ML20217F033
| ML20217F033 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 12/31/1997 |
| From: | Eng R, Miller S ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9803310245 | |
| Download: ML20217F033 (167) | |
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ARMED FORCED RADIOBIOLOGY RESEARCH INSTITUTE 8901 WISCONSIN AVENUE BETHESDA. MARYLAND 20889-5603 5002 20 Mt.rch 98 RSDR
SUBJECT:
Submission of Annual Report U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
Attached please find the 1997 Annual Report for the AFRRI TRIGA reactor facility, submitted as required by license R-84, facility docket 50-170.
Should you need any further information, please contact the undersigned at (301) 295-1290.
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Attachment:
e iller as stated R or acility Director .
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U.S. Nuclear Regulatory Commission ATrN: Mr. Marvin Mendonca, Mail Stop 11B20 Washington, DC 20555 Regional Administrator U.S. Nuclear Regulatory Commission, Region I ATrN: Mr. Thomas Dragoun g 475 Allendale Road King of Prussia, Pa.19406 O l
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Armed Forces Radiobiology Research Institute AFRRI Triga Reactor Facility 1 January 1997 - 31 December 1997 l
To satisfy the requirements of U.S. Nuclear Regulatory Commission, License No. R-84 (Docket No. 50-170),
l, Technical Specification 6.6.1.b.
The Reactor Facility Director acknowledges the participation of the following personnel for their contributions to this annual report.
Written by Robert George MAJ Kenneth L. Wrisley, CM, USA SSG Samuel Osborne, USA 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 Fax: (30l) 295-0735 I
1997 Annual Report ofthe AFRRI TRIGA Reactor
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Docket 50-170 License R-84 Submitted by Stephen Miller Reactor Facility Director
T 1997 ANNUAL REPORT TABLE OF CONTENTS
! Introduction General Information Section I Changes to the fr.cility design, performance characteristics and operational procedures, results of surveillance tests and inspectionsSection II e Energy generated by current reactor core and number of pulses $2.00 or larger Section III Unscheduled shutdownsSection IV Safety-related corrective maintenance Section V Facility changes and changes to procedures as described in the Safety Analysis Report.
New experiments or tests during the year Section VI Summary of radioactive effluent released I
Section VII Environmental radiological surveys Section Vill 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 of modifications, changes, and enhancements to i procedures or facilities l Attachment C Appointment letters for various Reactor and Radiation Facility Safety Committee changes i
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1997 ANNUAL REPORT
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INTRODUCTION '
The AFRRI reactor facility was available in 1997 for irradiation services throughout the year with only a brief nonoperational period during the annual reactor maintenance shutdown.
AFRRI received a closure order from the Deputy Secretary of Defense in 1995. As of December 31,1997, there is strong support to keep AFRRI open and possibly transfer it to another agency; ;
no decision has been made as to which agency. AFRRI has been funded to continue operating
. for the next several years. No funding has been allocated to close AFRRI.
The annual reactor facility audit was held in November 1997. The auditors concluded that the
' reactor was being operated in conformance with the Technical Specincations and Operating License. No items of concern were identiGed during this audit. Discussion of the audit is covered in Section IE. The Nuclear Regulatory Commission did not inspect the AFRRI TRIGA 1 Reactor during 1997.
The reactor core remained unchanged throughout the year.
Reactor staff changes included the departure and replacement of all existing military staff and Mr. Mark Moore. Mr. Moore had served as the Reactor Facility Director for many years and was replaced by Mr. Step.: :n Miller. The transition occurred smoothly without any operational ;
disruptions. Currently there is no authorization to fill the position vacated by Mr. Miller.
A new plate and frame heat exchanger was purchased for the reactor to replace the old tube and l shell heat exchanger. The new heat exchanger, scheduled to be installed in 1998, is physically smaller but matches the heat transfer specifications of the existing exchanger. The new exchanger will be easier to maintain and repair. The replacement of the heat exchanger is part of a continuing effort to maintain and upgrade the reactor facility to the highest possible i standards. Upgrades and timely replacements prevent possible malfunctions and emergency repairs of older equipment.
Staff time was used in numerous projects through 1997. Acquisition and installation of a multichannel analyzer was initiated to enhance the reactor staff's ability to perform neutron activation analysis in support of future projects. A renewed interest in creating a beam tube has staff members researching the design features and capabilities. Time was spent educating people in various public relations projects about the aspects of radiation.
Irradiations were performed for several archaeologists to trace and categorize clay pottery found at sites in Virginia and Maryland. These studies try to match pottery to sources of clay and track the distribution of pottery throughout the colonies. Other archaeological samples were irradiated for various neutron activation studies.
Changes were made to the procedures and facilities during 1997. In accordance with the
1 provisions of 10 CFR 50.59, an extensive safety review was conducted and supported. See discussion in Sections I and V.
The reactor staff provided personnel to assist in conducting operational and safety inspections of the Fast Burst Reactor facilities at Aberdeen Proving Grounds in Maryland and at White ,
Sands Missile Range in New Mexico. At the request of Cornell University in Ithaca, New York, j an operations audit ofits reactor facility was also conducted. I J
The remainder of this report is written in the format designed to include information items that are required by 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 as listed in Section 6.6.1.b of the AFRRI TRIGA Reactor Technical Specifications.
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- i f 3 Key Personnel .
1:1 Reactor and Radiation Facility Safety Committee
GENERAL INFORMATION All personnel held positions as listed throughout the year unless otherwise specified.
Key AFRRI administration personnel (as of 31 December 1997) are as follows:
Chairman; Radiation Sciences Department: CAPT James Malinoski, MSC, USN
._ Radiation Protection Officer: Maj Bruce White, USAF (25 November 1997)
- 2. Reactor Senior Technical Manager:
s Reactor Facility Director and Senior Reactor Operator (SRO): Stephen Miller
- 3. Current Reactor Operations Personnel:
Reactor Operations Supervisor: Robert George (SRO)
Training Coordinator: Robert George (SRO)
Maintenance: John Nguyen (SRO)
Administration: SSG Samuel Osborne, USA (as of 27 May 1997)
Senior Staff Engineer: MAJ Kenneth L. Wrisley, CM, USA (as of 2 June 1997)
- 4. Other Senior Reactor Operators: None
SSG Samuel Osborne, USA (27 May 1997)
MAJ Kenneth L. Wrisley, CM, USA (2 June 1997)
CPT Michael Ortelli, FA, USA (30 June 1997)
SFC William Baxter, USA (23 October 1997)
HM1 Deborah Gilchrist, USN (18 July 1997)
- 6. Newly Licensed Operators: None
- 7. Additions to staff during 1997: SSG Samuel Osborne, USA (27 May 1997)
MAJ Kenneth L. Wrisley, CM, USA (2 June 1997)
CPT Michael Ortelli, FA, USA (30 June 1997)
SFC William Baxter, USA (23 October 1997)
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- 8. Departures during 1997: SFC Brian Cohill, USA (6 May 1997)
LTC Leonard Alt, EN, USA (6 May 1997)
SFC Danny McClung, USA (6 August 1997)
Mark Moore (3 August 1997)
- 9. There were several staff changes to the Reactor and Radiation Facility Safety Committee (RRFSC) during 1997. SSG Samuel Osborne replaced SFC Danny McClung as recorder. William Powers was appointed to the RRFSC when he replaced Mark A. Miller acting Radiation Safety Officer at the Naval Research laboratory. Dr. David McKown replaced CAN C. B. Galley as the Radiation Safety Officer (acting) and was later replaced by MAJ Bruce White, USAF. The appointment letters are provided in attachment C.
, In accordance with AFRRI Reactor Technical SpeciGcations, the 1997 RRFSC consisted of the following members as of 31 December 1997.
Regular Members:
MAJ Bruce White (Radiation Protection Of6cer)
Stephen Miller (Reactor Facility Director)
Marcus Voth (Reactor Operations Specialist)
William Powers (Health Physics Specialist)
Chairman:
Col Curtis Pearson, USAF, MSC (Director's Representative) i Special Members: l CAPT James Malinoski, MSC, USN (Chairman, Radiation Sciences Department, AFRRI)
Nonvoting members:
Edward Herbert, Montgomery County Government, Environmental Protection Agency Leslie McKinney, Ph.D. (Radiation Pathophysiology and Toxicology Department, AFRRI) :
Recorder:
. SSG Samuel Osborne, USA l
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E As required by the Reactor Technical Specifications, four meetings of the RRFSC were held on
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19 March 1997. Full Committee Meeting, 23 June 1997, Subcommittee Meeting, 22 September 1997, Full Committee Meeting, and l 8 December 1997, Full Committee Meeting.
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. )f O Changes to the Facility Design, Performance Characteristics and Operational Procedures 3 Results of Surveillance Tests and Inspections 1
i f l SECTION 1 A summary of changes to the facility design, performance characteristics, administrative procedures, operational procedures, and the results from surveillance testing are provided in this section. Revised reactor administrative and operational procedures are in attachment A, and the l 10 CFR 50.59 reviews are in attachment B for the following changes. A. DESIGN CHANGES: There were no design changes to the facility during 1997. All changes were procedural or administrative. o B. PERFORMANCE CIIARACTERISTICS: No changes to the core occurred during 1997. 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: The Safety Analysis Report was changed to allow the use of a reporting method for Argon-41 releases that was approved by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA). This change was necessitated by the NRC's adoption of the EPA's 10-millirem constraint rule. No changes to the operation of the reactor were necessary because AFRRI's total Argon-41 releases for 1997 were only 3% of the 10-millirem annual constraint limit. D. OPERATIONAL PROCEDURES:
- 1. A new procedure .h1050, Cooling Tower Drain and Refill, was established. This procedure instructs an operator on how to drain and refill the cooling tower by using the new drain line installed in 1996. As the cooling tower operates, water evaporates
. and causes calcium from the water to plate out inside the cooling tower. Use of this new procedure will replace the calcium-rich water with fresh water and reduce the !
deposits that build up in the sump of the cooling tower.
- 2. Procedure 8 at Tab H was changed to specify calendar week for recording ;
l demineralizer information on the sheet. This change is to provide for consistent recording of information.
- 3. Another new procedure, hiO51, Channel Test of the Stack Gas hionitor (SGhi), was ,
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established. This procedure instructs an operator how to channel test the SGM This procedure was created to provide additional channel tests of the SGM during the year.
- 4. Procedure A007, Emergency Training of ECP Personnel, was changed to add a line instructing the person training the ECP staff to check the contents of the ECP inventory box against any inventory sheet in the box. This change was made because of a comment from the 1996 Emergency Drill after-action report.
- 5. Procedure S011 was changed to remove unnecessary details. Specifications such as cycles and divisions on graph paper were unnecessary in the procedure. The purpose of the procedure is to draw a curve, and check two specific points on the curve that are required by the Technical Specifications for the facility. The modified procedure specifies the required poin s and additional points as necessary to produce a smooth
, curve.
- 6. Procedure 11, Air Particulate Monitor (CAM), was rearranged. The content of the procedure did not change. The last section of the procedure specified test frequency; the test frequency should be first in the procedure. The frequency specification was moved to the first line.
- 7. Procedure C006, Stack Gas Mcnitor Calibration, was corrected to reset a toggle switch that is used to put the unit into calibration mode. Failure to reset the switch renders the unit inoperative. During the initial testing and calibration of the unit and the writing the associated procedure, the switch was flipped back into the operational mode, but this step was not recorded.
- 8. Procedure C007 was moved to C026 ar.d renamed Operational Channel Alignment, and a new Calibration of Operational Channel, procedure C007, was created. An Operational Channel Alignment is required when new components are installed into the operational channel or if the alignment gets out of specification. The new C007 procedure (Calibration of Operational Channel) checks the trip points, voltages, and alignment of the channel and allows for minor adjustments of reactor power indications. If any of the adjustments become too great, the new channel calibration procedure directs that a channel alignment be performed. The new procedure checks
, and adjusts key set points and verines the alignment of the channel where the old procedure sets up individual components to operate together. A channel alignment performs all the functions of a channel calibration but has not been necessary since the , individual components were initially set up.
- 9. Procedure C012, Control Rod Calibration, was modified to remove the specifications for the old reactivity computer, which is no longer used, and replaced with instructions for either of two newer digital reactivity computers. The procedure is used to produce control rod worth measurements. Each of the reactivity computers produces results comparable to the stopwatch method, which is also specified in the procedure as an alternate method to produce curves. This change will allow use of new methods to produce control rod calibration curves.
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- 10. A tag was created to indicate the status of the radiation area monitors (RAMS). This was a response to a 1997 annual audit comment. RAMS are normally turned up during pu!se, high power steady state, and square wave operations. This change also changes the daytime setpoint for RAM R5 and eliminates need to change the setpoint for high power steady state and square wave operations.
Procedures 8G1 and 8G2 were changed to add the use of a high setting indicator tag for critical and suberitical pulse operations. Proceduce 8E, 8F1 and 8F2 were changed to eliminate the requirement of turning up the RAMS during steady state, critical, and suberitical square wave operations. The RAM R5 setting was changed to 500 mrem on the daily startup checklist (Procedure 8B), and annotated on the Nuclear instrumentation Set Points list (Procedure 8C).
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The change of the RAM R5 setting is higher than past checklists but is far more ! conservative during high power steady state and square wave operations. The previous setting during high power operations would probably not allow the RAMS to alarm in the event of a fuel cladding rupture. The new set point is high enough to prevent inadvertent alarming during normal power operations, but should still alarm in the event of a fuel cladding rupture. RAM R2 maintains its daytime alarm point of 10 millirem. RAM R2 is located 12 feet from the reactor pool. A fuel cladding rupture would elevate the airborne radiation levels to well above the 10-millirem setpoint for RAM R2, as well as alarming the continuous air monitors (CAMS). E. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS: All required maintenance and surveillance tasks during 1997 were accomplished as required. Malfunctions are detailed in section IV. One outside audit was conducted during 1997. The audit was conducted by Daniel H ,;hes of the Penn State University Breazcale Nuclear Reactor Facility. Mr. Hughes is a licet d Senior Reactor Operator and the Manager of Engineering at Penn State University. No safety
. concerns were found by the auditor.
The Nuclear Regulatory Commission did not inspect the reactor facility during 1997, nor were they required to do so. l l I
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A 3 Energy Generated by Current Reactor Core and Number of Pulses $2.00 or Larger
i I l SECTION II l i Energy generated by the reactor core: Month Kilowatt-Hours JAN 467.3 FEB 595.1 MAR '403.6 , APR 218.9 I MAY 442.8 JUN 2,882.1
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JUL 407.4 AUG 2,554.7 SEP 5,599.0 OCT 696.4 NOV 813.2 DEC 7.339.9 TOTAL- 22,420.4
- J Total energy generated in 1997: 22,420.4 kwhr Total energy on fuel elements: 917,244.2 kwhr ;
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Total energy on FFCRs*: 184,446.1 kwhr i Total pulses this year 1 $2.00: 4 Total pulses on fuel elements 1 $2.00: 4,195 Total pulses on FFCRs* 1 $2.00: 83 Total pulses this year: 125
' Total pulses on fuel elements: 11,284 ' i Total pulses on FFCRs*: 1,519
- Fuel Following Control Rods !
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D Unscheduled Shutdowns
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- SECTION III Unscheduled Shutdowns:
There was one unscheduled shutdown in 1997. During an operation on 18 March 1997, the regulating (REG) control rod dropped into the core causing the reactor power to decrease. The console indicated no apparent reason for this event.
- Several systems were diagnosed and tested, but all systems were operating properly and were found to be in calibration. The surfaces between the armature and magnet on the control rod drive were cleaned. Dirt and dust are suspected to have kept the two pieces of the drive from coupling securely. The drop-off event did not recur.
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3 Safety-Related Corrective Maintenance
SECTION IV '
, V Safety-Related Corrective Maintenance v j
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The following are exddrpts from the malfunction logbook during the reporting period. The' reason for the corrective action taken, in all cases, was to return the failed equipment to its proper operational status. / '
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m jf 17 Jan 1997 The primary continuous air monitor (CAM) pump was found not operating during the daily startup. The problem was discovered to be a broken power cable inside the motor circuit. Operations were resumed after switching the primag CAM operations to the backup CAM. The defective motor was replaced with a spare motor, the new motor was tested, and the CAM was channel tested before being placed back in service. 14 Feb 1997 The stack gas monitor (SGM) air pump motor was discovered during the daily j startup to be non-operational. Diagnosis found the pump fuse was blown. The fuse holder had become corroded and the additional resistance in the circuit was suspected to have caused heating of the fuse and thus the fuse to blow. The fuse holder and fuse were replaced, and the SGM was channel tested. After successful l testing, the SGM was placed back on line. l i 24 Feb 1997 Resolution to 15 Oct 1996 problem with the AFRRI air compressor. The AFRRI , air compressor was repaired and placed back on line. The air supply operating the i cooling tower bypass valve was switched from the reactor air compressor back to the AFRRI air supply. 17 Mar 1997 The control system console (CSC) computer monitors were found blank during daily startup. The problem was found to be a bad power supply in the CSC computer. The power supply was replaced with a spare. The computer powered up, and all startup checks functioned properly. 18 Mar 1997 During an at-power operation, the REG control rod dropped from its electromagnet into the core. There was no indication or reason for the unplanned shutdown. The other control rods remained in position. Several systems relating L to the REG rod drive were tested and found to be in calibration. The surfaces ,' between the magnet and armature were cleaned to ensure good contact when the l- components couple. The REG rod drive was tested and found to be operational. This anomaly did not occur again. 18 Mar 1997 A non-reactor staff member complained of a loud " whoosh" at the end of each reactor air compressor cycle. The whoosh of air was determined to be a normal function of the air compressor. During the evaluation and careful examination of the air compressor, a hairline crack was discovered in a high pressure coupling
attached to the compressor head. The air compressor head was replaced with a spare and placed back on line. The replacement unit made the same whoosh at the end of each cycle. 22 Jul 1997 The high resolution monitor stopped displaying information after an update to the configuration. The attempted change was to add a piece ofinformation to the low resolution monitor. General Atomics staff stated that the change made to the configuration should not disrupt the operations of the console. The old configuration was reloaded and operated properly. In the process of diagnosing the configuration problem, a bad memory segment was found on the memory board. The bad memory segment was high enough in memory that it was not suspected to have been causing any problems. A new
, memory board was installed in the computer and tested.
After both the memory card was replaced and the configuration was restored, all functions of the CSC were tested and operated properly. The console was placed back on line. 11 Sep 1997 The CSC was found locked up. The console was rebooted and it promptly locked up again with a message on the Data Acquisition and Control (DAC) unit stating
" Network Looks Dead". Diagnosis found a bad network card in the CSC. The card was replaced with a spare network card, and the console booted up properly.
All scrams and interlocks were tested and operated properly, and the console was placed back on line. 23 Sep 1997 Fuel Temperature Channel 1 did not give a scram message when tested during the daily startup. Diagnosis found that the relay in the Mighty Module, which creates . the scram message signal, had failed to change states at the time of the scram. The Mighty Module contains two relays. One of the relays causes the reactor to scram, the other creates a scram message signal. Only the message signal had failed. The scram for the fuel temperature channel had operated properly. The Mighty Module was replaced, and the fuel temperature channel was calibrated and tested. The reactor was placed back on line once operational verification was complete. 05 Dec.1997 During the daily startup, the SHIM rod drive failed to drive up. The problem was . identified as the SHIM translator blowing its fuse. A rod drive translator creates step signals to drive stepper motors. The translator was replaced, and the new translator was tested and found to operate properly. The step speed was adjusted, and the reactor was placed back on line.
