 1992 RRFSC Notified Date 4

_ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ . .. ~

7-----.-~ _ __,-.. n,,,.~~,,- _ -.<n -.y~ _,_~~

LI,PE, RATIONAL PR,0CEDURE_ _ ,, ,i '

_Proced,re 8t TA,, I _,

DAILY OPERATIONAL SHUTDOWN CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by I. REACTOR ROOM (Room 3161)

1. All rod drives DOWN .

2. Carriage lights OFF .

3. Door 3162 SECURED

4. Channel test completed on both CAM's

5. Door 3161 locked with key .

II. EQUIPMENT ROOM (Room 3152)

1. Distillation unit discharge valve CLOSED .

2. Air dryer OPERATIONAL

3. Doors 231,231 A, and roof hatch SECURED .

Ill. EQUIPMENT ROOM (Room 2158) 1 Primary discharge pressure (11 - 16 psig)

• l 2 Demineralizer flow rates set to (5.5 - 6.5 gpm)

• 3 Visual inspection for leaks

4. Door 2158 and 2164 SECURED IV. PREPARATION AREA

1. ER2 plug door CONTROL LOCKED Door closed; and handwheel PADLOCKED 2 ER2 lights ON and rheostat at 10%

3 ERI plug door CONTROL LOCKED .

Door closed; and handwheel PADLOCKED .

4. ERI lights ON and rheostat at 10%

5. Visualinspection of area 6 Warm storage doors closed .

l i

AFRR1 Form 62(R) Revised: 27 November 98 1:\PROCEDWP\0P_81.WP6 Page 1

V. LOBBY ALARM Lobby alarm audio ON .. . . .... . ... .. . . ..

VI. REACTOR CONTROL ROOM (Room 3160)

1. Reactor tank lights OFF .. . . .. . .. . .. . . .... .

2.' Console chan recorder pens raised

3. Steady-state timer OFF . .. ..... .... . .

4. Console LOCKED, and all required keys neturned to lock box . . .

5. Diffuser pumps OFF ..

6. Purification, secondary and primary pumps ON . .. .

7. Reactor monthly usage summary completed . . .

8. Auxiliary chan recordere operating and tracing . .. . .

9. Radiation monitors . ... . . .

e MONITOR READING HIGH LEVEL ALARM SETTING (mrem /hr) a R-1 *

(<10) 10

b. R-2 (< 10) 10

c. R-3 (<10) 10 _

d.R-5 (<10) 10

e. E-3 *

(<10) 10

f. E-6 (<10) 10

g. R-6 *

(<10) l

• Numerical Entry AFRR1 Form 62(R) Revised: 27 November 98 I:\PROCEDWP\0P__81.WP6 Page 2

[ymm*-s-wwwwmmmwwwwcw*m-m mmem;mppggggperemmwgqqpmwwwwwwmewe 9 E D E S$ O$$E N ES M b m dauxs k a di$w a ddssh D E* M Al l.!$$h$$

DAILY OPERATIONAL SHUTDOWN CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by

1. REACTOR ROOM (Room 3161)

1. All rod drives DOWN .

2. Carriagelights OFF . .

3. Door 3162 SECURED

4. Channel test completed on both CAM's . .

5. Door 3161 locked with key . .

11. EQUIPMENT ROOM (Room 3152)

l. Distillation unit discharge valve CLOSED

2. Air dryer OPERATIONAL

3. Doors 231,231 A, and roof hatch SECURED 111. EQUIPMENT ROOM (Room 2158)

1. Primary discharge pressure (15 - 25 psig) .

2 Demineralizer flow rates set to (5.5 - 6.5 gpm)

• 3 Visualinspection forleaks 4 Door 2158 and 2164 SECURED IV. PREPARATION AREA

1. ER2 plug door CONTROL LOCKED Door closed, and handwheel PADLOCKED

2. ER2 lights ON and theostat at 10%

3. ERI plug door CONTROL LOCKED Door closed, and handwheel PADLOCKED

4. ERI lights ON and rheostat at 10%

5. Visualinspection of area . ,

6. Warm storage doors closed .

AFRR1 Form 62(R) Revised: 18 March 98 Page 1

V. LOBBY ALARM Lobby alarm audio ON . . .. . . . . . ..... . . . ..

VL REACTOR CONTROL ROOM (Room 3160)

