ML20150E602
| ML20150E602 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 12/31/1987 |
| From: | Hogdon K, Maria Moore, Munno A ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE |
| To: | |
| References | |
| NUDOCS 8804010112 | |
| Download: ML20150E602 (127) | |
Text
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l Reactor Facility Annual '
Report 1 Jan 1987 to 31 Dec 1987 M. L. Moore ,
Reactor Facility Director l
l DEFENSE NUCLEAR AGENCY ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE BETHESD A, M ARYLAND 20814-5145 ff Distrevtion limited to U. S. Government nencies onty: for officiallooerational use. Other reuests for this document mwst be an U*' #""'d "" ' ' '#""""'"'"
8804010112 371231 PDR ADOCK 0500(>170
ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE (AFRRI)
TRIGA MARK-F REACTOR ANNUAL REPORT 1 January 1987 to 31 December 1987 Prepared by:
M. L. Moore K. M. Ilodgdon A. M. Munno G. F. Talkington Approved for Release:
4 George / Irving, ill U Colon y, USAF, BSC Director
Table of Contents Introduction 1 General Information 3 Section I (Changes to the Facility Design, 5 Performance Characteristics, and Operating Procedures, and Results of Surveillance Testing)
Section II (Energy Generated on Reactor Core) 5 Section III (Unschedule ' Shutdowns) 5 Section IV (Safety-Related Corrective Maintenance) 6 Section V (Facility Changes, Changes to 9 Procedures, and New Experiments)
Sectior. VI (Summary of Safety Evaluation Changes 11 not Submitted to NRC Pursuant to 10 CFR 50.59)
Section VII (Summary of Radioactive Effluents 11 Released)
Section VIII (Environmental Radiological Surveys) 12 Section IX (Exposures Greater than 25% of 12 10 CFR 20 Limits)
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Introduction Although 1987 brought many changes to the Reactor Facility, it also presented many opportunities for the Reactor Staff to broaden its scope of operations. The Military Construction (MILCON) project begun in 1986 was finally complete, and the reactor staff was able to resume a normal operational sched-ule. Other milestones in 1987 were the licensing of three members of the staff to become Senior Reactor Operators (SROs), and the reorganization of the management structure of AFRRI.
Many of the renovations brought about through the MILCON project resulted in changes to the Safety Analysis Report.
This necessitated a document to be developed which described each modification, and its applicability under 10 CFR 50.59.
The creation of this document provided members of the reactor staff the experience of documenting facility modifications, and demonstrating the absence of unreviewed safety questions.
This document was presented to, and accepted by, the Reactor and Radiation Facility Safety Committee, and will be elabo-rated upon in Section V of this report.
The addition of three SRO's doubled the Reactor Operational Staff. This was fortuitous inasmuch as requests from outside investigators to use the reactor facility greatly increased.
These outside investigators included the Federal Bureau of Investigations (FBI), the National Bureau of Standards (NDS),
the National Institutes of Health (NIH), and the University of Maryland (UM). The Reactor Operational Staff was also tasked to provide personnel to assist in conducting Department of Army Inspector Generals (DAIG) Inspections at the Fast Burst Reactor at the Aberdeen Proving Grounds in Maryland, and the White Sands Missile Range Fast Burst Reactor in New Mexico. These inspections require persons knowledgeable in reactor operations, health physics, emergency response, and other matters related to the safe operation of a reactor facility. The AFRRI Reactor Staff also provided the Maryland University Training Reactor (MUTR) an independent audit to satisfy their biennial audit requirement.
The reorganization of the administrative structure of AFRRI was brought about by a study that determined a more stream-lined structure was desirable. The change which impacted the Reactor Facility most was the creation of the Radiation Sources Department (RSD). This enabled the Reactor Facility Director (RFD) . (who is also Chair of the RSD) to be directly
2 under the Director of AFRRI administratively as well as op-erationally. Furthermore, the Reactor Organization became a separate division in the RSD. A dual chain now exists under the Department Head. The Reactor Operations Supervisor re-ports directly to the Department Head /RFD on matters that pertain to reactor operations, safety and emergency condi-tions, and the Reactor Division Chief reports directly to the Department Head /RFD on administrative matters. This reor-ganization is shown in Attachment 1 to this report. Another major change was the merging of the Radiation Safety Depart-ment (SAF) and the Occupational Safety and Health Agency (OSHA) into one department - the Safety and Health Department (SHD). Support previously provided by SAF is currently supplied by SHD.
Finally, significant progress toward the implementation of plans to install at AFRRI a new microprocessor based instru-mentation and control system, which is being developed by General Atomics, has been made. The Reactor Staff has re-ceived extensive training at General Atomics, and will be receiving more training when the new console is installed at AFRRI. The installation of the new console under 10 CFR 50.59 is progressing, and the RRFSC has been informed as to the status and functions of the new console during its development.
The remainder of this report is written in a format to in-clude notification items required by the AFRRI Reactor Tech-nical Specifications. Items not specifically required but of a general information value will be given in the General Information section at the beginning of the report. Each section thereafter corresponds to the required section as listed in Section 6.6.la of the AFRRI Technical Specifica-tions.
3 General Information
- 1. Current key AFRRI personnel are as follows:
Director
- Col George W. Irving, III, BSC, USAF Scientific Director (Acting)
- CAPT Richard I. Walker, MSC, USN Chairman, Radiation Sources Department
- Mr. Mark Moore (SRO)
Manager, Radiation Sources Program
- MAJ Leonard A. Alt (SRO)
Chief, Reactor Division
- MAJ James R. Felty (SRO)
- 2. Current key Reactor Operations Personnel Reactor Facility Director
- Mr. Mark Moore Reactor Operations Supervisor
- Capt Kenneth Hodgdon Operations Officer
- Miss Angela Munno Training Coordinator
- SFC Gary Talkington Procurement Coordinator
- SFC Philip Cartwright Maintenance Coordinator
- SFC Wayne Reed
- 3. Other Personnel:
Senior Reactor Operator SFC Stephen Holmes Senior Reactor Operator Candidate
- Ms. Wendy Ting
- 4. There were no departures during this period.
- 5. There were two individuals entered into the Senior Reactor Operator Training Program:
CPT Philip J. Mattson Ms. Wendy Ting
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- 6. There were changes to the RRFSC during the 1987 calendar year. MAJ David Alberth replaced Mr. Michael Terpilak on the RRFSC, Dr. Lawrence Myers retired from AFRRI, and Mrs. Debbie Evans replaced Ms. Betty McCormic as the Recorder. The 1987 RRFSC consisted of the following membership to satisfy the Reactor Technical Specifica-tions.
Chairman
- CAPT Richard I. Walker (Sc. Dir., AFRRI)
Regular Members Dr. Naresh Chawla (Chr ir , SHD, AFRRI)
Mr. Mark Moore (Chair RSD, AFRRI)
Dr. Frank J. Munno (U. of Maryland)
Mr. Jathan W. Stone (Naval Research Labs)
MAJ David Alberth (USUHS)
Special Members CDR Gary H. Zeman (Chair, MRA, AFRRI)
Observer Mr. John Menke (Montg. County Env. Prot. Ag.)
5 SECTION I. CHANGES TO THE FACILITY DESIGN, PERFORMANCE CHARACTERISTICS, AND OPERATING PROCEDURES, and RESULTS OF SURVEILLANCE TESTING.
A. A number of facility design changes were completed in 1987. These changes are discussed in more detail in Section V and Attachment 2 to this report.
B. Due to the AFRRI reorganization, a number of Operational Procedures were modified to reflect current names of departments. Furthermore, several operational proce-dures were modified. A complete set of the revised operational procedures is Attachment 3 to this report.
C. All surveillance items were accomplished on time. Mal-functions discovered during operations are discussed in Section IV.
SECTION II. ENERGY GENERATED BY REACTOR (ON CURRENT CORE)
Month Kwh Jan 155.2 Feb 1481.3 Mar 1851.0 Apr 1748.6 May 1612.3 Jun 6476.0 Jul 3699.4 Aug 3497.4 Sep 5103.7 Oct 5961.9 Nov 3908.1 Dec 2102.8 Total Energy generated this year .......... 37,597.9 Kwh Total Energy on this core ................ 597,744.5 Kwh Total pulses this year > $2.00 ............ 105 Total pulses on this core > $2,00 ......... 3,882 SECTION III. UNSCHEDULED SHUTDOWNS There were no unscheduled shutdowns in this reporting period.
6 SECTION IV. SAFETY-RELATED CORRECTIVE MAINTENANCE The following are excerpts from the malfunction logbook during this reporting period. The reason for the corrective action taken, in all cases, was to return the failed unit to its proper operational status.
13 Jan 1987 Problem: The Stack Gas Monitor (SGM) calibration test was found to be out of specification during the daily start-up on 22 Dec 1986. Reactor Operations were suspended pending investigation.
Solution: The SGM was inspected and tested by the manufacturer's represen-tative and determined to be functioning properly. It was determined that the specifications were set too conser-vatively. The tolerance levels were increased from 2% to 5%, as recommended by the manufacturer, approved by the RFD, and concurred with by the RRFSC. The unit wcs returned to service on 13 Jan 1987 and operations were resumed.
30 Jan 1987 Problem: A slow upward drift developed in the REG rod drive motor.
Solution: The REG Rod circuit was cleaned and tested. The drive was determined to be operational.
2 Feb 1987 Problem: A slow downward drift developed in the REG rod drive motor.
Solution: The REG rod drive "rod down microswitch" was replaced and tested.
The drive was determined to be opera-tional.
7 2 Feb 1987 problem: The TRANS rod drive potentio-meter appeared to be overdriving.
Solution: The TRANS rod drive potentio-meter was correctly adjusted and tested.
The drive was determined to be opera-tional.
17 Mar 1987 Problem: Reactor Room Radiation Area Monitor (RAM) R1 failed; both the low and high level alarm lights were illuminated and the Control Room and Remote alarms activated. Operations were suspended pending investigation.
Solution: An investigation determined that five wires had been accidentally severed by a construction worker from the remote readout in the Emergency Response Center. These wires were reconnected and the system was retested and determined to be operational. The RAM R1 was put back into service on 18 March 1987.
18 Sept 1987 Problem: The square wave mode servo mechanism malfunctioned. The square wave mode was disconnected from the console and all operators were notified of the suspension of square wave operations pending investigation.
Solution: A diode in the square wave mode servo relay was found to be shorted.
The diode was replaced. The square wave mode was tested and determined to be operational on 21 Sept 1987. The square wave servo was returned to service, and square wave operations resumed.
8 27 Nov 1987 Problem: While performing the daily start-up checklist, arcing was noted in the rear of the Console right-hand drawer upon opening it.
Solution: The contacts were cleaned and tightened. A full console checkout was completed and the console was determined to be operational.
3 Dec 1987 Problem: The timer scram reset button malfunctioned while resetting a timer scram.
Solution: The button holder was re-placed, tested and found to be opera-tional. The timer unit was returned to service.
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9 SECTION V. FACI _*ITY CHANGES, CHANGES TO PROCEDURES, AND NEW EXPERIMENTS A. In 1987, the MILCON phase for the Reactor Facility was completed. The renovations brought about by MILCON neces-sitated a number of changes to the Facility Safety Analysis Report (SAR). In accordance with section 50.59 of 10 CFR Part 50, these changes were analyzed for unreviewed safety questions. Attachment 2 (Safety Analyses of Modifications to Upgrade the Reactor Facility at the Armed Forces Radiobiology Research Institute) to this report describes the changes to the reactor facility. Correspondingly, this document pro-vides the basis for the conclusion that the changes to the facility involve no unreviewed safety questions. This docu-ment was approved by the RFD, and was reviewed and concurred with by the RRFSC on June 3, 1987.
In addition to these changes, MILCON created other modifi-cations to the Reactor Facility, including an Uninterruptable Power Supply (UPS), a new Emergency Response Center, and a new Fire Suppression system.
- 1. Uninterruptable Power Supply (UPS)
The old UPS for the security Intrusion Detection System (IDS) was out of date and prone to failure. This system was there-fore removed during the MILCON renovation. After MILCON was completed, a new UPS was installed in room 3152. This system is capable of supplying uninterruptable power to the IDS for approximately one hour. This will allow sufficient time for the emergency generator to pick up the load. If the emer-gency generator fails to operate, sufficient time is also available to pursue an alternative power supply. This system was not previously described and is not included in the Faci-lity SAR, and is included in the annual report for informa-tional purposes.
- 2. Remote Radiation Area Monitor Readout Location The remote readout location for the reactor radiation area monitors (RAMS) has been changed from room 3434 to Room 3430.
This is a result of the change of location of the Emergency Response Center (ERC) from room 3434 to across the hall in room 3430. The move to the new, larger Emergency Response Center was dictated by AFRRI's management to allow the acces-
10 sion of room 3434 to the AFRRI library and to consolidate AFRRI's Emergency Response capabilities into one location.
This location provides more effective management and use of these resources. The location of the ERC RAM readouts is not used as a basis for any Technical Specification. Therefore, there is no unreviewed safety question for this item.
- 3. Fire Suppression System
- a. During MILCON, fire sprinklers were installed in Ex-posure Room 1 (room 1122) and the Reactor Room (room 3161).
The system used is a "dry system"; no water is in the system until an alarm is activated. Consequently, there is no prob-ability that a failure of the system will result in an inad-vertent flooding. Prior to this, no fire sprinklers had been installed in these locations, therefore the advent of this system has increased the fire protection capability in these rooms. Accordingly, this system was not previously described and is not included in the Facility SAR, and is included in the annual report for informational purposes.
- b. A Halon system is installed in the Reactor Control Room (room 3160). Approximately 30 seconds after activation of the Halon alarm. Halon Gas is introduced into the Reactor Control Room to suppress the fires. These types of systems are used in rooms where electronic circuitry cannot be ex-posed to water. The major components of the Halon system are: a warning horn, smoke detectors, and dispersal nozzle located in the Control room; an AFRRI Interface panel, an abort station, main tank and reserve tank in located in room 3152; and a manual pull station located outside the control room (hallway 3106).
The Halon system can be operated manually by a pull station outside the Reactor control Room or automatically activated if both smoke detectors in the reactor control room alarm. There is a 30 second delay between the activa-tion of the warning horn and the injection of the Halon gas into the control room. This allows time for the system to be deactivated, and the halon dump aborted, if necessary, by the halon abort system in room 3152. This 30 second delay also provides ample time for personnel to evacuate the area prior to the release of Halon into the room.
As with the fire sprinklers, the introduction of a fire suppression system in the control room increases the fire protection capabilities in that room.
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B. A complete set of revised procedures are included as to this report.
C. There were no new experiments or tests performed during this reporting period:
SECTION VI.
SUMMARY
OF taFETY EVALUATION CHANGES NOT SUBMITTED TO NRC PURSUANT TO 10 CFR 50.59 satisfies the requirements of this section.
Each modification is described and the basis for the conclusion that each change involves no unreviewed safety question, and that there are no changes to the Technical Specifications, has been provided.
The additional modifications provided in Section V are not included in the SAR nor the Technical Specifications.
Neither are they required for the safe operation of the Reactor. Therefore, there exists no unreviewed safety question for these items.
SECTION VII.
SUMMARY
OF RADIOACTIVE EFFLUENTS RELEASED A. Liquid Waste - The estimated average release on a quarterly basis is less than 25% of the allowable amounts under 10 CFR 20 App B.
B. Gaseous Waste - There were no particulate discharges in CY 1987. The total Argon-41 dibcharges in CY 1987 was 16.82 Ci.