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1 Section V
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@ Facility Changes and Changes to Procedures as Described in the Safety Analysis Report 3 New Experiments or Tests During the Year
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F, SECTION V Changes 'to the facility and procedures as described in the Safety Analysis Report (SAR) and new experiments or tests performed during the year are contained in this section. A._ _ The SAR was' changed'to reflect-the use of an NRC/ EPA-approved method for !- calculating argon releases. This change was necessitated by the Nuclear Regulatory - Commission's adoption of the Environmental Protection Agency's 10-millirem constraint
- rule. Reactor operations remain unchanged because AFRRI's total Argon-41 releases are far below the 10-millirem annual constraint. Data for this year's releases can be foand
- l. 'in section VII.
B.' There were no new experiments or tests performed during the reporting period. 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 L 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. 4-l - t 1 4
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; . 'e 3 Summary of Radioactive Effluent Released 3 Summary of Radiological Surveys 3 Exposures Greater than 10% of 10 CFR Limits 1
SECTION VI Summary of Radioactive Effluent Released:
A. Liquid Waste: The reactor produced no liquid waste during 1997.
B. Gaseous Waste: There were no particulate discharges in 1997. The total ' activity of Ar-41 discharged in 1997 was 9.06 curies. The. estimated activity from the release of Argon-41 was below the constraint _
.- limit for unrestricted areas (Table 2 'of Appendix B to 10 CFR 20).
Quarterly: Jan - Mar 1997 0.36 Ci
- Apr - Jun 1997 1.68 Ci Jul - Sep 1997 3.44 Ci Oct - Dec 1997 3.58 Ci C. Solid Waste: All solid radioactive waste material was transferred to the AFRRI byproduct license; none was disposed of under the R-84 License.
SECTION VII
.. Environmental Radiological Surveys:
A. Environmental sampling of soil and vegetation reported radionuclide levels that were not above the normal range. The radionuclides that were detected were those normally_ expected from natural background and from long term fallout. B. The calculated annual dose, due to Argon-41 release to the environment for 1997, was J0.3 mrem at the location of maximum exposure. This location is 91 meters from the release
- point. Exposure to the general populatic 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 plublic is 10 millirem per year. The exposure dose was calculated using COMPLY code, level 2. E.nissions due to reactor operations were 3% of the constraint limit.
.- iq C. The reactor in plant surveys, specified in HPP 3-2, did not exceed any of the action levels specified in HPP 0-2.
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SECTION VIII -l 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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ATTACHMENT A Revised Reactor Administrative and Operational Procedures Procedure 8, Tab B Daily Operational Startup Checklist . Procedure 8, Tab C Nuclear Instrumentation Set Points Procedure 8, Tab E Steady State Operation Procedure 8, Tab F1 Square Wave Operation (Suberitical) Procedure 8, Tab F2 Squars Wave Operation (Critical) Procedure 8, Tab G1 Pulse Operation (Critical) i Procedure 8, Tab G2 Pulse Operation (Subcritical) Procedure 8, Tab H Weekly OperationalInstrument Checklist Procedure 11 Air Particulate Monitor (CAM) Procedure f Procedure A007 Emergency Training of ECP Personnel Procedure C006 Stack Gas Monitor Calibration Procedure C007 Calibration of Operational Channel Procedure C012 Control Rod Calibration Procedure CO26 Operational Channel Alignment Procedure M050 Cooling Tower Drain and Refill . Procedure M051 Channel Test of SGM ) Procedure S011 Power Coefficient of Reactivity
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a IM kdk b b b $ N b [$f2k b 3 $ N M D B[ B) [ d DAILY OPERATIONAL STARTUP CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by { l I. EQUIPMENT ROOM (Room 3152) i i
- 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 1 Lobby alarm turned off . ... .. . . . I I 1 III. EQUIPMENT ROOM (Room 2158)
- 1. Prefilter difTerential pressure (< 8 psid)
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- 2. Primary discharge pressure (15 - 25 psig) . .
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- 3. Demineralizer flow rates set to 6 gpm (5.5 - 6.5 gpm) *
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- 4. Stack roughing filter (notify supervisor if > 1.0" ofwater) . . .. . 1
- 5. Stack absolute filter (notify supervisor if > 1.35" of water) .. . ..
- 6. Visualinspection of area .
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- 7. Door 2158 SECURED . .. . . . .
IV. PRE'PARATION AREA Visual inspection of area . l V. REACTOR ROOM (Room 3161)
- 1. Transient rod air pressure (78 - 82 psig) .
- 2. Shield door bearing air pressure (8.5 - 11 psig) I
. 3. Visual inspection of core and tank
- 4. Number of fuel elements and Fuel elements control rods in tank storage Control rods l
- 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: 24 Nov 97 Page 1
[DPERAtlONARPR, [dsDURE[ ["][^]((Pr55urehTkB'C 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 . 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
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- b. CAMS: 10,000 CPM
- c. Stack Gas: 3.2E-5 microCi/cc at stack top
- d. Water Monitor Box Gamma: 7000 CPM
- e. Criticality Monitor (RS): 500 mrem day 20 mrem night Revised: 24 Nov 97 Page 1
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[,ORERATIONAL~ PROCEDURE ,
, 'f ; , ; r %j Procedure'88 TAB,E STEADY STATE OPERATION GENERAL The reactor shall not be operated at a power greater than 1.0 MW, SPECIFIC
- 1. Set tne mode owitch to manual mode and clear all warning messages and scrams.
- 2. Raise control rods with the appropriate banking, taking into consideration the location in the pool power level ,and experimental requirements
- 3. If final approach to criticalis to be made in Auto mode, perform the following:
- a. Set the the thumb wheel dials to the desired power.
- b. Raise the rods to the appropriate banking.
- c. Select the rods that are to servoed. ]
- d. Make sure that all rods that will be servoed have been raised at least 5%.
i e. Enter Auto mode.
- 4. Scram the reactor at the end of the run using the manual or timer scram.
- 5. Ensure the appropriate entries have been made in the operations logbook.
l l l 1 Revised: 24 Nov 97 Page 1
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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 ($)
- For demand powers up to 25 KW, insert 50.70
- For demand powers greater than 25 KW, insert 50.75 !
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- 2. Apply air to the transient rod and raise the anvil to the citical position that was calculated above.
- 3. Bring the reactor cold critical using the three standard control rods; use a rod configuration commensurate with the core position and experimental requirements. If Auto Mode is used, select the rods to be used. Ensure that these rods have been raised at least 5% before entering Auto Mode. Set the cold critical power level on the Power Demand thumb wheels and enter Auto Mode.
- 4. Stabilize the reactor in Manual Mode.
- 5. Set power demand thumb wheels to desired power level.
- 6. Select the standard control rods to be servoed. Make sure that all control rods to be servoed have been raised at least 5%.
- 7. Scram the transient rod.
- 8. Raise the anvil to the desired final position.
- 9. Allow the power level to fall below 1 watt.
Revised: 24 Nov 97 Page1
- 10. Switch into Square Wave mode.
- 11. Depress Fire button.
- 12. As the power level approaches the power demand level, the console will switch into .
Auto Mode. If power can not reach the demand power, it will automatically change , to manual mode At this time, either switch to Auto Mode or bring the reactor to the desired power level manually. Scram the reactor at the end of the run using the manual or timer scram. i 13.
- 14. Ensure all pertinent information has been entered in the reactor operations logbook.
f Revised: 24 Nov 97 Page 2 1
[6EEN fiON l[PROCEb~UNEf ^["~["" ~ ~C3oEiduie 8,$ TAB 5 SQUARE WAVE OPERATION (Critical) ) l GENERAL i The square wave mode will not be used above a demand power of 250KW. SPECIFIC
- 1. Bring the reactor cold critical using the three standard control rods. I Use a rod configuration commensurate with the core position and experimental
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requirements. If Auto Mode is used, select the rods to be used, ensure that all rods to be servoed have been raised at least 5% before entering Auto Mode, set the cold critical power J level on the Power Demand thumb wheels, and enter Auto Mode. l
- 2. Stabilize the reactor in Manual Mode.
- 3. Determine TRANS rod anvil setting for desired insertion.
Insert 70 cents for demand powers up to 25 KW. Insert 75 cents for demand powers greater than 25 KW.
- 4. Rise the anvil to the appropriate setting corresponding to these values using the transient rod calibration curve corresponding to current core position.
- 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. Switch into Square Wave mode.
- 8. Depress Fire button.
As the power level approaches the 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.
- 9. Scram the reactor at the end of the run using the manual or timer scram.
l Revised: 24 Nov 97 Page 1 l 1 l
- 10. Ensure all pertinent information has been entered in the reactor operations logbook. l l
I l Revised: 24 Nov 97 Page 2 l l
MERAfl6AA'LPRdCEDUlkEI mi(($23[Pio855uIr$M ~Bji 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 senes 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, tum 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.
- 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 Page 1
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and tum over the RAM indicator sign to denote that the RAMS are set normal.
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l Revised: 24 Nov 97 Page 2
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^ ,I PER Ti65 E}RDCEDER5) []3][ ']hj@NdB'52 PULSE OPERATION (SUBCRITICAL) ,
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. Turn 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:
$ Value = Total worth ($) Transient rod (to 100% or mechanical stop) -
Desired pulse ($) 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 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 1 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.
- 7. Scram the Transient rod.
- 8. Raise the Transient rod anvil to 100% or the mechanical stop if installed.
Revised: 24 Nov 97 Page 1
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- 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 $2.00 or smaller. Enter the pulse number at the next prompt.
- 11. Fire the pulse by depressing the " Fire" button on the reactor console.
- 12. Record the appropriate data in the reactor operations logbook from the pulse display.
- 13. Reset R-1 and R-5 to their normal alarm points when pulsing operations are complete
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and turn over the RAM indicator sign to denote that the RAMS are set back to normal. f I Revised: 24 Nov 97 Page 2
1 [OE5RATIOA !?PROCED'UR$ m _[mj[ ']g[ [Pid64 dure l5[ TAB [N WEEKLY OPERATIONAL INSTRUMENT CHECKLIST CHECKLIST # DATE ; SUPERVISED BY f ASSISTED BY REVIEWED BY
- 1. WATER LEVEL INDICATOR A. In pool, east side, depress float on water level indicator . . . .
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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 i DM2 i ill. RADIATION ALARMS A. Test alarm functions for high level and failure Monitor Failure alarm functional HIGH Level alarm functional ! R-1 l R-2 R-5 (criticality) E-3 E-6 Reactor Room CAM Gas Stack Monitor i B. Reset alarms.. . . .. .. .. ... . I IV. OTHER A. Top lock key seals at Security Desk and at LOG verified intact ... B. Change Filter in the Stack Gas Monitor . . . .... ...... .
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Revised: 13 Feb 97 4
@pERITiUA [PhDCED R'Ei . [ 3] E 5 [ 2[%h O es 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 i checklist. Items 2,3a and 3d will be performed again as part of the daily shutdown checklist.
- 2. OPERATING and TP. ACING i 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 >G 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. 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 c!ose. 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: 04 Aug 97 Page 1
f performed for primary CAM. Annotate completion of the channel test on secondary CAM chart oaoer only when primary CAM is bvoassed.
- 4. BY-PASS of PRIMARY CAM l When the primary CAM is by-passed, the secondary CAM chart recorder needs to be activated, then perform items 2, 3a, and 3d.
l l l Revised: 04 Aug 97 Page 2
[56 MIN.i5 R ilEE5iOdEDi[RE'~ 7[ ((((hig (( , [ U6$ Emergency Training of ECP Personnel I. General:
- 1.
Reference:
Emergency Plan Section 8.1
- 2. Requirement: Annual training to be provided to Senior level personnel involved with emergency response.
- 3. Tools: None
- 4. Equipment: Applicable Emergency Equipment
- 5. Coordination: ERT Commander; ECP Commander; Head, Resources and Administration; and Head, Radiation Sources Department.
! 6. Estimated Time: 2 hrs
- 7. Safety Precaution / Protection: None i
ll. Procedural Sequence:
- 1. Notify ERT Commander; ECP Commander; Head, Administration Services l Department; Head, Radiation Sciences Department; Emergency Coordinator; Search Team Marshall; and Health Physics Advisor at least one month in advance.
- 2. Contact ASDI to reserve use of Conference Room
- 3. Contact ASDI to have training placed on Institute monthly calendar and reactor operations schedule.
- 4. Review training records for outline of training.
- 5. Modify training as appropriate.
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- 6. As minimum, training must include:
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- a. Emergency Classifications
- b. Notification requirement
- c. Communications
- d. Base Support Agreements l
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- e. State and local agency support
- f. Location of keys for phone boxes
- 7. Review ECP box. Check contents against any inventory sheet in the box.
Verify that all instrurnentation is in calibration (if required) or functional. Check voltage on redio battery and verify it is at or above listed voltage.
- 8. Record training and file outline in training files and update Triga Tracker.
O W 9 Revisues 4 Aug 97 R W W 7 wp6 e
IMTION#DCE60stE!lTT "ls3R@[6Byg&gl@$$@%l$1EM008]l 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)
- 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
- 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 plugging or unplugging any of the circuit boards. The " unit" refers to the rack mountable electronics section of the SGM.
- 11. Procedural Sequence:
- l. 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: 25 Aug 97 Page1
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 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 1C-13 Card. Place the card extension card into the CRA-14B/91 slot and attach the CRA-148/91 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 voit 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
- 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.
l l Revised: 25 Aug 97 Page 2
I I l 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.
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- 18. Adjust the potentiometer on the 0-10 VDC card to give 1000 cpm on the remote
' chart recorder in the control room, l
e 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
- 0.15 VDC 100 cpm 1.00
- 0.15 VDC 1000 cpm 2.00 i 0.15 VDC L 10,000 cpm 3.00
- 0.15 VDC
! 100,000 cpm 4.0010.15 VDC
- 1,000,000 cpm 5.00
- 0.15 VDC I
- 20. Adjust the potentiometer, located above the yellow fail button, while pressing the yellow fail button such that the analog meter reads about 12-15 cpm. Set the pulse l
generator to 10 cpm. Verify that the fail alarm lamp illuminates when the analog meter needle drops below 12-15 cpm. 1
- 21. Press the meter reset and alarm reset buttons.
! 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 l l respective lamps on top of the stack gas monitor illuminate at their set points and l 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.
l Set toggle switches to the following configurations: SW1 - Closed, SW2 -Open, i SW3 - Open. Replace the CRA-14B/91 card back into its slot. Attach the detector l cable to the back of the unit. l
- 24. Remove the IC-13 card and set the dip switches into the following configuration for spectrometer mode:
Revised: 25 Aug 97 Page 3 t
S1 Open S5 Open (10% Window) S2 Open S6 Closed (20% Window) 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. 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 tha 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 adjusting the potentiometer located directly above the button to give the proper alarm point reading 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.
Revised: 25 Aug 97 Page 4 ~ i
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 i 4 VDC
- 12. AA-13A/91 Jack . -5.00
- 0.01 VDC
- 17. Control Room Meter 1000
- 18.- Control Room Chart 1000
- 19. Inject Signals Pulse Generator Voltage AA-13A/91 Meter Reading 0 cpm (O cps) V cpm 100 cpm (1.666 cps) V cpm i 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 epm ;
High Alarm Set Point cpm Counts Generated From Sodium-22 Source cpm 1 i Revised: 25 Aug 97 Page 5
[5 OBLR TiO5PRdCE60NEiL [7["["((]i[ ' (COW Control Rod Calibration
- 1. General:
- 1.
Reference:
Tech Spec 4.1a & 3.1.2
- 2. Requirement: Annual
- 3. Tools: lon chamber, High voltage power supply, Keithley 610C electrometer or reactivity computer, stopwatches and calculator.
- 4. Coordination: Several reactor staff members required to operate stopwatches or second staff member to record data.
- 5. Estimated Time: Up to 3 hours per rod
- 6. Safety Precaution / Protection: Practice ALARA when handling ion chamber ll. Procedural Sequence: STOPWATCH METHOD
- 1. Place ion chamber above core centered between fuel elements C-3 and C-2.
- 2. Connect ion chamber to input of electrometer.
- 3. Set electrometer as follows:
Zero Check: Lock Feedback: Fast Meter: Off Selector: Amperes (10-7) Multiplier: 1
- 4. Apply 750 Vdc to ion chamber.
- 5. Locate the reactor in one of its operating positions.
- 6. Operate the reactor at 500 watts and set the ion chamber to output up to 1 milliAmp.
- 7. Establish a critical configuration with the reactor power steady at a low level (approx. 2 watts.) Rod banking to be employed will approximate the banking used for normal operations at that core position.
- 8. Ensure criticality by waiting one (1) minute after last rod adjustment before l proceeding to Step #8.
- 9. Record all rod positions.
- 10. Withdraw the rod to be calibrated to obtain an indicated positive period of 10-40 seconds.
- 11. Record the control rod positions immediately after rod withdrawal is completed.
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- 12. Power level increase will be timed by several persons using stop watches and observing the electrometer, the asyr-ototic period calculated, and the resulting reactivity insertion determined from a graph of insertions versus periods as determined by the in Hour equation.
NOTE: Period measurements should be performed at less than 500 watts to avoid neaative reactivity effects due to fuel temperature.
- 13. Reduce reactor power to approximately 3 watts using a control rod other than the one being calibrated.
- 14. Repeat steps six (6) through eleven (11) as required to calibrate the entire rod.
- 15. Scram the reactor.
Method of Analysis for Stopwatch Methoo From the power increase factor, P2/P1, and the time, T, measured for the particular power increase, the reactor period T, associated with incremental movement of a control rod can be calculated from: T= t in P2/P1 , This period can be converted to a reactivity value using either a tabulation or a plot of the in Hour relationship. From the data, two (2) significant curves can be developed. One of these, a differential control rod curve, illustrates the rate of reactivity change as a function of rod position. The second curve to be developed,
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an integral control rod curve, relates the total reactivity change as a function of control rod movement.
- 11. Procedural Sequence: REACTIVITY COMPUTER METHOD SETTING UP
- 1. Place an independent ion chamber above the reactor core
- 2. Input 0 to .1 microamp into the action pack and calibrate O to 10 volt output from the action pack.
- 3. Run a calibration program for the reactivity computer l/O board and input signals of 0 and 10 volts to verify the calibration of the board. Check manufacturers literature for specifics if board needs adjustment.
- 4. Connect the output of the action pack to the reactivity computer.
- 5. Connect the ion chamber to the input of the reactivity computer action pack.
- 6. Follow the in.oruction manual for the reactivity computer to set the ion chamber height at the maximum power desired for the computer. Maximum power should be less than 500 watts.
ROD CALIBRATIONS Follow the instructions for the reactivity computer to perform rod calibrations. l
# 1procee.oic012 we6 Usested 24 peo= 97 e
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1 i fdNU5R Tid 5'iSNdd5dONE5 ^\ " " J ~ l f 2 3 9 P f m j dO262 Operational Channel Alignment i i
- 1. General:
- 1.