1. Reactor tank lights OFF . . . .

2. Console chart recorder pens raised . .... . . .

3. Steady-state timer OFF , . . .. . ..

4. Console LOCKED, and all required keys returned to lock box

5. Diffuser pumps OFF . . . . .

6. Purification, secondary and primary pumps ON .. . .

7. Reactor monthly usage summary completed .. . .. .  ;

8. Auxiliary chart recorders operating and tracing .. . .

9. Radiation monitors .

MONITOR READING HIGH LEVEL ALARM SETTING (mrem /hr) a R-1 (< 10) 10 b.R-2 (< 10) 10

c. R-3

• 10

(<10) l d.~ R-5

• 10

(< 10) e E-3 (<10) 10

f. E 6 (<10) 10 g R-6 (<10)

• Numerical Entry AFRR1 Form 62(R) Revised 18 March 98 Page 2

R Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Change of Daily Safety Checklist.

Modification to: Procedure _XX_ Facility Experiment Submitted by: Marte' Date _27 Nov 98

1. Description of change:

Section III, Line 2. Discharge pressure changed to Il-16 psig. New heat exchanger provides less resistance to primary pump.

Section VI, Line 8.(b), " Alarm check" changed to "SGM High Indicator Check". The alert device for this point is a lamp, not an audible warning as may have been mferred from the word " Alarm".

Section V1, Line 8.(c), *High alarm set to" changed to "High alarm point set to*, This is the point where the lamp on ime 8.(b)illummates.

Section VI Line 12 was clarified as *Demmeraluer inlet Temperature"

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

None, Items changed are adnumstrative changes.

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Facilities.

No change to draw mgs.

4. Determine what other procedures, logs, or training material may be affected and record below, None, Staff to sign ott on new procedure

5. List of associated drawings, procedures, logs, or other materials to be changed:

None

6. Create an Action Sheet containing the list of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Submitted

• Not Required _XX_

/ ,

Reviewed and approved by RFD [ Date /i/'1 7 b &

RRFSC Notified

.a

$ Date

pmmememmy--ww mmeymmmmmmmmeeme-memmmssengnpnrymmmeseewn m a >

• G u isd L Gak Wiil$5A?E$ $ k%s $i..* 3. . . 455 DAILY SAFETY CHECKLIST T

Checklist No. Date Time Completed Supenised by Assisted by I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) *

2. Water drained from air compressor

3. Air dryer operating

4. Doors 231,231 A, and roof hatch SECURED

11. EQUIPMENT ROOM (Room 2158)

1. Prefilter difTerential pressure (< 8 psid) .

2. Primary discharge pressure (11 - 16 psig)

• l

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) *

4. Stack roughing filter (notify supenisor if> 1.0" of water) *

5. Stack absolute filter (notify supenisor if > 1.35" of water) .

6. Visualinspection of area

7. Door 2158 SECURED III. PREPARATION AREA Visual inspection of area IV REACTOR ROOM (Room 3161) 1 Transient rod air pressure (78 - 82 psig) *

2. Shield door bearing air pressure (8.5 - 11 psig) *

3. Visualinspection ofcore and tank

4. Number of fuel elements and Fuel elements

• control rods in tank storage Control rods *

5. Air particulate monitor (CAM)

(a) Primary operating and tracing .

(b) Backup operating (c) Channel test completed, damper closure verified

6. Channel test completed on SGM

7. Door 3162 SECURED

• Numerical Entry AFRRI Form 62b (R) Revised: 27 November 98 1:\PROCEDWP\OP,,8Bl.WP6 Page 1

V. LOBBY AREA Lobby audio alarm turned off . ..... . . . . . . . . . . . . . . . . . . . . .. . . . . .

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset . ... . . .. . . . . .... .

2. Console recorders dated . . . .. . ... . .. .. .

3. Stack flow and fuel temperature recorders dated . . . . ...

4. Logbook dated and reviewed . . ... . . . . . .

5. Water monitor box (a) Background activity (10 - 60 cpm) . . . ..

(b) Water monitor box resistivity (> 0.2 Mohm-cm) .... .