C. Solid Waste - All solid material was transferred to the AFRRI byproduct license; none was disposed of under R-84.
12 SECTION VIII. ENVIRONMENTAL RADIOLOGICAL SURVEYS A. The environmental sampling of soil, water, and plant growth reported radionuclides levels that were not demonstrable above the normal range. the radionuclides that were detected were those normally expected from natural background and from long-term fallout.
B. The environmental monitoring (dosimetry) program reported the following results for CY 1987:
- 1. The average background was determined to be 115.58
+/- 3.19 mrem.
- 2. The average reading from near plant stations above background was determined to be -2.18 mrem.
- 3. The single highest station reading was 14.22 arem above background.
- 4. The above results are expressed at a 35% confidence level.
C. The in-plant surveys, including analysis of effluent fil-ters showed no measurable activity (except as reported in VII above) in all areas outside the normal restricted access areas.
D. There were no special environnental studies conducted this year.
SECTION IX. EXPOSURES GREATER THAN 25% OF 10 CFR 20 LIMITS There were no exposures to staff or visitors greater than 25%
of 10 CFR limits.
Attachment 1 Organization of Personnel for Management and Operation of the AFRRI Reactor Facility
DGECTOR, AFRRI 0 Jews )
t Safety & Health Reactor & Radiation
'"" S '""
Department Department Faclity Safety (Reactor Facety Drector) ""
Reactw j Division (Reactor Operatons S@ervoor) 1 Staff aaa Indcates "Adasory"
Attachment 2 Safety Analyses of Modifications to Upgrade the Reactor Facility at the Armed Forces Radiobiology Research Institute
SAFETY ANALYSES OF HODIFICATIONS TO UPGRADE THE REACTOR FACILITY AT THE ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE 1
H. L. MOORE K. H. HODGDON J. R. FELTY A. H. HUNNO W. W. TING W. W. REED l
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I have determined that modifications to the Reactor Facility. i l
as described in this Technical Report (Safety Analysis Report per 10CFR50.59), involve no unreviewed safety questions and, in fact are improvements to the facility design and radiological safety at AFRRI. I submit this Technical Report to the Reactor Radiation and Facility Safety Committee (RRFSC) for review and concurrence.
Id Mark Moore f
Reactor Facility Director The RRFSC has reviewed this Technical Report and concurs with the determination that the Modifications to the Reactor Facility, as described in this Technical Report, involve no unreviewed safety questions.
5 O / Z-Richard I. Walker CDR, MSC, USN Chairmen, RRFSC APPROVED eorge . rving, III Colone SAF, BSC Director
ABSTRACT This report describes changes to the reactor facility at the Armed Forces Radiobiology Research Institute (AFRRI) in Bethesda, Maryland. Classified as a Safety Analysis Report (SAR) that meets the requirements of Title 10, Code of Federal Regulations, Part 50.59 (10 CFR 50.59), this document provides the basis for the conclusion that the changes to the facility involve no unreviewed safety questions and, in fact, are improvements in the facility design and in the radiological safety at AFRRI. In order to accomplish these e changes, the SAR must be modified. The body of this report
! contains a complete description and detailed safety analysis of each of the SAR changes. Excerpts from the SAR and the proposed changes are included as appendices.
Under 10CFR50.59, a licensee may make changes to its facility provided that no changes are made to the Technical Specifications, and that there are no unreviewed safety l questions. The conditions for unreviewed safety questions are outlined in 10CFR50.59.a.2, and are summarized below:
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If the affected equipment is related to safety:
- i. The probability of occurrence or the consequences of an accident or equipment malfunction shall not be increased.
ii. The possibility for an accident or malfunction of a different type than previously evaluated in the SAR shall not exist.
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iii. The margin of safety as defined in the Basis for j I
any Technical Specification shall not be reduced.
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TABLE QE CONTENTS I. Introduction II. Facility Modifications Safety Analyses
- 1. Windows
- 2. Reactor (Room) Building Roof
- 3. Overpressure Relief Valve
- 4. Reactor Cooling Tower
- 5. Primary Water Makeup System
- 6. RadiatAon Area Monitor Readout Location
- 7. Stack Gas Monitoring System
- 8. Air Supply for Dampers
- 9. Exposure Room Monitoring
- 10. Reactor Control Room Air Conditioner i
Appendix A: Listing of Corrections to be Hade to the SAR Appendix B: Proposed SAR Changes for the Previous Facility l Modifications Safety Analyses Appendix C: Additional Proposed SAR Wording Changes l
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INTROCUCTICN Present conditions at the Armed Forces Radicbiology Research Institute (AFRRI) require that certain modifications be made to upgrade the reactor facility. Some of these changes have been a direct result of the AFRRI Facility upgrade which is an ongoing project called MILCON (Military Construction).
The changes being made to the Safety Analysis Report (SAR) inclume: the Reactor Room Windows, the Reactor (Room)
Building Roof, the Reactor Room Over Pressure Relief Valve, the Reactor Cooling Tower, the Primary Water Makeup System, one of the Remoto Radiation Area Monitor Readout Locations, the Stack Gas Monitoring System, the Air Supply for the Reactor Room Dampers, the Monitoring for Exposure Room 52, and the Reactor Control Room Air Conditioner.
The Code of Federal Regulations (Title 10 Part 50.59) requires that modification of a portion of a licensed facility as described in the facility SAR be doeur.ented with a written safety ana.ysis. Such documentstion provides the basis for determining that the change does not involve an unreviewed safety question. Based on the analyses in thia Technical Report, it has been determined that the propo.td changes to the Reactor Facility do not involve unreviewed safety questions and will actually improve the facility design and radiological safety at AFRRI.
l This technical report describes changes and modifications made to the AFRRI reactor facility as depicted in the facility's SAR. These changes have beon reviewed by the Reactor Facility Director and found to centsia no unreviewed safety questions. This report is submitted to the Reactor and Radiation Facility Safety Committee (RRFSC) for their concurrence that conditions of 10CFR50.59 are met. These conditions are that no unreviewed safety questions are present and that the changes made do not increase the probability of occurrence or the consequences of an accident or malfunction.
The proposed modifications require minor administrative changes in the SAR. The body of this report contains a complete description and detailed safety analysis of each of the 10 CFR 50.59 SAR changes. Appendix A contains a specific page/section index of all of the SAR changes. Appendix B contains excerpts from the SAR, for each of these 10CFR50.59 modifications, and the proposed changes to the SAR; and Appendix C contains additional proposed changes to the SAR which are not 18CFR55. 59 modifications.
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FACILITY MODIFI'JATIONC GAFETY ANALYCES
- 1. Windsws The 3AR is being changed to specify tnat the three 1sege sealed windcws on the east wall of the reactor control room are used to provide visual observation of operations within the reactor room. This change is to eliminate any smbiguity regarding the windows being referenced in Section 3.2.3 of the SAR, which presently reads: 'Large, sealed windows l provide visual observation of operations within the reactor room from the reactor control room and rooms 3156 and 3158."
This passage will be changed to read: "Three large sealed windows on the east wall of the reactor control room allow visual observation by the on duty operator of operations within the reactor room."
Although the windows in 3156 and 3158 may be useful for visual observation of operations within the reactor room, it is not necessary to restrict these windows solely for this purpose since the primary observation must be with the operator in the control room. Additionally, the change of wording in the SAR will not affect the intent of having an operator on duty in the control room who has the ability to view the reactor support structure and pool while operating the reactor. Because this is not a Technical Specification related item, nor is "equipment malfunction" involved, there exists no unreviewed safety question in this revision.
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l W. Remeter 1Reem) Building Egit The roof tcp exterior seal portien of the reactor building rcof has been changed to a four ply hot application roofing compound over three to twelve inches of solid foam insulation. This change was maded to improve the energy ,
efficiency of the building's heating and cooling system and to improve the drainage of the reactor roof.
As described in Sections 3.2.1 and 3.2.4 of the SAR. the roof of the reactor building is composed of ordinary concrete poured over a corrugated steel form which is supported by steel roof trusses. The roof is sealed and waterproofed by the application of roofing compound. The contact surfaces between the concrete roof and the reinforced concrete external walls are further sealed by flashing, expansion-joint material, and roofing compound. As a result of MILCON, the composition of the roof was modified. The roof is now sealed with a four ply hot application roofing compound over three to twelve inches of solid foam insulation. This insulation is sloped from the center of the roof to the corners, where the drains are located. Additionally, the roof hatches have been extended upward by about nine inches to accommodate the thicker, roof. The extensions were welded onto the existing hatch easing and the hatch doors were then attached to these extensions. The security balanced magnetic contact points were moved up to continue the monitoring of the hatch doors.
The purpose of the rect is the confinement of the reactor room air volume. The roof was designed to restrict the leakage of radioactive material into the atmosphere, should an accident occur. Since the structure c: the roof has not been changed (only foam insulation has been added to the top exterior seal portion of the roof), the new roof construction does not decrease the roof's effectiveness in confining the reactor room air volume. Foam insulation has been add-d under the four-ply hot application in order to insulote and slope the roof. Slanting the roof towards the draina has eliminated the former problem of having standing water on the reactor roof during inclement weather conditions. The new sloped roof allows the rain water to be gravity-fed into the drainage network. The construction of the roof is not used as a basis for any Technical Specification. Accordingly, there exists no decrease in the margin of safety as defined in any basis for any Technical Spe:ification item. The foam insulation is made of fire resistant composite material which consists of polyurethane boards factory bonded'to mineral fiber boards. This insulation has a flame spread rating of 75, a smoke development rating of 150 and meets Federal Specifications l HH-i-530 for fire safety. Since the use of this foam insulation poses no increased fire hazard, improves the ef ficiency of the building's heating and cooling system, and facilitates the water drainage on the reactor roof, this new top exterior seal portion of the reactor (room) building roof
I is an improvement in th, t s.:i i t t y design. This design ehsnge has neither increased the pr:.bability of occurrence or the consequences of an sceident nor created the possibility of a different type of malfunction. Therefore, there is no unreviewed safety question for this item.
- 3. Overeressure Relief Valve The atmospheric relief valve vent line addressed in the SAR (Section 3.2.4) has been relocated to provide environmental monitoring of effluents which might be vented out of the valve.
The location of the outlet for the atmospheric relief valve was at the top of and external to the AFRRI stack.
This ' candy cane" shaped vent line exhausted away from the stack into the atmosphere. The outlet for this line was l moved to a new locatica inside the AFRRI stack near the roof
! level of building 42, upstream of the environmental monitoring system which is located at the top of the AFRRI stack. This relocation of the overpressure relief line will ensure monitoring of any releases vented through the over-pressur9 relief valve and line. The function of the overpressure relief line has not been changed. However, the monitoring of effluents is now ensured.
If the main exhaust fans are operating and the exhaust system is pressurized there will be a back pressure on the vent line which will keep the overpressure relief valve closed (due to the higher pressure in the stack compared to
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l the lower or relative negative pressure However, in the reactor rocm!
if the reactor ventilation system loses air, the back pressure in the vent line will no longer exist. This allows an overpressure of air in the reactor room to be vented through the overpressure line to the inside of the AFRRI stack.
A release thus vented to the stack will not flow back into the building for two rosasons. First, if the AFRRI exhaust fans are still working, normal airflow through the stack would force any vented release up the stack .
Second, if the AFRRI exhaust fans have failed, special louvers that sense the loss of air flow will fail closed and isolate the building air system from the AFRRI stack . In either case, an overpressure in the reactor room will be vented into the stack, and any resultant releases will be monitored by the AFRRI gas stack monitoring system.
This change will improve the Reactor Facility's ability to monitor potential environmental releases under emerg ency conditions and will not result in the increase of the probability of occurrence or the consequences of an accident .
Furthe rmore, no new possibility for an accident nor a malfunction has been introduced. The overpressure relief valve is not used as a basis for any Technical Specification .
Accordingly, there exists no decrease in the margin of safety as defined in any basis for any Technical Specification item.
Therefore, there is no unreviewed safety question for this item.
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- 4. Reactor C2211ns Tower i
As a result of the MILCUN renovations, the cooling
- tcwer, used by the secondary water system of the reactor, was replaced by a newer more reliable cooling tower at a different location. This change will reduce the clogging of the secondary coolant system strainer by wood from the deterioration of the old cooling tower, and by leaves, which fell into the old cooling tower by virtue of its location on the ground.
The cooling tower (Section 3.3.2 of the SAR) is a forced-airflow wet tower with a sump. The secondary pump draws chemically-treated raw industrial watert from the sump of the cooling tower, passes the water through the shell-side of the heat exchanger at a rate of about 700 rpm, and returns
! the water to the top of the cooling tower, providing a heat sink for the secondary system to cool the primary water.
During MILCON, the older cooling tower (which was approximately 20 years old) was replaced by a newer, more efficient cooling tower. The location of the old cooling l
tower as shown in Figures 3.3, 3.13, and 3.15 of the SAR has been changed from the ground level behind building 45 to the roof of building 45.
The newer cooling tower is more reliable and satisfies the same purpose as the old cooling tower. Also, the new cooling tower will reduce the maintenance and the down-time associated with isolating and cleaning the secondary coolant system strainer, which was constantly being clossed by wood 1
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i and leaves. The use and tne :hange in location of this new cooling tower does not increase the consequences of an accident, nor does it bring forth the possibility for an accident of a different type than previously evaluated in the SAR. Additionally, the specific type and location of the cooling tower is not used as a basis for any Technical Specifications. Accordingly, there exists no decrease in the margin of safety as defined in any Basis for any Technical Specification item. Therefore, thoro is no unreviewed safety question for this item.
- 5. Primary Water Makeum System The primary makeup water system has been changed from the straight feed system (Millipore Coupling System > to the distillation system (Still) to provide cleaner primary coolsnt makeup water and to reduce the costs associated with routinely replacing the Mil 11 pore Coupling System filters.
Experience has demonstrated that the distillation unit provides a higher quality water than does the straight feed system. The descriptions of these two systems, as described in Section 3.3.4 of the SAR, have not been changed. The only change that was made is that the distillation unit is now the primary makeup water system, and the straight feed system is the backup makeup water system. The higher purity water provided by the distillation unit will increase the assurance that the basis of Techincal Specification 3.3 for maintaining clean water will be met. Also, no new equipment has been
introduced with this change. Therefore, there exists no unreviewed safety questien for this item. l I
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- 6. Radiat m AI.n @ nitor Readout Loestion Section 3.6 of the SAR is being changed to reflect a different location for one of the remote radiation area monitor readouts. The location was changed to inersase the capabilities of the Emergency Response Team by consolidating the informst. ion f rom the readout units with other items necessary for emergency response and placing this information into the Emergency Response Center, Room 3434.
MILCON has required the shuffling of departmental and divisional offices within AFRRI in order to accommodate the progression of contruction throughout the building. As a result, the security office was moved and the room (room 3112) which it occupied has now changed into the AFRRI Civilian Personnel Office (CPO). The remote readout monitors which were located in this room have been moved to the Emergency Response Center (Room 3434). Room 3434 is located in the entrance foyer to AFRRI, within twenty feet of the AFRRI Front Desk; the same as room 3112, however, on the opposite side of the front desk.
This room is still in the vicinity of the AFRRI front desk, and as a result, maintains the ease of access by the emergency response team during an emergency. These remote readouts are used only during an emergency condition by the emergency response personnel. Therefore, the change in
iocation or the remcte re:w it s de,es ne t increase the pr:bability or consequence c improves an accident, but actually tne performance capabilities of the Eme rgency Response Team by incorporating these remote readouts into the newly created Emergency Response Center.