Reference:
General Atomics Technical Staff
- 2. Requirement: Upon installation of new components or as needed ,
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- 3. Tools: Small Flat Sciewdriver, Philips Screwdriver
- 4. Equipment: Pool stirrer, digital thermometer, ion chamber, high voltage power supply, electrometer (610C), coax signal cable, battery operated voit meter, battery operated current meter, various I connectors and adapters
- 5. Coordination: Operations Schedule
- 6. Estimated Time: 4 to 8 days
- 7. Safety Precaution: Electrical shock hazard due to high voltage in lower section of PA15
- 11. Procedural Sequence:
1 Move the core to the center of the pool.
- 2. With an operator on console remove the neutron source and see that the console power drops to zero. It often takes a couple minutes for the console power to drop. If the reactor has been to power within the last hour there will probably be enough delayed neutrons that the power will not drop to zero and therefore no
. adjustment should be made. If the console has not been to power and the power does not drop to zero then adjust the discriminator no more than 1/8th turn every - 1 minute until the console power drops to zero. The discriminator potentiometer is located inside a hole on the top of the PA15. There are two holes in the top right side of the PA15. The discriminator is located in the hole closest to the plug. Usually a tool is left in the hole. If not, the cover can be removed from the PA15 to find the discriminator. Warning: There is high voltage in the lower R twocedwp c026 wp6 Renned 26 Aug 1997,16 Sep 1997 1
I section of the PA15. Counter Clockwise to decrease counts.
- 3. Place an independent ion chamber above the core. Adjust the chamber to be about 3 to 4 inches above the core.
- 4. Attar.h a high voltage power supply to the HV line of the chamber
- 5. Attach a signal line from the chamber to an electrometer in the control room. ' A signal line is usually behind the DAC and in the control room cable tray. Hang the power cables and signal lines along the boom.
- 6. Perform a thermal power calibration according to procedure C015 except for adjustment of the chamber. Adjust the reactor power such that the reactor is at 100 Kw. Turn on the electrometer and the high voltage power supply. Take the reading on the electrometer at 100 Kw reactor thermal power. The reading should be no greater than 0.01 ma. Adjust the independent chamber height to get the proper current. The reading is
- 7. Scram the reactor. Do not move the independent ion chamber until this procedure is finished.
- 8. Turn off AC power in the enclosure containing the PA15 high voltage ' power supply. This is the left gray steel enclosure.
- 9. Disconnect the high voltage coax from J2 of the high voltage distributing and monitoring assembly. This assembly is the box located on the bottom right of the enclosure.
- 10. Assemble the necessary fittings to add a current meter in series with the high voltage line and J2. The current meter should be battery operated and able to read current as low as .01 ma and as high as 1.00 ma. ,
- 11. Attach a battery operated voltmeter capable of reading 1000 volts in 1 volt divisions. .
- 12. Turn the AC power on. Use caution around any exposed high voltage connections.
- 13. Adjust the potentiometer labeled HV on the front of the high voltage distributing and monitoring assembly to give between 720 an'd 740 Volts (Nominal set point a m a- a. =ues,cm 2
)
- <10% loss ) on the volt meter.
- 14. Adjust the potentiometer labeled UV TRIP (under voltage trip) until there is a high voltage trip on the NM-1000 or console.
- 15. Adjust the potentiometer labeled HV to give 840 volts (Nominal set point + 5%)
on the voltmeter. WARNING: DO NOT EXCEED 1000 VOLTS. DAMAGE MAY OCCUR TO THE PA15 IF VOLTAGE EXCEEDS 1000 VOLTS. ,
- 16. Adjust the potentiometer labeled OV TRIP (over voltage trip) until a trip occurs
~ on the NM-1000 or console.
- 17. Adjust the potentiometer labeled HV to give 800 Volt on the voltmeter.
- 18. Change item #31 in the NM-1000 to 1. Press (F3)(1)(F8)(1)(enter)
- 19. Remove the cover on the Campbell amplifier.
- 20. Press (F3) on the NM-1000.
21 Increase reactor power to 1 Mw based on the independent ion chamber. !
- 22. Read and record the at power current from the high voltage power supply.
ma
- 23. Adjust the height of the fission detector to give an at power current of .25 mA.
This means that the fission detector is outputting .25 milliamp at 1 Mw. CAllBRATING THE CAMPBELL REGION 4
- 24. Read and record the NM-1000. The NM-1000 should have approximately 80,000 displayed.
- 25. Adjust the "AC GAIN" potentiometer in the Campbell amotifier to give an average reading of 80,000 on the NM-1000. If 80 K is unobtainable then adjust the potentiometer "DC GAIN" to achieve 80 K on the NM-1000. Scram and allow the reactor gamma background to decay for at least half an hour.
. 26. Increase the reactor power to 10 kw based on the independent ion chamber.
- 27. Read the NM-1000 item 30 (F3). The average value 8000 should be displayed.
- 28. Adjust the " BALANCE" potentiometer in the Campbell amplifier to display an average of 8000 on the NM-1000 and 10 Kw on the console.
- 29. Increase reactor power to 1 Mw based on the independent ion chamber, a -wa a- a % w. i. s., - 3
- 30. Road item 30 (F3). The NM-1000 should read 80,000.
- 31. Adjust the "AC GAIN" potentiometer in the Campbell amplifier to give 80,000 on the NM-1000.
- 32. Check item #10, press (F1) _
and item #35, press (F3)(5) . If Necessary, calculate a new item #35 to give 100% power on the console. Use the formula: Item #35
- 100 / Item #10 = New item #35
- 33. Enter the new item #35 by pressing (F3)(5)(F8)(number see below)(enter)
For Example: The number 2.109E-8 would be entered (F3)(5)(F8) (2) (.) (1) (0) (9) (Space)(-)(8).
- 34. Observe the item #10, (F1), on the NM-1000, or the CSC console for the proper reactor power. If the power is incorrect go back to step 33.
- 35. When the reactor power is 1 Mw on the console, and the NM-1000 displays 100% on item #10 (F1), and item #30 (F3) is 80,000 then scram and let the reactor cool for at least 30 minutes.
- 36. Raise power to 10 Kw. Item #30 (F3) should display 8000 and console shoM read 10 Kw. If not adjust the " BALANCE" potentiometer in the Campbell amplifier to give 8000 on the NM-1000 and 10 Kw on the console.
We have been adjusting the Campbell region "Zero" 8000 on item #30 at 10 kw with the " BALANCE" pot and the " Span" 80,000 on item #30 at 1 Mw with the "AC GAIN" pot. The Burr Brown unit should display 2500 at 1 kilowatt,8000 at 10 Kilowatt,25,000 at 100 kilowatt, and 80,000 at 1 megawatt. To verify the 1 kw and 10 Kw points the reactor will have to be allowed to cool overnight. The core , gamma background gives false readings on the independent ion chamber at low powers if the gamma is not allowed to decay for a significant period of time after , a power run. Figure: number of hours for decay = (decades - 1) squared.
- 37. At this point the Campbell region should be calibrated. If the console reading is not correct go back to step 30 and continue, if it is correct then continue.
mm . ~ ,,,,.,. .,., 4 I ( l
4 CAllBRATING THE COUNT RATE REGION.
- 38. Allow the reactor to cool for several hours before taking the power to 1 kw.
- 39. Change the Campbell crossover point item #39 in the NM-1000 to 2000. Press (F3)(9)(F8)(2)(0)(0)(0)(enter) to prevent the NM-1000 from changing into count rate region.
- 40. Decrease reactor power to 1 kw based on the independent ion chamber.
Stabilize in manual mode such that the reactor power does not change. The reactor must be very stable. The CSC should indicate approximately 1 kw. Be sure that the NM-1000 is using Campbell mode. Press (F2). There will be only zeros if the MN-1000 is in Campbell region.
- 41. Change item #39 to 4000. Press (F3)(9)(F8)(4)(0)(0)(0)(enter) to force the NM-1000 to use count rate region
- 42. Read item #20, press (F2), on the NM-1000.
- 43. Read item #20 on the NM-1000. Average several readings of item #20.
Calculate the new item 25. Use the formula: 0.1/ Item #20 = ltem #25.
- 44. Enter the new item #25. Press (F2)(5)(F8)(number), see below,(Enter).
~ Example number; 1.471E-7. Press (1)(.)(4)(7)(1)(space)(-)(7)
Power is determined in the count rate region by multiplying the number of counts by a constant. Zero counts multiplied by a constant gives zero power. Approximately 680,000 counts (item #20) multiplied by some constant gives 0.1 % power or 1 kw in count rate mode. Therefor the "Zero" is an absolute zero and ; cannot be set, and the " Span" is set by item #25.
.45. Calculate the new .5 CPS interlock and enter as item #40. j l..- Multiply .5
- Item #25 as calculated two steps above.
Press (F4)(F8)(number see below)(enter).
- l. Example number: 7.355E-8. Press (7)(.)(3)(5)(5)(space)(-)(8). j
- 46. Change item #29 (count rate crossover point) for 700,000. !
Press (F2)(9)(F8)(7)(0)(0)(0)(0)(0) a v-x- am e a- a % w. 4. s., = 5 l b
- 47. Set item #39 (Campbell crossover point) for 2400.
Press (F3)(9)(F8)(2)(4)(0)(0)(enter).
- 48. Increase and decrease the reactor power slowly from about 3 kw to 5 kw based on the CSC console power to check the crossover point. The crossover points are typically between 1 kW and 2 kW. There should not be a jump in power when the crossover occurs. If there is a big cross over jump that can not be corrected by adjusting item #31, go back and start this section (Calibrating the Count Rate Region) over. If the cross over has a small jump, item #31 can be I increased or decreased (no more than +/- 400) to line up the Campbell and count rate regions. To change the offset press (F3)(1)(F8)(guessed number, no -
calculation here)(enter). Check crossover point. The number in item #31 changes the lower end of the Campbell range.
- 49. The console power should be calibrated and linear at this point. Scram and allow the reactor gamma background to cool. Increase the reactor power from 100 watts to 1 Mw by decades based on the independent ion chamber and graph the results. Maintain the power at 1 Meg for 10 minutes and generate a scram curve.
CORRECTING THE PRESTARTS: The NM-1000 inserts 4 signals into the PA15 and campbelling amplifier to test the circuitry during prestarts. Two of the signals are generated in the NM-1000 and test the count rate region. The PA15 signals cannot be modified. Two of the signals test the campbelling region and are adjusted in the campbelling amplifier with two , potentiometers. The " CAMP Hi" signal checks the campbelling range at 1.1 Mw and the " CAMP LO" at a lower area in the Campbell range. ,
- 50. Press (F5)(F8)(5)(enter) to insert the CAMP HI signal. Press (F1) to read the indicated reactor power. The power should be 109 or 110 which is the percentage of full power.
- 51. Adjust the CAMP HI pot to give an indication of 109 or 110 on the NM-1000.
a-* .- x . =7. 4. s., =7 6
)
I 1 [
- 52. > Exit calibrate mode by pressing (F5)(F8)(0)(enter).
- 53. Press (F5)(F8)(4)(enter) to insert the CAMP LOW signal.
Press (F3) to display the Campbell counts. Adjust the j Low Carnp potentiometer to give as low an indication on the NM-1000 as possible but not lower than 2500.
- 54. Exit calibrate mode by pressing (F5)(F8)(0)(enter).
- 55. Run prestarts. Expect that the NM-1000 calibration modes 2, 3, 4, and 5 will fail.
The new constants on the prestart printout will have to be changed in the CSC configurator. Accidents modifying the configurator can blow the database and cause the conrole to not boot up properly. Do not attempt to change the configurator without proper assistance from experienced staff. The information on how to change the configurator is not included here. For changes to the configurator, see the ROS or RFD.
- 56. Copy the following NM-1000 constants into the core physics log: Items 21,25, 29=700,000, 31, 33=0.370, 35, 39, 40, 41 =109, 42=0.1, 43=3.0, 51 =1, 52=0, 53=0. Note: some of the items above have numbers attached (=) and should not )
change, but should be checked for accuracy. 1
- 57. Replace covers on the PA15 and campbelling amplifier. j
- 58. Turn off high voltage power supply for the independent ion chamber and remove.
- 59. Remove independent ion chamber from core and hang along the side of the reactor pool. Do not remove the chamber from the pool for several weeks due to high activation o'f the chamber.
- 60. Clean up any additional mess or apparatus.
- 61. Update Triga Tracker.
l
= mwo n- a a m7. is s mr 7
i NM-1000 CHANNEL ALIGNMENT DATA SHEET DATE Personnelinvolved i Equipment used Serial Number Cal Expir Date Voltmeter-Current Meter- , Electrometer-Points Tested or Changed As Found As Left Under Voltage Trip Point Volt Volt Over Voltage Trip Point Volt Volt High voltage set to Volt Volt Current at 1 Meg mA mA NM-1000 item #31 (offset) NM-1000 item #30 at 1 Mw (-80k) CTS NM-1000 item #30 at 10 Kw (-8,000) CTS NM-1000 Item #35 (Campbell region span) NM-1000 item #39 ( # crossover) 2400 CTS 2400 CTS NM-1000 item #20 at 1 Kw CTS NM-1000 item #25 (count region span) NM-1000 item #29 ( t crossover) 700,000 CTS 700,000 CTS NM-1000 item #40 (.5 cps interlock) CAMP HI Calibration Signal CAMP LO Calibration Signal NM-1000 item #33 (Camp Constant) .370 .370 ' NM-1000 Item #41 (Max Reactor power) 109 109 NM-1000 item #42 (1 kw interlock) .1 .1 - NM-1000 item #43 (3 sec interlock) 3.0 3.0 NM-1000 item #51 1.0 1.0 , NM-1000 item #52 0.0 0.0 NM-1000 item #53 0.0 0.0
- Information not required l
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[ MAINTENANCE PROCED,UREj , ., g ,a , , ;3guagm m. L.M050j l COOLING TOWER DRAIN and REFILL
- 1. General 1
- 1.
Reference:
None l 2. Requirement: Monthly ' ~
- 3. Tools: Broom
- 4. Coordination: Operations schedule. Not to be performed while cooling I .
tower is needed. Notify guards that staff will be entering roof.
- 5. Estimated Time: Half hour
- 6. Safety Precaution / Protection: Shut off cooling tower fan.
II. Procedural Sequence: The cooling tower sump needs to be drained more often in the summer than in the I winter. Perform this procedure in the following months: January, March, May, June, July, August, September, and November. In months not listed go to step 9, Update Triga Tracker.
- 1. Ensure that the reactor will not be operating at power for 24 hours.
- 2. Shut off the secondary pump. Label the control room switch indicating that it should not be turned on until the cooling tower sump is refilled. !
- 3. Shut off the cooling tower fan. The switch is on the south end of the cooling tower.
- 4. - Open the cooling tower sump drain valve located under the east side of the cooling tower.
- 5. Stir the deposits in the sump of the tower with the broom and attempt to flush as much of them down the drain line as possible. You may refill the cooling tower l
and redrain to flush out more deposites if desired. Not all deposites need to be
removed every time the tower is drained.
- 6. When the cooling tower sump is empty, close the drain valve and allow the sump to refill.
- 7. Turn the cooling tower fan back on.
- 8. When the low water in cooling tower lamp located over the motor control center goes out (about 15 minutes) turn the secondary pump back on.
- 9. Update Triga Tracker.
O N NN e e
I l l MiSTENAA6E~fiitddEDUR5T ~ '""T"?.m!~I"~". "m"m!T. ^' ~ _f2MU5ff m Channel Test of SGM
- l. General
- 1.
Reference:
None
- 2. Frequency Quarterly
- 3. Requirement: Internal
(
- 4. Tools: None i 1
- 5. Coordination: Operations schedule. Not to be performed while reactor is operating.
- 6. Estimated Time: 5 minutes
- 7. Safety Precaution / Protection: None
- 2. Procedural Sequence:
- 1. Remove detector chamber cover
- 2. Insert Sodium-22 calibration source fully into the chamber.
- 3. Allow SGM counts to stabilize. (1 to 2 minutes)
- 4. Check range limits on the source count sheet created at the last SGM calibration. If the reading on the SGM does not fall within these limits, do not operate the reactor. Notify the ROS or RFD. The ROS or RFD will repeat the test and evaluate what action to take. If the ROS or RFD determines the SGM to be out of specifications, notify SHD and calibrate the SGM.
- 5. Update Triga Tracker.
I I R WeewpWOM wp6 4 June 1997
[SditOEI)ll NNPROClEI5dRE" t[2((dy](([12" ' 40% POWER COEFFICIENT OF REACTIVITY
- 1. General:
- 1.
References:
Tech Specs Section 4.1f
- 2. Requirements: The power coefficient of reactivity at 100 KW and 1MW will be measured annually, not to exceed 15 months
- 3. Tools: None
- 4. Equipment: None
- 5. Coordination: Nono
- 6. Estimated time: 1 hour
- 7. Safety precautions / protection: None
- 11. Procedural Sequence:
- 1. After calibration of all power monitoring channels and development of new rod worth curves, move core to position 500
- 2. Bring reactor critical at 15 watts with safe & shim rods full up, trans rod at 250 and use reg rod to reach critical
- 3. Stabilize reactor at 15 watts for 4-5 minutes & note all rod positions in logbook & core physics log
- 4. Using reg rod, increase power to 1KW, stabilize, and note new rod positions 5 Using rod worth curves, calculate amount of additional reactivity inserted for power increase & enter in core physics log
- 6. Increase power stopping at 100 KW and 1MW as required by Tech Spec's.
Collect data at a minimum of three other power levels to create a smoother curve.