(c) DM1 resistivity (> 0.5 Mohm-cm) . .... . . . .

(d) DM2 resistivity (> 0.5 Mohm-cm) . . ... .. . .. .

6. Stack gas flow rate (15 - 35 Kcfm) .. . . .... . .

7. Stack linear flow rate (1.0 - 2.0 KfVmin) . . .. . . .

8. ~ Gas stack monitor  ;

(a) Background (2 - 20 cpm)

'J (b) SGM High indicator Check .. . . . .

(c) High alarm point set to 3.2 E-5 microCi/cc at stack top .. L (d) SGM chart recorder operating and tracing ... . ..

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr)

• 10 (a) R-1 (< 10)

(b) R-2 (< 10) 10

• 10 (c) R-3 (< 10)

(d) R-5 (<10) 10

• 10 (e) E-3 (< 10)

(O E-6 (<10) 10 10 TV monitors on . . . . ... .,

11. CAM high level audible alarm check .

12 Demineralizer inlet temperature (5 - 35 "C) . . ..

• k 13 Water level log completed . . .

14 Source level power greater / equal to 0.5 cps . . . . . .

• Numerical Entry AFRR1 Form 62b (R) Revised: 27 November 98 1:\PROCEDWP\0P_8Bl.WP6 Page 2

E)PEx eYONKW M @ URE M N ,TSBbiF3 DAILY SAFETY CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by i I

i I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) ... .. ....

2. Water drained from air compressor . ...... . . . .. . . .

3. Air dyer operating . . ... . . ... .

4. Doors 231,231 A, and roof hatch SECURED . . .

II. EQUIPMENT ROOM (Room 2158)

1. Prefilter differential pressure (< 8 psid) .. .

2. Primary discharge pressure (15 - 25 psig) . . .

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) . .

4. Stack roughing filter (notify supervisor if > 1.0" of water) .

5. Stack absolute filter (notify supersisor if > 1.35" of water) . .

6. Visualinspection of area . .. . .. . .

7. Door 2158 SECURED . . .. . ...

III. PREPARATION AREA Visual inspection of area . . .. . . ... . .

IV. REACTOR ROOM (Room 3161) i I

1. Transient rod air pressure (78 - 82 psig)

2. Shield door bearing air pressure (8.5 - 11 psig) . . . .. .

3. Visualinspection ofcore and tank . . . ..

4. Number of fuel elements and Fuel elements

• Control rods

• control rods in tank storage

5. Air particulate monitor (CAM)

(a) Primary operating and tracing . . . . .. . .

(b) Backup operating .. . . .

(c) Channel test completed, damper closure verified .

6. Channel test completed on SGM . . .

7. Door 3162 SECURED .

i i

f

• Numerical Entry AFRR1 Form 62b (R) Revised: 18 March 98 R:\PROCEDWP\0P_8Bl.WP6 Page 1 1

V. LOBBY AREA

)

Lobby audio alarm turned off .. ..... . . ... . . . . . . . . . .. . . . . . . . . . . . . . . . . . .

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset . . .... .. . . . ..... ... .....

2. Console recorders dated . . .. . . ... ........ .. .

3. Stack flow and fuel temperature recorders dated . . ........ .... .

4. Logbook dated and reviewed . . ... . .. . .......... .....

5. Water monitor box (a) Background activity (10 - 60 cpm) . . ..... .......... ..

(b) Water monitor box resistivity (> 0.2 Mohm-cm) . ..... .. . .

(c) DMI resistivity (> 0.5 Mohm-cm) . .. . . . .

(d) DM2 resistivity (> 0.5 Mohm-cm) ... .. . .. .

6. Stack gas flow rate (15 - 35 Kcfm) . .... . .. .. ..

7. Stack linear flow rate (1.0 - 2.0 KfVmin) . . ... . .. ... . . .

8. Gas stack monitor (a) Background (2 - 20 cpm) . . ... . .. . .. . .

(b) Alarm check .. .. .

(c) High alarm set to 3.2 E-5 microCi/cc at stack top . ..