Finally, the location of the radiation area monitorsreadouts not used i as a basis for any Technical Specifications, and accordir. gly there is no decrease in the margin of safety as defined in any Basis for any Technical Specification item .
Therefore, there is no unreviewed safety item for thi s item.
7.
Stack QA2 Menitorins System A new stack gas monitoring system has been install e to d
decrease reactor downtime, cause, by problems associated with the cid stack gas monitoring system. and to provide the capability of selectively monitoring the environmental releases from the reactor facility. The new system uses a Nal scintillation detection system, and is more reliable than the gas flow proportional systoa.
The new NaI scintillation detection is now the reactor stack gas monitoring syst em.
The old gas flow proportional system will still be maintai ned and operated by AFRRI's Radiation Safety Department to provide continuous environmental monitoring of the efflu ents released by all of AFFRI through the ATRRI Facility stack and to serve as a backup to the reactor system .
These two systems have been operated in parallel for about a year .
The old stack gas monitoring (SGM) system (SAR Section
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3.6.3.3) continuously samples the effluent AFRRI Facility stack. at the top or the The effluent is passed thesugh a filter to remove particulates and then is pass ed through a gas ficw proportional detector system, which detect and gamma activity present. s the beta A system of timers and scalers outputs raw data in epm.
Normal background is nominally about 600 cym.
The air sampled by this system is returned to the AFRRI stack.
i The counting gas utilized by the detector is propane, i
which is supplied by two pressurized propane cylinders.
The propane, used at a rate of about 0.1 cubic foot per hour, is discharged outside of the building directly to the atmosphere.
A visual alarm in the reactor equipment roca is activated when the propane cylinder pressure drops below about 25 pounds per e squar anch (psi).
This alarm set point allows approximately 3 months service before the propane cylinders are depl ee t dA visual and audible alarm in the reactor control room is activated when a low flow condition occurs in gas monitor sampling system.
the AFR stack The old stack gas monitoring system is capable of activating alarms at two levels.
The setpoints for these alarms can be found in the appropriate AFRRI internal documents. <
The readouts for the stack gas monitoring system are a strip chart recorder located in the reactor control room and a meter and a strip chart recorder located in the Emergency Responso Center (Room 3434);
with a local readout i
__ n in the reactor equipment room (3152).
The new reactor 3GM system is a NaI scintillation detection system which samples exhaust air from the reactor facility ventilation exhaust duct.
The air is passed through a filter to remove particulates before being analyzed. This new system will detect those effluents (Ar 41) which have been released into the reactor facility ventilation exhaust duct as opposed to aonitoring the effluents released from all of AFRRI into the AFRRI Facility stack.
The new SGM alarms at two levels.
The setpoints for these alarms can be found in the appropriate AFRRI internal documents.
The readouts for this new system are a meter located in the reactor control room and a local readout (printed hard copy) in the reactor room (3161). This new system reports the average Ar-41 concentration at the sample point every six hours on a printout.
An hourly report of the Ar-41 concentration for each of the previous thirty hours is printed out at the end of each day.
These printouts are maintained in a historical logbock This provides the equivalent hard copy documentation of releases as the strip chart recorder for the old system.
A stack gas monitoring system is required by Technical Specifications (3.5.1) to sample and measure the gaseous effluent in the reactor facility exhaust system. In the event of a SGN malfunction, the reactor is not permitted to operate. Therefore, there is no increase in the consequences of equipment malfunction.
Also, the new SGM system is more
reliable than the old SGM system.
First, because the new SGM system does not rely on the :entinuous ficw of propane (the propane supply system has been susceptible to running out of propane and to developing leaks).
And, secondly, because the new system uses current state of the art components which are readily available as opposed to the parts in the old system which are no longer commercially available. Thus, the probability of occurrence of equipment malfunction is decreased.
There were no accidents or malfunctions evaluated for this system in tne SAR.
The Te<,nnical Specification Basis (3.5.1) for the radiation monitoring system is '
to characterize the normal ope rational radiologier.1 environment of the f acility and to aid in evaluating any abnormal operatier.s or
- nditions.
The radiation monitors provide information to the operatiag personnel of any existing or impending da nger from radiation, to give sufficient time to evacuate the facility and take necessary staps to prevent the spread of radioactivity to the surroundings".
I The new SGH only monitors releases from the reactor areas.
Therefore, The old SGM monitors releases from a.11 of AFRRI.
the new synten will better characterize the normal operational radiological environment of the reactor facility .
Furthermore, the alarm setpoint of both systems is set at 800 MFC Ar-41.
as specified in the Emergency Plan, and so the margin for safety has not changed. Since the margin of
safety as described in the basis for the Technical Specifiestions has not changed, the probability of occurence of equipment malfunction has been decreased, and the capability cf selectively monitoring the environmental releases from the reactor facility has been enhanced, the new primary reactor SGH system will improve the radiological safety st the Reactor Facility. Therefore, there exists no unreviewed safety question for this item.
- 8. Air Sueolv M Damners During the MILCON renovation of the ventilation system, '
the source for the compressed air to the isolation dampers for the reactor room and reactor offices has been changed from the air compressor in equipment room 3152 to the air compressor in Penthouse A on top of AFRRI building 42. This change was made as part of the reactor and AFRRI facilities ventilatioa system upgrade as submitted to the NRC in 1983 under a previous 10CFR50.59 Safety Analysis Report (Safety Analysis of Modifications to Upgrade the Reactor Research Institute, AFRRI TR83-1). The building ventilation duct system may be seen in the f acility building drawings.
The source for compressed air to the isolation dampers for the reactor room ventilation system (as stated in Section 3.7.4 of the SAR) has been changed from the air compressor located in room 3152 to the air compressor in Penthouse A on top of AFRRI building 42. The purpose of the compressed air is to maintain the sealing dampers in an open condition.
Loss of compressed air to these dampers results in a closure of the dampers.
Previously, upon alarm ccndition, a signal was sent from the reactor reem primary CAM to a relay in the Reactor Control Panel where a signal was then directed to a venting solenoid.
This air solenoid then vented the air supplied by the air compressor located in equipment room 3152 to the atmosphere.
This, in turn, caused the spring actuated dampers to close.
Presently, the signal is sent from the reactor room primary CAM to the relay in the Reactor Control Panel, and then to the AFRRI ventilation computer in Penthouse A, where a signal is then directed to a venting solenoid. This air solenoid then vents the air supplied by the air compressor located in Penthouse A to the atmosphere. This, in turn, causes the spring actuated dampers to close.
This change was mace to facilitate the control and interaction of the Reactor Ventilation Branch with the remaindet of the AFRRI Ventilation System.
The probability of occurrence of equipment malfunction has not been increased since the change has been made to state of the art equipment. The probability of occurrence of equipment f ailure due to the different compreened air line or signal line is not increased since these lines are located in AFRRI controlled areas. The consequences of equipment malfunction has not been changed since the dampers will still
'close on failure' as described in the SAR. There is no newly introduced possibility for an accident or malfunction
not previously evaluated in the SAR. The Technical Cpecifications Basis (3.4) which relates to this part of the venttiasten system states: 'In the event of a :iad rupture resulting in a substantial release of airborne particulate radioa:tivity, the ventilation system shall be shut down, thereby isolating the reactor room automatically by spring-1:aded, positive sealing dampers". This function is still being performed as stated. Therefore, the margin of safety has not been reduced and there exists no unreviewed safety question for this item.
- 9. Excesure Raam Monitorinn The return line from the Exposure Room 2 Continuous Air Monitor (CAM) has been moved to reduce the radioactivity levels in Warm Storage during and immediately following a reactor run in Exposure Room 2 (ER2).
Previously, this return line from the ER2 CAM exhausted into the Warm Storage area, and then was vented with all of the air in Warm Storage through the absolute filters to the reactor stack. This then increased the radioactivity levels in the Warm Storage area during and immediatley following a reactor run in ER2. To reduce these levels, the return line from the ER2 CAM was moved to exhaust dirsetly back into Exposure Room 2. This sample air would then be vented through the absolute filters to the reactor stack along with all of the air from ER2.
This change was made to further comply with ALARA
1 principles and to reduce radiatten levels in the Warm Storage rcom during and immediately following reactor runs in ER2.
The resultant icwor radiation levels will increase the radiological safety within the reactor facility.
The location of the outlet hose for the CAM for ER 82 is not used as a basis for any Technical Specification.
Accordingly, there exists no decrease in the margin of safety as defined in any basis.
Therefore, there is no unreviewed safety question for this item.
- 10. Remeter Control 8222 Air Cenditioner An opening, large enough to accommodate a small air conditioner has been cut in the east wall of the reactor control rocm. There have been a number of times during the summer months in 1986 when the building air conditioning had failed.
< Because of the need to insure that the electronic equipment in the control room is maintained at a reasonable 1
temperature (especially in light of the scheduled installation of the new microprocessor controlled console this summer, in August 1987), it was necessary to install a small air conditioner in the control room for use when the AFRRI building air conditioner is not working.
There is nothing in the SAR concerning this specific
{ opening. However, section 3.2.4 states that all penetrations into the reactor room for conduits and piping are sealed. In j acccrdance with this requirement, a cover for the air 1
conditioner that seals the entire opening has been installed.
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- This cover will only be removed if emergency ecoling s i
- required in the reactor cente,1 r:cm.
There is no newly introduced possibility for an ac:tcent or malfunction not previously evaluated in the SAR.
Additionally, the installation of this new emergency air conditioner is not used as a basis for any Technical Specification. Accdordingly, there is no unreviewed safety question for this item, a
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. . . . . = .. . . . - . . . .
Accendix &
Listins 21 Corrections 12 ha RAlit 12 1ha EAS I
Paze Section Chanas 2 17 2.5 Change "National Naval Medical Center" to "Naval Medical Command, National Capitol Region"; and each instance of "NNMC" to "NHCNCR".
3-1 3.1 Paragraph corrected to indicate that employees may now enter and exit the AFRRI facility through either the front or back entrance, as opposed to only the front entrance as stated in the SAR.
3-4 Fig. 3-3 Location of reactor cooling tower and Security Office have changed.
See 19CFR50.59 writeup.
3-6 3.1 Change "front entrance" to "front or back entrance".
Refers facility.to access to the AFRRI 3-6 3.2.1 The roof seal for the reactor building has been changed.
See 19CFRSO.59 writeup.
3-7b 3.2.2 3-7b,9 Fan EF-1 is now f an EF-5.
3.2.3 Description of windows has been changed.
See 10CTR58.59 writeup.
3-10 3.2.4 The roof seal for the reactor room has been changed.
See 19CFR59.59 writeup.
3-10 3.2.4 An air conditioner has been installed in the east wall of the control room.
See 19CFR59.59 writeup.
3-12 3.3.2 The cooling tower and its location have been changed.
. See 19CFR50.59 writeup.
3-13 3.3.3 The word 'available' to be replaced by ' read out". This refers to the conductivity at the outlet of each domin-eralizer, and simply clarifies the statement.
3-13 3.3.4 :
This passage is corrected to !
indicate that the still is the primary makeup water system, and the straight feed is the backup system.
See 10CFR50.59 writeup.
3-14 Fig. 3-6 This figure will be changed to remove the temperature indicator on the primary water system, and to relabel the valving for the makeup water systems.
3-15 3.3.6 This passage will be changed to clarify that the audible alarm on the annunciator panel is on only during off duty hours.
3-22 Fig. 3-9 The figure will be corrected by removing the lables for "Dosimetry Room" and "Maintenance Shop". This figure will also be corrected to indicate the cooling tower location change.
3-25 3.6 One of the radiation monitor readouts is no longer in the security office, but now in the Emergency Response Center.
See 10CFR59.59 writeup.
3-26 3.6.1 Change "Security Office (Room 3112) to Emergency Response Center (Room 3434).
See 10CFR58.59 writeup.
3-27 Table 3-1 Each instance f "Security Office (Roon .2)" to be chnnged to "E: gency Response Cente. (Room 3434)"
(three instances).
_ . - . - .. ~ - -
3-27 Table 3-1 The RAM labled "Stack" will be clarified as "R6", the location is four feet above the upper level of the third floor equipment room.
3-30 Fig. 3-13 This figure will be corrected to include the Emergency Response Center.
3-31 3.6.3 The last sentence will be corrected to read "The stack flow monitor measurements are recorded by a strip chart ,
recorder. The stack gas monitor measurements are automatically printed every six hours, and an hourly summary is printed at the end of each day of opera' ion."
5-31 3.6.3.1 Change IF-1 to EF-5.
3 33 Fig. 3-14 Change "NNMC" to "NMCNCR".
1-34 3.6.3.2 Correction for stack par-ticulats monitor alaras. The system is " ... capable of alarming at a preset radiation level." as opposed to " ... capable of alarming at two radiation levels."
3-34 3.6.3.3 The stack gas monitoring system has been replaced.
See 10CFR59.59 writeup.
3-35 Table 3-3 The readout for the Stack Gas ,
Monitor System is corrected to readt Meter in reactor control I room, and printout in the reactor room (included in the 10CFR59.59 writeup).
3-35 Table 3-3 i Delete "local readout in Equipment Room" for Stack Particulate Monitor.
Change IF-1 to EF-5.
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__._m_._____
_ _ _ _ . _ . U __ _ _. _ _
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3-36 3.6.4 Change ' National Naval Medical Center" to 'NMCNCR" Change "five" to ' fifteen" environmental monitoring stations.
3-36 3.6.5 Change '1,@@0 mR/hr to
- 100.000 mR/hr" 3-38 3.7.1 Change "National Naval Medical Center" to "NMCNCR".
3-39 3.7.3 Change Security Office. Room 3112" to "Emergency Response Center Roem 3434".
3-39,40 3.7.4 Compressed Air Supply for the dampers has been changed.
See 10CTR50.59 writeup.
3-40 3.7.5 Change "National Naval Medical Center" to "NMCNCR.
5-5 5.2.3 The outlet hose for the CAM i
for ER2 now discharges tack into IR2 instead of into Warm Storage as described in the SAR.
See 10CFR50.59 writeup.
5-9 Table 5-1 Change "Room 3112" to "Emergency Response Center".
(Four instances) 5-16 5.7 Change "Physicist-in-Charge (PIC)" to "Reactor Facili+.y Director (RFD)".
1 7-5 7.4.1 "Reactor Overstors (RO's)
... " will be changed to "Senior Reactor Operators (SRO's) and Reactor Operators (RO's) ... . " The last sentence of this paragraph will be corrected to read "SRO's shall possess an NRC Senior Operator's License and RO's shall possess an NRc Operator's License for the ATRRI-TRIGA reactor."
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7-9 7.6
- The last two paragraphs et l this section should be l deleted. This was apparently
! an oversight while typing the 3 previous revision of the SAR. l, t
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I APPENDIX 3 i t
I f
Sneeifie faAB M chansen fqr she creviouniv discuamed Facility Modification Safety Analvaan.
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- 1. WINDOWS (section 3.2.3 of the SAR)
CURRENT SAR WORDING:
"Large, sealed Mindows provide visual observation of operations within the reactor room from the reactor control room and rooms 31i6 and 3158."
PROPOSED SAR WORDING:
"Three, large sealed windows on the east wall of the reactor control room allow visual observation by the on duty operator of operations within the reactor room."