- 7. In each case, calculate additional reactivity inserted from initial 15 watt rod position l
- 8. When reg rod alone is not enough to reach new power, use transient rod in conjunction with reg rod keeping shim & safe rods full out l
- 9. After taking data at 1MW, scram reactor
- 10. Using semi-log graph paper, plot reactor power on log axis and reactivity inserted above critical on linear (horizontal) axis
- 11. Plot best curve through data points and label graph
- 12. Repeat process at pool positions 250 and 750 and enter all 3 curves in reactor curve reference book
- 13. Update Triga Tracker e
D 4 Aug $7 , Wtn011 wp6 l______.______.____________
ATTACHMENT B 10 CFR 50.59 Safety Evaluations of Modifications, Changes, and Enhancements I to Procedures or Facilities Procedure M050 Cooling Tower Drain and Refill Procedure 8, Tab H Weekly OperationalInstrument Checklist Comply Code Replaces TLD's in SAR Procedure M051 Channel Test of SGM Procedure A007 Emergency Training of ECP Personnel Procedure S011 Power Coefficient of Reactivity Procedure 11 Air Particulate Monitor (CAM) Procedure Procedure C006 Stack Gas Monitor Calibration Procedure CO26 Operational Channel Alignment Procedure C007 Calibration of Operational Channel Procedure C012 Control Rod Calibration RAM's TURNED UP Tag Created and Procedures Updated
. I l
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C . L S F AR VR 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 7 Ot r r p p p p p p p 9 9 RE e e e n u e e e e e e c c PT M M S J S S S S S S e e PA 9 9 2 3 2 2 2 2 2 2 D D AD 1 1 2 2 2 2 2 2 2 2 8 8 L)D AF VR 7 9 7 9 6 9 7 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 9 O( 9 g g p v v RE b e g u b e n g u g u g u u u e o o PT F A F u A A A A A S N N PA 1 6 J 5 7 9 4 4 AD 1 6 2 4 4 4 4 2 2 1 2 2 E T E 7 7 7 7 7 7 7 7 7 7 7 7 . L 9 9 9 9 9 9 9 9 9 9 9 . P E 9 b b r n g g g g u g u p v v - MT e e p u u u u e o o F F A A A A A A S N N OA 1 3 3 J 5 5 6 4 4 CD 1 1 2 4 4 4 4 2 2 1 2 2 T S 2 2 1 2 2 2 2 2 2 2 2 2 E W E . H . S d r n r o e Y a f s d e g e r e r , t uyt . R n s e t n n u dO u7 pi v yle A ia d r D L r u io a r d e c eO e s a mi oc t las i o d n T d p r cC ca M r e f o e r e c o t s a e r o r p o r e pr e r c yre go nc M w t u e s u n it ir e E o is e d r p t a n t nd i ivd e uh U s e o t G t g l k u c e y r w it e ec t o ci z ar dt r S N in c e s s o r h t a s e a r mo nr 6 o r e r e t mo e f p s r b g p u A lo h c u o e u i 2t Oce R g N 7 H o is c e c t c d e la iewl l Ct e Ap Gmo mto O9 I C C t n e d n a d d e e n n c o M c ee lenn n dn d e c 0e e n 0 e T 19 D E r u m u h g icn n e d a u r p G ntea ano h t w 5t a - A S d e t r h r wto i t n s r o g n S aah h e c 7i s O r fo ne oe t r C f s i a a f crCon s O c n i s i r o Oi f sh g c - I P o i sn m w n o 3 la .i C n nt mdn F r no o n6 atr i I O p ly k om M w o it it n 2 p o2 e so e i ow t t a e D t R e e i t G b a o i r e a , P c n e ct e n S P ic m e t aOp Co ug cm st s O t a w se y C f ic e s r e pof d a et i e f ih 5i l k n Rf lu o ct Mc M t e n t o Af e lr t e E f o e p t la u t n o t o r7 n co ov r l e pe s ca re. A e dr S n r s cy eOo pg R hc Y ia o eo a u k e it it r r it o bOi t ei n el vpt u ep T m w gi na t q c e v o a a pc l c e mCa u r gt n ar o er p gu nt nmb I h L I wt efi l d d ai h d w e c m e ir r r r o e oe l e ae h p md enom ar h at C Nr e A Cr a N A R Af o C Rf rC Co R ec Cs A F , , H C1 0 b 8G 5 a 1 5 7 1 6 6 7 2 .8 T 0 1 O 2 O 1 8 0 O 0 O O O 0 82, N M 8. M A 0 S 1 C C C C O 1 s F I e r e r e r e r e r e r e r e r e r e r e8 r T u u u u u u u u u u u1
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- r o
r r r r r TC P P F P P P P P P P P P 7 7 7 7 7 7 7 7 L 9 9 9 7 7 7 7 9 9 9 9 9 9 9 9 9 g g p v v AE I b e b e r p n g g g u u e o o T T F F A u u u u A A S N N I A 1 3 3 J A A A 5 7 9 4 4 ND I 1 1 2 4 4 4 4 2 2 1 2 2 M U 0 1 2 N 1 2 3 4 5 6 7 8 9 1 1 1
i Facility Modification Work Shoot 2 No 10 CFR 50.59 Analysis Required Proposed Change: New Procedure M050 Coolina Tower Drain and Refill Modification to: Procedure _XX_ Facility Experiment Submitted by: Georce Date _11 Feb 97
- 1. Description of change:
The cooling tower had a drain line added several months ago. The 50.59 Cnalysis (9 Aug 96) for this change states that procedura M015 would be C:dified. A further analysis was made which determined that a new . procedure should be created and that m015 should be left as it stood. This 50.59 is to introduce the new procedure for draining the refilling the cooling tower. The procedure covers any safety precautions the operator needs to provide for a safe change of cooling tower water. 1
- 2. Verify that the proposed change does not involve a change to the Tschnical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved anfety issue as defined in 10 CFR 50.59(a) (2) . I NONE
- 3. If' change involves a f acility 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.
NONE
- 5. List of associated drawings, procedures, logs, or other materials to b2 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_ R3 viewed and approved by RFD , /- Date / / f t5 9 9 RRFSC Notified $p() Date NMR i o tog 7 u, -
[M@yR.!LA$CEf5f@$(($$$$$2(g@M$d@M[gjyhis(([My@j COOLING TOWER DRAIN and REFILL
- 1. General
- 1.
Reference:
None
- 2. Requirement: Monthly
- 3. Tools: Broom
- 4. Coordination: Operations schedule. Not to be performed while cooling tower is needed. Notify guards that staff will be entering roof.
- 5. Estimated Time: Half hour
- 6. Safety Precaution / Protection: Shut off cooling tower fan.
II. Procedural Sequence: The cooling tower sump needs to be drained more often in the summer than in the winter. Perform this procedure in the following months: January, March, May, June, July, August, September, and November. In months not listed go to step 9, Update Triga Tracker.
- 1. Ensure that the reactor will not be operating at power for 24 hours.
- 2. Shut off the secondary pump. Label the control room switch indicating that it should not be turned on until the cooling tower sump is refilled.
- 3. Shut off the cooling tower fan. The switch is on the south end of the cooling tower.
- 4. Open the cooling tower sump drain valve located under the east side of the cooling tower.
- 5. Stir the deposits in the sump of the tower with the broom and attempt to flush as much of them down the drain line as possible. You may refill the cooling tower and redrain to flush out more deposites if desired. Not all deposites need to be
removed every time the tower is dreined.
- 6. When the cooling tower sump is empty, close the drain valve and allow the sump to refill.
- 7. Turn the cooling tower fan back on.
- 8. When the low water in cooling tower lamp located over the motor cc otrol center goes out (about 15 minutes) tum the secondary pump back on.
- 9. Update Triga Tracker.
9
?
N $
G Fccility Modific2 tion W rk ShOct 2 No 10 CFR 50.59 Analysis Required Proposed Change: Procedure 8, Tab H Add a word to Section II Modification to: Procedure _XX_ Facility Experiment Submitted by: Georce Date __13 Feb 97
- 1. Description of change:
The word " Calendar" was added to section II to specify that the readings ca the domineralisers are for the previous calendar week.
. This change will allow for consistant recording of the information on the ccekly checklists.
- 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 cafety issue as defined in 10 CFR 50.59(a) (2) .
NONE
- 3. If change involves a facility modification, attach a drawing if cppropriate. 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 offected 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 l Not Required _XX_ R3 viewed and approved by RFD v Date N /l f N RRFSC Notified us,m>w Date b b3I
_--n. _-._ ,,, .
. ,, ., _n.-,,,
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E s+w~w.nww. URE.o m m.+w.ene.v-aub.. .,a.,,_,a a .-.~.m. - m. J.:1:::m.G:a n,Pr_ocedure 8fM+-m~ TAB*<a
. m+r+*e smo@%Wakuae:s+: - v-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. MON TUE WED THU FRI AVG Monitor Box DM1 DM2 Ill. 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 (criticality) ~ 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: 13 Feb 97 R:\PROCEDWP\0P._8H.WP6
1
} l Fccility Modification Work Shsst 1 10 CFR 50.59 Analysis l
Proposed Chainge: CHANGE SAR SECTIONS WHICH DISCUSS USE OF TLD FOR RADIATION EFFLUENT MONITORING Submitted by: GEORGE Date 23 APRIL 97
- 1. Description of change:
This change is to reinove the TLD monitoring program as the program used to determine the radioactive effluent releases to the public. The doses released to the public will be assessed using the NRC/ EPA approved comply code. I l l
- 2. Reason for change:
NRC has adopted the EPA constraint on effluent release limits. They have also accepted the use of the i comply code for effluent monitoring. The TLD monitoring system in use has a lowest detectable limit of 56 millirem per year. The new release constraint of 10 millirem is at a level too low to be measured ' effectively. This change will adopt the system currently accepted by the NRC and EPA for effluent reporting.
- 3. Verify that the proposed change does not involve a change to the Tochnical Specifications or produce an unresolved safety issue as epecified in 10 CFR 50.59 (a) (2) . Attach an analysis to show this.
Analysis attached? No
- 4. The proposed modification constitutes a changes in the facility or an cperational procedure as described in the SAR. Describe whj;n (check all that apply).
Procedure Facility Experiment
Facility Modification Work Shost 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.
Section 3.6.4 Perimeter Monitoring This section states that the perimeter monitoring system consists of TLD's which detect radiation. All references to TLD's need to be removed from this section. The section will be rewritten explaining that the comply code will be used to determine doses to the public.
- 6. For facility modifications, specify what testing is to be performed to assure that the systems involved operata in accordance with their design intent.
N/A Comply code accepted by EPA and NRC.
( Facility Modification Work Shrest 1
- 7. Specify associated information.
New drawings are: Attached l Not required _XX_ 1 i Does a drawing need to be sent Logistics? Yes No _XX_ Are training materials effected? Yes _XX_ No l Will any Logs have to be changed? Yes No _XX_ 1 Are other procedures effected? Yes No _XX_ < List of items effected: Training Program Chapter 13, Updated for 10 mrem dose constraint.
~
l No reactor procedures will need to be changed. )
- 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 Rsviewed and approved by RFD / Date M,f[/} h 2 RRFSC Concurrence Date
ACTION SHEET CHANGING SAR ON RADIATION EFFLUENT MONITORING / Update section 3.6.4 of SAR. O e e l
N
~
IM05U [MKistEi4ANd55ROCEDUR55.. > tm , Channel Test of SGM
- l. General
- 1.
Reference:
None
- 2. Frequency Quarterly I
- 3. Requirement: Internal
- 4. Tools: None
- 5. Coordination: Operations schedule. Not to be performed while reactor is operating.
- 6. Estimated Time: 5 minutes
- 7. Safety Precaution / Protection: None
- 2. Procedural Sequence:
- 1. Remove detector chamber cover
- 2. Insert Sodium source fully into the chamber.
- 3. Allow SGM counts to stabilize. (1 to 2 minutes) l
- 4. Check range limits on the source count sheet created at the last SGM calibration. If the reading on the SGM does not fall within these limits, do not operate the reactor. Notify the ROS or RFD. The ROS or RFD will repeat the test and evaluate what action to take, if the ROS or RFD determines the SGM to be out of specifications, notify SHD and calibrate the SGM.
- 5. Update Triga Tracker.
R WrocmewpWO51 wp6 4 June 1997 l
5 Fccility Modification Work Shast 2 No 10 CFR 50.59 Analysis Required Proposed Change: __ A Check of ECP Box was added to crocedure A007 Modification to: Procedure _XX_ Facility Experiment Submitted by: Georae Date _ 4 Aua 97 _
- 1. Description of change:
. Additional step 7 was added. This step directs the trainer to check the contents of the ECP box for missing or out of date equipment. This change is in response to a comment from the last emergency drill.
- 2. Verify that the proposed change _does not involve a change to the Tschnical 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.
NONE o 5. List of associated drawings, procedures, logs, or other materials to bn 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_ Raviewed and approved by RFD i ,L Date 17 RRFSC Notified Date SEP 2 21997 ew-w
[A6MINISIli fiS5 PND6EdUFiE[ ("[ m " , " jn; ' [ [ l$00$ Emergency Training of ECP Personnel
- 1. General:
- 1.
Reference:
Emergency Plan Section 8.1
- 2. Requirement: Annual training to be provided to Senior level personnel involved with emergency response.
- 3. Tools: None
- 4. Equipment: Applicable Emergency Equipment
- 5. Coordination: ERT Commander; ECP Commander; Head, Resources and Administration; and Head, Radiation Sources Department.
- 6. Estimated Time: 2 hrs
- 7. Safety Precaution / Protection: None ll. Procedural Sequence:
- 1. Notify ERT Commander; ECP Commander; Head, Administration Services Department; Head, Radiation Sciences Department; Emergency Coordinator; Search Team Marshall; and Health Physics Advisor at least one month in advance.
- 2. Contact ASDI to reserve use of Conference Room
- 3. Contact ASDI to have training placed on Institute monthly calendar and reactor operations schcdule.
- 4. Review training records for outline of training. )
i'
- 5. Modify training as appropriate.
- 6. As minimum, training must include:
- a. Emergency Classifications
- b. Notification requirement ;
- c. Communications
- d. Base Support Agreements
l
- e. State and local agency support i
- f. Location of keys for phone boxes
- 7. Review ECP box. Check contents against any inventory sheet in the box.
Verify that all instrumentation is in calibration (if required) or functional. Check voltage on radio battery and verify it is at or above listed voltage.
- 8. Record training and file outline in training files and update Triga Tracker.
o O W Renewed 4Aq 97 R WedwpWOO7 wp6 i i l I
- y Fccility Modification Work Shoot 2 .
No 10 CFR 50.59 Analysis Required l Pr posed Change: chance Procedure S011 to P - ve 'Soecifications For l Unnecessary Test Points Modification to: Procedure _n_ Facility Experiment Submitted by: cooram Date 4 Auo 97
- 1. DescriptionJof change:-
, . Th2 specifications for the specific power levels at which reactivity is to be measured l w20 removed. only the 100.KW and 1 Meg power levels are required by Tech spec's. Specification of other ' exact points is unnecessary. Three additional points are cufficient to make a smooth curve. Th2 specification for 4 cycle x 70 divisions graph paper was removed. The size of the l p;per does not' matter for graphing the results. 4 cycle x 70 divisions had been used l ct the time of the original procedure creation and the information was copied into the procedure..
- 2. . Verify that the proposed change does not involve a change to'the j 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. j affected and record below.
NoNE j
>5. List-of associated drawings, procedures, logs, or other materials to l - .bn-changed:
NoNE ]
- 6. ' Create an Action Sheet containing the list of associated work, ,
l specified above, attach a copy, and submit it to the RFD. l /\ l Action' Sheet: Submittad'/I l' Not Required xx ; Rsviewed and' approved by RFD Date //# 7 7 RRFSC Notified k' Date SEP 2 P lag 7 j
$ ~ " 3 " , ,, [ m [ $ " [ ][5 @ [
~
[50iN51Ef A65)fR.DCEDUNEJ POWER COEFFICIENT OF REACTIVITY
- 1. General:
- 1.
References:
Tech Specs Section 4.1f
- 2. Requirements: The power coefficient of reactivity at 100 KW and 1MW will be measured annually, not to exceed 15 months
- 3. Tools: None
~
- 4. Equipment: None
- 5. Coordination: None
- 6. Estimated time: 1 hour
- 7. Safety precautions / protection: None ll. Procedural Sequence:
- 1. After calibration of all power monitoring channels and development of new rod worth curves, move core to position 500
- 2. Bring reactor critical at 15 watts with safe & shim rods full up, trans rod at 250 and use reg rod to reach critical
- 3. Stabilize reactor at 15 watts for 4-5 minutes & note all rod positions in logbook & core physics log
- 4. Using reg rod, increase power to 1KW, stabilize, and note new rod positions
- 5. Using rod worth curves, calculate amount of additional reactivity inserted for i power increase & enter in core physics log
- 6. Increase power stopping at 100 KW and 1MW as required by Tech Spec's.
Collect data at a minimum of three other power levels to create a smoother curve.
- 7. In each case, calculate additional reactivity inserted from initial 15 watt rod position
- 8. When reg rod alone is not enough to reach new power, use transient rod in conjunction with reg rod keeping shim & safe rods full out l
l
4
- 9. After taking data at 1MW, scram reactor l
- 10. Using semi-log graph paper, plot reactor power on log axis and reactivity inserted above critical on linear (horizontal) axis j l
- 11. Plot best curve through data points and label graph i
- 12. Repeat process at pool positions 250 and 750 and enter all 3 curves in i reactor curve reference book
- 13. - Update Triga Tracker l
i i 4 Aug 97 rmW11 wp6
Fccility Modification Werk Shost 2 No 10 CFR 50.59 Analysis Required Pr posed Change: REARRANGE PROCEDURE 11. AIR PARTICULATE MONITOR ICAM) PROCEDURE I Modification to: Procedure _xx_ Facility Experiment submitted by: cEoRGE Date _4 Aug 97_ i i
- 1. Description of change:
. S:ction 3 was moved to Section 1. The test frequency was moved to the first part of the i precedure. The content was not changed.
I
- 2. Verify that the proposed change does not involve a change to the Tschnical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved I
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 offected and record below.
NoNE
- 5. List of associated drawings, procedures, logs, or other materials to ba changed:
NONE
- 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 _xx_ Rsviewed and approved by RFD 6 Date Ib RRFSC Notified b Date SEP 2 219; L
{ [df5 M fid N }8 @ j hE] [ 2 T57 7 (([ [ [ M [$ N A 3] AIR PARTICULATE MONITOR (CAM) PROCEDURE GENERAL This procedure specifies how to test the CAM to ensure proper operation of this monitoring 1 device. A channel test will be performed on both reactor room CAMS at the beginning and l 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. 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 Revised: 04 Aug 97 C:\WP\0P,_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.
- 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.
l Revised: 04 Aug 97 C:\WP\OP_.11.WP6 Page 2
' D Facility Modification Work Shsst 2 No 10 CFR 50.59 Analysis Required Prcposed Change: Update of c006. sGM calibration.
Modification to: Procedure _XX_ Facility Experiment submitted by:- George Date _ 25 Aug 1997 _ l_ 1. Description of change: Correction to Step 23. The toggle switches which were flipped in step 5 were never reset. Step 23 was changed to add the resetting of the switches toggle. All other switches are reset in step 24. 2.; Verify that the proposed change does not involve a change to the
-Tschnical: Specifications, the facility as described in the SAR, or I . procedures _as described in the SAR, and does not produce an' unresolved J safety . issue' as defined in 10 CFR 50.59 (a) (2) . 4
.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.
NONE'
- 5. List of associated drawings, procedures, logs, or other materials to ba changed:-
NONE
- 6. Create _ an _ Action Sheet containing the list of associated work,_
specified above, attach a copy, and submit it to the RFD. j
. 1 Action Sheet: Submitted /' Not Required _XX_ l
!Raviewed and approved by RFD , Date L Tb $
RRFSC' Notified .h Date SEP 2 21997 somone *
[CADBRATION!PRQCEDURE'$ diWJ:'79T'iN N" J" ^<lC006] t STACK GAS MONITOR CALIBRATION I 1
- 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 3 annually, not to exceed 15 months. (HPP 7.3) l 1
- 3. Tools: Crescent wrench, screwdriver, special calibration connectors.
l
- 4. Equipment: Oscilloscope w/ leads, voltmeter, pulse generator, pulse counter, I 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 i operations. l J
- 6. Estimated time: One day
- 7. . ety precautions: Use caution when vc 4 ng around high voltage sources and minimize exposure to Ar-41 or Na-22 L etion 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:
- l. Schedule date for calibration with RFD/ROS and SHD.
- 2. Assemble required tools and equipment l 3. Produce Argon-41 (for argon calibration) with reactor. l i
Revised: 25 Aug 97 Page 1 l l l i 4
i I
' iggest: 2 syringes, 50-60 cc P-10 gas irradiated for 5 min at 100 Kw.
ELECTRONIC CAllBRATION i
- 4. Turn 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 S5 Open (10% Window) . S2 Open SS 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 < , the unit.
- 8. Verify 24
- 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-148/91 card to give -5.00 i 0.01 VDC.
d
- 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: 25 Aug 97 Page 2
1 l l 1
- 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 I in the reactor control room reads 1000 cpm.
l
- 18. Adjust the potentiometer on the 0-10 VDC card to give 1000 cpm o1 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 folic. 'q outputs. I Pulse Generator Voltage @ AA-13A/91 10 cpm 0.00 i 0.15 VDC 100 cpm 1.00 i 0.15 VDC 1000 cpm 2.0010.15 VDC 10,000 cpm 3.00 t 0.15 VDC , 100,000 cpm 4.00 t 0.15 VDC 1,000,000 cpm 5.00 i 0.15 VDC
- 20. Adjust the potentiometer, located above the yellow fail button, while 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 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-148/91 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: 25 Aug 97 Page 3
S1 Open SS Open (10% Window) S2 Open S6 Closed (20% Window) S3 Closed S7 N/C
~ S4 Open (5% Window) S8 N/C l
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 cource 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. 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 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 adjusting the potentiometer located directly above the button to give the proper alarm point reading 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.