(d) SGM chart recorder operating and tracing . .. . . .... .. .

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr)

(a) R-1 (< 10) 10

• 10 (b) R-2 (< 10)

(c) R-3 (< 10) 10 (d) R-5 (< 10) 10 (e) E-3 (< 10) 10 (f) E-6 (< 10) 10

10. TV monitors on .. . .

I1. CAM high level audible alarm check . . .. . .

12 Water temperature (inlet)(5 - 35 *C) *

13. Water levellog completed . . .

14. Source level power greater / equal to 0.5 cps

• Numerical Entry AFRRI Form 62b (R) Revised: 18 March 98 R:\PROCEDWP\0P_8B1.WP6 Page 2 s

\5 I Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Change of Operational Startup Checklist.

Modification to: Procedure _XX_ Facility Experiment Submitted by: Marte' Date _27 Nov 98

1. Description of change:

Section III, Line 2, Discharge pressure changed to Il-16 psig. New heat exchanger provides less resistance to primary

< pump.

Section VI, Line 8.(b), " Alarm check" changed to "SGM High indicator Check". The alert device for this point is a lamp, not an audible warning as may hase been inferred from the word " Alarm"Section VI, Line 8.(c), "High alarm set te" changed to "High alarm point set to" his is the point where the lamp on line 8.(b) il!ummates.

Lme 15. Time Delay Operative Moved to below hne 17. Prestart operability checks performed. De prestart checks can be run wnhout the key in the console.

Lme 12. Was clarified as "Dernmerahier inlet Temperature"

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

None, items changed are admitustrat ve changes.

3. If change involves a facility modification, attach a drawing if appropriate. If structurai facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Facilities.

No change to draw mgs.

4. Detennine what other procedures, logs, or training material may be affected and record below.

None, Staff to sign off on new procedure

5. List of associated drawings, procedures, logs, or other materials to be changed:

None

6. Create an Action Sheet containing the list of associated work, specified above, attach a copy, and submit it to the RFD.

Action Sheet: Submitted A Not Required _XX_

Reviewed and approved by RFD J

f Date n /2N$ F RRFSC Notified w.. .a -

$40 Date DEC 4 1998

nammm-w nnmm nnwnemmmnnnummemmmmmmyawm' PERAT.I.ONAIJPROCEDURE i.. i L-n- -

~mmun.Z::::? JnaMProcedure

^ ^ = - - 84 TAB 1-x - --

AM -

DAILY OPERATIONAL STARTUP CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by

1. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) *

2. Water drained from air compressor ..

3. Air dryer operating .

4. Doors 231,231 A, and roof hatch SECURED . ..

II. LOBBY AREA Lobby alarm turned off . . . ,

111 EQUIPMENT ROOM (Room 2158)

1. Prefilter differential pressure (< 8 psid) .

2. Primary discharge pressure (11 - 16 psig) . .

l 3 Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) . .

4 Stack roughing filter (notify supervisor if > 1.0" of water) .

5. Stack absolute filter (notify supersisor if> 1.35" of water) .

6. Visualinspection of area .. .

7. Door 2158 SECURED IV. PREPARATION AREA Visual inspection of area V. REACTOR ROOM (Room 3161)

1. Transient rod air pressure (78 - 82 psig)

• 2 Shield door bearing air pressure (8.5 - 11 psig) .

3 Visual inspection of core and tank 4 Number of fuel elements and Fuel elements

• control rods in tank storage Control rods *

5. Air particulate monitor (CAM)

(a) Primary operating and tracing (b) Backup operating .

(c) Channel test completed, damper closure verified

6. Channel test completed on SGM

7. Door 3162 SECURED i

• Numer. cal Entry AFRRI Form 62a (R) Revised: 27 November 98 1:\PROCEDWP\0P_8B.WP6 Page 1 l

l VI. REACTOR CONTROL ROOM (Room 3160) .l If Emergency a:r dampers reset ... .... ... ... . . .... ... ...

2. Console recorders dated- .. ...... .. ...... ....... .. ...

3. Stack flow and fuel temperature recorders dated ........ .... .. .

4. - Logbook dated and reviewed . ... ... ....... ....... .