- 2. REACTOR (ROOM) BUILDING RQQI (sections 3.2.1 and 3,2.4 of the SAh)
REACTOR BUILDING RQQI (section 3.2.1 of the SAR)
CURRENT SAR WORDING:
"The roof is sealed and waterproofed by the application of five ply, hot-application, roofing compound."
PROPOSED SAR WORDING:
"The roof is sealed with a four-ply hot application i roofing compound over three to twolve inches of solid foam insulation. This insulation is sloped from the center of the roof to the corners, where the drains are located.
REACTOR ROOM SQQI (section 3.2.4 of the SAR)
CURRENT SAR WORDING:
"The roof is sealed and waterproofed by the application of roofing compound. "
PROPOSED SAR WORDING:
"The roof is sealed with a four-ply hot application roofing compound over three to twelve inches of solid foam insulation. This insulation is sloped from the i center of the roof to the corners, where the drains are located.
"In order to acco eodate significant changes in barametric pressure or a change in the reactor room t air temperature that could appreciably alter the pressure in the reactor room, a special normally-
1 1
l closed atmospheric relief valve connects the reactor room directly to the atmosphere. A rise or fall in pressure sufficient to cause structural damage to the reactor room would open the atmospheric relief valve, allowing air to be expelled from the room to the atmosphere through a pipe attached to the stack."
PROPOSED SAR WORDING:
"In order to accommodate significant changes in barametric pressure or a change in the reactor room air temperature that could appreciably alter the pressure in the reactor room, a special normally-closed atmospheric relief valve connects the reactor room directly to the atmosphere through a pipe connected directly into the base of the exhaust stack. A rise or fall in pressure sufficient to cause structural damage to the reactor room would open the atmospheric relief valve, allowing air to be expelled from the room through a pipe into the base of the exhaust stack."
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- 4. REACTOR COOLING TOWER Figures 3-3, 3-9, 3-13, and 3-15 in the SAR are being changed to reflect the change in location of the cooling tower.
CURRENT SAR FIGURE 3-3: i l
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PROPOSED SAR FIGURE 3 3:
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f ' e= ' e= * = e m . es . am .
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OFFICES-4 .g w -, 9 - i_~ p ,,, 1
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.e e em. AREAS THAT en e am CONTAIN OR&:NS FIGURE 34 LM3UlO RADIOACTIVE WASTE DMAINS LOCATED ON THE THIRD LEVEL
PROPOSED GAR FIGURE 3-9:
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PIOURE 34 LN3UlO RADICACTIVE WASTE DRAINS LOCATED ON THE THIRO LEVEL
. - - - , . , . - . _ . . - - , , , . , - _ . . _ - - - . _ _ _ _ . _ _ , , . _ . , , . _ _ _ . . . . _ . _ _ _ , , .____,,,,m-, ,__.-,c, _ . _ , . _ , _ - _ - , , , . , , , , - _ _ - , _ _ _ - _ _ - , . _ - _ . . , , ,
CURRENT SAR FIGURE 3-13: )
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PROPOSED SAR FIGURE 3-13:
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F10URE 315 PERIMETER MONITORING SYSTEM NEAM MRRl C00 FLEX
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, PROPOSED SAR FIGURE 3-15:
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PRIMARY WATER MAKEUP CYGTEM lsection 3.3.4 sf the GAE)
CURRENT SAR WORDING:
'The primary water makeup system consists of a straight-feed system (with valving and coupling) which system. contains a mixed-bed domineralizer and filter The system is capable of using raw l
industrial water as feed water. Before being i discharged into the reactor pool, the primary makeup 1 water is checked to ensure a conductivity at or below that of the reactor pool water. In the event of a primary makeup water system failure, the replenishing of the evaporated reactor poor water is achieved via an 80 gallon holdup tank and distillati n unit (still) connected via valving and piping to the primary water makeup line."
PROPOSED SAR WORDING:
"The primary water makeup system consists of a 100 gallon holding tank and distillation unit (still) connected via valving and piping to the primary water makeup line. This system is capable of using raw industrial water as feed water. In the event of a primary makeup water system failure, the replenishing of the evaporated reactor pool water is achieved via a straight-feed system (with valving and coupling) which contains a mixed bed desineralizer and filter system. This system is also capable of using raw industrial water as feedwater.
- 6. RADIATION ABEA MONITOR READOUT LOCATION (sections 3.6, 3.6.1 and tables 3-1 and 3-3 of the SAR)
CURRENT SAR WORDING:
"These locatins are:
- Reactor Room (room s3161)
- Reactor Control Roos (room s3169)
- Security Office (roca #3112)..."
PROP 06ED SAR WORDING (soction 3.8):
"These locations are:
- Reactor Room (room s3161)
- Reactor Control Room (room s3160)
- Emergency Response Center (room s3434)..."
CURRENT SAR WORDING (SECTION 3.8.1):
'The monitors also activate visual alaras in the control room and the Security Office (room s3112). '
PROPOSED SAR WORDING (section 3.8.1):
"The monitors also activate visual alarme in the control room and the Energency Response Center (room s3434)."
CURRENT SAR WORDINO (TABLE 3-1):
TABLE 3-1
- i. REACTOR REMOTE AREA MONITORS RAM LOCATION READOUT RADIATION ALARM R-1 Approximately 2 Meter in Activates audible feet above the reactor and visual alarm in-reactor pool control the reactor room and surface on the room and in the reactor east side of the Security control room:
reactor pool Office activates visual 3112) alarms in the Emergency Response Center (Room 3434);
activates visual and optional audible alarm on annunciator panel in Hallway 3101 R-2 Approximately 7 Same Activates visual feet above the as R-1 alarm in the reactor floor on the control room, in the reactor room Security Office west wall (Room 3112) and in the Health Physics Division (Room 1420) i E-3 6 feet above the Same Same as R-2. In i
floor on the West as R-1 addition, a visual Wall prep area local alarm exists opposite ER si in the prep area plug door near ER #1 E-6 About 6 feet above Same Same as E-3 except the floor on the as R-1 the local visual West Wall of the alarm in the prep prep area area is located opposite ER #2 near ER 82
, STACK Approximately Same Same as R-2 l
6 feet above the as R-1 l floor of Room 3152 on the out-side of the air exhaust stack.
l
? l l
PROPOSED SAR WORDING (TABLE 3-1):
TABLE 3-1 REACTOR REMOTE AREA MONITORS RAM LOCATION READOUT RADIATION ALARM R-1 Approximately 2 Meter in Activates audible feet above the reactor and visual alarm in reactor pool control the reactor room and surface on the room and in the reactor east side of the Emergency control room; reactor pool Response activates visual Center alarm in the (Room Emergency Response 3434) Center (Room 3434);
activates visual and optional audible alarm on annunciator panel in Hallway 3101 R-2 Approximately 7 Same Activates visual feet above the as R-1 alarm in the reactor floor on the control room, in the reactor room Emergency Response west wall Center (Room 3434)
E-3 6 feet above the Same same as R-2. In floor on the West as R-1 addition, a visual Wall prep area local alarm exists opposite ER *1 in the prep area plug door near ER #1 E-6 About 6 feet above Same Same as E-3 except the floor on the as R-1 the local visual West Wall of the alarm in the prep prep area area is located opposite ER #2 near ER *2 R-6 Approximately Same Same as R-2 4 feet above the as R-1 upper level of Room 3152 on the out-side of the air exhaust duct
g ..
CURRENT SAR WORDING (TABLE 3-3)
Readout...
... Meter and strip chart recorder in reactor control room and Gecur-ity Office (Room 3112);..'
PROPOSED SAR WORDING (TABLE 3-3)
' Readout...
... Meter in reactor control room and printout in the reactor. room (Room 3161);..."
- 7. STACK QAg MONITORING SYSTEM (Section 3.6.3.3 and Table 3-3 of the SAR)
CURRENT SAR JORDING (Section 3.6.3.3)
... The system samples a small portion of the stack air through a multiported sampling probe centered inside the stack near the top. The air is passed through a filter to remove particulates and then is passed through a gas flow proportional detector system, which measures the beta gamma activity present. The system has a range of 1.0E2 cpm to 1.0E6 cym. Normal background is nominally about 600 cym. The air sampled by this erstem is returned to the stack.
The counting gas utilized by the detector is propane, which is supplied by two pressurized propane cylinders. The propane, used at a rate of about 0.1 cubic foot per hour, is discharged outside the l
building directly to the atmosphere. A visual alarm l in the reactor equipment room is activated when the propane cylinder pressure drops below abou 25 pounds per square inch (psi). This alarm set point allows approximately 3 months' service before the propane cylinders are depleted, ensuring essentially continuous uninterrupted operation of the stack gas monitoring system. A visual and audible alaza in the reactor control room is activated when a low flow condition occurs in the stack gas monitor.
The stack gas monitoring system is capable of activating radiation alarms at two levels. The location of the system readouts and alarms are illustrated in Table 3-3. The setpoints for the radiation alarms can be found in the appropriate AFRRI internal documents."
PROPOSED SAR WORDING (Section 3.6.3.3)
"The stack gas monitor (SGM) system is a NaI scintillation detection system tahich samples exhaust
air from the reactor stack. The air is passed through a filter to remove particulates before being analyzed. This system will detect those effluents which have been released into the reactor stack, and reports the average Ar-41 concentration at the sample point every six hours on a printout. An hourly report of the Ar- 41 concentration f or the previous 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> is printed at the end of each day.
The stack gas monitoring system is capable of activating alarms at two levels. The location of the system readouts and alarms are illustrated in Table 3-3. The setpoints for the radiation alarms can be found in the appropriate AFRRI internal documents."
CURRENT SAR WORDING (TABLE 3-3)
TABLE 3-3 STACK MONITORING SYSTEMS SYSTEM READOUT RADIATION ALARM Stack Flow Strip chart recorder in Monitoring (Not applicable) reactor control room; However, EF-1 System local readout in reactor failure gives equipment room (Room audible and 3152) visual alarm in reactor control room.
Stack Gas Meter and strip chart Monitoring recorder in reactor Activates visual System control room and Secur- alarm in reactor ity Office (Room 3112); control room local readout in reactor equipment room (3152)
Stack Meter in reactor control Particulate Same as Stack Gas Monitoring room and local readout Monitoring System in reactor equipment System room (3152)
'l I
l
PROPOSED SAR WORDING (TABLE 3-3)
TABLE 3-3 STACK MONITORING SYSTEMS SYSTEM READOUT RADIATION ALARM Stack Flow Strip chart recorder in (Not applicable)
Monitoring reactor control room; However, EF-5 System local readout in reactor failure gives equipment room (Room audible and 3152) visual alarm in reactor control room.
Stack Gas Meter in reactor Activates visual Monitor- control room and alarm in reactor ing System printout in reactor control room room (Room 3161)
Stack Meter in reactor Same as Stack Gas Particulate control rooa. Monitoring System Monitoring System
CURRENT SAR WOR)ING:
". .The air supply system also supplies air ( 80 psi) to the trarsient rod system and air ( 20 psi) through a surge taak and solenoid valve to the reactor room ventilation system dampers. To remain..."
PROPOSED SAR WORDING:
"...The air supply system also supp]ies air ( 80 psi) to the transjent rod system. Compressed air for the reactor room ventilation system isoletion dampers
( 20 psi) is supplied by the air compressor in Penthouse A on top of AFRRI building 42. To remain..."
- 9. EXPOSURE ROOM MONITORING (Section 5.2.5 of the SAR):
CURRENT SAR WORDING:
'...The ER#2 CAM samples air taken directly from ER#2 and discharges the air to Warm Storage (Room 1120). ."
PROPOSED SAR WORDING:
.The ER#2 CAM samples air taken directly from ERN2 and discharges the air back into ER#2..."
- 10. REACTOR CONTROL ROOM AIB CONDITIONER: (section 3.2.4 of the SAR)
CURRENT SAR WORDING:
"The windows between the reactor room and the reactor control room and adjacent offices are sealed and can not be opened. All penetrations in the walls and floor for conduits and pipina are also sealed."
PROPOSED SAR WORDING:
"The windows between the reactor room and the reactor control room and adjacent offices are sealed and can not be opened. All penetrations in the walls and
- floor for conduits and piping are also sealed.
An air conditioner has been installed in the east wall of reactor the control room. It's use is optional. In accordance with the requirement that all penetrations into the reactor room for conduits and piping be sealed, a cover for the air conditioner that seals the entire opening has been installed.
This cover will only be removed if emergency cooling is required in the reactor control room.
l
l APPENDIX C Specific jifB wordins channes that de n.21 recuire Facility Modification Safety Analvais.
i l
l I
l i
l
- 1. Section 3.1 CURRENT SAR WORDING:
"Access to the entire AFRRI complex is controlled and all personnel are required to enter and exit the facility through the front entrance. ... A computerized card-key system restricts access through the front entrance and into the reactor area and records the entrance and exit times cf personnel.'
PROPOSED SAR WORDING:
"Access to the entire AFRRI complex is controlled and all personnel are required to enter and exit the facility through the front and back entrances. ... A computerized card-key system restricts access through the front and back entrances and into the reactor area and records the entrance and exit times of personnel."
- 2. Section 3.3.3 CURRENT SAR WORDING "The conductivity, measured at the outlet from each dimineralizer, is also available in the control room."
PROPOSED SAR WORDING
'The conductivity, measured at the outlet from each domineralizer, is also read out in the control room.'
- 3. Section 3.3.6
~
CURRENT SAR WORDING "When activated, the switch also causes a visual alarm on the reactor console and an audible and visual alarm on the annunciator panel in Hallway 3191."
PROPOSED SAR WORDING "When activated, the switch also causes a visual alarm on the reactor console and an audible (during off duty hours) and visual alarm on the annunciator panel in Hallway 3101."
- 4. Water Purification and Cooling Gystem Figure 3-6 in the SAR is being changed to remove the thermometer indication in the primary water system.
CURREtiT SAR FIGURE 3-6:
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FIGURE 34 WATER PURIFICATION ANO COOLING SYSTEMS
l PROPOSED SAR FIGURE 3-6:
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FIGURE 34 WATER PURIPICATION AND COOLING SYSTEMS
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- 5. Reactor Offices Figure 3-9 in the GAR is being changed to indicate that rooms 3157 and 3159 are no longer the Dosimetry Room nor the Maintenance Shop. j CURREt4T SAR FIGURE 3-9:
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9 W ARM WASTE CR AINS ',ello.
.um e an. AREASTHAT am i um CONTAIN OR A:NS F10URE 3 4 LlOUID RADIO ACTIVE W ANTE DM AING LOCATED ON THE TNIROLEVEL
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PROPOSED SAR FIGURE 3 3:
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.Weem. AREA $THA7 en e sus CONTAIN OR A:N5 F10URE 34 LN3UlO RADIOACTIVE WASTE DAAINS LOCATED ON THE THIRO LEVEL
- 6. Table 3-1 CURRENT SAR WORDING "bad Location STACK Approximately 6 feet above the floor of room 3152 on the outside of the air exhaust stack.
PROPOSED SAR WORDING r "bad Location R6 1
Approximately 4 feet above the upper level of room 3152 on the outside of the air exhaust duct. "
- 7. Section 3.6.3 CURRRENT SAR WORDING "The stack flow monitor and stack gas monitor measursments are recorded by strip chart recorders."
PROPOSED SAR WORDING "The stack flow monitor measurements are recorded by a strip chart recorder. The Stack Gas Monitor measurements are automatically printed every six hours and an hourly summary is printed at the end of each day of operat.4.on. The printouts are maintained in a historical logbook."