Revised: 25 Aug 97 Page 4
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 i 4 VDC
- 12. AA-13A/91 Jack - 5.00
- 0.01 VDC
~
~ 17. Control Room Meter 1000
- 18. Control Room Chart 1000
- 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 i Audible Alarm Operates YES/NO High Voltage Set Point VDC Alert Alarm Set Point epm High Alarm Set Point epm Counts Generated From Sodium-22 Source cpm Revised: 25 Aug 97 Page5 I
Fecility Modificaticn Work Shsst 2 {
)
No 10 CFR 50.59 Analysis Required Proposed Change: Uodate and Move Procedure C007 to CO26 ~ and Create New Procedure C007 Modification to: Procedure _H_ Facility Experiment _ _ Submitted by: George Date _ 25 Aug 1997 ,
- 1. Description of change:
Procedure C007 was written as a channel alignment procedure. This procedure is to be used
' when new parts are installed into the operational channel or the normal yearly calibration indicates en alignment problern. Once the channel is aligned, only a yearly check is necessary of that clignment. Procedure C007 was moved to CO26 and renamed Operational Channel Alignment.
.. A new procedure C007 was created and called Operational Channel Calibration.
The new procedure will check the alignment annually and adjust the indicated power to match that m:asured with the power calibration. Procedure CO26 was updated as per under voltage trip and zero/ span points for campbell c*libration.
- 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
- cafety issue as defined in 10 CFR 50.59 (a) (2) .
NONE
- 3. If change involves' a facility modification, attach a drawing.if i appropriate. If structural facility drawings need updating, forward a l copy of changes necessary to Facilities.
NONE
- 4. Determine what other procedures, logs, or training material may be affected and record below. .
NONE The procedure number is maintained such that all references do not need i to be changed. ;
- 5. List of associated drawings, procedures, logs, or other materials to i
. bn 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: r\ Not Required _H_ Submittedg) Raviewed and approved by RFD /b Date Nb9 RRFSC Notified Date SEP 2 2 1997 mem w , i 1
[y@yMf[UM}Rd[kyhM { E 2 Z $ ] [$$$2][ E jyy@j Operational Channel Alignment
- 1. General:
- 1.
Reference:
General Atomics Technical Staff
- 2. Requirement: Upon installation of new components or as needed
- 3. Tools: Small Flat Screwdriver, Philips Screwdriver
- 4. Equipment: Pool stirrer, digital thermometer, ion chamber, high voltage power supply, electrometer (610C), coax signal cable, battery operated voit meter, battery operated current meter, various connectors and adapters
- 5. Coordination: Operations Schedule
- 6. Estimated Time: 4 to 8 days l j
- 7. Safety Precaution: Electrical shock hazard due to high voltage in lower section of PA15
- 11. Procedural Sequence:
1 Move the core to the center of the pool.
- 2. With an operator on consc!e remove the neutron source and see that the console power drops to zero. It often takes a couple minutes for the console power to drop. If the reactor has been to power within the last hour there will probably be !
enough delayed neutrons that the power will not drop to zero and therefore no adjustment should be made. if the console has not been to power and the power does not drop to zero then adjust the discriminator no more than 1/8th turn every
. 1 minute until the console power drops to zero. The discriminator potentiometer is located inside a hole on the top of the PA15. There are two hole.t in the top right side of the PA15. The discriminator is located in the hole closest to the plug. Usually a tool is left in the hole, if not, the cover can be removed from the PA15 to find the discriminator. Warning: There is high voltage in the lower section of the PA15. Counter Clockwise to decrease counts. l
1
- 3. Place an independent ion chamber above the core. Adjust the chamber to be about 3 to 4 inches above the core.
4.- Attach a high voltage power supply to the HV line of the chamber
- 5. Attach a signal line from the chamber to an electrometer in the control room. A signal line is usually behind the DAC and in the control room cable tray. Hang the power cables and signal lines along the boom.
- 6. Perform a thermal power calibration according to procedure C015 except for adjustment of the chamber. Adjust the reactor power such that the reactor is at 100 Kw. Turn on the electrometer and the high voltage power supply. Take the reading on the electrometer at 100 Kw reactor thermal power. The reading should be no greater than 0.01 ma. Adjust the independent chamber height to I get the proper current. The reading is
- 7. - Scram the reactor. Do not move the independent ion chamber until this procedure is finished.
- 8. Turn off AC power in the enclosure containing the PA15 high voltage power supply. This is the left gray steel enclosure.
- 9. Disconnect the high voltage coax from J2 of the high voltage distributing and monitoring assembly. This assembly is the box located on the bottom right of the enclosure.
- 10. Assemble the necessary fittings to add a current meter in series with the high voltage line and J2. The current meter should be battery operated and able to read current as low as .01 ma and as high as 1.00 ma.
- 11. Attach a battery operated voltmeter capable of reading 1000 volts in 1 volt divisions.
- 12. Turn the AC power on. Use caution around any exposed high voltage ,
connections.
- 13. Adjust the potentiometer labeled HV on the front of the high voltage distributing and monitoring assembly to give between 698 and 720 Volts (Set point - <10%
loss ) on the volt meter.
- 14. Adjust the potentiometer labeled UV TRIP (under voltage trip) until there is a high l
I voltage trip on the NM-1000 or console. l
- 15. Adjust the potentiometer labeled HV to give 845 volts (775 + 10%) on the i i
voltmeter. i 1
- 16. Adjust the potentiometer labeled OV TRIP (over voltage trip) until a trip occurs '
- on the NM-1000 or console.
- 17. Adjust the potentiometer labeled HV to give 775 Volt on the voltmeter. '
- 18. Read and record the idle current from the high voltage power supply.
ma
- 19. Change item #31 in the NM-1000 to 1. Press (F3)(1)(F8)(1)(enter)
- 20. Remove the cover on the Campbell amplifier.
- 21. Press (F3) on the NM-1000. 1 1
22 increase reactor power to 1 Mw based on the independent ion chamber.
- 23. Read and record the at power current from the high voltage power supply, ma
- 24. Adjust the height of the fission detector to give an at power current of .25 mA.
This means that the fission detector is outputting .25 milliamp at 1 Mw. 1 CAllBRATING THE CAMPBELL REGION
- 25. Read and record the NM-1000. The NM-1000 should have approximately 80,000
. displayed. _
, 26. Adjust the "AC GAIN" potentiometer in the Campbell amplifier to give an average reading of 80,000 on the NM-1000. If 80 K is unobtainable then adjust the potentiometer "DC GAIN" down to achieve 80 K on the NM-1000
- 27. Decrease the reactor power to 100 kw based on the independent ion chamber. l
- 28. Read the NM-1000 item 30 (F3). The average value 25000 should be displayed. l
-29. Adjust.the " BALANCE" potentiometer in the Campbell amplifier to display an average of 25000 on the NM-1000 and 100 Kw on the console. l
- 30. Increase reactor power to 1 Mw based on the independent ion chamber.
- 31. ! Read item 30 (F3). The NM-1000 should read 80,000.
- 32. Adjust the "AC GAIN" potentiometer in the Campbell amplifier to give 80,000 on ,
the NM-1000. 1
- 33. Check item #10, press (F1) and item #35, press (F3)(5) . If Necessary, calculate a new item #35 to give 100% power on the console.
Use the formula: Item #35
- 100 / ltem #10 = New item #35
- 34. Enter the new item #35 by pressing (F3)(5)(F8)(number see below)(enter)
For Example: The number 2.109E-8 would be entered (2) (.) (1) (0) (9) (Space)(-)(8).
- 35. Observe the item #10, (F1),'on the NM-1000, or the CSC console for the proper reactor power. If the power is incorrect go back to step 33.
~
- 36. When the reactor power is 1 Mw on the console, and the NM-1000 displays 100% on item #10 (F1), and item #30 (F3) is 80,000 then scram and let the reactor cool for at least 30 minutes.
- 37. Raise power to 100 Kw. Item #30 (F3) should display 25000 and console should I read 100 Kw. If not adjust the " BALANCE" potentiometer in the Campbell I I
amplifier to give 25000 on the NM-1000 and 100 Kw on the console. We have been adjusting the Campbell region "Zero" 25000 on item #30 at 100 l kw with the " BALANCE" pot and the " Span" 80,000 on item #30 at 1 Mw with the "AC GAIN" pot. The Burr Brown unit should display 2500 at 1 kilowatt, 8000 at 10 Kilowatt,25,000 at 100 kilowatt, and 80,000 at 1 megawatt. To verify the 1 kw and 10 Kw points the reactor will have to be allowed to cool overnight. The core gamma background gives false readings on the independent ion chamber at low powers if the gamma is not allowed to decay for a significant period of time after a power run. Figure: number of hours for decay = (decades - 1) squared. .
- 38. At this point the Campbell region should be calibrated. Increase power to 1 Mw based on the independent ion chamber and recheck the console reading. If the ,
l console reading is not correct go back to step 31 and continue. If it is correct then continue. cal.lBRATING THE COUNT RATE REGION.
- 39. Begin decreasing power toward 10 kw to decrease radiation exposure to workers.
- 40. Change the Campbell crossover point item #39 in the NM-1000 to 2000. Press
- (F3)(9)(F8)(2)(0)(0)(0)(enter) to prevent the NM-1000 from changing into count rate region.
- 41. Decrease reactor power to 1 kw based on the CSC console power. Stabilize in manual mode such that the reactor power does not change. The reactor must be very stable. Verify that the independent ion chamber indicates 1 kw. Be sure that the NM-1000 is using Campbell mode. Press (F2) There will be only zeros if the MN-1000 is in Campbell region.
- 42. Change item #39 to'4000. Press (F3)(9)(F8)(3)(0)(0)(0)(enter) to force the NM-1000 to use count rate region
- 43. Read item #20, press (F2), on the NM-1000. Item # 20 should be 680,000. If not, adjust the discriminator in the PA15 to give 680,000 on the NM-1000. The discriminator potentiometer is located inside a hole on the top of the PA15.
There are two holes in the top right side of the PA15. The discriminator is located in the hole closest to the plug. Usually a tool is left in the hole. If not the cover can be removed from the PA15 to find the discriminator. Warning: There is high voltage in the lower section of the PA15.
- 44. Read item #20 on the NM-1000. Average several readings of item #20 which should be 680,000. Calculate the new item 25. Use the formula:
0.1/ Item #20 = ltem #25.-
- 45. Enter the new item #25. Press (F2)(5)(F8)(number), see below,(Enter).
Example number: 1.471E-7. Press (1)(.)(4)(7)(1)(space)(-)(7) Power is determined in the count rate region by multiplying the number of counts by a constant. Zero counts multiplied by a constant gives zero power. 680,000
., counts (item #20) multiplied by some constant gives 0.1 % power or 1 kw in count rate mode. Therefor the "Zero"is an absolute zero and cannot be set, and the
" Span" is set by item #25.
- 46. Calculate the new .5 CPS interlock and enter as item #40.
Multiply .5
- Item #25 as calculated in step 44.
F Press (F4)(F8)(number see below)(enter). L i
Example number: 7.355E-8. Press (7)(.)(3)(5)(5)(space)(-)(8).
- 47. Change item #29 (count rate crossover point) for 700,000.
Press (F2)(9)(F8)(7)(0)(0)(0)(0)(0)(enter).
- 48. Set item #39 (Campbell crossover point) for 2400.
Press (F3)(9)(F8)(2)(4)(0)(0)(onter).
- 49. Increase and decrease the reactor power slowly from about 3 kw to .5 kw based on the CSC console power to check the crossover point. There should not be a jump in power when the crossover occurs. If there is a big cross over jump (100 Watts) go back to step 40 and start over. If the cross over has a small jump item
#31 can be increased or decreased (no more than +/- 400) to try and line up the Campbell and count rate regions. To change the offset press (F3)(1)(F8)(guessed number, no calculation here)(enter) check crossover point.
- 50. The console power should be calibrated and linear at this point. Increase the reactor power to 1 Mw for 10 minutes and generate a scram curve.
CORRECTING THE PRESTARTS: The NM-1000 inserts 4 signals into the PA15 and campbelling amplifier to test the circuitry during prestarts. Two of the signals are generated in the NM-1000 and test the count rate region. The PA15 signals cannot be modified. Two of the signals test the campbelling region and are adjusted in the campbelling amplifier with two potentiometers. The " CAMP Hi" signal checks the campbelling range at 1.1 Mw and the " CAMP LO" at a lower area in the Campbell range.
- 51. Press (F5)(F8)(5)(enter) to insert the CAMP HI signal. Press (F1) to read the indicated reactor power. The power should be 109 or 110 which is the percentage of full power.
- 52. Adjust the CAMP HI pot to give an indication of 109 or 110 on the NM-1000. ,
- 53. Exit calibrate mode by pressing (F5)(F8)(0)(enter).
- 54. Press (F5)(F8)(4)(enter) to insert the CAMP LOW signal.
Press (F3) to display the Campbell counts. Adjust the Low Camp potentiometer to give as low an indication on the NM-1000 as
l possible but no lower than 2500.
- 55. Exit calibrate mode by pressing (F5)(F8)(0)(enter).
' 56. Run prestarts. Expect that the NM-1000 calibration modes 2, 3,4, and 5 will fail.
The new constants on the prestart printout will have to be changed in the CSC configurator. Accidents modifying the configurator can blow the database and cause the console to not boot up properly. Do not attempt to change the j configurator without proper assistance from experienced staff. The information on how to change the configurator is not listed here. For changes to the configurator, see the ROS or RFD.
- 57. Copy the following NM-1000 constants into the core physics log: Items 21,25, 29=700,000, 31, 33=0.370, 35, 39, 40, 41 =109, 42=0.1, 43=3.0, 51 =1, 52=0, 53=0. Note: some of the items above have numbers attached (=) and should not change, but should be checked for accuracy.
- 58. Replace covers on the PA15 and campbelling amplifier.
- 59. Turn off high voltage power supply for the independent ion chamber and remove.
- 60. Remove independent ion chamber from core and hang along the side of the reactor pool. Do not remove the chamber from the pool for several weeks due to high activation of the chamber.
- 61. Clean up any additional mess or apparatus.
. 62. Update Triga Tracker.
4
NM-1000 CHANNEL ALIGNMENT DATA SHEET DATE Personnelinvolved l Equipment used Serial Number Cal Expir Date Voltmeter-Current Meter-Electrometer-Points Tested or Changed As Found As Left Under Voltage Trip Point Volt Volt Over Voltage Trip Point Volt Volt High Voltage At Power Current Amp Amp NM-1000 item #31 (offset) NM-1000 item #30 at 1 Mw (80k) CTS l NM-1000 item #30 at crossover (~2500) CTS NM-1000 item #35 (campbell region span) NM-1000 Item #39 (crossover) 2400 CTS 2400 CTS NM-1000 item #25 (count region span) NM-1000 Item #29 (crossover) 700,000 CTS 700,000 CTS NM-1000 item #40 (.5 cps interlock) CAMP Hi Calibration Signal CAMP LO Calibration Signal NM-1000 item #33 (Camp Constant) .370 .370 NM-1000 Item #41 (Max Reactor power) 109 109 NM-1000 item #42 (1 kw interlock) .1 .1 NM-1000 item #43 (3 sec interlock) 3.0 3.0 NM-1000 item #51 1.0 1.0 . NM-1000 item #52 0.0 0.0 NM-1000 item #53 0.0 0.0 , R WM sup6 Revoed M AuS 1887
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Calibration of Operational Channel /
- l. General:
- 1. Requirements: Tech Spec 4.2.2c
- 2. Frequency: Annual
- 3. Tools: None
- 4. Equipment: Pool stirrer, digital thermometer, ion chamber, high voltage power supply, electrometer (610C), coax signal cable, various cor.nectors and adapters
- 5. Coordination: Operations Schedule
- 6. Estimated Time: 4 hours.
- 7. Safety Precaution / protection: Electrical shock hazard due to high voltage in lower section of PA15
- 11. Procedural Sequence.
1 Move the core to the center of the pool.
- 2. Turn off AC power to the NM-1000 (left side). Attach a battery operated voltmeter capable of reading 1000 volts in 1 volt divisions to the coax line into the high voltage distributing and monitoring assembly.
- 3. Turn the AC power on. Use caution around any exposed high voltage connections.
- 4. Adjust the potentiometer labeled HV on the front of the high voltage distributing and monitoring assembly to give between 698 and 720 Volts (Setpoint - <10%
loss ) on the volt meter.
. 5. Check to see a trip on the NM-1000 or console. If it does not trip, adjust the potentiometer labeled UV TRIP (under voltage trip) until there is a high voltage trip on the NM-1000 or console.
- 6. Reset the high voltage to 775 volts. Power off the NM-1000 and remove the voltmeter from the line. Power on the NM-1000.
- 7. With an operator on console remove the neutron source. See that the console l
power drops to zero. It often takes a couple minutes for the console power to drop. If the reactor has been to power within the last several hours, there will be enough delayed neutrons that the power will not drop to zero. If so, you must wait several hours to continue this procedure. If the console has not been to power and the power does not drop to zero then exit this procedure and perform procedure CO26, Channel Alignment.
- 8. Place an independent ion chamber above the core. Rough adjustment for the chamber is about 3 to 4 inches above the core.
- 9. Attach a high voltage power supply to the HV line of the chamber
.10. Attach a signal line from the chamber to an electrometer in the control room. (A signal line is usually behind the DAC and in the control room cable tray.) Hang the power cables and signal lines along the boom.
- 11. Perform a thermal power calibration according to procedure C015.. Adjust the reactor power such that the actual power is 100 Kw (the console indication may be off). Turn on the electrometer and the high voltage power supply. Read the electrometer at 100 Kw reactor thermal power. The reading should be no greater than 0.01 ma. Adjust the independent chamber height to get the proper current.
The reading is
- 12. Increase the reactor power such that the electrometer indicates one decade higher power. The reactor should be in manual mode and stable to continue.
- 13. Adjust the operational channel chamber height to increase indicated reactor power by lowering the chamber, or to decrease indicated power by raising the operational channel chamber,
- 14. Scram the reactor. Observe the log and linear chart recorders. When the power drops below the crossover point, see that there is not a jump in indicated power ,
when the NM-1000 crosses the crossover point. Jumps can be corrected by changing item #31 on the Burr Brown unit. Item #31 should not be increased to greater than +/- 400. To change item #31 press (F3)(1)(F8)( +/- number desired)(enter). If a change of more than 400 is required, perform a channel alignment because the correction factor is too large. Increase and decrease the
power as necessary to verify or correct the crossover jump. Scram when complete.
- 15. Verify the following items are correct in the NM-1000 Burr Brown unit as per the last channel alignment of the operational channel. The data for the current settings can be located in the core physics / calibration log.
Item #26, item #29 ltem #35, item #39 ltem # 40, item # 41, item #42, item #43
- 16. Allow the reactor to cool for several hours or overnight.
- 17. Increase reactor power from 10 watts to 1 megawatt by decades based on the independent chamber. Plot the independent chamber against the operational channel on graph paper to verify the linearity of the operational channel. Present this data to the ROS or RFD for approval. If the ROS or RFD reject the data, proceed with procedure C026 to perform a Channel Alignment. (Note: if there is a significant core history, the 10 watt and 100 watt data from the ion chamber will be bad. Skip it.)
- 18. Record into the core physics / calibration log any changes to the Burr Brown unit, a verification that items listed above have not changed, and that the linearity has been approved by the ROS or RFD.