5. Water monitor box

- (a) Background activity (10 - 60 cpm) . .. . ...... ... ... .

(b) Water monitor box resistivity (> 0.2 Mohm-cm) . . ... .

(c) DM1 resistivity (> 0.5 Mohm-cm) . .. . .... . .... . .

(d) DM2 resistivity (> 0.5 Mohm-cm) . .. . ... . . .. .... . .

6. Stack gas flow rate (15 - 35 Kcfm) . . . . ... ., . .

i

• I

7. Stack linear flow rate (1.0 - 2.0 KfVmin) . . . . . . . . . . . . . . . . ... ..

8. ' Gas stack monitor (a) Background (2 - 20 cpm) .. ... .... . . . . . .... .

(b) SGM High Indicator Check . . . ... . ... . ....

(c) High alarm point set to 3.2 E-5 microCi/cc at stack top .. . ...

(d) SGM chart recorder operating and tracing . .. ... .. .. ..

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting 'I Functional (mrem /hr) (mrem /hr)

(a) R-1 (< 10) 10

• 10 (b) R-2 (< 10)

• 10 (c) R-3 (< 10)

• 10 (d) R-5 (< 10)

• 10 (e) E-3 (< 10)

(f) E-6 (< 10) 10

10. TV monitors on . ...... . .... ..

11. CAM high level audible alarm check . .. . . ... .

12. Demineralizer inlet temperature (5 - 35 *C) . . ....,..... . ..

13. Water levellog completed . . . . . ..

14. Console lamp test completed . . .. . .. . ... ... .

15 Source level power greater / equal to 0.5 cps ... .. . .. .

16 Prestart operability checks performed . .. . ,

17, Time delay operative . . .. . .. .

18 Interlock Tests (a) Rod raising, SS mode (e) I kW/ Pulse mode (b) Rod raising, Pulse mode (f) NM-1000 HV (c) Source RWP- (g) Inlet Temp (d) Period RWP 19 SCRAM checks (at least one per rod)

(a) % Power 1 (h) Reactor key (b) % Power 2 (i) Manual (c) Fuel temp 1 (j) Emergency Stop (d) Fuel temp 2 (k) Timer (e) HVloss 1 (1) CSC Watchdog (f) HV loss 2 (m) DAC Watchdog (g) Poollevel 20: Zero power pulse .. . .. .. .

• Numerical Entry AFRR1 Form 62a (R) Revised: 27 November 98 I:\PROCEDWP\0P_8B.WP6 Page 2

N!$ N$NSINN!$bI3NNNN$NNMsh ,

DAILY OPERATIONAL STARTUP CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 120 psig) ...... . . . .. .... .. ..

2. Water drained from air compressor . ... ...... .

3. Air dryer operating . .... .. . . . . . .. .

4. Doors 231,231 A, and roof hatch SECURED . . . .. . ..

I II. LOBBY AREA Lobby alarm turned off . . . . . .

III. EQUIPMENT ROOM (Room 2158)

1. Prefilter differential pressure (< 8 psid) . . .. .

2. Primary discharge pressure (15 - 25 psig) .. .... . .

3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) .

4. Stack roughing filter (notify supervisor if > 1.0" of water) .. .

5. Stack absolute filter (notify supervisor if > 1.35" of water) .

6. Visual inspection of area

7. Door 2158 SECURED . . . ... .

IV. PREPARATION AREA Visual inspection of area . . .

V. REACTOR ROOM (Room 3161)

1. Transient rod air pressure (78 - 82 psig) *

2. Shield door bearing air pressure (8.5 - 1I psig) *

3. Visual inspection of core and tank

4. Number of fuel elements and Fuel elements

• control rods in tank storage Control rods *

5. Air particulate monitor (CAM)

(a) Primary operating and tracing .