- 8. Section 3.6.3.2 CURRENT SAR WORDING:
"The system is capable of activating alarms at two radiation levels."
PROPOSED SAR WORDING:
"The system is capable of activating alarms at a preset radiation level."
9 Table 3-3 CURRENT SAR WORDING:
"System Readout Stack Particulate Monitoring System Meter in reactor control room and local readout in reactor equipment room (3152). "
PROPOSED SAR WORDING:
"System Readout Stack Particulate Monitoring System "
Meter in reactor control room.
- 10. Section 3.6.5 CURRENT SAR WORDING:
"Tho reactor room criticality monitor has a range of 1 mr/hr to 103 mr/hr, ..."
PROPOSED SAR WORDING:
"The reactor room criticality monitor has a range of 1 mr/hr to 105 mr/hr, ...
- 11. Section 5.7 CURRENT SAR WORDING:
"A Reactor Use Request (RUR) must also be completed, approved, and signed by the AFRRI Reactor Physicist-in-Charge (PIC) before an experiment can be performed."
PROPOSED SAR WORDING:
"A Reactor Use Request (RUR) must also be completed, approved, and signed by the AFRRI Reactor Facility Director (RFD) before an experiment can be performed."
- 12. Section 7.4.1 CURRENT SAR WORDING:
' Reactor Operators (RO's) are directly responsible to the Reactor Operations Supervisor for the safe and legal operation of the AFRRI-TRIGA reactor in compliance with NRC licenses and regulations, and internal RSD and AFRRI instructions. RO's shall possess an NRC Senior Rector Operator License or an NRC Reactor Operator License for the AFRRI TRIGA reactor.'
PROPOSED SAR WORDING:
' Senior Reactor Operators (SRO's) and Reactor Operators (RO's) are directly responsible to the Reactor Operations Supervisor for the safe and legal operation of the AFRRI-TRIGA reactor in compliance with NRC licenses and regulations, and internal RSD and AFRRI instructions. SRO's shall possess an NRC Senior Rector Operator License; RO's shall possess an NRC Reactor Operator License for the AFRRI TRIGA reactor.'
Attachment 3 Current Reactor Operating Procedures
REACTOR OPERATING PROCEDURES INDEX
- 0. PROCEDURE CHANGES I. CONDUCT OF EXPERIMENTS TAB A - Exposure Room Entry TAB B - Core Experiment Tube (CET)
TAB C - Extractor System TAB D - Pneumatic Transfer System (PTS)
TAB E - In-Pool /In Core Experiments II. REACTOR STAFF TRAINING III. MAINTENANCE PROCEDURES IV. PERSONNEL RADIATION PROTECTION V. PHYSICAL SECURITY VI. EMERGENCY PROCEDURES VII. REACTOR CORE LOADING AND UNLOADING VIII. REACTOR OPERATIONS TAB A - Logbook Entry Checklist TAB B - Daily Operational Start-up Checklist TAB C - Nuclear Instrumentation Set Points TAB D - K-Excess TAB E - Steady State Operation (Mode I/IA) '
TAB F - Square Wave Operation (Mode II)
TAB G - Pulse Operation (Mode III)
TAB R - Weekly Operational Instrument Checklist TAB I - Daily Operational Shut-down Checklist
TAB J - Reactor Monthly Usage Summary TAB K - Stack Gas Monitor Procedure IX. REACTOR ROOM SAFETY
PROCEDURE O PROCEDURE CHANGES General: This establishes procedures for permanently or temporarily changing reactor operating procedures.
Specific:
- 1. Permanent changes are made by revising the entire procedure. The revised procedures will be approved by the Reactor Facility Director (RFD) and reviewed by the Reactor and Radiation Facility Safety Com-mittee (RRFSC).
- 2. Temporary changes may be made in pen and ink on the ,
current procedure when initialed by the RFD or Re-actor Operations Supervisor (ROS). These changes must be documented and subsequently reviewed by the RRFSC at the next scheduled meeting.
- 3. Temporary procedures may be established by the RFD for a specific situation.
- 4. All procedures (temporary or permanent) will have an initial block for all operators and reactor staff members. When the initial block is com-plated, the procedure will be placed in the Reactor Operation Binder and kept available far operator review.
l
PROCEDURE I CONDUCT OF EXPERIMENTS General:
- 1. All experiments will be observed during irradiation with the exception of CET experiments or those in which no movement is possible. The closed-circuit televisions (CCTV's) in the exposure rooms and over the reactor pool can be used to meet this require-ment.
- 2. All experiments will be set up so as to preclude movement unless the experiment apparatus is designed for movement (such as rotators, etc.).
- 3. The Reactor Staff will conduct a thorough inspection of all experiments to determine that no unauthorized materials, items or substances, or equipment are ir-radiated.
- 4. ALARA will be practiced during all experiments.
Specific:
- 1. Experiment Review (processing of Reactor Use Request (RUR)):
- a. Check RUR for completeness (Section I should be filled out).
- b. Check experiment protocol against reactor authorizations. Assign reactor authorization number.
- c. Fill in Section II of RUR with special instruc-tions, as appropriate. Assign RUR sequence num-ber. Write in estimated or measured experiment worth in the appropriate block (lower left hand corner of form).
- d. Have the Reactor Facility Director (RFD) revtew and sign the form.
- e. Forward the RUR to the Military Requirements &
Applications, Dosimetry Division (MRAD) and the Safety & Health Department (SHD) for coordina-tion, f., Ensure the RUR form is returned prior to irradt-ation.
r 4
- 2. Conduct of Experiments. Perform setup and irradi-ation of experiments in accordance with the follow-
)
ing procedures:
- a. Exposure Room Entry - TAB A.
- b. Core Experiment Tube (CET) - TAB B.
- c. Extractor System - TAB C.
, d. Pneumatic Transfer System (PTS) - TAB D.
- e. In-pool /In-core Experiments - TAB E.
- 3. Complete the RUR by filling out Section IV with the appropriate information. '
- 4. Attach form to clipboard in the control room.
J J
l 4
4 4
.)
i i
i TAB A: REACTOR EXPOSURE ROOM ENTRY PROCEDURE
- 1. GENERAL 4
- a. PURPOSE: This procedure specifies all safety and security procedures for activities involving entry into the AFRRI TRIGA REACTOR exposure rooms, cur-rently designated exposure rooms 1 and 2 ( rooms 1123 and 11221.
- b. AUTHORIZED ENTRY: Both green and orange badged per-sonnel, may enter a reactor exposure room under the ,
supervision of the Reactor Facility Director (RFD) or '
his representative, and Head Safety & Health Depart-ment (SHD) or his representative. Visiting personnel (V badge) require special authorization by both the Head SHD and RFD to enter either exposure room. In general, permission to enter the exposure rooms will be granted personnel whose duties require such entry, however permission may be denied to personnel for serious or repeated safety or security violations, or for safety reasons emanating from conditions in the exposure rooms themselves. All personnel with access to the prep and/or warm storage areas will be re-quired to receive a special safety briefing prior to being granted unescorted access to the areas. The names of all personnel granted access will be posted in the prep area. Persons not having received the special briefing will be escorted while in the area by a member of the reactor or safety staff, or have a specific clearance from the RFD.
- c. ER ENTRY INSTRUCTIONS - All personnel will:
(1) Know the Reactor staff representative is in charge of all operations in the prep area. Ob-tain permission to enter either exposure room from the Reactor staff representative.
(2) Wear AFRRI TLD badge, wrist dosimeter
- and pocket dosimeter (3) Wear booties, eye protection, gloves *8 . and coatie,
(4) Check and los pocket dosimeter reading on los in prep area prior to entry.
(5) Familiarize themselves with what approximate l radiation levels are in the room, based on ra-diological surveys data performed by SHD.
I (6) Ensure that all materials removed from the expo-l sure room are properly labeled and entered on j
the exposure room entry los AFRRI form 130 (en-closure 2 of this procedure), and the activated materials control log.
1
- If handling radioactive materials.
Olove and coat requirements may be waived, by the Reactor Representative or SHD Monitor, on an individual basis, for personnel who will not be touching anything in the exposure room. There must be a specific reason for waiving such re-quirements.
- d. DEPARTURE FROM REACTOR EXPOSURE ROOM ENTRY PROCEDURES:
(1) Any departure from the below procedures will re-quire a special work permit (SWP). Exceeding any
, radiation dose limits will require a written j
justification from the supervisor of the re-search project which must be approved by the Head, SHD.
- 2. REFERENCES
- a. 10 CFR 20 "Standards for Protection Against Radiation"
- b. USNRC licenses: R-84. 19-08330-02
- c. AFRRI Radiological Safety Instructions
- 3. SHD EXPOSURE ROOM SURVEY
- a. EXPOSURE ROOM CAM: Prior to opening either exposure I room, the respective CAM must read 2000 cpm or less.
l above background. If the CAM reads 2000 cpm or l greater above background, change the filter of the CAM. If 10 minutes or more have lapsed since the end of the reactor run, the door may be opened to the
i t
'l t
first step to facilitate radioeffluent clearance i in the room. Then check the CAM after 1 minute if the #
reading is below 2000 cpm above background, proceed !
with the exposure room opening. If its above, change i the filter and wait another minute. If the CAM alarms during or immediately after a run, change the filter and-reset the CAM.
. DOSE RATE AT FACE OF 000R: If the dose rate at the face of the plus door in the direct line of sight of !
?.h e reactor tank bulge reads greater than 100 mr/hr. '
the door will be closed for 10 minutes before resum- i ing room entry. If the reading is 100 mR/hr or less. ;
the door may be fully opened for internal room !
measurementa.
- c. DOSE LEVELS IN ROOM: Exposure rates will be measured at specific sites in the rooms. These measurements will be given to both the reactor representative and ;
the personnel entering the room. Additionally the y readings will be entered in the room entrance log *
(form 130) and kept in the prep area. The levels will be measured at: I i
(1) The reactor door face in the direct line of sight <
of the reactor tank bulge :
(2) The middle of the room i (3) One meter from the tank wall or shield (
(4) Contact with the tank wall or shield :
(5) and any other place deemed necessary by the SHD ;
or reactor representatives. !
Entry is routinely permitted only when the maximum reading in any occupiable area is 1 R/h or less.
Entry may be permitted if levels are 1-5 R/h, but no work will be permitted in fields over 1 R/h. When I working in a specific area for any extended time is i expected the dose rate in that area will also be i measured and recorded.
(1) If any area inside the exposure room reads ever :
100 mR/hr (closed window), the SHD monitor will remain in the prep area until the room is I closed. All personnel entering will be assigned a stay time if they will be working in the high [
radiation area. AFRRI limits of 100 mR/ week and l 50 mR/ day are to be used as the basis of stay l time determinations. I k
[
(2) All exposure room entries will be checked by the SHD monitor for compliance with radiation safety aspects of applicable Reactor Use Requests (RUR's). If not, non-compliance will be reported to the RFD and to SHD.
- d. FILLING OUT THE SURVEY OF EXPOSURE ROOM OPENING LOG:
(1) A survey of. exposure room opening los sheet must be filled out completely for each opening of an
! exposure room (see enclosure 2). Care must be i taken to fill out each blank on the entry log i" sheet, if a section is not applicable to the par-ticular opening, N/A should be filled in the blank.
- e. NON MONITORED OPENING: the exposure rooms may be opened without a SHD monitor present if ALL the i following conditions hold:
(1) The reactor has not been to power in that ER j since the last survey, and
) (2) The last survey indicated that there were no
. radiation levels in excess of 100 mR/hr in any
- area of the ER where extended stay time is possible, and
- (3) Survey meter readings at the door indicate safe
, entry conditions (should be less than 1 mR/hr).
4 j (4) The ER CAM should be observed, a".d its reading 2 (net) should be less than 200 cpm above back-j ground.
! (5) An entry will be made in the exposure room log by
! a reactor staff member, with a note that the sur-vey has been waived.
! 16) SHD must be notified if any radioactive materials or equipment are to be removed from the prep area.
l f. PERSONNEL PROTECTION PROCEDURES 1
. (1). Dosimetry and protective clothing requirements
! are given in paragraph 1.c, entry instructions.
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(2) Entr.v is permitted only after the SHD monitor has completed the survey and reported results to those about to enter.
(3) All personnel shall read and log dosimeters when leaving the exposure room using the dosimeter log in the prep area.
(a) Net doses over 10 mrem must be reported to the SHD Monitor.
(4) Protective clothing will be removed in such a way as not to contaminate "clean" areas by items from "dirty" areas.
(5) All personnel entering the yellow area will "frisk" themselves before leaving the prep area
- g. SPECIFIC ACTIONS TO OPEN EXPOSURE ROOM DOORS ,
(1) Turn up exoosure room lights (this can be waived for experiment needs)
(2) Check plus door tracks for obetructions; insure all obstacles are clear of the door (including ropes).
(3) Secure both entrances to the prep area.
(4) Insure thst only authorized personnel isee 1. b.)
are present in the reactor prep area during ex-posure room openings.
(5) When blue light on exposure room door key panel is on and with proper authorization (SHD, CAM, etc..)
insert key and open door. DO NOT LEAVE KEY IN LOCK UNATTENDED.
(6) Open door in accordance with entry procedures.
Ensure all required data is logged in entry log.
(7) Ensure that individuals that will be moving lead.
bismuth, or other heavy materials are wearing steel-toed shoes.
(8) Limit exposure times of all personnel entering the exposure rooms based on the results of the radia-tion survey.
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- 4. ACTIVATED MATE ALS
- a. PLACING MATERIAL IN EXPOSURE ROOM: Before placing a n .v equipment or material in an exposure room for irradi-ation the following will be observed: ,
8 (1) Equipment tagged as AFRRI property: a DF must be sent to both the RFD and the AFRRI property officer. The DF must state that the equipment is knowingly being irradiated and therefore request that it be removed from the property books. It must also state that should the material remain byproduct material after a reasonable amount of time it will be disposed of as radioactive waste.
The DF must contain all nomenclature ac well as an adequate description of the equipment in order for it to be identified on the property book.
(2) Non tagged AFRRI equipment or material (to be re-turned): a DF or statement on the reactor RUR must be sent to the RFD giving the kinds and amounts of byproduct material expected to be pro-
' duced (that is the material that the experimenter wishes to be returned) and a copy or number of their radionuclide authorization number. The DF or RUR statement must be specific and contain an accurate description of the material being ex-posed (converted to byproduct). Other information will be required from personnel before any ma-terial is allowed to be removed from the prep or i warm storage areas (see next section of this pro-cedure 4.b. and 4.c.)
(3) Non tagged equipment or material (not to be re-turned): A DF or statement on the RUR that the
- experimenter understands that byproduct material produced as a result of their irradiations will be disposed of as radioactive waste, and addi-tionally any material not specifically requested i to be held will be disposed of as radioactive waste in the next shipment.
i (4) Non AFRRI owned equipment / material: A signed memorandum from the responsible property owner that they understand that byproduct materials generated in excess of their license will be dis-posed of as rad waste unless prior arrangements have been made with the reactor /SHD staffs for storage. Any material not removed within a .
reasonable amount of time will automatically be disposed of an radioactive waste.
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- b. SURVEY OF MATERIALS COMING OUT OF EXPOSURE ROOM (1) All material leaving the exposure rooms must be surveyed for activation or contamination. Survey meter readings will be used to determine dose levels. Smear surveys may be used, if the SHD representative deems them necessary. All materi-als will be labeled appropriately in accordance with HPP 0-2 and enclosure 1 of this procedure.