4 1
NM-1000 CAllBRATION DATA SHEET DATE Last Channel Alignment Personnel involved Equipment used Serial Number Cal Expir Date Voltmeter-Electrometer-Points Checked or Changed Expected Actual Under Voltage Trip Point 698-720 Volt . NM-1000 item #25 (count region span) NM-1000 item #29 (crossover) 700,000 700.000 NM-1000 item #31 (offset) < +/- 400 NM-1000 item #33 (Camp Constant) .370 .370 NM-1000 item #35 (Campbell region span) NM-1000 item #39 (crossover) 2,400 2,400 NM-1000 item #40 (.5 cps interlock) NM-1000 item #41 (Max Reactor power) 109 109 NM-1000 item #42 (1 kw interlock). .1 .1 l NM-1000 item #43 (3 sec interlock) 3.0 3.0 Linearity curve approved by ROS or RFD
- Check last Channel Alignment for "As Left" data. .
R W eewp W7wp6 Created 25 Aug 1997
to Facility Modification Work Shsst.2 No 10 CFR 50.59 Analysis Required Proposed Change: Channe Procedure C007 and C026 to increase Ooeratine Voltane on Fission Detector Modification to: Procedure _H_ Facilicy Experiment Submitted by: Georae Date 16 Sep 97
- 1. Description of change:
Both procedures C007 and C026 were changed to increase the operating voltage of the detector from 775 volts to 800 volts. The over and under voltage set points were changed to reflect a 5% and 10% change respectively from the new high voltage set point. Also a statement to never take the voltage over 1000 volts was added In procedure C026, the zero point for the Campbell region was changed from 100 Kw to 10 Kw. The data sheet was modified to match the new data taken during this procedure.
- 2. Verify that the proposed change does not involve a change to the Tschnical 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.
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.
NONE Action Sheet: Submitted _ Not Required _E_
)L Raviewed and approved by RFD M Date /#1A $2 RRFSC Notified rr< m .,
k Date SEP 2 21997
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- - - - -- ou T LC w""a;w a, C ~n I*i_fD6_0$a Calibration of Operational Channel I. General: l
- 1. Requirements: Tech Spec 4.2.2c
- 2. Frequency: Annual i l
- 3. Tools: None '
- 4. Equipment: Pool stirrer, digital thermometer, ion chamber, high voltage power supply, electrometer (610C), coax signal cable, various connectors and adapters
- 5. Coordination: Operations Schedule
- 6. Estimated Time: 4 hours.
- 7. Safety Precaution / protection: Electrical shock hazard due to high voltage in lower section of PA15
- 11. Procedural Sequence:
1 Move the core to the center of the pool.
- 2. Turn off AC power to the NM-1000 (left side). Attach a battery operated voltmeter capable of reading 1000 volts in 1 volt divisions to the coax line into the high voltage distributing and monitoring assembly.
- 3. Turn the AC power on. Use caution around any exposed high voltage connections.
4.- Adjust the potentiometer labeled HV on the front of the high voltage distributing and monitoring assembly to give between 720 and 740 Volts (Nominal set point l
- <10% loss ) on the voit meter. . 5. Check to see a trip on the NM-1000 or console. If it does not trip, adjust the potentiometer labeled UV TRIP (under voltage trip) until there is a high voltage trip on the NM-1000 or console. Set point
- 6. Adjust the potentiometer labeled HV to give 840 volts (Nominal set point +5%)
on the voltmeter. WARNING: DO NOT EXCEED 1000 VOLTS. DAMAGE MAY t R W,ocedwpW7 wp6 Created 25 Aug 1997 Reesed 19 Sep 1997 l
l OCCUR TO THE PA15 IF VOLTAGE EXCEEDS 1000 VOLTS.
- 7. Adjust the potentiometer labeled OV TRIP (over voltage trip) until a trip occurs on the NM-1000 or console. Set point
- 8. Reset the high voltage to 800 volts. Power off the NM-1000 and remove the voltmeter from the line. Power on the NM-1000.
- 9. With an operator on console, remove the neutron source. See that the console power drops to zero. It often takes a couple minutes for the consolo power to drop. If the reactor has been to power within the last several hours, there will be enough delayed neutrons that the power will not drop to zero. If so, you must wait several hours to continue this procedure. If the console has not been to power and the power does not drop to zero then exit this procedure and perform procedure CO26, Channel Alignment.
- 10. Place an independent ion chamber above the core. Rough adjustment for the chamber is about 3 to 4 inches above the core.
- 11. Attach a high voltage power supply to the HV line of the chamber
- 12. Attach a signal line from the chamber to an electrometer in the control room. (A signal line is usually behind the DAC and in the control room cable tray.)
Recommendation: Hang the power cables and signal lines along the boom.
- 13. Perform a thermal power calibration according to procedure C015. Adjust the reactor power such that the actual power is 100 Kw (the console indication may be off). Turn on the electrometer and the high voltage power supply. Read the electrometer at 100 Kw reactor thermal power. The reading should be no greater than 0.01 ma. Adjust the independent chamber height to get the proper current. .
The reading is
- 14. Increase the reactor power such that the electrometer indicates one decade ,
. higher power. The reactor should be in manual mode and stable to continue.
- 15. Adjust the operational channel chamber height to increase indicated reactor power by lowering the chamber, or to decrease indicated power by raising the operational channel chamber.
c, a - s.,mr 2 a w.=w a % m7
)
- 16. Scram the reactor. Observe the log and linear chart recorders. When the power drops below the crossover point, see that there is not a jump in indicated power when the NM-1000 crosses the crossover point. Jumps can be corrected by changing item #31 on the Burr Brown unit. Item #31 should not be increased to greater than +/- 400. To change item #31 press (F3)(1)(F8)( +/- number desired)(enter). If a change of more than 400 is required, perform a channel alignment because the correction factor is too large. Increase and decrease the power as necessay to verify or correct the crossover jump. Scram when complete.
- 17. Verify the following items are correct in the NM-1000 Burr Brown unit as per the last channel alignment of the operational channel. The data for the current settings can be located in the core physics / calibration log.
Item #25, item #29 Item #35, Item #39 l Item #40, item #41 > ltem #42, item #43
- 18. Allow the reactor to cool for several hours or overnight. '1
- 19. Increase reactor power from 100 watts to 1 megawatt by decades based on the l independent chamber. Plot the independent chamber against the operational channel on graph paper to verify the linearity of the operational channel. Present ,
this data to the ROS or RFD for approval. If the ROS or RFD reject the data, proceed with procedure CO26 to perform a Channel Alignment. (Note: if there is a significant core history, the 10 watt and 100 watt data from the ion chamber will be bad. Skip it.)
- 20. Record into the core physics / calibration log any changes to the Burr Brown unit, a verification that items listed above have not changed, and that the linearity has been approved by the ROS or RFD.
c, 3 n w m7.,,. uo m7 a-e s., .7
NM-1000 CALIBRATION DATA SHEET - DATE Last Channel Alignment Personnelinvolved Equipment used Serial Number Cal Expir Date Voltmeter-Electrometer 1 Points Checked or Changed Expected Actual Under Voltage Trip Point 720-740 Volt Over Voltage Trip Point 5840 Volt High voltage set point 800 Volt NM-1000 item #25 (count region span) NM-1000 item #29 ( t crossover) '700,000' 700.000 NM-1000 item #31 (offset) < +/- 400 NM-1000 item #33 (Camp Constant) .370 .370 NM-1000 item #35- (Campbell region span) NM-1000 item #39 . ( 4 crossover) 2,400 2,400 NM-1000 item #40 ( 5 cps interlock) NM-1000 item #41 (Max Reactor power) 109 109 NM-1000 item #42 (1 kw interlock) .1 ' .1 - NM-1000 item #43 (3 sec interlock) 3.0 3.0 ' Linearity curve approved by ROS or RFD
- Check last Channel Alignment for "As Left" data.
,=7 4~
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l [CXUBR fiONPROCEDORE} 9[ ~ $UU55$ Operational Channel Alignment l
- l. General:
- 1.
Reference:
General Atomics Technical Staff
- 2. Requirement: Upon installation of new components or as needed
- 3. Tools: Small Flat Screwdriver, Philips Screwdriver l, 4. Equipment: Pool stirrer, digital thermometer, ion chamber, high voltage power supply, electrometer (610C), coax signal cable, battery operated voit meter, battery operated current meter, various connectors and adapters
- 5. Coordination: Operations Schedule
- 6. Estimated Time: 4 to 8 days
- 7. Safety Precaution: Electrical shock hazard due to high voltage in lower section of PA15
- 11. Procedural Sequence:
1 Move the core to the center of the pool.
- 2. With an operator on console remove the neutron source and see that the console power drops to zero. It often takes a couple minutes for the console power to drop. If the reactor has been to power within the last hour there will probably be -
enough delayed neutrons that the power will not drop to zero and therefore no adjustment should be made. If the console has not been to power and the power does not drop to zero then adjust the discriminator no more than 1/8th turn every
. 1 minute until the console power drops to zero. The discriminator potentiometer 1 is located inside a hole on the top of the PA15. There are two holes in the top right side of the PA15. The discriminator is located in the hole closest to the
, plug. Usually a tool is left in the hole. If not, the cover can be removed from the PA15 to find the discriminator. Warning: There is high voltage in the lower l n u _ =m c a- a avm. ie s.,iw 1 ) I
section of the PA15. Counter Clockwise to decrease counts.
- 3. Place an independent ion chamber above the core. Adjust the chamber to be about 3 to 4 inches above the core.
4.- Attach a high voltage power supply to the HV line of the chamber
- 5. Attach a signal line from the chamber to an electrometer in the control room. A signal line is usually behind the DAC and in the control room cable tray. Hang the power cables and signal lines along the boom.
- 6. Perform a thermal power calibration according to procedure C015 except for -
adjustment of the chamber. Adjust the reactor power such that the reactor is at 100 Kw. Turn on the electrometer and the high voltage power supply. Take the reading on the electrometer at 100 Kw reactor thermal power. The reading should be no greater than 0.01 ma. Adjust the independent chamber height to get the proper current. The reading is
- 7. Scram the reactor. Do not move the independent ion chamber until this procedure is finished.
Turn off AC power in the enclosure containing the PA15 high voltage power 8. supply. This is the left gray steel enclosure.
- 9. _ Disconnect the high voltage coax from J2 of the high voltage distributing and monitoring assembly. This assembly is the box located on the bottom right of the enclosure.
i f). Assemble the necessary fittings to add a current meter in series with the high - voltage line and J2. The current meter should be battery operated and able to read current as low as .01 ma and as high as 1.00 ma.
- 11. Attach a battery operated voltmeter capable of reading 1000 volts in 1 volt
,. divisions. ,
- 12. Turn the AC power on. Use caution around any exposed high voltage p
connections.
- 13. Adjust the potentiometer labeled HV on the front of the high voltage distributing and monitoring assembly to give between 720 and 740 Volts (Nominal set point l n__ -- w a - a in7.ies.,i=> 2 1
- <10% loss ) on the volt meter.
- 14. Adjust the potentiometer labeled UV TRIP (under voltage trip) until there is a high voltage trip on the NM-1000 or console.
- 15. Adjust the potentiometer labeled HV to give 840 volts (Nominal set point + 5%)
on the voltmeter. WARNING: DO NOT EXCEED 1000 VOLTS. DAMAGE MAY OCCUR TO THE PA15 IF VOLTAGE EXCEEDS 1000 VOLTS.
- 16. Adjust the potentiometer labeled OV TRIP (over voltage trip) until a trip occurs on the NM-1000 or console.
- 17. Adjust the potentiometer labeled HV to give 800 Volt on the voltmeter.
- 18. Change item #31 in the NM-1000 to 1. Press (F3)(1)(F8)(1)(enter)
- 19. Remove the cover on the Campbell amplifier.
- 20. Press (F3) on the NM-1000. -
- g. 21 Increase reactor power to 1 Mw based on the independent ion chamber.
- 22. Read and record the at power current from the high voltage power supply.
ma
- 23. Adjust the height of the fission detector to give an at power current of.25 mA.
This means that the fission detector is outputting .25 milliamp at 1 Mw. CAllBRATING THE CAMPBELL REGION
- 24. Read and record the NM-1000. The NM-1000 should have approximately 80,000 displayed.
- 25. Adjust the "AC GAIN" potentiometer in the Campbell amplifier to give an average reading of 80,000 on the NM-1000. If 80 K is unobtainable then adjust the potentiometer "DC GAIN" to achieve 80 K on the NM-1000. Scram and allow the rasctor gamma background to decay for at least half an hour.
, 26. Inc ease the reactor power to 10 kw based on the independent ion chamber.
- 27. Read the NM-1000 item 30 (F3). The average value 8000 should be displayed.
- 28. Adjust the " BALANCE" potentiometer in the Campbell amplifier to display an
. average of 8000 on the NM-1000 and 10 Kw on the console. l 29.' Increase reactor power to 1 Mw based on the independent ion chamber.
nwn w a% =7.us =7 3
l l
- 30. Read item 30 (F3). The NM-1000 should read 80,000.
- 31. Adjust the "AC GAIN" potentiometer in the Campbell amplifier to give 80,000 on the NM-1000.
- 32. Check item #10, press (Fi) and item #35, press (F3)(5) . If Necessary, calculate a new item #35 to give 100% power on the console. I l
Use the formula: ltem #35
- 100 / l'em #10 = New item #35 1
- 33. Enter the new item #35 by pressing (F3)(5)(F8)(number see below)(enter)-
For Example: The number 2.109E-8 would be entered (F3)(5)(F8) (2) (.) (1) (0) (9) (Space)(-)(8).
- 34. Observe the item #10, (F1), on the NM-1000, or the CSC console for the proper reactor power. If the power is incorrect go back to step 33.
- 35. When the reactor power is 1 Mw on the console, and the NM-1000 displays 100% on item #10 (F1), and item #30 (F3) is 80,000 then scram and let the reactor cool for at least 30 minutes.
- 36. Raise power to 10 Kw. Item #30 (F3) should display 8000 and console should f read 10 Kw. If not adjust the " BALANCE" potentiometer in the Campbell amplifier to give 8000 on the NM-1000 and 10 Kw on the console.
We have been adjusting the _ Campbell region "Zero" 8000 on item #30 at 10 kw with the " BALANCE" pot and the " Span" 80,000 on item #30 at 1 Mw with the "AC GAIN" pot. The Burr Brown unit should display 2500 at 1 kilowatt,8000 at 10 f Kilowatt,25,000 at 100 kilowatt, and 80,000 at 1 megawatt. To verify the 1 kw and 10 Kw points the reactor will have to be allowed to cool overnight. The core . gamma background gives false readings on the independent ion chamber at low l powers if the gamma is not allowed to decay for a significant period of time after , a power run. Figure: number of hours for decay = (decades - 1) squared.
- 37. ' At this point the Campbell region should be calibrated. If the console reading is not correct go back to step 30 and continue. If it is correct then continue.
nw e n- m em.us.,an 4
I l CAllBRATING THE COUNT RATE REGION.
- 38. Allow the reactor to cool for several hours before taking the power to 1 kw.
- 39. . Change the Campbell crossover point item #39 in the NM-1000 to 2000. Press (F3)(9)(F8)(2)(0)(0)(0)(enter) to prevent the NM-1000 from changing into count rate region.
- 40. Decrease reactor power to 1' kw based on the independent ion chamber. l Stabilize in manual mode such that the reactor power does not change. The reactor must be very stable. The CSC should indicate approximately 1 kw. Be sure that the NM-1000 is using Campbell mode. Press (F2). There will be only
~
zeros if the MN-1000 is in Campbell region.
- 41. Change item #39 to 4000. Press (F3)(9)(F8)(4)(0)(0)(0)(enter) to force the <
NM-1000 to use count rate region
- 42. Read item #20, press (F2), on the NM-1000.
- 43. Read item #20 on the NM-1003. Average several readings of item #20. ,
Calculate the new item 25. Use the formula. ,
)
. 0.1/ Item #20 = ltem #25.
- 44. Enter the new item #25. Press (F2)(5)(FS)(number), see below,(Enter).
Example number: 1.471E-7. Press (1)(.)(4)(7)(1)(space)(-)(7) Power is determined in the count rate region by multiplying the number of counts by a constant. Zero counts multiplied by a constant gives zero power.
. Approximately 680,000 counts (item #20) multiplied by some constant gives 0.1%
power or 1 kw in count rate mode. Therefor the "Zero"is an absolute zero and cannot be set, and the " Span" is set by item #25.
- 45. Calculate the new .5 CPS interlock and enter as item #40.
Multiply .5? Item #25 as calculated two steps above. l Press (F4)(F8)(number see below)(enter). Example number: 7.355E-8. Press (7)(.)(3)(5)(5)(space)(-)(8). 1
' 46. Change item #29 (count rate crossover point) for 700,000.
Press (F2)(9)(F8)(7)(0)(0)(0)(0)(0) n- -
- a- a u m7. w s., mr 5 ,
~ 47. Set item #39 (Campbell crossover point) for 2400. Press (F3)(9)(F8)(2)(4)(0)(0)(enter).
- 48. Increase and decrease the reactor power slowly from about 3 kw to .5 kw based on the CSC console power to check the crossover point. The crossover points are typically between 1 kW and 2 kW. There should not be a jump in power when the crossover occurs. If there is a big cross over jump that can not be corrected by adjusting item #31, go back and start this section (Calibrating the Count Rate Region) over, if the cross over has a small jump, item #31 can be increased or decreased (no more than +/- 400) to line up the Campbell and count rate regions. To change the offset press (F3)(1)(FB)(guessed number, no calculation here)(enter). Check crossover point. The number in item #31 changes the lower end of the Campbell range.
- 49. The console power should be calibrated and linear at this point. Scram and allow the reactor gamma background to cool. Increase the reactor power from 100 watts to 1 Mw by decades based on the independent ion chamber and graph -
the results. Maintain the power at 1 Meg for 10 minutes and generate a scram curve. CORRECTING THE PRESTARTS: The NM-1000 inserts 4 signals into the PA15 and campbelling amplifier to test the circuitry during prestarts. Two of the signals are generated in the NM-1000 and test the count rate region. The PA15 signals cannot be modified. Two of the signals test the campbelling region and are adjusted in the campbelling. amplifier with two potentiometers. The " CAMP HI" signal checks the campbelling range at 1.1 Mw and the " CAMP LO" at a lower area in the Campbell range. ,
- 50. Press (F5)(F8)(5)(enter) to insert the CAMP HI signal. Press (F1) to read the indicated reactor power. The power should be 109 or 110 which is the percentage of full power.
- 51. Adjust the CAMP H1 pot to give an indication of 109 or 110 on the NM-1000.
. a me n,- a% mu.s.,m7 6
- 52. Exit calibrate mode by pressing (F5)(F8)(0)(enter).
- 53. Press (F5)(F8)(4)(enter) to insert the CAMP LOW signal.
Pres.s (F3) to display the Campbell counts. Adjust the Low Camp potentiometer to give as low an indication on the NM-1000 as possible but not lower than 2500.
- 54. Exit calibrate mode by pressing (F5)(F8)(0)(enter).
- 55. Run prestarts. Expect that the NM-1000 calibration modes 2, 3,4, and 5 will fail.
The new constants on the prestart printout will have to be changed in the CSC configurator. Accidents modifying the configurator can blow the database and cause the console to not boot up properly.' Do not attempt to change the configurator without proper assistance from experienced staff. The information on how to change the configurator is not included here. For changes to the configurator, see the ROS or RFD.
- 56. Copy the following NM-1000 constants into the core physics log: Items 21,25, 29=700,000, 31, 33=0.370, 35, 39, 40, 41 =109, 42=0.1, 43=3.0, 51 =1, 52=0, 53=0. Note: some of the items above have numbers attached (=) and should not change, but should be checked for accuracy.
- 57. Replace covers on the PA15 and campbelling amplifier.
- 58. Tum off high voltage power supply for the independent ion chamber and remove.
- 59. Remove independent ion chamber from core and hang along the side of the reactor pool. Do not remove the chamber from the pool for several weeks due to high activation of the chamber.