(b) Backup operating (c) Channel test completed, damper closure verified

6. Channel test completed on SGM .

7. Door 3162 SECURED .

• Numerical Entry AFRRI Form 62a (R) Revised: 18 March 98 R:\PROCEDWP\0P_8B.WP6 Page 1

- VI. REACTOR CONTROL ROOM (Room 3160)

1. Emergency air dampers reset .. ..... . . .. ..... . .

2. Console recorders dated . . .. .. . .... . ....

3. Stack flow and fuel temperature recorders dated ... ..... . ... .

4. Logbook dated and reviewed .. . .. . ...... ....... ..

5. Water monitor box (a) Background activity (10 - 60 cpm) . . . . .. . .

(b) Water monitor box resistivity (> 0.2 Mohm-cm) . ....... .

(c) DM1 resistivity (> 0.5 Mohm-cm) ....... .. .. .. .

(d) DM2 resistivity (> 0.5 Mohm-cm) . .. . .... .

6. Stack gas flow rate (15 - 35 Kcfm) . . . .. ..

7. Stack linear flow rate (1.0 - 2.0 Kfl/ min) . .

8. Gas stack monitor (a) Background (2 - 20 cpm) . . ......

(b) Alarm check . .. .. ..

(c) High alarm set to 3.2 E-5 microCi/cc at stack top . . . . . .

(d) SGM chart recorder operating and tracing .

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr)

(a) R-l (< 10) 10 (b) R-2 (< 10) 10 (c) R-3 (< 10) 10 (d) R-5 (< 10) 10 (e) E-3 (< 10) 10 (f) E-6 (< 10) 10

10. TV monitors on . . .. . ... ... . . .. ...... .

I1. CAM high level audible alarm check ... . .. .. .

12. Water temperature (inlet)(5 - 35 *C) .. . ... ..

13. Water level log completed . .

14. Console lamp test completed .

15. Time delay operative . . .

16 Source level power greater / equal to 0.5 cps . . .. .

17. Prestart operability checks performed . . . . .

18. Interlock Tests (a) Rod raising, SS mode (e) I kW/ Pulse mode (b) Rod raising, Pulse mode (f) NM-1000 HV (c) Source RWP (g) Inlet Temp (d) Period RWP

19. SCRAM checks (at least one per rod)

(a) % Power 1 (h) Reactor key (b) % Power 2 (i) Manual (c) Fuel temp 1 (j) Emergency Stop (d) Fuel temp 2 (k) Timer (e) HVloss 1 (1) CSC Watchdog (f) HVloss 2 (m) DAC Watchdog (g) Poollevel

20. Zero power pulse . ..

• Numerical Entry AFRRI Form 62a (R) Revised: 18 March 98 R:\PROCEDWP\0P_8B.WP6 Page 2

ATTACHMENT C Appointment Letters for Current Reactor and Radiation Facility Safety Committee Changes

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m ARMED FORCED RADIO lOLOGY REHEARCH INSTITUTE 8901 wlSCONSIN AVENUE BE7NEsDA. MARYLAND 20889 5603 w

AFRRl/RSD 6055 31 December 1998 MEMORANDUM FOR REACTOR DEPARTMENT FILES

SUBJECT:

Reactor and Radiation Facility Safety Committee Membership Effective this date, the following individuals are members of the Armed Forces Radiobiology Research Institute (AFRRI) Reactor and Radiation Facility Safety Committee (RRFSC). Memberships are in accordance with the Technical Specifications of Nuclear Regulatory Commission license R 84.

PERMANENT MEMBERS Stephen 1. Miller, AFRRl, Reactor Facility Director Voting Member Bruce A. White, MAJ, USAF, AFRRI, Radiation Safety Officer Voting Member APPOINTED MEMBERS Curtis W. Pearson, COL, USAF, MSC, Chairman Voting Member Dr. Marcus Voth, Monticello Nuclear Generating Plant, Voting Member Licensing Project Manager Bill Powers, Naval Research Laboratories, Voting Member Radiation Safety Officer SPECIAL MEMBERS J.W. Malinoski, CAPT, MSC, USN, AFRRI, Special Voting Member Head, Radiation Sciences Department Edward R. Herbert, Montgomery County Government, Special Non-Voting Member Environmental Protection Department RECORDER Samuel D. Osborne, SFC, USA, AFRRI I

CJL ( ,

ROBERT R. ENG COL, MS, USA Director DISTRIBUTION:

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