(2) All special equipment that has been activated such as chambers, rotaters, motors, meters, etc.,
will be stored under the control of the reactor license or the AFRRI byproduct license in warm storage or the prep area. Removal of items from the prep area will only be allowed in accordance with the disposition of a.ctivated materials, section 4.c. of this procedure.
- c. DISPOSITION OF ACTIVATED MATERIALS (1) prior to removing activated material or equipment from the prep area or an entry must be made in the Activated Materials Control Log. The infor-mation that must be entered in this log is as follows:
(a) ITEM NUMBER: will be assigned by the SHD mon-itor in sequence and be prefixed with an A and the year (i.e. A86-001, A86-002). Each item that has been activated must be assigned an activated item number, for example if a dog was activated in a plastic case both the dog and the cage must be numbered and tagged or if an activated camera is tagged both the lens and the camera must be numbered if the lens is removable. In cases where there are small animals being activated the tag may be placed on the case to indicate the activity levels of the animals as long as the person taking them is aware that the label must stay with the animals.
(b) ITEM DESCRIPTION, AFRRI NUMBER. SERIAL NUM-BER, enter a brief description of the item removed. The AFRRI number and serial number shall be entered if applicable.
(el-BACKGROUND LEVELS,-enter the background radi-ation levels of the area where the survey is conducted.
(d) LEVELS ON CONTACT CLOSED WINDOW, LEVELS ON .
CONTACT OPEN WINDOW, enter the radiation' l levels detected on the surface of the item being surveyed using both open and closed windows.
(e) SMEAR RESULTS. enter the results of the smear test if it was taken, see section 4.a.1. of this procedure.
(f) LOCATION MATERIAL REMOVED TO: enter the lab or area to which the materials are being taken. Ensure that the lab is qualified to hold the radioactive materials in accordance ;
with enclosure one to this procedure, all ;
appropriate Radiological Safety Instructions and Health Physics Procedures. l (g) PERSON REMOVING MATERIALS, enter the name of the investigator or technician that is taking the materials, ensuring that the person is listed under the principal investigators authorization for handling radioactive ma-terials.
(h) SIGNATURE OF PERSON REMOVING MATERIAL, have person receiving custody of the materials sign the log with the understanding that the materials being received have been activated.
4 (1) INITIAL OF SHD PERSONNEL, the person that re-leased the activated materials will initial here.
(j) REMOVE FROM LOG, this space is to be checked off when the radioactive material har decayed below activation action levels indicated in enclosure 1 to this procedure.
(2) It is required that the los be reviewed by the ,
Chairman of SHD. and the Reactor Facility Direc- '
- tor annually to determine the disposition of all listed materials.
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- 5. COMPLETION OF ENTRY
- a. The SHD monitor or Reactor Staff Representative will check to see that all personnel have left the exposure room before the plug door is closed.
- b. The SHD monitor will not leave the area while the plug door is open without notifying the Reactor Staff Rep-resentative,
- c. Lock the exposure room door control panel; reset lights, if appropriate, and rope off yellow area.
- d. Resecure the prep area on departure.
TAB B: CORE EXPERIMENT TUBE (CET)
General: ALARA principles will be practiced during CET operations.
Specifics:
- 1. CET Insertion into the core:
- a. Ensure a reactor operator is monitoring the reactor console,
- b. Ensure a reactor staff member is present in the reactor room.
- c. Establish communications between the reactor room and the control room,
- d. Test fuel-handling tool for operability.
- e. Lower the fuel-handling tool into the core and attach to element F28. Notify operator on the console that you are prepared to lift the fuel element. When acknowledged, lift fuel element from the core.
- f. Transfer element to a storage rack location and secure fuel handling tool cable,
- 1. Lift CET from the storage rack location and transfer to the reactor carriage, ensuring that the CET remains as low in the water as possible.
J. Notify the console operator that you are pre-pared to lower the CET into the core; when ack-nowledged, lower the CET into the core, ensur-ing that it is properly seated in the lower grid plate.
- k. With a downward pressure on the CET to keep it seated, secure the CET bracket with the two bolts.
- 1. Ensure appropriate entries are made in the op-erations logbook and the fuel book.
- 2. Irradiation:
- a. Clean the rabbit (s) using alcohol and water.
- b. Once clean, do NOT handle the rabbit except with gloves, Kimwipes, or handling tools,
- c. Ensure that the rabbit cap is secured tightly.
- d. Bring the reactor up to the appropriate power.
- e. Have another person drop or lower the rabbit into the core WITH THE CAP UP. Ensure that this individual spends a minimum amount of time in the vicinity of the carriage. Do NOT lower the rabbit with the extractor tool while at power.
- f. Complete irradiation and shut down reactor.
. g. Ensure appropriate entries are made in the op-erations logbook and the CET logbook.
- 3. Rabbit Retrievals:
- a. Ensure that a reactor staff member and a Safety
& Health Department (SHD) monitor are present in the reactor room and that they are wearing wrist dosimetry. If the CET is in the core, a reactor operator must monitor the console during the re-trieval.
- b. Test the rabbit extractor ("fishing pole") for operability.
- c. Insert the extractor head mechanism into the CET and reel out cable until you reach the low end indicator painted on the cable.
- d. Drop the extractor head firmly on the rabbit. ,
- e. Ensure the SHD monitor has a teletector posi-tioned near the CET top to monitor the rabbit.
- f. If the CET is in the core, notify the reactor operator that the rabbit is being pulled and continue when acknowledged.
- g. Reel in the cable at a rate commensurate with radiation levels; lower the rabbit back into the CET if the rabbit is excessively hot.
- h. Stop when upper end indicator is visible on the cable; have SHD take an accurate radiation reading.
- 1. If radiation levels are acceptable, swing rabbit away from carriage and have another individual grab it with a handling tool.
J. Release extractor head and detach rabbit from head. !
- k. Unless working with the rabbit, or radiation levels are very low (<1 mR/hr), store rabbit or irradiated material in a lead pig or storage cask.
- i. Make appropriate entries in the operations and CET logbooks.
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- 4. CET Removal from Core: I
- a. Complete steps la-d above. '
- b. Loosen the CET bracket bolts while holding the '
CET down; remove.the CET bracket.
- c. Notify the console operator that you are pre-pared to remove the CET. !
- d. When acknowledged, transfer the CET to the :
storage rack, ensuring that it is kept as low in -
the water as possible. !
- e. Secure the CET with cable ties. I
- f. Secure the CET bracket with the two bolts.
- g. Remove the fuel element from the storage rack :
and transfer to core. Notify the console op- !
erator and receive acknowlegement prior to insertion of element into fuel position F28. '
- h. Ensure the element is properly seated in the t lower grid plate by listening for the "double clicks". ;
- i. Make appropriate entries in the operations and :
fuel logbooks.
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TAB C: EXTRACTOR SYSTEM t
i GENERAL: The extractor system will be tested for oper-ability prior to the initial experiment for the !
day.
i SPECIFIC: :
- 1. Assembly of the extractor system: I'
- a. Inside the exposure room:
3 (1) Move the inside receiver section into po-
- sition in front of the core; screw tube supports to the floor and place lead bricks on them.
(2) While nolding the appropriate connecting j tube in position, tie the strings in the j tube to the two ends com:ng out of the ex-
. posure room wall and to the two ends in the i i receiver section.
1 (3) Align the ends of the tubes and slide the clamp over each joint. !
i (4) Place the alignment tools into the appro- !
j priate holes to check the tube allanment; !
i tighten down the clamps. i (5) Connect the electrical cable to the limit '
i switch, i (6) Remove the alignment tools. !
j b. Outside the exposure room: ,
i (1) Remove tube plug. L
- (2) Move the receiver section close to the tube "
a projecting from the wall. l (3) Tie the string from the end of the small ;
tube to the end of the wire cable.
(4) Pull the string in the large tube slowly I
! while having someone inside the room guide 4
4 the string. t
- (5) When the cable is all the way through both !
i tubes, thread the cable through the re- !
2 ceiver tube while moving the receiver table [
! into final position against the wall (if i 4 necessary, add an additional length of j
] cable to the take-up reel). [
j (6) While someone else is pushing the table !
toward the wall, insert two screws into the !
I holes on the securing bracket (beneath the I table). )
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(7) Position and tighten clamp over the joint:
position carrier in tube and connect cable to each end; remove the tape on the take- I up reel. I (8) Pull back on the drive motor assembly until there is no slack in the cables; tighten the adjustment bolts on the drive assembly.
(9) Connect the electrical cables to the motor, control unit, and limit switches.
- 2. Disassembly:
i
- a. Reverse the order of the above with the fol- :
lowing changes:
(1) Before loosening the motor assembly, place tape on the cable drum to keep the cable from moving (ensure the carrier is in the receiver section).
(2) Before pulling the cable through the tubes, attach a new string to it.
(3) Leave enough slack for disassembly inside the exposure room.
(4) Cut the string at the Joints in the room and tape the ends to the tubes.
- b. Ensure the tube plus is in place, and the con-trol unit is secured.
- 3. Operations:
- a. On the motor control, initially set controls as follows:
(1) Power switch: "0FF".
(2) Torque control: "0FF".
(3) In/out switch: "BRAKE".
(4) Speed control: "0%".
- b. Plug motor control into AC outlet; switch the power switch to "ON".
- c. Switch in/out switch to appropriate position.
- d. Slowly increase speed to an appropriate level; as the carriage approaches its full in/out po-sition, decrease the speed slowly to "0%".
- e. Turn the in/out switch to "BRAKE".
- f. During power operations, ensure that the fol-lowing requirements are met:
(1) The prep area is sealed off.
(E) A Safety & Health Department (SHD) monitor f is present.
TAB D: PNEUHATIC TRANSFER SYSTEM (PTS)
General:
- 1. This (PTS) procedure is inactive. If the PTS Facility is reactivated, then this procedure must be reviewed by the RRFSC and approved by the Reac-tor Facility Director.
- 3. All PTS operations will be directly supervised by a reactor operator present in the Hot Lab.
Specific:
- 1. PTS Setup:
- a. Position core at 833 (inside region III).
- b. Ensure communications are established between the hot lab and the control room.
- c. Inspect rabbits to be used in the PTS for cracks or other damage,
- d. Aluminum rabbits must be diverted to the Hot Cell and therefore may only be used on the "A" system.
- e. If the anticipated radiation level of any re-tarned rabbit is greater than 1.0 R/hr at one meter, take the following precautions:
(1) Use the remote control unit, unless exper-iment requirements dictate otherwise.
(2) Place a radiation survey meter next to the receiver / sender station so that it can be monitored frca the remote control unit.
(3) The rabbit will be irradiated in the "A" system and then diverted to the Hot Cell or returned to the irradiation location.
- 2. Manual Operations:
- a. Ensure all switches on both the local and re-mote control units are in the "OFF" position; place the local / remote switch in the desired position,
- b. Place blower switch in the "ON" position.
- c. Insert key into local control unit; turn key to "0N" position,
- d. Ensure tubes are empty, e, Set modo switch (man /off/ auto) to "MAN" posi-tion. Blower will start.
- f. Set in/out switch to the "OUT" position and the
tube on/off switches to "ON"; allow the system to run for a short time,
- g. Set tube on/off switches to "OFF" and turn in/
out switch to "IN".
- h. Load samples into tubes.
- i. Check communications with reactor operator at the reactor consol..
J. When the reactor is at the designated power level, set the tube on/off switches to "ON" one at a time, to send rabbits into the irradiation location.
. k. Begin stopwatch or timer.
- 1. Turn tube on/off switches to "OFF" and turn in/
out switch to "OUT".
- m. Ensure a Radiation Safety Department (SAF) mon-itor is present during retrievals,
- n. Set on/off switch to "ON" one at a time; rab-bits will return to sender / receiver station.
- o. Set all switches to "OFF", and remove key from control unit.
- 3. Automatic Mode:
- a. Complete steps 2a-d above.
- b. Set mode switch to "AUTO" position. Blower will start,
- c. Complete steps 2f-i above.
- d. Set timer (0 to 5 minutes) by turning the red and black arrows to the desired irradiation time.
- e. When the reactor is at the desired power level, briefly push the timer push botton and release.
The rabbits will leave the receiver / sender sta-tion and will automatically return at the end of the preset irradiation period. The timer will automatically reset.
- f. Turn all switches to "OFF" and remove key from the control unit.
- 4. Diverting Samples:
- a. Diversion of samples to the Hot Cell may only be made using the "A" system,
- b. After the rabbit has returned to the receiver /
sender station, set the divert / send switch to "DIVERT" and hold it until the loading port handle trips to the rear position.
- c. Send the divert /sond switch to "SEND" and hold for a few seconds. The rabbit will leave the receiver / sender station and travel to the Hot Cell.
PROCEDURE II REACTOR STAFF TRAINING
- 1. The reactor staff training is delineated in the current "AFRRI Reactor Operator Requalification Program".
- 2. The Reactor Facility Director (RFD) determines who is allowed into the training program. As part of the training /requalification program, the following will be performed:
- a. A training file will be maintained for each trainee / operator,
- b. When a section of training is completed, it will be annotated on the training checklist in each file,
- c. A record of operations will be kept for each trainee / operator.
TAB E: IN-POOL /IN-CORE EXPERIMENTS j
i General: ALARA principles will be followed during these experiments, These procedures apply to all in-pocl or in-core experiments except CET operations (See Procedure I-Tab B).
Specific:
- 1. All operations will be supervised by an SRO.
- 2. Actions will be taken to prevent damage to the reactor core or aluminum tank,
- 3. The removal of experiment materials frem ths pool or core will be monitored with a radiation survey meter; additionally, a reactor operator will mon-itor the reactor console during insertion and re-moval of in-core experiments.
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l PROCEDURE III MAINTENANCE PROCEDURES i
General: Maintenance procedures are provided in other references.
Specific:
- 1. Preventative Maintenance procedures for each item of the reactor syttems are provided in the main- '
tenance logbook.
- 2. Annual shutdown procedures are given in the Annual Shutdown Checklist which is revised each year by the Reactor Operations Supervisor (ROS) and ap-proved by the Reactor Facility Director.
- 3. Malfunctions are annotated in the Malfunction Log-book. Each entry is made by the operator who dis-covered the deficiency. When corrective actions have been made and annotated in the malfunction logbook, the RFD or ROS shall review and initial the entry.
- 4. Procedures for maintenance of specific equipment are provided in the manufacturers' literature.
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l PROCEDURE IV PERSONNEL RADIATION PROTECTION General: All activities performed in areas of potential personnel radiation exposure will be done in accordance with ALARA principles. These areas are the reactor room, upper equipment room (3152),
lower equipment room (2158), warm storage, prep area, exposure room 1, exposure room 2,and the hot lab / cell.
Specific:
- 1. Reactor Room:
- a. CET Operations: See Procedure I-Tab B.
i
- b. Working inside chained in area around pool:
The reactor operator on the console shall be responsible for controlling entry into the chained area around the pool.
- 2. Warm Storage: See HPP 3-3.
- 3. Prep Area: See Prep Area Briefing.
- 4. Exposure Rooms: See HPP 3-1 and Procedure I-Tab A.
l 5. Hot Lab / Cell: See HPP 3-5 and Procedure I-Tab D.
- 6. Upper and Lower Equipment Rooms:
1
- a. No written radiation protection procedures are required for entry into these rooms.
- b. Access to these areas is controlled by the AFRRI Reactor Physical Security Plan.