- 60. Clean up any additional mess or apparatus.
- 61. Update Triga Tracker.
i l
= w nw a- a noe iser se s.,ise7 7 f
I 1 NM-1000 CHANNEL ALIGNMENT DATA SHEET DATE Personnelinvolved Equipr. ant used Serial Number Cal Expir Date Voltmeter-Current Meter-Electrometer-Points Tested or Changed As Found As Left Under Voltage Trip Point Volt Volt Over Voltage Trip Point Volt Volt High voltage set to Volt Volt l Current at 1 Meg mA mA NM-1000 item #31 (offset) NM-1000 item #30 at 1 Mw (-80k) CTS NM-1000 item #30 at 10 Kw (~8,000) CTS I NM-1000 item #35 (Campbell region span) NM-1000 Item #39 ( # crossover) 2400 CTS 2400 CTS NM-1000 item #20 at 1 Kw CTS i NM-1000 Item #25 (count region span) NM-1000 Item #29 ( t crossover) 700,000 CTS 700,000 CTS NM-1000 Item #40 (.5 cps interlock) CAMP HI Calibration Signal CAMP LO Calibration Signal NM-1000 Item #33 (Camp Constant) .370 .370 NM-1000 item #41 (Max Reactor power) 109 109 NM-1000 item #42 (1 kw interlock) .1 .1 . NM-1000 item #43 (3 see interlock) _ 3.0 3.0 ) NM-1000 item #51 1.0 1.0 ~ NM-1000 Item #52 0.0 0.0 NM-1000 item #53 0.0 0.0
- Information not required R WoompW 26 wp6 Reemed 26 Aug 1997,16 Sep 1997 8
m
- . - Engineering Data Sheet 9.29 T xu s -
.; . tw I;1 l RS-P6-0805-134 Fiss on Counter For neutron counting in a high gamma flux
. v s
The RS-P6-0805-134 is a fission counter for use in a mixed neutron and gamma flux. It has special advantages in applications where the detector must operate while exposed to high gamma flux (>108/R/hr). In such cases, the very large fission pulses permit discrimination against gamma pulses and pulse pile-up because of the high neutron-to-gamma signalratio. B-10and BF3 counters
- would experience gamma pulse pile-up to the extent that they cannot be operated satisfactorily.
An additional advantage of a fission counter is that it does not suffer the rapid lifetime degradation common to B-10 and BF, counters. r - -
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I. RS-P6-0805-134 Fission Counter
. For neutron counting in a high gamma flux The RS-P6-0805-134 is a fission counter for use in a mixed neutron and gamma flux.
It has special advantages in applications where the detector must operate while exposed to high gamma flux (>103/R/hr). In such cases, the very large fission pulses permit discrimination against gamma pulses and pulse pile-up because of the high neutron-tc>-gamma signal ratio. B-10and BF, counters
- would experienca gamma pulse pile-up to the extent
, that they cannot be operated satisfactorily.
An additional advantage of a fission counter is that it does not suffer the rapid lifetime degradation common to B-10 and BF, counters. r- ' ~- - a,,cp in all potential applications the inherent low g,gg , y .,;,
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against the advantage of satisfactory performance (with reduced neutron sensitivity)in a high gamma
; MATESWITH ANY .[ %. environment.
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II i Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Update Procedure C012 for use With Reactivity Computer. Modification to: Procedure _XX_ Facility Experiment Submitted by: Geroge Date 24 Nov 97
- 1. Description of change:
Procedure C012 was modified to remove the specifications for the General Atomics reactivity computer and to replace them with the new computerized reactivity computer.
- 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).
T.S. does not specify the method of performing rod calibrations.
- 3. If change involves a facility modification, attach a drawing if appropriate. If structural l facility drawings need updating, modification of drawings must be approved by RFD and l forward a copy of changes necessary to Facilities.
No Change to Facility
- 4. Determine what other procedures, logs, or training material may be affected and record i below. An index search of procedures showed no other procedure changes. New staff will be trained on use of reactivity computer during annual shutdown.
- 5. List of associated drawings, procedures, logs, or other materials to be changed: .l
- 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_ ( '.a F I b'l n.. i* Reviewed and approved by RFD-] y / \ x Date RRFSC Notified msem Mh Date DEC 8 1997 l
[dEUk5YEdNND5kdO5$$S CIENI .$[2((IN2ddib Control Rod Calibration
- 1. General:
- 1.
Reference:
Tech Spec 4.1a & 3.1.2
- 2. Requirement: Annual
- 3. Tools: lon chamber, High voltage power supply, Keithley 610C electrometer or reactivity computer, stopwatches and
~
calculator.
- 4. Coordination: Several reactor staff members required to operate
~
stopwatches or second staff member to record data. I
- 5. Estimated Time: Up to 3 hours per rod
- 6. Safety Precaution / Protection: Practice ALARA when handling ion chamber ll. Procedural Sequence: STOPWATCH METHOD l
- 1. Place ion chamber above core centered between fuel elements C-3 and C-2.
- 2. Connect ion chamber to input of electrometer.
- 3. Set electrometer as follows:
Zero Check: Lock Feedback: Fast Meter: Off Selec;or: Amperes (10-7) Multiplier: 1 , 4. Apply 750 Vdc to ion chamber. l
- 5. Locate the reactor in one of its operating positions.
t 6. Operate the reactor at 500 watts at ed set the ion chamber to output up to 1 milliAmp. l 7. Establish a critical configuration with the reactor power steady at a low level (approx. 2 watts.) Rod banking to be employed will approximate the banking used for normal operations at that core position.
- 8. Ensure criticality by waiting one (1) minute after last rod adjustment before proceeding to Step #8.
- 9. Record all rod positions.
- 10. Withdraw the rod to be calibrated to obtain an indicated positive period of 1
10-40 seconds. 1
- 11. Record the _ control rod positions immediately after rod withdrawal is completed.
- 12. Power level increase will be timed by several persons using stop watches I and observing the electrometer, the asymptotic period calculated, and the I resulting reactivity insertion determined from a graph of insertions versus periods as determined by the in Hour equation. .
i NOTE: Period measurements should be performed at less than 500 watts to avoid ) neaative reactivity effects due to fuel temperature.
- 13. Reduce reactor power to approximately 3 watts using a control rod other than the one being calibrated.
- 14. Repeat steps six (6) through eleven (11) as required to calibrate the entire red. ;
- 15. Scram the reactor.
Method of Analysis for Stopwatch Method l Frorn the power increase factor, P2/P1, and the time, T, measured for the particular l i j power increase, the reactor period, T, associated with incremental movement of a l control rod can be calculated from: T= t in P2/P1 , This period can be converted to a reactivity value using either a tabulation or a plot of the in Hour relationship. From the data, two (2) significant curves can be l developed. One of these, a differential control rod curve, illustrates the rate of reactivity change as a function of rod position. The second curve to be developed,
l l 4. an integral control rod curve, relates the total reactivity change as a function of control rod movement. II. Procedural Sequence: REACTIVITY COMPUTER METHOD SETrlNG UP
- 1. Place an independent ion chamber above the reactor core
- 2. Input 0 to .1 microamp into the action pack and calibrate O to 10 volt output from the action pack.
- 3. Run a calibration program for the reactivity computer I/O board and input signals of 0 and 10 volts to verify the calibration of the board. Check manufacturers literature for specifics if board needs adjustment.
- 4. Connect the output of the action pack to the reactivity computer.
- 5. Connect the ion chamber to the input of the reactivity computer action pack.
- 6. Follow the instruction manual for the teactivity computer to set the ion chamber height at the maximum power desired for the computer. Maximum power should be less than 500 watts.
ROD CAllBRATIONS Follow the instructions for the reactivity computer to perform rod calibrations. t t' - A312 wp6 Opdeced 24 Nov 97
DYNAMIC REACTIVITY COMPUTER instruction Manual i This procedure requires 2 personnel, one to operate the consolo and the other to run the computer. This procedure is used with the two-rod calibration sheet and two control rods. Rod A is fully inserted to begin, Rod B is fully withdrawn. (The other two rods are one fully withdrawn, one balanced to establish criticality.) . No rod calibration should be performed with a hot core. A pulse or a power run will affect the core neutronics. In general, the following will define a ' hot core': e A power pulse in the previous hour. s A power pulse over $2.00 in rescevity in the previous 2 hours. s A steady state or square wave run over genersene over 5 kW-hr in the previous hour a A steady state or square wave run over generating over 50 kW-hr in the previous 12 hours a Any deviellon from " normal" k excess over $.02 The independent gamma ion chamber should be placed above the core, approximately 2 inches above the top grid plate. The output from the chamber is run into the input Jack on the Reactivity Action Pak. The output of the Reactivity Action Pak is connected to the reactivity computer I/O board located next to the Action Pak. The red lead goes to the screw marked " Chi". The black lead goes to the screw marked "S Gnd". 750 volts should then be applied to the chamber. Ensure that the high voltage to the independent chamber is turned on. The digital I/O board should be calibrated annually. This calibration will include a linearity check. Reference the DT2812 user's manual for the appropriate calibration j procedure. Run the program ADJUST.EXE, by entering < ADJUST >, adjust the ion chamber such that the computer reads digital 4000 i 150 when the reactor is at 325 W of i thermal power. ! l The Dynamic Reactivity Computer program is named RX_JCV.EXE, this i program should be run by entering <RX_JCV> ) The appropriate log book entry is as follows:
"X, Y on Console, Y in charge" (BLACK ENTRY)
(Person X will be the console Operator i Person Y will be the Calibrator operating the computer)
" Calibrating (Rod A) and (Rod B) dynamically in position (core position) with the CET ('in whichever location' or 'out')" (RED ENTRY)
(Rods A and B are "TRANS", " SHIM", " SAFE", or " REG" as defined above.)
I Operational Procedure All items may be performed by either the Operator, X, or the Calibrator, Y, unless specifically indicated. It is recommended that sticky notes or other indicators be placed pointing to the UP button for rod A and the DOWN button for rod B.
- 1. (Operator) Bring reactor critical at 30 W in the manual mode.
- 2. (Calibrator) Run program.
- 3. (C) input 30 W as initial power level and accept the value as correct.
- 4. (C) When reactor is critical, press any key. ;
- 5. Observe the RED power trace and the light BLUE reactivity traca. -
- 6. (C) When the light Blue reactivity trace stabilizes, press the <J> key to i establish an initial baseline.
- 7. (C) Immediately direct the operator to raise rod A approximately 100 units.
I
- 8. (O) Raise rod A approximately 100 units.
Announce the new rod position to the Calibrator.
- 9. (C) Record the new rod position.
- 10. .(C) Obsorve the reactivity trace, when it stabilizes, press the key.
- 11. (C) Instructions for determining the next rod movement:
. If the BLUE trace is below the zero line, direct the Operator to raise rod A.
- If the BLUE trace is above the zero line, direct the Operator to insert rod B.
. The above information not withstanding: .
- If the power is above 200 W, insert rod B. ,
- If the poweris below 10 W, raise rod A.
.- - These insertions and withdrawals should be between 60 to 80 units in the middle of a rod,100 units at the ends of the rod.
. The Operator may also use the Reactivity Computer to judge the size of his next pull.
. In all cases, whether to insert rod A or withdraw rod B is at the Calibrator's discretion.
- 12. (O) Make the directed rod movement and announce the new rod position.
- 13. (C) Record the yellow number for change in reactivity for the previous pull.
- 14. (0/C) Repeat steps 9 thru 13 until either rod A is completely withdrawn or rod B is completely inserted. These steps are time critical and should be performed with as little delay as possible.
- DO NOT DROP the last section of rod B by cutting magnet power, this will cause a much faster insertion than driving the rod all the way down. (A
. step insertion will yield inaccurate results.)
- 15. (C) The screen will clear when the data traces approach the right hand boundary, it is recommended that the screen be manually cleared by the Calibrator when the trace is level and near said boundary. This is accomplished by pressing the <C> key.
- 16. Should you make an error or allow the reacte r to exceed the maximum -
power of the computer (=300 W), you will nei d to abort the run. Bring the reactor critical with the initial rod banking, th.sn press the <R> key. (This is starting over, as the entire calibration will need to be repeated.)
- 17. (C) When rod A or rod B is used up, direct the Operator to use one of the two non-calibration rods to balance the remaining calibration rod. Continue to ;
repeat steps 9 thru 12 as before, using the non-calibration rod in place of the used up rod. After moving a non calibration rod, press the <J> key to establish a new baseline. (Pressing the key would add the non-calibration data to the rod's being calibrated.)
- 18. (C) When both rods are used up, press the
key to display data. l Check the data on the screen against the data on the sheet to verify that you have copied the information correctly. i I
- 19. (C) The computer will prompt you for the names of the two calibrMions. It will then create a data file for each rod calibration.
SUMMARY
OF HOT KEYS
Establish a baseline and automatically add change to correct calibration rod <J> Establish a baseline and but do not add change to calibration rod <C> Manually clear traces, but not data displays <R> Roset initial pwerQuit and display reactivity data
IMPORTANT: A. Keep the RED power trace below the 200 W line. If power gets above 300 W, it will saturate the detector. (See note below under error conditions.) B. Keep the RED power trace above the 30 W line, if the power gets below 30 W, the reactivity trace becomes less stable. C. If you forget to record a number see note below under error conditions. 1 . l D. The BLUE line will saturate at
- 30 cents. If this occurs, watch the average reactivity numeric display and determine stabilization from that.
ERROR CONDITIONS: 1 A. Power too high. l If the power gets above 300 W, the chamber will saturate. l Because a rod calibration takes only 10 minutes and the i recovery procedure would take 5 minutes itself, the most j l efficient response to an error condition is to start over. The system will force you to reset all variables and begin again. B. Operator Error, failed to write down reactivity reading: If you fail to write down the reactivity reading, leave that space
; blank on the calibration sheet. At the end, the computer will display all values of reactivity changes that were calculated. You ;
may write down the value(s) that you missed from that display. R:\REACTPC\ DYNAMIC \DYN_ MAN.WP6 l l I l I l
Reactivity Computer - Designed by Steve Miller ( Theory of Operation:- The SIM RC-1a uses an IBM compatible 486-33 computer system equipped with a Data Translation DT2812-A digital I/O board. The board is capable of acquiring data at rates which vary from single sample to 100 khz. The DT2812 requires an input ranging from 0 - 10 volts, and is capable of 12 bit resolution. ~. The software was written using the Data Translation DT2812 toolkit with Borland Turbo Pascal 6.0. The analog signal supplied from Boron lined, uncompensated Reuter-Stokes ion chamber is converted from a 0 .1pA to a 0-10 volt DC signal using an Action instruments model 4300-5500S Action-Pak. The signalis then read by the computer. Samples are taken in groups of 2-10000, (1000 samples works well), averaged, and
. then put into a table. Averaging the data in this way filters out much of the noise associated with this type of input signal. The averaged groups are then fed into a stack (a stack size of 100 works well), which is then averaged (this type of averaging is referred to as a running average). Each time a number is fed onto the stack, the entire stack is averaged, and the time.of the measurement recorded. The next value is then pushed onto the stack, and the averaging repeated. The period is calculated using the standard formula where A= A,e". The reactivity is then calculated using the inhour equation where p($) = t'/#,,,T + 1/#,,, I #/1 +AT. The first term is not significant until the period is very short (less than".1 seconds), and may therefore be j neglected. (See figure 1).
. The rod pull is initiated from 2 watts, and the period and reactivity calculations are i
. performed in real time and displayed. The value of the period, and corresponding l calculated reactivity at 60 seconds after the start of the rod withdrawal has been
. experimentally determined _ as the best measure of actual insertion worth. The 60. !
<second delay from initial rod withdrawal eliminates prompt jump effects. The period '
.- 'and corresponding calculated reactivity values at the 60 second point are' displayed.
in black and white at the bottom of the operators screen. i The reactor is configured with the following equipment in preparation for the rod calibrations. !
- 1. The CET is placed in F13
- 2. The Reuter-Stokes chamber is'placed in the CET. ;
i i
~
l l I l
- 3. The high voltage is set to 750 volts.
- 4. The reactor is brought critical at 250 watts.
- 5. The chamber is lowered into the CET until the voltage on the output of the Action Pak reads nominally 10 volts.
i
- 6. At the C> prompt of the SIM RC-1a, type "R2812" < enter >. This will start !
the reactivity computer program. I
- 7. Accept all defaults until the prompt " Bring the reactor critical at 2 watts and '
press enter" appears. At this time, stabilize the reactor at 2 watts, and press enter. In approximately 10 seconds, the reactivity display will begin. The reactivity and period will be displayed at the bottom of the window when . appropriate. Parameters required for operation are:
- a. Samples in the running average - 100
- b. Samples collected at a time - 1000
- c. Delay time in milliseconds - 25
- d. Number of seconds for the final number - 60
- e. Beta Effective .0070 These values are defaults, just press return at the prompts.
The rod calibration will proceed as follows:
- 1. Bring the reactor critical at 2 watts
- 2. ' Pull approximately 20 cents of reactivity out of the core
- 3. Wait. As the reactor power passes approximately 10 watts, the SIM-RC-1a will .
beep, and the display willindicate that the 60 second timer has started. At the second beep, the final values for reactivity and period will be displayed. Take down the appropriate information (including all rod positions), and get ready for the next rod pull. 4.- While the reactor is stabilizing at 2 watts, press the "T" key or the "C" key (They are equivalent) on the SIM RC-1a keyboard. This will clear all values from the data registers, and reset them to 0.0 for the next run.
- 5. The SIM RC-1a is now ready for the next pull. Repeat steps 1 through 4 until the calibration is complete.
Note: An error message will be displayed if the reactor power ' exceeds 250 watts. A dialogue box with black letters will ' display instructions if this shouk. ;ccur. Other functions built into the SIM RC-1a
]
"R" - This key will allow the user to reset the two watt point without restarting the program. This should be done at the beginning of each rod calibration.
"G" - This key will retrieve another value for period and reactivity without restarting the 60 second timer. Use this key if the value given is in obvious error.
"T", or "C" -These keys are functionally identical. They reset the values and registers for reactivity and period, and clear all other functions in preparation for the next pull.
I "Q" - This returns the computer to a DOS C> prompt. This operation ! is performed after the operations for the day are complete. l
" CTRL-BREAK" - This will stop the program and return to the C>
prompt. ; l
References:
I ! Nuclear Reactor Engineering (Fort Belvoir Book) Page 70 l l
. Reactivity vs Reactor Period in seconds As Per GA-P-14-101 . Attachments:
- 1. Figure 1 General Atomic curve - excess reactivity vs reactor period
- 2. Figure 2 Fort Belvoir Book - Increase in neutron population
- 3. Attachment 1 Turbo Pascal Source Code - R2812
- 4. . Attachment 2 Reuter Stokes ion chamber data sheets
- 5. Attachment 3 Base data for control rod calibration - Reactor curves reference book
- 6. Attachment 4 Excerpt from Fort Belvoir Text
- 7. Attachment 5 Calibration Program for DT2812 Digital I/O Board e
i e
)
l
o IL l Facility Modification Work Sheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: . Tan Cr- *-d for: R - Turned Un/n-- Normal. and Pred== es 8B. 8C. 8E. 8Fl. 8F2. 8Gl. and 8G2 F--4 For M= Tan and Ram R5 Set To 500ne - Modification to: Procedure A Facility Experiment ; Submitted by: Gnorme Date 24 Nov 97 i
]
- 1. Description of change:
. A tag was created to indicate to the operator that *.he Radisdion Area Monitors (RAMS) are turned up or that the RAMS are set normal. His was a response to the 1997 annual audit where the inspector noted that there was no indication to the operator as to whether the RAMS had been set back to normal after a pulse or high power steady state operation. RAMS are normally turned up during pulse, high power steady state, and square wave operations. The following changes are to add the use of a high setting indicator tag for the pulse operations (Procedures BG1
& 8G2) and to eliminate the redremant of tuming up the RAMS during steady state (Procedure SE) and square wave operations (Procedures 8F1 & 3F2) by setting RAM R5 to 500 mrem during the daily startup checklist (Procedure 88), and to annotate it on the Nuclear Instrumentation Set Points list (Procedures 8C).
He change of the RAM R5 setting is higher than past checklists but is far more conservative during high power steady state and equare wave operations. The set pomt is high enough to prevent inadvertent alarming during normal power operations, but should still alarm in the event of a fuel cladding rupture. RAM R2 will still maintain its day time alarm point of 10 millirem. RAM R2 is located 12 feet from the reactor pool. A fuel cladding rupture would elevate the airborne radiation levels to well above the 10 millirem setpoint for RAM R2 and the Continuous Air Monitors (CAMS) would alarm. All RAMS are channel checked during the daily startup.
- 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 T.S and SAR do not specify the set points for the RAMS. 1
- 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 i forward a copy of changes necessary to Facilities.
Not a facility change
- 4. Determine what other procedures, logs, or training material may be affected and record below. HPPs being checked by SHD
- 5. List of associated drawings, procedures, logs, or other materials to be changed:
No drawings need changed
- 6. Create an' Action Sheet containing the list of associated work, specified above, attach a copy, !
and submit it to the RFD. ! All Changes Complete, Procedures updated Action Sheet: Submitted Not Required _XX_ Reviewed and approved by RFD + Date M 'N '7 w ; RRFSC Notified ms+ IN ' Date DEC 8 1997
1 G1 2 @ 7 3 [j M M $$[NNT$$$$MfGIs[ @ l@j M W W 9 l l DAILY OPERATIONAL STARTUP CHECKLIST I i Checklist No. Date Time Completed Supervised by Assisted by I. EQUIPhENT 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 .. .... . . . . . . . . l l III. EQUIPMENT ROOM (Room 2158) l
- 1. Prefilter differential pressure (< 8 psid) . .. . . .
- 2. Primary discharge pressure (l5 - 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. Visualinspection of area . . . . .. .
- 7. Door 2158 SECURED .
IV. PREPARATION AREA i Vi.sual 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. Visualinspection of core and tank . . .. .
Fuel elements *
- 4. Number of fuel elements and control rods in tank storage Control rods
- 5. Air particulate monitor (CAM)
(a) Primary operating and tracing . (b) Backip 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: 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 . . . .. . ... . . ... . .. . q
- 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 Kil/ 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)
- 500 (a) R-1 (< 20)
- 10 (b) R-2 (< 10)
- 10 (c) R-3 (< 10)
- 500 (d) R-5 (< 20) l
- 10 (e) E-3 (< 10)
- 10 (f) E-6 (< 10)
- 10. TV monitors on ........ . .. . . ...... .. . . . .....
I1. CAM high level audible alarm check . . .. .... . ... .
- 12. Water temperature (inlet) (5 - 35 C) . . .. .. .. ....
- 13. Water levellog 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 rnode (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 j (b) % Power 2 (i) Manual , l (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 .. .. . .... . . ..... . .. . .
1
- Numerical Entry AFRRI Form 62s (R) Revised: 24 Nov 97 R:\PROCEDWP\OP_,8B.WP6 Page 2 I
h$0$$ff fb$h &5h5 W D?l{ W hihWW0b DAILY OPERATIONAL STARTUP CHECKLIST Checklist No. Date Time Completed Supervised by Assisted by j i I. EQUIPMENT ROOM (Room 3152) I
- 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 to 6 gpm (5.5 - 6.5 gpm) . .
l
- 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 l 7. Door 2158 SECURED . . . .
IV. PREPARATION AREA Visualinspection of area . . . V. REACTOR ROOM (Room 3161) I . ! 1. Transient rod air pressure (78 - 82 psig) . .
- 2. Shield door bearing air pressure (8.5 - 11 psig) . .
. 3. Visualinspection 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: 01 May 96 R:\PROCEDWP\OP_8B.WP6 Page1
VL REACTOR CONTROL ROOM (Room 31CO)
- 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 Kft/ 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-1 (< 20) 500 (b) R-2 (< 10) 10 (c) R-3 (< 10) 10
- 100 (d) R-5 (< 20)
* ~10 (e) E-3 (< 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. 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) 1 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 j (d) Fuel temp 2 (k) Timer (e) HV loss 1 (1) CSC Watchdog (f) HV loss 2 (m) DAC Watchdog (g) Poollevel
- 20. Zero power pulse .. . . .. . ... . ..
- Numerical Entry AFRRI Form 62a (R) Revised: 01 May 96 R:\PROCEDWP\0P_8B.WP6 Page 2
fNhk N I NMbbNhhh((( (( (( DNC i NUCLEAR INSTRUMENTATION SET POINTS { l l GENERAL: 1 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 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 Gamma: 7000 CPM
- e. Criticality Monitor (RS): 500 mrem day l
20 mrem night Revised: 24 Nov 97 R:\PROCEDWP\0P_8C.WP6 Page 1
[NkNkIf M M kdEDUk5f $""$$fi[h(([l [ k M U M5% 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 e,hannel 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:
- 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
- e. Criticality Monitor (RS): 100 mrem day 20 mrem night Revised: 01 Feb 94 R:\PROCEDWP\OP_8C.WP6 Page 1
, _ _ _ . _ _ _ . ____,-__,,_.,yyy ,., , m _ m , , ,,,, m, m _ ,. ,- ,ORERATIONAL
[ PROCEDURE C i ,,mm;g, ,,,&,Hyj!E^1 Procedure; 8[ TAB. E STEADY STATE OPERATION GENERAL The reactor shall not be operated at a power greater than 1.0 MW. SPECIFIC i
- 1. Set the mode switch to manual mode and clear all warning messages and scrams. ,
- 2. Raise control rods with the appropriate banking, taking into consideration the location l
- \ in the pool, power leval, and experimental requirements. l l
- 3. If final approach to critical is to be made in Auto mode, perform the following:
- a. Set the the thumb wheel dials to the desired power.
l
- b. Raise the rods to the appropriate banking.
- c. Select the rods that are to servoed.
- d. Make sure that all rods that will be servoed have been raised at least 5%.
- e. Enter Auto mode.
- 4. Scram the reactor at the end of the run using the manual or timer scram.
- 5. Ensure the appropriate entries have been made in the operations logbook.
o l l 1 Revised: 24 Nov 97 R:\PROCEDWP\OP,_8E.WP6 Page 1
r- -+- ------+-4 = > :==, <<m- --e4- , mss ~~~'* -~~-
. . $ vi: ~- A &&AA $L-: s idiY .- . .
STEADY STATE OPERATION I J GENERAL The reactor shall not be operated at a power greater than 1.0 MW. SPECIFIC
- 1. Set the mode switch to manual mode and clear all warning messages and scrams.
- 2. For runs greater than 200 KW, adjust alarm points on R-1 and R-5 to full scale.
- 3. Raise control rods with the appropriate banking, taking into consideration the location in the pool, power level, and experimental requirements. j
- 4. If final approach to critical is to be made in Auto mode, perform the following:
1
- a. Set the the thumb wheel dials to the desired power.
- b. Raise the rods to the appropriate banking.
- c. Select the rods that are to servoed.
- d. Make sure that all rods that will be servoed have been raised at least 5%.
- e. Enter Auto mode.
- 5. Scram the reactor at the end of the run using the manual or timer scram.
- 6. Ensure the appropriate entries have been made in the operations logbook.
- 7. If no further steady state runs, square waves or pulses are anticipated, adjust R-1 and R-5 alarm points to their normal settings.
Revised: 15 May 91 R:\PROCEDWP\0P_8E.WP6 Page1
R @ i [o M B 6 6 E E 0 h i l ? P E :i;!B Z : 3 f f 2 L ;! E @ R f A s h SQUARE WAVE OPERATION (Subcritical) i GENERAL . 1 The square wave mode will not be used above a demand powar of 250 KW. SPECIFIC I
- 1. Determine the transient rod critical position using the core position, the final transient l 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 air 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 Auto Mode.
- 4. Stabilize the reactor in Manual Mode. l
- 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.
I
- 9. Allow the power level to fall below 1 watt.
Revised: 24 Nov 97 R:\PROCEDWP\0P ,8F1.WP6 Page 1
- 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 pertinent information has been entered in the reactor operations logbook.
l l i l l L ( i Revised: 24 Nov 97 R:\PROCEDWP\OP_8F1.WP6 Page 2
-----__,-.----,,,,,,,,,,,,,,,,,,,_,,,,,n n .- ..
10EER&T!ONAL P8OCEDUREL mam%p jgfrocedure 8 DAB.F1 SQUARE WAVE OPERATION (Subcritical) GENERAL The square wave mode will not be used above a demand power of 250 KW. SPECIFIC
- 1. Set R1 and R5 to fu!! scale
- 2. Determine the transient rod critical position using the core position, the final transient 9 l 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
- 3. Apply air to the transient rod and raise the anvil to the citical position that was calculated above.
- 4. Bring the reactor cold critical using the three standard control rods; use a rod j 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.
- 5. Stabilize the reactor in Manual Mode.
- 6. Set power demand thumb wheels to desired power level.
- 7. Select the standard control rods to be servoed. Make sure that all control rods to be servoed have been raised at least 5%.
- 8. Scram the transient rod. ,
- 9. Raise the anvil to the desired final position.
Revised: 15 Jan 93 R:\PROCEDWP\0P_8F1.WP6 Page1
- 10. Allow the power level to fall below 1 watt.
~ 11. Switch into Square. Wave mode.
12.' Depress Fire button.
- 13. 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.
~
- 14. Scram the reactor at the end of the run using the manual or timer scram.
l l 15. Ensure all pertinent information has been entered in the reactor operations logbook.
- 16. If no further steady state runs, square waves or pulses are anticipated, adjust R-1 and R-5 alarm points to their normal settings.
i 1 I l T Revised: 15 Jan 93 R:\PROCEDWP\OP_8F1.WP6 Page 2 l 1
..m.
[N N $ N NEC22f!$Ed$C[E55231 M TsN5
)
l,. SQUARE WAVE OPERATION (Critical) GENERAL l The square wave mode will not be used above a demand power of 250KW. i SPECIFIC i .* 1. Bring the reactor cold critical using the three standard control rods. j 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 all rods to be servoed 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.
- 2. Stabilize the reactor in Manual Mode.
- 3. Determine TRANS rod anvil setting for desired insertion.
Insert 70 cents for demand powers up to 25 KW. Insert 75 cents for demand powers greater than 25 KW.
- 4. Rise the anvil to the appropriate setting corresponding to these values using the transient rod calibration curve corresponding to current core position.
- 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. Switch into Square Wave mode.
- 8. Depress Fire button.
As the power level approaches the 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.
- 9. Scram the reactor at the end of the run using the manual or timer scram.
Revised: 24 Nov 97 R:\PROCEDWP\OP_8F2.WP6 Page1 j
- 10. Ensure all pertinent information has been entered in the reactor operations logbook.
Revised: 24 Nov 97 R:\PROCEDWP\0P_8F2.WP6 Page 2 l
I55iI55 N N I N NI$$5llEEI!$$$MI2$ @ 5255 l SQUARE WAVE OPERATION (Critical) GENERAL The square wave mode will not be used above a demand power of 250KW. SPECIFIC
- 1. - Set R-1 and R-5 to full scale.
- 2. 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 all rods to be servoed have been raised at least 5% before entering Auto Mc 1e, set the cold critical power level on the Power Demand thumb wheels, and enter Auto Mode.
- 3. Stabilize the reactor in Manual Mode.
- 4. Determine TRANS rod anvil setting for desired insertion.
Insert 70 cents for demand powers up to 25 KW. Insert 75 cents for demand powers greater than 25 KW.
- 5. Rise the anvil to the appropriate setting corresponding to these values using the transient rod calibration curve corresponding to current core position.
' 6. Set power demand thumb wheels to desired power level.
- 7. Select the standard control rods to be servoed. -
Make sure that all control rods to be servoed have been raised at least 5%.
- 8. Switch into Square Wave mode.
- 9. Depress Fire button.
As the power level approaches the 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. Revised: 15 Jan 93 R:\PROCEDWP\OP_,8F2.WP6 Page1 t
- 10. Scram the reactor at the end of the run using the manual or timer scram. I
- 11. Ensure all pertinent information has been entered in the reactor operations logbook.
- 12. If no further steady state runs, square waves, or pulses are anticipated, adjust R-1 and R-5 alarm points to their normal settings.
l Revised: 15 Jan 93 R:\PROCEDWP\OP_8F2.WP6 Page 2
o Gl 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. l
- 4. Raise the transient rod anvil to the desired pulse position. (This position is obtained l I
from the control rod worth cer.,es for the appropriate core operating position)
- 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 a 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 $2.00 or smaller. Enter the pulse number at the next prompt. Remember, the power level must be below 1 kW to enter Pulse Mode.
- 8. Fir; ine pulse by depressing the " Fire" button on the reactor console.
- 9. Record the appropriate data in the reactor operations logbook from the pulse display,
- 10. Reset R-1 and R-5 to their normal alarm points when pulsing operations are complete l Revised: 24 Nov 97 R:\PROCEDWP\OP_8G1.WP6 Page1
and tum over the RAM indicator sign to denote that the RAMS are set normal. l 9 F Revised: 24 Nov 97 R:\PROCEDWP\OP_8G1.WP6 Page 2
ME5 6 N ii6C566fi5[ [ [ [ T "$ ((P'MMi lidi 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.
- 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. . i
- 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 tanklights. ;
Detector 1 = Pulse lon (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 alam1 points when pulsing, square wave, or steady state operations are complete.
Revised: 02 Jan 92 R:\PROCEDWP\0P_8G1.WP6 Page 1
I PULSE OPERATION (SUBCRITICAL) GENERAL Pulses above $2.00 must be approved by the RFD (prior to pulse initiation). Specification l on the RUR may be used to meet this requi 3 ment. 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:
$ 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 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, 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.
- 7. Scram the Transient rod.
l
- 8. Raise the Transient rod anvil to 100% or the mechanical stop if installed.
Revised: 24 Nov 97 R:\PROCEDWP\OP._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 t200 MW full scale and should be used for pulses of $2.00 or smaller. Enter the pulso number at the next prompt.
- 11. Fire the pulse by depressing the " Fire" button on the reactor console.
l
- 12. Record the appropriate data in the reactor operations logbook from the pulse display.
l 13. Roset R-1 and R-5 to their normal alarm points when pulsing operations are complete and turn over the RAM indicator sign to denote that the RAMS are set back to normal. l i l l l l l Revised: 24 Nov 97 R:\PROCEDWP\OP_8G2.WP6 Page 2 I
4 M@ Dyh)[ (( ]3$ [ 3 f ](( @ %IM D i PULSE OPERATION (SUBCRITICAL) j GENERAL Pulses above $2.00 must be approved by the RFD (prior to pulse initiation). Specification 3 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.
v
- 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 ($) Transient rod (to 100% or mechanical stop) -
Desired pulse ($) 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 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 l detector is selected, turn off the reactor room and tank lights.
l Detector 1 = Pulse lon (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.
- 9. Let the power decay to approximately 1 watt or less.
Revised: 15 Jan 93 Page1
- 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. Roset R-1 and R-5 to their normal alarm points when pulsing, square wave, or steady state operations are complete.
]
Revised: 15 Jan 93 Page 2
ATTACHMENT C Appointment Letters for Current Reactor and Radiation Facility Safety Committee Changes
ARMED FORCES RADIOBIOLOGY RESEARCH lidSTITUTE 8901 WISCONSIN AVENUE BETHESDA. MARYLAND 20889-5603 120 3 September 1997 MEMORANDUM FOR DISTRIBUTION A
SUBJECT:
Reactor and Radiation Facility Safety Comm.ittee Member The following appointment is made: Dr. David McKown ACTION: CAP'T C.B. Galley is replaced by Dr. David McKown, Acting RSO, AFRRI AUTHORITY: Verbal orders, Director, AFRRI EFFECflVE: 2 September 1997 PERIOD: Until superseded or rescinded SPECIAL INSTRUCTIONS: Dr. McKown is appointed as RSO ( permanent voting member) to the RRFSC. This appointment is made in accordance with the AFR.RI Reactor Technical Specifications of NRC License R-84. All questions regarding AFRRI Reactor and Radiation Facility Safety Committee should be directed to SSG Osborne at 295-4692.
%@d4 h CURTIS W. PEARSON Colonel, USAF, MSC Deputy Director for Administration
ARMED FORCES RADIO 210 LOGY RESEARCH INSTITUTE 8901 WISCONSIN AVENUE O. l BETHESDA, MARYLAND 20889-5603 l 120 3 September 1997 MEMORANDUM FOR DISTRIBUTION A
SUBJECT:
Reactor and Radiation Facility Safety Committee Member The following appointment is made: Mr. Bill Powers ACTION: Mr. Mark A. Miller is replaced by Mr. Bill Powers, Acting RSO, NRL AUTIIORITY: Verbal orders, Director, AFRRI EFFECTIVE: 2 September 1997 l PERIOD: Until superseded or rescinded SPECIAL INSTRUCTIONS: Mr. Powers is appointed to the RRFSC in his capacity, as Acting RSO, Naval Research Laboratories ( permanent voting member). This appointment is made in accordance with the AFRRI Reactor Technical Specifications of NRC License R-84. All questions regarding AFRRI Reactor and Radiation Facility Safety Committee should be directed to SSG Osborne at 295-4692. was CURTIS W. PEARSON
, etw Colonel, USAF, MSC Deputy Director for Administration
9' ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE 8901 WISCONSIN AVENUE BETHESDA. MARYLAND 20889-5603 605.01 23 June 1997 i MEMORANDUM FOR DISTRIBUTION A
SUBJECT:
Reactor and Radiation Facility Safety Committee Member The following appointment is made: SSG Sam Osborne ACTION: Appointed as recorder (non-voting) for the Reactor and Radiation Facility Safety Committee. Danny K. McClung, SFC, USA is replaced by Sam Osborne, SSG, USA. AUTHORITY: Verbal orders, Director, AFRRI EFFECTIVE: 23 June 1997 PERIOD: Until Superseded or rescinded SPECIAL INSTRUCTIONS: All questions regarding AFRRI Reactor and Radiation Facility Safety Committee should be directed to SSG Sam Osborne at 295-1291. FOR THE DIRECTOR: 4 Nk CURTIS W. PEARSON Colonel, USAF, MSC Deputy Director for Administration
ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE , 8901 WISCONSIN AVENUE BETHESDA. MARYLAND 20889 5603 605.01 11 June 1996 MEMORANDUM FOR DISTRIBUTION A
SUBJECT:
Acting Chairman of Reactor and Radiation Facility Safety Committee The following appointment is made: Captain Charles B. Galley, MSC, USN ACTION: Appointed as Acting Chairman of Reactor and Radiation Facility Safety Committee AUTHORITY: Verbal orders, Director, AFRRI EFFECTIVE: 11 June 1996 PERIOD: Until superseded or rescinded SPECIAL INSTRUCTIONS: All questions regarding AFRRI Reactor and Radiation Facility Safety Committee should be directed to Captain Charles B. Galley at 295-9261. FOR THE DIRECTOR: J ' M CURTIS W. PEARSON Colonel, USAF, MSC Deputy Director for Administration d
)
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