- 7. Personnel Dosimetry and Monitoring: See HPP 3-1, 3-2, and the Prep Area Briefing.
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i PROCEDURE V PHYSICAL SECURITY 1
I i
General: Physical Security requirements are given in the AFRRI Reactor Physical Security Plan.
Specific:
- 1. The reactor control room will be secured if no reactor staff member is present for a prolonged 4
period of time during duty hours.
- 2. Control of keys is delegated to the Reactor Opera-tions Supervisor. Key inventories will be performed annually, not to exceed 15 months.
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i PROCEDURE VI EMERGENCY PROCEDURES General: The reactor emergency organi:ation, emergency classes, and emergency action levels are set forth in the current copy of the AFRRI Reactor Emergency Plan.
Specific: Perf orm the f ollowing, as appropriate (need not be done in order). l
- 1. Reactor Emergency: I
- a. SCRAM reactor.
- b. Check radiation monitors; use portable survey instruments to assess situation, i if necessary.
- c. Notify EAS Commander of situation.
- d. Activate emergency organisation.
- 2. AFRRI Complex Emergency Evacuation:
- a. SCRAM reactor.
- b. Secure any exposure facilities which are in use,
- c. Remove logbook, emergency guide, radios, teletector, tool kit, and keys; report to EAS.
- d. Do NOT lock reactor area doors.
L a
e PROCEDURE VII REACTOR CORE LOADING AND UNLOADINO General: Loading and unloading of the reactor core shs11 be under the supervision of the Reactor Facility j
Director or the Reactor Operations Suptrvisor.
{ These procedures are superseded in ths following situations: during CET Operations (see Procedure I-Tab B) and during annual shutdown maintenance (see the current Annual Shutdown Checklist).
3 Specific:
- 1. Setup
- a. Ensure at least one nuclear instrumentation channel is operational.
- b. Ensure an operator monitors the reactor console j during all fuel movements.
- c. Check new fuel elements prior to insertion into 1
the core: this includes cleaning, visual inspec-tion, and length and bow measurements.
j
- d. If irradiated fuel elements are to be removed unshielded from the pool, a Special Work Permit 1
(SWP) will be obtained from the Safety & Health j Department'(SHD); fuel elements with a power i
history (greater than 1 KW) in the previous two
? weeks shall not be removed from the reacto-
{ pool.
- 2. Core Loading
! a. After each step of fuel movement perform the l following:
i (1) Record detector readings.
! (2) Withdraw control rods 50%; record readings.
4 (3) Withdraw control rods 100%; record readings.
l (4) Calculate 1/M.
i (5) Plot 1/M versus number of elements (and total mass of U-235).
! (6) Predict critical loading.
l (7) Insert ALL rods; continue to next step.
I
- b. Load elements in the following order:
(1) Load the "B" ring thermocouple element.
(2) Load the "C" ring thermocouple element.
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(3) Install temperature measurement system (to l l
measure fuel temperature. [
(4) Install any other thermocouple elements. l (5) Complete loading of "B" and "C" rins !
elements (total of 18 elements).
, (6) Load "D" ring (total of 33 elements) 4 (7) Load the following "E" ring elements: l 1.2.4.6.8.9.10.12.14, 16.17.18.20.22.21 ,
(total of 48 elements). !
(8) Complete the "E" ring (total of 57 ele-ments).
(9) 3 Load the following "F" ring elements: ;
i 1.5.9.13.17.21.22.23 27 (total of 66 !
elements). ;
j (10) Load two elements per step until critical loading is achieved.
(11) Load core to s2.00 excess reactivity.
(12) Estimate control rod worth using rod drop techniques.
~i (13) Estimate the control rod worth of the re-maining unloaded elements.
(14) Load the core to achieve a K-excess that will allow calibration of the TRANS rod based on the last available worth curve of the TRANS rod.
(15) Calibrate the TRANS rod.
1 (16) Estimate the shutdown margin.
j (17) Estimate K-excess with a fully loaded core (must not exceed 85.00).
(18) Load core to fully operational load and re-calibrate all control rods.
_I 1 3. Core Unloading:
i a. The reactor core will be unloaded starting with l "F" ring and ending with the "B" ring.
j b. The fuel elements will be individually removed a from the reactor core, identified by serial i number, and placed in either the fuel storage racks or a shipping cask.
- c. If elements are to be loaded into a shipping cask. perform a complete cleaning of the cask and check for radiologieni contamination prior to placing the cask in or near the pool. Load cask in accordance wit.h procedures specific to the cask.
- d. Once the cask is loaded, perform an air sample and survey; check temperature and pressure in-side cask, if necessary.
- e. If elements are placed in temporary storage away from core monitoring, insure criticality moni-toring in accordance with 10 CFR 70 is in place.
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PROCEDURE VIII REACTOR OPERATIONS General: Logbook entries will be made in accordance with g the Logbook Entry Checklist (Tab A). t_.
Specific:
- 1. Each line on the daily and weekly checklists shall be initialed by the Reactor Operator or Trainee who performs that item. -
- 2. Perform reactor daily operational startup checklist "
(Tab B), utilising appropriate nuclear instrumen- '
tation set points (Tab C). -
- 3. Record in logbook who the SRO On-Call is.
- 4. Perform K-excess measurement (Tab D).
- 5. Perform operations in accordance with the follow-ing:
- a. Steady state operation (Tab E).
- b. Square wave operation (Tab F).
- c. Pulse operation (Tab G).
- d. CET operations (Procedure I, Tab B). '
- e. Pneumatic Transfer System (Procedure I, Tab D).
- 6. Perform weekly operational instrument checklist once during calender week (TAB H).
- 7. Upon completion of operations for the day, perform daily operational shutdown checklist (Tab I).
- 8. Complete the monthly summary (Tab J).
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TAB A: LOGBOOK ENTRY CHECKLIST
- 1. The reactor operations logbook is a before-the-fact record, that is, entries will be logged before the operator actually performs the planned function. Any late entries will be so noted.
- 2. The operations logbook will have a hardbound cover and will be sequentially numbered by volume. The pages will be dated at the top of each page and each page will be sequentially numbered.
- 3. The Reactor Facility Director (RFD) will review each logbook upon its completion; he will make an appropriate entry in the back of the logbook and sign the entry.
- 4. The entries will be made in ink and in accordance with the following designated color code:
- a. Black and Blue-Black:
l (1) Console locked and unlocked. The individual at the console will enter his/her name and the su-pe rvisory licensed operator's name, if neces-i sary.
l (2) Checklist number and completion time.
(3) Power level at criticality and subsequent power I level changes.
l (4) Reactor SCRAM.
(5)
Mode of operations. Use appropriate stamp or entry ta designate the operation:
(a) Mode I or IA Steady State (b) Mode II Square Wave (c) Mode III Pulse (6) Operation of reactor associated facilities such as lead shield doors pneumatic tube systems, etc., unless such operations cause a change of reactivity (see 4.b.(2) below).
(7) Change of personnel at the console. Name of personnel will be entered along with the licen-sed operator present in the contrcl room, if the person at the console is not a licensed operator.
(8) Completion of the daily startup and shutdown checklists, and weekly checklists.
(9) Signature of reactor operator to close out the I log for the day.
I (10) Reactor calibrations and data.
k _ _ .- - _ _ _ . . . _ _ _
- b. Red.
(1) K-excess measurements, to include experiment worth determinations.
(2) Actions which affect reactivity:
(a) Core movement.
(b) Fuel movement.
(c) Control rod physical removal for mainten-ance.
(d) Experiment loading and removal from the CET, PTS, pool, or core.
- c. Green.
(1) Reactor malfunction,to include the reactor sys-tems and support equipment taken out of service for maintenance and returned to service.
(2) Additional items entered at the discretion of ll the operator such as addition of makeup water to the reactor pool, etc.
- 5. When an operation requiring entry into the logbook falls under more than one color code, the color to be used will be determined via the following order of prece-dence: RED - GREEN - BLACK / BLUE-BLACK.
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TA5 3 : A :l'. .: I .:, ~ ~ . ' . - : ' . .! ' - 7
.i ._ - '
Checklist 2 DATE SENIOR SRO PRESENT/ON CALL _ _____ PERFOR.9ID BY ____
'~~~~~
OPERATORS TIME COMPLETED ___
I. EQUIPMENT ROOM (RM - 3152)
- 1. Gas Stack Monitor and cooling air elower QH . ... ..
- 2. Air compressor pressure (psi) . .. .. .... . ... ... ..
~
- 3. Air compressor water trap DRAINED .. . . ..
~
- 4. Air Dryer Operating ... ... . .................... . .
~~~
l
- 5. Doors 231,231A, 3152, and roof hatch SECURED ...
I II. LOBBY AREA Lobby Audio Alarm turned QEZ ........... .. .. . ... ..
III. EQUIPMENT ROOM (RM-2158)
I 1. Prefilter differential pressure .................... ..
- 2. Primary Discharge Pressure (PSI) ................... .. ;
- 3. Demineralizer flow rates set to 6 gym ................
- 4. Stack roughing filter $p (inches of water) ............ _
- 5. Stack absolute filter 89 (inches of water) . .
- 6. Visual inspection of area ....... ... ......... ... ..
- 7. Door 2158 SECURED .. . .... . .. .. .... .... .
1 IV. PREPARATION AREA Visual Inspection of Area .............................
l 8 V. REACTOR ROOM (RH - 3161) }
l
'l. Transient Rod air pressure (psi) ...................... _._
l 2. Shielding doors bearing air pressure (psi) .......... .
- 3. Tank water level below full mark (inches) ............
,4. Visual inspection of core and tank ....................
- 5. Number of fuel elements and control rods in fuel l tank storage control
- 6. Air particulate monitor (CAM) ,
(a) Operating and Tracing .... ........... .... . . . _'
(b) Alarm test complete ............................... ,
- 7. Door 3162 SECURED ... . ....... ... .. .. . _-
- 8. Stack Gas Monitor Quality Assurance Checked ..... .... _
AFFRI FORM 61(R) revised: 18 Dec 1988
VI. REACTCR CCNTRCL RCCM
- 1. Emergency Air System RESET ---
- 2. Console Recorder DATED ... . .. . . . .... ..- ~
- 3. Stack Gas & Fuel temp. Recorder DATED . .
- 4. Logbook DATED and REVIEWED .. . ........ .. ..... . ..
- 5. Water Monitor Box a) Background activity (mA) .... ........... . .... ..
b) Alarm test completed and alarm reset to 0.5 mA . . .
c) Water monitor box conductivity (HQ-cm] .............
d) DM1 conductivity (HQ-cm) ......... ......... ......
e) DM2 conductivity (HQ-cm) ...........................
(all conductivities must be > 0.5 MO-cm)
- 6. Stack Gas Flow Rate (Kcfm] ........................... __
- 7. Gas Stack Monitor a) Background (cpm) ...................................
b) Alarm Check ..... ... ...... ... .. ......... .
c) High Alarm set to 1.5 E3 epm .. ...................
- 8. Stack Particulate Monitor a) Background (cpm) .. .. . ... . ............. ..
b) Alarm Check . . .............................
c) High Alarm set to 2.0 E3 cpm ................... ...
- 9. Radiation Monitors ALARM POINT READING ALARM SETTING MONITOR Functional (mR/hr) (mR/hr) a) R-1 500 .
b) R-2 10 c) R-3 10 d) E-3 10 e) E-6 10 f) R-5 50
- 10. Timer ON .............................................
- 11. TV Monitors ON ....................... ..............
- 12. Beeper System ON .......... ........... .......... ..
- 13. Source level on log channel 2 0.5 cps .......... ...
- 14. Check 0.5 cps source RWP .............................
- 15. Time delay OPERATIVE ................... ....... . .. __
- 16. OPERATIONAL CHANNELS Cal. Log Switch Pos. # Range Switch % Linear % Log 1 0.3 watts 2 30 watts 3 300 watts 4 1 kw 5 10 kw 6 3 Mw
- 17. Rod raising interlock for Mode I .....................
- 18. Rod raising interlock for Mode III ...................
- 19. Zero Power Pulse (obtain signal w/ trip test) .........
- 20. SCRAM CHECKS (Ensure each rod is checked w/at least one scram) a) Safety Flux 1 g) Emergency Stop b) Fuel Temp 1 h) Pool H2O level c) HV loss safety 1 i) Fuel Temp 2 d) Manual j) Safety Flux 2 e) Reactor Key k) HV loss safety 2 f) Timer
- 21. Water Temperature (INLET)....................... ....
- 22. Period trip test for 1 kw interlock............. .. __
- 23. CAM high level audible alarm check.......... . . . __
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/-
DAILY SAFETY CHECKLIST PROCEDURE General: It is intended that this procedure only be in effect for periods of extended down-time.
"Extended down-time" is considered to be those periods where no Reactor Operations are planned for three or more consecutive duty days. Com-pletion of a full Startup Checklist always sat-isfies this requirement.
Specific: 1. The attached Daily Safety Checklist may be used on duty days when the reactor facility is opened, but no reactor operations are planned.
- 2. If operations are planned, the Daily Opera-tional Startup Checklist provided in Pro-cedure VIII will be used.
- 3. If operations are planned after a Safety Checkliat is completed, a regular checklist will be completed; items previously checked on the Safety Checklist may be transferred to the Operational Startup Checklist. Both the Safety Checklist and the operational Startup Checklist will be retained.
TAB B1: DAILY SAFETY CHECKLIST Checklist s DATE SENIOR SRO PRESENT/ON CALL PERFORMED BY l OPERATORS TIME COMPLETED l
- 1. EQUIPMENT ROOM (RM - 3152) l
- 1. Gas Stack Monitor and cooling air blower QH ...........
- 2. Air compressor pressure (psi) .........................
- 3. Air compressor water trap DRAINED .....................
i
- 14. Air Dryer Operating ...................................
l
'5. Doors 231,231A, 3152, and roof hatch SECURED ..........
l l l
l II. LOBBY AREA Lobby Audio Alarm turned QZZ ..........................
1 1
III. EQUIPMENT ROOM (RM-2158)
- 1. Profilter differential pressure .......... ............ I
- 2. Primary Discharge Pressure (PSI) ......................
- 3. Demineralizer flow rates set to 6 gpa .................
- 4. Stack roughing filter op (inches of water) ............
I 5. Stack absolute filter 6p (inches of water) ............
- 6. Visual inspection of area .............................
- 7. Door 2158 SECURED .....................................
l l
l IV. PREPARATION AREA l Visual Inspection of Area .............................
AFRRI FORM 61a (R) Revised: 18 Dec l
! V. REACTOR ROOM (RM - 3161)
- 1. Transient Rod air pressure (psi) ......................
I 2. Shielding doors bearing air pressure (psi) ..... ......
- 3. Tank water level below full mark (inches) ............
- 4. Visual inspection of core and tank .................
- 5. Number of fuel elements and control rods in fuel tank storage control
- 6. Air particulate monitor (CAM) 1 (a) Operating and Tracing ...... ......................
(b) Alarm test complete ...............................
l
- 7. Door 3162 5ECURED ....................................
- 8. Stack Gas Monitor Quality Assurance Checked ...........
VI. REACTOR CONTROL ROOM
- 1. Emergency Air System RESET .............. ............
i 2. Console Recorder DATED ...........................
- 3. Stack Gas & Fuel temp. Recorder DATED .................
- 4. Logbook DATED and REVIEWED ...........................
- 5. Water Monitor Box a) Background activity (mA) ...........................
b) Alarm test completed and alarm reset to 0.5 mA ....._
c) Water monitor box conductivity (HQ-cm) .............
d) DM1 conductivity (MQ-cm] ...........................
e) DH2 conductivity (HQ-cm] ...........................
(all conductivities must be > 0.5 HQ-cm)
- 6. Stack Gas Flow Rate (Kcfm) ...........................
- 7. Gas Stack Monitor a) Background (cpm) ............ .....................
b) Alarm Check . .................................
c) High Alarm set to 1.5 E3 cpm .......................
- 8. Stack Particulate Monitor a) Background (cpm) ...................................
b) Alarm Check ...................................
c) High Alarm set to 2.0 E3 cpm .......................
- 9. Radiation Monitors ALARM POINT READING ALARM SETTING MONITOR Functional (mR/hr) (mR/hr) a) R-1 500 b) R-2 10
.c) R-3 10 d) E-3 10 e) E-6 10 i f) R-5 50
- 10. TV Monitors ON ......... .............................
- 11. Beeper System ON .....................................
- 12. Source level on log channel 2 0.5 cps ................
- 13. Wat e r Tempe ratu re ( IN LET ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 14. CAM high level audible alarm check....................
l
TAB 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 nonconservative 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: Loss of 20%
- d. Pulse Timer: 0.555 seconds
- e. Steady State Timer: as necessary
- 2. Rod Withdrawal Prevents:
- a. Period: 3 seconds
- b. 1 KW (Pulse Mode): 1 KW
- c. Source: 0.5 CPS
- d. Water Bulk Temperature: 50 'C
- e. Fission Chamber HV Loss: 20%
- 3. Alarms:
- a. RAMS: As directed in procedures
- b. CAMS: 10,000 CPM
- c. Stack Gas: 1.5E+3 CPM
- u. Stack Particulate: 2.0E+3 CPM
- e. Water Monitor Box Gamma: 0.5 mA
- f. Criticality Moni. tor (RS): 50 mR/hr day -
20 mR/hr night or as directed l
TAB D: K-EXCESS
- 1. Withdraw SAF and SHIM rods 100% and withdraw the TRANS rod 25%.
e jb
- 2. Use tne REG rod to bring the reactor to cold critical at <
15 watts. If criticality can not be reached with the REG rod full out, use the TRANS rod to bring to criti-cal.
- 3. When power is stabilized at 15 watts, record rod posi- ,l tions in reactor operations logbook, entering all infor-mation in red ink.
- 4. Using rod worth curves, compute K-excess for the core position
- used and record in the reactor operations log-book and on the Monthly Summary Sheet.
- Note: Use the curves for position 567 when doing K-excess at 290. .
s
)
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TAB E: STEADY STATE OPERATION (MODE I/IA)
General: The reactor shall not be operated at a power greater than 1.0 MW.
Specific:
- 1. Set the linear channel range select switch to the appropriate scale for the desired power (at this power the linear pen should be as close to 50% es possible).
- 2. Set the mode switch to manual mode.
- 3. Raise control rods with the appropriate banking, taking into consideration the location in the pool, power level, and experiment array.
- 4. If final approach to critical is to be made in auto-matic mode, perform the following:
- a. Set the proper percentage on the flux control to obtain the desired power.
- b. Raise the TRANS, SAFE, and SHIM rods to the appropriate banking.
- c. Raise the REG rod approximately 5%.
- d. When the servo has locked in, switch to auto-matic mode.
- e. When the reactor reaches critical, fine tune the flux control for the desired power.
- 6. Ensure the appropriate entries have been made in the operations logbook.
Note: For runs greater than 800KW, adjust alarm points on R-1 and R-5 to full scale.
TAB F: SQUARE WAVE OPERATION (MODE II)
General: The square wave modo can not be used above 900KW.
Spect.fic:
- 1. If appropriate, set timer for run duration and flip =
timer SCRAM switch to "GN".
- 2. Set the TRANS drive anvil as follows:
- a. If the TRANS rod is not to be used for criti- ,
cality, use the applicable rod worth curve to L determine the anvil position for a 75 cent in-sertion and raise the anvil to that position. -
Adjust the REG rod to 90 percent; achieve criti-cality using the SHIM and SAFE rods.
- b. If the TRANS rod is to be used for criticality, drop the TRANS rod and proceed as outlined in 2a. above.
l 3. Adjust power range select switch to the desired 1 range.
- 4. Set square wave percent demand dial to 80 percent of final desired power.
- 5. Set flux controller dial to final desired power level.
- 6. Switch into square wave mode, making sure the TRANS rod ready light is "ON".
- 7. Depress ready / fire button.
- 8. After the servo has locked in, raise the square wave percent demand dial setting to the final desired l power.
1
- 9. Switch to manual mode and lower REG rod to 80 per-l cent while raising the TRANS rod; maintain desired l I power level and then switch to automatic mode.
l l
- 10. Scram the reactor with the timer or manually, as -
appropriate; move the core if applicable.
- 11. Ensure all pertinent information has been logged in the reactor operations logbook.
PULSE OPERATION (MODE III)
G:n=ral: Pulses above $3.50 must be approved by the RFD or ROS. Specifi-cation on the RUR may be used to meet this requirement.
Sp;cific: For pulses fired from COLD CRITICAL, omit steps 2, 5, 6, and 8.
For pulses fired from SUBCRITICAL, omit step 7.
- 1. Set the alarm points on R-1 and R-5 (the criticality monitor) to full scale.
- 2. Given a core position, set the transiest rod at a position correspond-ing to the dollar value determined by the following equation:
$ Value - Total Worth ($) TRANS Rod - Desired Pulse (3) Value
- 3. Bring the reactor to cold critical (15 watts) with the three standard rods, using a rod configuration commensurate with core position.
- 4. Stabilize in manual mode.
- 6. Raise the transient rod anvil to 100%
- 7. Raise the transient rod anvil to the desired pulse position. ,
- 8. Let the power decay to approximately one watt.
- 9. Place power range select switch on the "3 MW-PULSE" position.
- 10. Place mode select switch in "PULSE HI" (greater than or equal to $2.15) or "PULSE LO" (less than $2.15) position, as appropridte.
t 11. Fire pulse by depressing "READY" button on the console (Note:
power must be below 1 KW).
- 12. Record data in the reactor operations logbook as follows:
s
- a. NVT: Read from Safety Channel 2/NVT meter on right side of console. Multiply Safety channel 2/NVT meter reading by 1.2 to obtain actual NVT reading in MW-s, 36.0 MW-s is full scale.
- b. NV: Read black pen on chart recorder, center of console with the following scales:
(1) Pulse Hi Switch: 100% - 3000 MW (2) Pulse Lo Switch: 100% - 600 MW l
- c. Fuel Temperature: Read red pen of chart recorder, center of console, where 100% - 600 C t 13. Reset mode select switch to manual mode after readings are recorded.
I
- 14. Reset R-1 and R-5 ta their normal alarm points.
TAB H '
WEEKLY OPERATIONAL INSTRUMENT CHECKLIST CHECKLIST No. DATE PERFORMED BY REVIEWED BY
- 1. SAFETY CHANNEL ONE A. Aaise rod =w2%. decress and reteese switen raarved av 2 in left hand drawer. ocserve and reset scram .
S. Rotate Ocerate switen to tero cnect '*ettf for tero. reset scram C. Aotate ccerate switen to cancrate. c'ect meter for 100 %. reset scram
- 11. OPERATIONAL CHANNEL HIGH VOLTAGE Cecress and nold in switen HV Je 1 'n 'ef t mano drawer Attemot to raise contrei rod Ill. SAFETY CHANNEL TWO A Aaise rod ~2%. decress and release switen MV trio test in regnt nand Orawer.
C:sene and reset scram . . ..
B. Actate ocerate sWiten to tero, enect *eter for lefo. reset scram C. Rotate ocerate switen to cancrate cnect i-eter for 100 %. reset scram IV. NV NVT A. NV. In manual mode, sat 20% on safety enannel se 2 with trio test knoe. Switch to oulse Hl. chart tecorder snould read 20%. Aeoest for 40%. 60%. 80%. and 100%. Check scram at 110% . .
e
- 8. NVT Check NVT circuit ey orocedure 3 3 5.2 theougn 3.3.5.4 in console maintenance manual.
l l V. FUEL TEMPERATURE NO.1 Rotate switch to calibrate position, ooserve 100% on meter, reset seam . .
VI. FUEL TEMPERATURE NO. 2 Rotate switen to cahbrate ecsition, ooserve 100% on meter. reset scram .
Vll. WATER LEVEL INDICATOR A. In cool, east side, deoress float on water levelindicator . _ _ . _ . ,
B. Ceserve scram on console, (scram indication should reset automatically) .
l Vill. WATER CONDUCTIVITY L st resistivity readings for previous week from daily startup enecklists. Determine that average at each point s greater : an 0 5 M G cm.
MON TUE WE0 THU FRI A VE Vonitor Box OM1 OM2 IX. R ADI ATION MONITORS A. Test alarm ' unctions for nign level and failure HIGH Level Monotor failure Alarm functional Alsem functional A .1 R.2 E3 E.6 R 5 (criticahty)
Aeactor Rm APM Gas Stacx Monitor - 3 3 Aeset Atar~s AeRRtPORM96 (PREVIOut EDiflONS QP TMt3 POAM A AR 0000tttt.)
19 OCT 84 l
l l
l TAB I: DAILY OPERATIONAL SHUT-DOWN CHECKLIST Checklist
- 1. All rod drives DOWN ............................
- 2. Carriage lights OFF ............................
- 3. Door 3162 SECURED ............................
- 4. Door 3161 locked with key ......................
- 5. Print out an hourly report from the Stack Gas Monitor .....................
II. EQUIPMENT ROOM (RM 3152)
- 1. Distillation unit discharge valve CLOSED ......
- 2. Air Dr.ar OPERATIONAL .........................
- 3. Doors 231, 231A, 3152 and Roof Hatch SECUREE .........................
III. EQUIPMENT ROOM (RM 2158)
- 1. Primary discharge pressure (PSI) ..............
- 2. Demineralizer flow rates set to 6 spa .........
- 3. Visual inspection for leaks ...................
- 4. Door 2158 SECURED .........................
IV. PREPARATION AREA
- 1. ER 2 plus door CONTROL LOCKED; door CLOSED and handwheel PADLOCKED ...........
- 2. ER 2 lights ON and rheostat at 10% ............
- 3. ER 1 plus door CONTROL LOCKED; door CLOSED and handwheel PADLOCKED ...........
- 4. ER 1 lights ON and rheostat at 10% ............
- 5. Visual inspection of area .....................
l AFRRI FORM 62 (R) Revised: 18 December 198
t V. LOBBY AREA Lobby Alara Audio QM ..........................
r VI. REACTOR CONTROL ROOM (RM-3160) '
- 1. Reactor tank lights OFF .....................
- 2. Timer OFF ..................................
- 3. TV Monitors OFF .............................
- 4. Console LOCKED .............................
- 5. Diffuser and Secondary pumps OFF ............
- 6. Purification and Primary pumps ON ...........
- 7. Turn off Beeper System ......................
- 8. Reactor Monthly Usage Summary complete ......
- 9. Turn off Exposure Room Camera 3 Power Supply ..............................
- 10. Coffee Pot Off ............................. I
- 11. Radiation Monitors ...................... 1
+._______________________________________________+ y l MONITOR READING HIGH-LEVEL ALARM l l SETTING (mR/hr) l
+________________________________________________+
a) R-1 20 b) R-2 NA c) R-3 NA d) R-5 20 (criticality) e) E-3 NA f) E-6 NA g) R-6 NA (stack)
TAB J REACTOR MONTHLY USAGE
SUMMARY
POSITION STEADY STATE / PULSES K. EXCESS NUMBER NUMBER PULSES TOTAL TOTAL TOTAL U NP LAN.
AT ST A RT- 0F 2 ER NO.1 CENTER TUBES ER N0.1 OTHER STEADY PULSE POWER SHUT-POSITION UPS PULSES $2.00 (231) (547) (833) (903) ( ) STATE POWER 00WNS TOTALTO 833 TOTAL TOTAL POWER l TOTAL _
DATE TOTAL CA R RY.0V E R h % h - b ONN ,
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l i I i l P.Tt: l AF ARI FORM 74 6 JULY 82 MONTH -
TAB K STACK GAS MONITOR PROCEDURES GENERAL: This procedure specifies all the requirements for operation of the Stack Gas Monitor (SGM) in the reactor room. This instrumentation is used to monitor, measure, and record the amount of Argon-41 released to the environment through the reactor stack.
SPECIFIC:
- 1. QUALITY ASSURANCE PROCEDURES: A quality assurance check is performed dailye prior to reactor operations, as part of the reactor start-up. This check is performed in the following manner:
- a. The particulate filter is changed and the old fil-ter is discarded as radioactive waste.
- b. The date and time of this quality assurance check is entered in the log.
- c. The Detector voltage system set point is checked and recorded in the log.
- d. The air sampling flow rate (should be greater than 3.5 cubic feet per minute) is recorded in the log.
- e. The front cover of the detector shield is removed and the check source is inserted all the way in to the face of the detector. The blue alert light should come on as the count rate rises above I the alert setpoint. The red high level alert light l and bell should come on as the count rate rises above the high level setpoint. The audible alarm can be silenced by pushing the red button on the front of the SGM cabinet.
- f. After 5 minutes have elapsed, an historical one minute report printout should be made and the counts per minute for the third minute of high level readings ahould be recorded in the log.
- g. The alarms should be acknowledged in the log with the initials of the person performing the check and on the SGM by pushing the "acknowledge" button on the keyboard.
- h. The check source should be removed and the detector cover should be replaced.
l l
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- i. Finally, the counts per minute reading (paragraph 2f) should be checked against the plot of counts per minute versus Julian date to determine if it falls within a plus or minus 5% deviation for l the detector and check source. This check provides the necessary quality assurance for the SGM system prior to conducting any reactor operations for the day.
- 2. HISTORICAL REPORT REQUIREMENTS: There are two his-torical report requirements for proper documentation of argon-41 releases. ,
- a. The SGM automatically prints out the amount of argon-41 released every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Each of these 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reports must be taped into the historical release data log.
- b. Finally, at the end of each day, as part of the reactor shutdown, an historical one hour report should be printed and taped into the historical release data log. This report contains the average counts per minute for each of the 30 previous hours, This information can be used to calculate the amount of argon-41 released through through the reactor stack.
- 3. SYSTEM CHANGES OR OBSERVED ABNORMALITIES: Any changes to the system set points or observed abnormalities should be reported immediately to the Reactor Facility Director and to the Safety & Health Department.
N
PROCEDURE IX REACTOR ROOM SAFETY General: The following safety procedures will be observed while in the reactor room. l Specific: _
- 1. Hoist Operations: Perform the following before/
during any hoist operations:
- a. Inspect any lifting equipment (ropes, cables, ;
etc.) for wear or damage prior to use.
- b. Ensure that the hoist has a current load-testing .
g (within last 12 months). ]
Ensure areas beneath the hoist are clear of per-
~
- c. ,
sonnel when operations are underway. This is particularly important when using the hatches ,
between several floors.
- d. Each time a load approaching 10,000 pounds is handled, test the brakes by raising the load a few inches, applying the brakes and checking for
, slippage,
- e. Ensure a load is not lowered below the point where two full wraps of cable remain on the drum.
- f. Ensure no tools or poles longer than 10 feet are raised vertically in the reactor room.
- 2. Mercury thermometers are not allowed in the reactor room at any time.
- _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _