ML20101D579

1995 Annual Rept of Afrri Triga Reactor. W/Undated Ltr

ML20101D579
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	12/31/1995
From:	Maria Moore ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9603210007
Download: ML20101D579 (100)

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ARMED FORCED RADipBIOkOGY RESEARCH INSTITUTE 8901 WISCONSIN AVENUE BETHESDA. MARYLAND 20809-5603 RSDR

SUBJECT:

Submission of Annual Report U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 1

Dear ached please find the 1995 Annual Report for the AFRRI TRIGA reactor facility,

submitted as required by license R-84, facility docket 50-170.

Should you need any further information, please contact the undersigned at (301) 295-1290.

Attachment

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MARK MOORE (

as stated Reactor Facility Di tor

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U.S. Nuclear Regulatory Commission ATTN: Mr. Marvin Mendonca, Mail Stop 11B20 ,

Washington, DC 20555 l Regional Administrator U.S. Nuclear Regulator Commission, Region I ATTN: Mr. Thomas Dragoun 475 Allendale rom King of Prussia, Pa.19406 1

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l Submission of 1995 Annual Report .

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i' l Submitted by 4 8 h o- 94 MARK L. MOORE i Date l Reactor Facility Director i

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ERIC E. KEARSLEY U Date Captain, MSC, USN Diiector l l

Armed Forces Radiobiology Research Institute AFRRI Triga Reactor Facility 1 January, 1995 - 31 December,1995 To satisfy the requirements of:  ;

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

Technical Specification 6.6.1.b. ,

The Reactor Facility Director would like to acknowledge the participation of the following AFRRI personnel for their contributions to this annual report.

Edited by: '

Mr. Robert George, Reactor Operations Supervisor ,

With Contributions From:

LTC Ixonard Alt, Senior Staff Engineer Mr. Guy Bateman, Scientific Medical Illustrator SFC Danny McClung, Senior Reactor Operator Candidate Mr. Steve Miller, Deputy Reactor Facility Director Mr. John Nguyen, Senior Reactor Operator Mr. Tom O'Brien, Radiation Safety Officer Submitted By:

Mark Moore Reactor Facility Director Armed Forces Radiobiology Research Institute 8901 Wisconsin Ave.

Bethesda Md. 20889-5603 Telephone: (301) 295-1290 Fax: (301) 295-0735

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i 1995 ANNUAL REPORT '

OFTHE AFRRI TRIGA REACTOR

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J Docket 50-170 License R-84 Submitted By Mark Moore Reactor Facility Director

1995 ANNUAL REPORT TABLE OF CONTENTS Introduction General Information Section I ,

Changes to the facility design, performance characteristics and operational procedures, results of surveillance tests and inspectionsSection II Energy generated by current reactor core and number of pulses $2.00 or larger Section III Unscheduled shutdownsSection IV l Safety-related corrective maintenance l Section V Facility changes and changes to procedures as described in the Safety Analysis Report. l New experiments or tests during the year j Section VI Summary of radioactive effluent released Section VII Environmental radiological surveysSection VIII I Exposures greater than 10% of 10 CFR 20 limits Attachment A Revised Reactor Administrative and Operational Procedures Attachment P, 10 CFR 50.59 safety evaluations of modifications, changes, and enhancements to prxcaures or facilities Attachment C Appointment letters for various Reactor and Radiation Facility Safety Committee changes Attachment D Summary of all Maintenance for 1994

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4 NTRODUCTION

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1995 ANNUAL REPORT

! INTRODUCTION j

In 1995 the AFRRI reactor facility was available for irradiation services throughout the year with  !

, only the annual reactor maintenance shutdown causing any substantial non-operational period.

Members of the reactor staff were heavily involved in a DNA Dispersion project at White Sands, New Mexico. This project utilized the reactor for multiple irradiations throughout the year, i The microprocessor-based instrumentation and control console, fully installed in 1990 after a two j year test period, completed its fifth year of successful operation as the primary control and safety 1 instrumentation. The console operated throughout the year with only minimal malfunctions i (Section IV). There was only one unplanned shutdown during 1995, which is detailed in Section III.

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4 j The Deputy Secretary of Defense made a decision to close the Armed Forces Radiobiology i Research Institute and to begin decommissioning the reactor in FY97. The reactor staff began

several weeks determining methods to decommission the reactor and cost factors involved, as I

well as cost factors to keep the reactor open. All data was submitted to the institute director I in an attempt to provide additional information affecting the decision to close AFRRI or its ,

reactor. As of December 31, no change to the decision had been made. I l I The annual reactor facility audit was held on 25 and 26 October 1995. The auditors concluded l I that the reactor was being operated in a safe manner in conformance with the Technical l

Specifications and Operating License. No violations were observed during this inspection. l

, Discussion of the inspection is covered in Section 1. E. The auditors did note that the morale cf the staff was much higher than they would expect in the wake of the decision to close AFRRI.  !

The Nuclear Regulatory Commission did not inspect the AFRRI TRIGA Reactor during 1995,

nor was this required.

i j The reactor core remained unchanged except for the movement of a fuel element from grid i position E13 to D13 to allow for the placement of the Core Experiment Tube (CET) in a

. different location in the core. The CET was moved from F13 position near a control rod, to l E13 which is equal distance from, and further from, 'two control rods. This change did not i effect the performance of the core.

Reactor staff changes included the departures of SGM Harry Spence, SFC Mike Laughery, and Capt Daniel Robbins. Added to the staff was Capt Oscar lessard. Capt Lessard has begun his

operator training along with SFC Brian Cohill. SFC Danny McClung and ENS John Ventura

! were examined and licensed by the NRC as Senior Reactor Operators.

Director CAPT Robert L. Bumgarner departed AFRRI in January and was replaced by CAFT Eric E. Kearsley, as Acting Director, until he was appointed Director permanently in February.

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Changes were inade to the procedures and facilities during 1995. These changes were supported by an extensive safety review process in accordance with the provisions of 10 CFR 50.59.

These various changes will be discussed fully in Sections I & V.

The reactor staff provided personnel to assist in conducting operational and safety inspections of the Fast Burst Reactor facilities at Aberdeen Proving Ground, Maryland, and White Sands Missile Range, New Mexico. At the request of Cornell University, an operations audit of their reactor facility was conducted.

In August a lock on a pump house door was found to be broken allowing access to a fresh water supply by a group of construction contractors. The lock was immediately replaced and the workers were instructed that they would have to obtain water from~ some other source. For further information on this issue see Attachment E, " Fresh Water Use In Pump house".

The remainder of this report is written in a format designed to include information items required by the AFRRI TRIGA Reactor Technical Specifications. Items not specifically required are presented in the General Information section. Following sections correspond to the required items as listed in Section 6.6.1.b of the AFRRI TRIGA Reactor Technical Specifications.

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GENERAL INFORMATION

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Key Personnel

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GENERAL INFORMATION i All personnel held their positions as listed throughout the entire year unless otherwise specified.

1. Current key AFRRI administration personnel (as of 31 Dec 95) are as follows:

Director - CAPT Eric E. Kearsley, USN (Effective 17 Feb 1995)

Chairman, Radiation Sciences Department - CAPT C. B. Galley, USN AFRRI Radiation Protection Officer - Mr. Thomas J. O'Brien

2. Reactor Senior Technical Manager:

Reactor Facility Director - Mr. Mark Moore (SRO)

3. Current key Reactor Operations Personnel:

Deputy Reactor Facility Director - Mr. Stephen Miller (SRO)

Reactor Operations Supervisor - Mr. Robert George (SRO)

Training Coordinator - Mr. Stephen Miller (SRO)

Maintenance - Mr. John Nguyen (SRO)

Administration - SFC Danny McClung (SRO)

Senior Staff Engineer - LTC Leonard A. Alt (SRO)

4. Other Senior Reactor Operators: ENS John C. Ventura (SRO)  :

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5. Operator Candidates: SFC Brian Cohill (Effective 28 Dec 94)  !

Capt Oscar Lessard (Effective 5 June 95)  !

6. Newly Licensed Operators: SFC Danny K. McClung (SRO)(Effective 23 May 95 )

ENS John C. Ventura (SRO)(Effective 23 May 95 )

7. Additions to staff during 1994: Capt Oscar lessard (Effective 5 June 95) l i

8. Departures during 1994: SGM Harry Spence (20 Jan 1995)

SFC Mike Laughery (23 Jan 1995)

Capt Daniel Robbins (20 Jan 1995)

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9. There was several staff changes to the Reactor and Radiation Facility Safety Committee during 1995. COL David G. Jarrett replaced Col-John R. Sheehan as the chairman of the committee. Mr. Mark A. Miller of the Naval Research laboratories replaced Mr. Kirk King. Dr.

Ieslie McKinney replaced LTC Eric Daxon as a non-voting special member and SFC Danny McClung replaced Capt Daniel Robbins as the recorder. The appointment letters are shown at Attachment C.

The 1995 RRFSC consisted of the following membership in accordance with AFRRI Reactor i Technical Specifications (as of 31 Dec 95):

Regular Members:

Mr. 'Ihomas O'Brien (AFRRI Radiation Protection Officer)

Mr. Mark Moore (Reactor Facility Director, AFRRI)

Mr. Marcus Voth (Director, Bremmale Reactor, Pennsylvania State University)(Reactor Operations Specialist)

Mr. Mark A. Miller (Radiation Safety Officer, Naval Research Laboratory)

Chairman:

COL David G. Jarrett (Director's Representative)

Special Members:

CAPT Charles B. Galley, USN (Chairman, Radiation Sciences Dept., AFRRI)

(Certified HP) fon-voting members:

Mr. James Caldwell (Office of Environmental Protection, Montgomery County, MD)

Dr. Ieslie McKinney (Radiation Pathophysiology and Toxicology Department, AFRRI)

Non-Voting Recorder:

SFC Danny K. McClung As required by the reactor Technical Specifications, four meetings of the RRFSC were held:

1 March 1995 Full committee meeting 2 June 1995 Full committee meeting 18 October 1994 Subcommittee meeting 18 December 1994 Subcommittee meeting

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! - SECTION I s

l I: ' Change ~s to the Facility Design, i

i Performance Characteristics 1

! and Operational Procedures. I h

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Results of Surveillance Tests L and Inspections. ,

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SECTION 1 A summary of changes to the facility design, performance characteristics, operational procedures, and results from surveillance testing are contained in this section. The revised reactor administrative and operational procedures can be found at Attachment A, while the 10 CFR 50.59 reviews can be found at Attachment B for all of the following changes.

A. DESIGN CHANGES:

.l. The Continuous Air Monitor (CAM) electronics were replaced in all five of the reactor CAM's. The new electronics package replaces the older outdated shelf of electronics.

The unit was calibrated to respond to a radiation source with the same output reading as the previous electronics unit. The performance characteristics of the unit did not change.

2. The reactor security system interface was upgraded with a new and more user friendly computer interface. The upgrade involved replacing the computer terminal at which designated staff members interface with the D600 unit. The D600 unit, which controls and monitors the security system, was not changed or replaced. The functionality of the security system remained the same, only the operator interface to the system changed.

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3. The Safety and Health Department changed the supplier for the 16 in-plant perimeter i TLDs located on the AFRRI roof or at ground level near AFRRI. The new dosimeters from Naval Dosimetry use the same TLD-100 chip M detect radiation as did the Eberline Inc. dosimeters which have been used since approximately 1980.

4. A remote switch was installed in room 3106A to open the reactor ventilation dampers. j The purpose of this switch is to allow security guards to open !he reactor dampers after they have called a reactor staff member for authorization to do so. Guards have been instructed not to operate the switch unless directly authorized by a reactor staff member.

The switch is located behind a locked door so that access to the switch will not be inadvertent. Summer thunderstorms often disrupt building electrical power long enough to allow damper system relays to trip, thus causing the dampers to automatically close.  ;

This switch, which is wired in parallel to the control room switch, allows guards to reset the dampers for non problem trips and identifies if the trip is a non problem trip or if an actual problem exists. If an actual emergency condition exists, pressing this new switch will not cause the dampers to open and therefore will not proliferate the consequences of an actual event.

5. The sample port tubes in the reactor stack were replaced for the stack gas monitoring system. The old tubes were damaged during maintenance and were replaced.

6. The Stack Gas Monitor (SGM) printer was removed from the SGM unit and replaced by a remote chart recorder in the control room. The printer was used by the SGM computerized electronics to print an average Argon-41 concentration every six hours but because Argon releases are calculated by hand, the printouts from the SGM were never

l used for effluent release calculations.. The chart recorder in the control room will allow ,

operators to view any unusual trends in the output of the SGM. This change does not

-l decrease the effectiveness of the SGM.  !

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7. A 50.59 review was completed for the replacement of the Stack Gas Monitor (SGM) i digital electronics shelf with an analog based set of electronics. The new electronics j package will have outputs for alarms, lights, and remote meters or recorders. These  !

outputs will provide the same function as the old unit. The new electronics module

replaces the old unit with newer, more reliable electronics. As of the 31 December 1995, the new electronics had not arrived. They are expected to arrive early in 1996.

) B. PERFORMANCE CHARACTERISTICS:

No changes to the core occurred during 1995 which would affect performance. The performance characteristics of the core did not change.

i C. ADMINISTRATIVE PROCEDURES:

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, 1. HPP 7-3, " Airborne Radioactivity Samplers and Monitors", Table 4.a.(1), was updated to l indicate which of the CAM chart recorders would normally be running, or turned off. l Several of the non reactor CAMS do not require chart recorder operation to perform their intended function. j

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2. Procedure A3, " Facility Modification" was changed on page 2, Paragraph 3 to indicate that a change to the SAR would be made followed by a review by the RRFSC for changes that have no unreviewed safety issues. Previously the procedure required that

, all changes to the SAR be reviewed by the RRFSC before the change could be

implemented.

t D. OPERATIONAL PROCEDURES:

l 1. A change to Procedure 8, TAB A, Logbook Entry Checklist, added a section on malfunction log entries. The new section specifies key words to be used for formatting l malfunction entries. This change will help ensure that entries are made in a more consistent manner and that all information necessary for the entry is recorded.

2. In Procedure 1, TAB A, " Reactor Exposure Room Entry", and in HPP 3.1, " Reactor 1

Irradiation Facilities", the limit for the Exposure Room Continuous Air Monitor readings for non monitored openings was changed from 200 cpm above background to 2000 cpm inclusive of background. The purpose of this change was to eliminate interpretation of the procedure when performing non monitored openings.

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3. Procedure ll, " Air Paniculate Monitor (CAM) Procedure" was changed on two different i occasions during 1995 to reflect the change for the daily tests of the new CAM 4

electronics. The procedure was also changed to eliminate the use of the secondary CAM

! chart recorder unless the primary CAM is bypassed for maintenance or malfunctions.

l Both CAMS will retain the capability to close the dampers in the event of an emergency.

f I 4. Procedure A2, " Personnel Passage Through the Prep Area" was changed to add a specific section on prep area frisking policy / procedure. The section specifies that a person will 3 frisk if they have been in the yellow painted ama, been in an exposure room, handled potentially contaminated material, or at the request of reactor or SHD personnel.

i 5. The Startup, Shutdown, and Safety Checklists were all changed to place a "*" at the end j

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of each line on which a numeric entry is required. This will prompt operators to place numbers and not check marks on lines with limits indicated. Previously, either check

marks or numbers were accepted.

! E. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS:

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Two items in TRIGA TRACKER were not complete by the end of the year. Both items were briefings and are scheduled for February 1996. A list of completed tasks is in Attachment j D.

4 l Malfunctions discovered are detailed in section IV.

J There was only one audit during 1995. The audit was conducted by Mr. Thomas Wright

from the U. S. Department of Energy and Mr. Lewis Hulman of Parallax Inc. Mr. Wright  !

! was formerly a Senior Reactor Operator at the AFRRI facility and is currently involved in I

, safety activities with the Department of Energy. Mr. Hulman has previous experience on a  !

- USNRC Nuclear Power Reactor Inspection Team. No safety concerns or violations were  !

found by the auditors.

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jj EnergyLGenerated .by. Current.

! ' Reactor Core and Number of Pulses. '

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SECTION II Energy generated by the reactor core:

Month Kw-Hrs JAN 258.2 FEB 2711.0 MAR 1177.8 '

APR 943.2 MAY 1579.3 JUN 674.9 JUL 3952.8 AUG 2524.7 SEP 571.0 OCT 3019.6 NOV- 417.0 l DEC 485.2  :

TOTAL 18314.7 Total energy generated this year: 18,314.7 Kw-hrs Total energy on fuel elements: 873,719.4 Kw-hrs Total energy on FFCRs: 140,921.3 Kw-hrs '

Total pulses this year 1 $2.00: 0  :

Total pulses on fuel element 1 $2.00: 4159 Total pulses on FFCRs 1 $2.00: 47 Total pulses this year: 176 Total pulses on fuel elements: 10837 Total pulses on FFCRs: 1072

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I SECTION III Unscheduled Shutdowns:

There was one unscheduled shutdown during 1995. Power to the Control System

was lost when an Uninterruptible Power Supply (UPS) shut off power to the console loss was caused by one battery cell shorting out in one of the four 12 volt batteries intern the UPS unit The UPS electronics, detecting the low battery voltage, performed their inte function by shutting off the output power from the UPS to the CSC. The reactor scramme duringIV.a section low power operation when power to the CSC was lost. See the malfunction I

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A SECnOX IV i;

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, ' Safety-Related Corrective Maintenance

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i l SECTION IV i

Safety-Related Corrective Maintenance.

t l The following are excerpts from the malfunction logbook during the reporting period. The i reason for the corrective action taken, in all cases, was to return the failed equipment to its ,

, proper operational status, i  :

E l 17 Mar 95 During the daily startup checklist, a zero power pulse was fired and the console i resumed operation without collecting any data or indicating that a pulse was fired.

l The console was shutdown and rebooted. The console was tested by firing  ;

j several more zero power pulses with each of the zero power pulses successfully 3

collecting data. The console was determined to be fully operational and the  ;

startup resumed. l

.! l l 05 May 95 The auxiliary damper closed lamp at the guard desk indicated that the dampers l j had closed. An inspection of the dampers proved that they were indeed open and i that the indicator lamp at the guard desk was incorrect. The damper closure j system was tested to verify operability of the damper closure system. The f problem was determined to be the switch which controls the damper lamp was out of adjustment. The switch was adjusted, tested, and the system wa:; found to be fully operational. l i

i 07 Jun 95 The Stack Gas Monitor (SGM) was found to be indicating zero counts during the daily startup checklist. Reactor operations were suspended. The problem was determined to be a bad contact between the power supply and the main CPU board. The board contacts were cleaned and the board was rescated in the SGM unit. The unit was electronically and isotopically recalibrated before reactor operations resumed.

11 Jun 95 A suspected storm related power problem (lightning) caused two unrelated problems to reactor systems. A reactor staff member was called in after a t nighttime thunderstorm for an air damper closed problem. The operator reset the dampers and the dampers closed a few seconds later. Each attempt to open the dampers resulted in the dampers closing a few seconds later. Diagnosis of the problem revealed a problem with an air flow switch in an exhaust leg of the ventilation system. The switch was repaired and the damper system was tested.

The damper system remained open after the repair and closed when called for as intended by the CAM damper closure system. The closure system was determined to be fully operational and capable of performing its intended function.

The second problem was a message on the Control System Console (CSC) that the console network looks dead. Diagnosis of the problem proved that one of the

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i two network boards between the Control System Console (CSC) and Data j Acquisition and Control (DAC) unit had failed. Both network boards were 4

replaced thus allowing the resumed communications between the CSC and DAC.

The console booted up normally. The network was tested, found to be fully

operational, and a full daily startup proved all other systems were functioning l properly.

13 Jun 95 The Stack Gas Monitor (SGM) was indicating zero counts during the daily startup checklist. The problem was diagnosed as a power failure to the SGM which 4

caused the system to lose the system settings. The unit was reinit.ialized and the set points were reset. The SGM was source tested and found to be fully j operational.

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! 14 Jun 95 The Stack Gas Monitor was found to be non operational during the daily startup checklist. The historical record in the computerized unit showed a power loss to the unit the previous evening. Testing revealed a problem with the uninterruptible power supply (UPS) into which the SGM was plugged, the SGM i was plugged into an alternate UPS. The alternate UPS, which was being used to

! operate a PC type computer, was determined to be capable of operating both j units. A new UPS was ordered for the SGM.

j When the SGM again went down the staff suspected that the power problem (suspected lightning strike) from 11 June had made it through the UPS circuitry j and into the SGM circuitry. The staff replaced the SGM power supply, high i voltage and single channel analyzer card, printer card, printer, and NaI detector.  !

The CPU card was not changed. The new components were electronically calibrated, and after an isotopic calibration by Safety and Health Department

{ personnel, the unit was tested, found to be fully operational, and brought back on  ;

i line.

i j 15 Jun 95 Operators discovered that the security system monitor was blank. The j procurement office was notified of the situation and the procurement i representative called the security company (DEI) for a replacement monitor. The d

repair or replacement of the monitor was under contract with DEI. Until DEI

j. could arrive with a replacement monitor, a spare VGA computer monitor was i plugged into the security system computer. The temporary monitor provided the same picture as the DEI monitor which was also a VGA computer monitor.

03 Jul 95 The SGM was found to be indicating no counts during the daily startup checklist.

3 The problem was determined to be that the SGM had lost all its set points in the .

computerized CPU card. The set points were reentered and the SGM was source I

tested and found to be fully operational. Reactor scaff researched and ultimately i placed an order for a replacement set of electronics for the SGM. The new

electronics will have the same sensitivity, high and low alarms, and outputs for j remote meters and chart recorders.

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! -12 Sep 95 Excessive air was found to be leaking around the lower O-ring seal in the transient rod drive.~ The drive was initially replaced with a spare drive but a j problem with the drive mechanism resulted in cannibalizing the O-ring from the

l. replacement drive and using it to repair the original drive. The original drive was i reinstalled and all functions of the drive were tested. The reactor. was brought j back on line.

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! 13 Nov 95 The transient rod drive did not give a green (air applied) indication on the CSC l high resolution monitor when air was applied to the drive. The problem was i j discovered to be a crushed rubber dirt boot located inside the transient rod drive l l anvil. De boot was preventing the anvil from compressing when air was applied

to the drive. He anvil was repaired by obtaining an identical rubber boot and

! shock absorber from a spare drive anvil and replacing the unit in the original I

anvil. The unit was tested by applying air to the drive and seeing that the anvil l compressed enough to allow the air applied indication was displayed on the CSC l high resolution monitor. All transient rod drive functions were tested and the j reactor was returned to service.

I j 21 Nov 95 Both lamps (high and fail alarm) on the SGM remote meter came on and could I l not be reset. The problem was determined to be a lamp located inside the meter i had burnt out. The internal lamp is used to provide light for two photosensitive '

' transistors for the alarm points. When the lamp burned out the photo transistors could no longer detect the light thus causing both alarm points to trip. The meter

, was disassembled and the lamp was replaced. De alarm points were tested on

the meter, found to be fully operational, and the alarm points were reset. '

03 Dec 95 During a low power operation the reactor console lost power and the reactor I scrammed. This power loss was caused by one battery cell shorting out in one  !

i of the four 12 volt batteries internal to the UPS unit and the UPS electronics, i detecting the low battery voltage, shutting off the output power from the UPS to j the CSC. The UPS is suspected to have changed from line power to backup j power due to noise, power sag or some other power anomaly, and when the UPS 4 j could not maintain the output with the lower battery voltage, the UPS performed j its intended function and shut off the output power. The console was plugged 4

into another UPS which was operating a PC type computer. The replacement

UPS power rating was checked to verify that there would be no overloading j problems using it to operate the console electronics. The console was rebooted l and tested with the daily startup checkouts before normal operations resumed.

I i 08 Dec 95 The SGM was giving a high reading with the source in the detector chamber.

The high voltage and single channel analyzer card was replaced and the unit was

{ recalibrated. The Safety and Health Departinent performed an isotopic calibration

, of the unit before the unit was brought back on line. The replacement electronics j for the SGM are expected to arrive in early 1996.

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! SECTION V  !

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a f Facility Changes andLChanges to 4

i Procedures as. Described in the' -

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I Safety Analysis Report. New. j l:. Experiments or Tests During.the Year.

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SECTION V i

Changes to the facility and procedures as described in the Safety Analysis Report (SAR) and new experiments or tests performed during the year are contained in this section.

A. The SGM printer was removed from the unit and replaced by a remote chart recorder in l the control room. The SAR was changed to eliminate any references to the SGM printer

or printouts and the continuous chart recorder was added to provide a continuous record i of effluent counts. The chart recorder provides to the operator a chart showing any

unusual trends in the output of the SGM.

j B. A 50.59 review was completed for the replacement of the Stack Gas Monitor (SGM) l digital electronics shelf with an analog based set of electronics. The replacement will i

change several sections of the SAR and modify several procedures. As of 31 December 1995, the new electronics had not arrived and no changes had been made to either the l SAR or procedures. The electronics are expected to arrive early in 1996 and the SAR j and procedural changes' will be made upon installation of the electronics.

C. There were no new experiments or tests performed during the reporting period.

l Attachment B contains the safety evaluations made for changes not sebmitted to the NRC

, pursuant to the provisions of 10 CFR 50.59. Each modification was described and qualified i using Administrative Procedure A3, Facility Modification. This procedure utilizes a step-by-step j process to document that there were no unreviewed safety questions and no changes required to the Technical Specifications.

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i l-SECTIONS VI through VIII.  ;

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, Summary of Radioactive Effluent Released.

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Summary of Radiological Surveys.

Exposures Greater Than-10% of 10 CFR Limits I

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SECTION VI Summary of Radioactive Effluent Released:

A. Liquid Waste: The reactor produced no liquid waste during 1995.

B. Gaseous Waste: There were no particulate discharges in 1995.

The total activity of Ar-41 discharged in 1995 was 7.9 Curies. The estimated average activity release was less than 1% of the permitted  ;

effluent concentration for unrestricted areas (Table 2 of Appendix B to 10 CFR 20).

Quarterly: Jan - Mar 1995 1.8 Ci Apr - Jun 1995 1.3 Ci Jul - Sep 1995 2.6 Ci Oct - Dec 1995 2.2 Ci C. Solid Waste: All solid radioactive waste material was transferred to the AFRRI byproduct license; none was disposed of under the R-84 License.

SECTION VII Environmental Radiological Surveys A. Environmental sampling of soil and vegetation reported radionuclide Vevels that were not above the normal range. The radionuclides that were detected were those normally expected from natural background and from long-term fallout.

B. The environmental monitoring (TLD) program reported the following results at a 95%

confidence level for 1995:

1. The annual average reading of approximately 20 thermoluminescent dosimeters (TLD) background stations, located 2 miles or greater from the AFRRI site, was determined to be 22.0 i 1.8 millirem.

2. The annual average reading of approximately 30 environmental TLD stations located on the NNMC grounds was determined to be 20.5 i 1.6 millirem C. The reactor in-plant surveys, specified in HPP 3-2, did not exceed any of the action levels specified in HPP 0-2.

SECTION VIH Exposures Greater than 10% of 10 CFR 20 Limits:

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There were no doses to reactor staff personnel or reactor visitors greater than 10% of 10 CFR l 20 occupational and public radiation dose limits, respectively. l

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4. I F

ATTACHMENT A i Revised. Reactor Administrative and j

, Operational Procedures .l

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Procedure A2, Personnel Passage Through The Prep Area

Procedure A3, Facility Modification

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[- Procedure 1 Tab A, Reactor Exposure Room Entry I '

Procedure 8 Tab A,' Logbook Entry Checklist Procedure 8 Tab B, Daily Operational Startup Checklist  !

Procedure 8 Tab B1,- Daily Safety Checklist j Procedure 8 Tab I, Daily Operational Shutdown Checklist -

Procedure 11, Air Particulate Monitor (CAM) Procedure l

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PERSONNEL PASSAGE THROUGH THE PREP AREA GENERAL Access to the Reactor Prep Area is limited to personnel who are granted access in accordance with the reactor physical security plan and Operational Procedure 1.

The Reactor Facility Director is responsible for maintaining an unescorted access roster for the Reactor Prep Area and for providing a Prep Area briefmg to all persons listed on that roster. This administrative procedure does not recapitulate the operational procedure. Rather, it presents specific guidelines for Reactor Prep Area passage, and frisking for individuals who are authorized access.

SPECIFIC

1. ROUTINE PASSAGE:(EXPOSURE ROOM DOORS CLOSED)

a. Personnel who are suthorized unescorted access to the Reactor Prep Area may pass through the Prep Area as necessary.

b. Personnel who are being escorted through the Reactor Prep Area may pass through the Prep Area only with their escort.

c. Only appropriate personal dosimetry that has been issued by SHD or AFRRI Security is required for routine passage through the Reactor Prep Area. There is no requirement to wear a pocket chamber in addition to the AFRRI issued TLD for routine passage.

2. CONTROLLED PASSAGE:(EXPOSURE ROOM DOOR OPEN)

a. Only personnel associated with the experiment / operation being performed are normally authorized access to the Reactor Prep Area during an exposure room opening. These personnel will be required to wear the AFRRI TLD dosimeter (issued with their AFRRI badge), pocket chamber (if dose rate at face of door is 2 mrem /hr or more), and AFRRI wrist dosimeter or finger ring dosimeter if they enter the exposure room.

All personnel who enter an exposure room willlog their pocket chamber reading in the pocket chamber log prior to entering the room for the first time that day and will enter the fmal pocket chamber reading following their exit from the exposure room at the end of the day. Each individual who enters an exposure room is responsible for monitoring his accumulated dose throughout the day to ensure the he/she does not exceed the AFRRI daily Revised: 25 May 95 Page1

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d. Upon reauest of reactor staff or SHD personnel.

The frinking procedure is posted at both exits from the Prep Aren near the survey

. Instruments.

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Revised:25 May 95 Page 3 l

1 .

f ADMINISTRATIVE PROCEDURE [

_ g , myf 4Propure. A3]

FACILITY MODIFICATION GENERAL Changes to the Reactor Facility and operational procedures must comply with requirements specified in the Reactor License, and 10 CFR 50.59. It is required that modifications to the facility or procedures as described in the Safety Analysis Report (SAR) be documented with a written safety analysis. Under 10 CFR 50.59, a licensee may make changes to the facility provided there are no changes made to the Technical Specifications, there are no unreviewed safety questions, and that a proper safety analysis is carried out, documented, and reviewed.

Applicability:

The Facility Modification Procedure applies to proposed facility changes or changes in the operating procedures.

. The referenced procedure will not cover routine replacement of parts or components with equivalent parts or components.

DESCRIPTION This administrative procedure consists of these instructions, the Facility Modification Worksheet Guide, and two worksheets to facilitate a 10 CFR 50.59 review of modifications and to determine if a detailed safety analysis is necessary.

The instructions in the Facility Modification Worksheet Guide are used to determine which worksheet must be completed for the modification. One of three conclusions regarding the proposed facility modification will be reached:

1. The modification requires prior approval or a license amendment from the USNRC,

2. The modification may be made according to the provisions of 10 CFR 50.59(a)(1)(Facility Modification Worksheet # 1), or

3. The modification does not require a 10 CFR 50.59 safety analysis (Facility Modification Worksheet # 2).

Revised:09 Aug 95 Page1

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l Facility Modification Worksheet Guide  ;

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1. Technical Specification Change: If the proposed modification requires a change j in the Technical Specifications, a license amendment is required prior to making the change. NRC approvalis required; do not implement the change without this approval.

2. Unreviewed Safety Question: If an unreviewed safety question is created by the proposed change as defined in 10 CFR 50.59(a)(2) such that the change increases the probability of occurrence or severity of an accident described in the SAR, can malfunction in a manner that can cause an accident of a different type than described in the SAR or can decrease safety margins as defined in Technical l Specifications, then NRC approvalis required. Do not implement the change without this approval.

3. If the proposed modification makes a change in the facility as described in the SAR or changes a procedure as described in the SAR, the change can be' performed under a 10 CFR 50.59 analysis with a safety review,if there are no unreviewed safety issues (10 CFR 50.59(a)(2)). The change may be made followed j hy_a review by the RRFSC. Go to Facility Modification Worksheet # 1.

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4. If the proposed modification does not make a change to the facility as described in the SAR or to a procedure as described in the SAR and does not pose an i unreviewed safety issue, a 10 CFR 50.59 analysis is not required. Go to Facility l Modification Worksheet # 2. l I

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Facility Modification Worksheet 1 10 CFR 50.59 Analysis Proposed Change 1

Submitted by.: Date l 1. Description of change:

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2. Reason for change:

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

Analysis attached? Yes

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

Procedure Facility Experiment l

Revised:09 Aug 95 Page 3

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l Facility Modification Worksheet 1 I

5. Specify what sections of the SAR are applicable. In general terms describe the necessary updates to the SAR. Note that this description need not contain the final SAR wording. l l

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

Revised:09 Aug 95 Page 4

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Facility Modification Worksheet 1 I

7. Specify associated information.

New drawings are: Attached Not required 1

Does a drawing need to be sent to Logistics? Yes No Are training materials effected? Yes No Will any Logs have to be changed? Yes No Are other procedures effected? Yes No l

I List ofitems affected: )

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8. Create an Action Sheet containing a list of associated work specified in item #

7c attach a copy, and submit another to the RFD (modification of drawings must be approved by the RFD).

Action Sheet: Submitted Not Required Reviewed and approved by RFD Date RRFSC Concurrence Date Revised:09 Aug 95 Page 5

Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change Modification to: Procedure Facility Experiment Submitted by: Date

1. Description of change:

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2).

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics.

4. Determine what other procedures, logs, or training material may be affected and record below.

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

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

Action Sheet: Submitted Not Required Reviewed and approved by RFD Date RRFSC Notified Date Revised:09 Aug 95 Page 6

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REACTOR EXPOSURE ROOM ENTRY i

i l 1. REFERENCES l

m.10 CFR 20, " Standards for Protection Against Radiation" i

i b. USNRC licenses: R-84,19-08330-02 l

c. AFRRIInstruction 6055.8

d. AFRRI Health Physics Procedure 3-1

2. G ENERAL

a. PURPOSE: This procedure specifies all safety and security procedures for activities involving entry into the AFRRI TRIG A Reactor exposure rooms, currently designated exposure rooms 1 and 2 (rooms 1123 and 1122).

b. AUTHORIZED ENTRY: Both AFRRI picture badge and U-badge personnel, may enter a reactor exposure room under the supervision of the Reactor Facility Director (RFD) or his representative. Visiting personnel (V badge) require special authorization by both the Chairman, Safety and Health Department (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. All personnel who are granted unescorted access to the prep area or warm storage will receive a special prep area safety briefing prior to being granted access. Only personnel who have been granted permanent unescorted j access will be given card access to the prep area. The RFD is responsible for l maintaining a roster in the prep area for personnel who have been granted 1 permanent unescorted access. Other personnel requiring unescorted access to the prep crea or warm storage for a specific purpose or time period may be granted special access in writing by the RFD with concurrence of SHD. However, these personnel who are granted special access from the RFD will not be given card access to the prep area.

c. ER ENTRY INSTRUCTIONS - All personnel will:

Revised:01 Dec 94 Page 1

l (1) Know the Reactor staff representative is in charge of all operations in the l prep area. Obtain permission to enter either exposure room from the

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Reactor staffrepresentative.

(2) Wear AFRRI TLD whole body badge and pocket dosimeter, j (3) Wear wrist or finger dosimeter if work is to be performed on an i experimental array or within one meter of the core projection.

l (4) Weer bootics, eye protection, gloves and coat.

i (5) Check and log pocket dosimeter reading on log in prep area prior to entry.

l (6) Familiarize themselves with approximate radiation levels in the room,

based on radiological surveys performed and data obtained by SHD.

l (7) Ensure that all materials removed from the exposure room are properly j labeled and entered on the exposure room entry log (AFRRI FORM 130) 4 and the activated materials controllog.

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! (8) Glove and lab coat requirements may be waived by the SHD monitor or reactor representative 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 requirements.

d. DEPARTURE FROM REACTOR EXPOSURE ROOM ENTRY PROCEDURES: Any departure from the following procedures will require a special work permit (SWP). Exceeding any radiation dose limits will require a written justification from the supervisor of the research project which must be approved by the Head, SHD.

3. SHD EXPOSURE ROOM SURVEY

a. EXPOSURE ROOM CAM:

(1) Prior to opening either exposure room, the respective CAM must read 2000 cpm or less. If the CAM reads 2000 cpm or greater, change the filter on the CAM and put it in the radioactive materials bag in the CAM drawer. If 10 minutes or more have elapsed since the end of the reactor run, the door may be opened to the first step to facilitate radioeffluent clearance in the room. Then check the CAM after 1 minute and,if the reading has not increased by more than 100 cpm, proceed with the exposure room opening. Ifit has increased by more than 100 cpm, change the filter and wait two more minutes and repeat as necessary. If the CAM alarms during or immediately after a run, change the filter and reset the CAM.

(2)If either exposure room CAM or the Prep Area CAM is found malfunctioning or inoperable, notify the Reactor Representative or Revised:01 Dec 94 Page 2 l

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Reactor Operations Supervisor (ROS) and Radiation Safety Officer (RSO)immediately. No opening shall be initiated if the exposure room to

, be opened does not have an operable CAM.

b. DOSE RATE AT FACE OF DOOR: If the dose rate at the face of the plug door in the direct line of sight of the reactor tank bulge reads greater than 100 mrem /hr, the door will be closed sufficiently to preclude access. The plug door will be reopened upon agreement of the SHD and RFD representatives for reevaluation of radiation levels. When the dose rate at the face of the door is below 100 mrem /hr, the opening procedure may continue.

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 readings will be entered in the room entrance log (AFRRI FORM 130) and kept in the prep area. The levels will be measured at:

(1) The reactor door face in the direct line of sight of the reactor tank bulge (2) At the contamination line in the entrance of the room (3)The middle of the room (4) 30 cm from the tank wall or shield l (5) Contact with the tank wall or shield (6) The area (s) where individual (s) will be working for an extended period of time and any other place deemed necessary by the reactor representative.

d. ROUTINE ENTRY: Entry is routinely permitted only when the maximum reading in any occupiable area is 1 rem /h or less. Entry may be permitted iflevels are 1-5 rem /h, but no work will be permitted in fields over 1 rem /h. If personel are working in a specific area for an extended period of time, the dose rate in that area will be measured.

(1) Readings over 100 mrem /hr (closed window) will be specifically identified.

All dose rate readings will be reported to the Reactor representative and entry personnel. When appropriate, after consultation with the SHD and Reactor representatives, stay times will be assigned for entry personnel.

AFRRI limits of 100 mrem / week and 50 mrem / day are to be used as the basis of stay time determinations.

(2) All exposure room entries will be checked by the SHD monitor for compliance with radiation safety aspects of applicable Reactor Use Requests (RURs). If not, non-compliance will be reported to the RFD and to SHD.

Revised:01 Dec 94 Page 3

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l e. FILLING OUT THE SURVEY OF EXPOSURE ROOM OPENING LOG:

{ The exposure room opening log sheet must be filled out completely for each opening of an exposure room. Care must be taken to fill out each blank on the entry log sheet. If a section is not applicable to the particular opening, N/A should

! be filled in the blank.

j 4. NON-MONITORED OPENING:

a. Personel may enter the exposure rooms without a SHD monitor present if l

ALL the following conditions hold:

(1) The reactor has not been to power in that ER since the last survey.

l (2) Survey meter readings at the door indicate safe entry conditions (should j be less than 1 mrem /hr).

! (3) The ER CAM should be observed, and its reading (net) should be less j than 200 cpm above background.

j (4) The last survey indicates that the maximum dose rate in any area where i work is to performed did not exceed 100 mrem /hr.

b. An entry will be made in the exposure room log by a reactor staff member, with a note that the survey has been waived.

i c. SHD must be notified if any radioactive materials or equipment are to be l removed from the prep area.

5. PERSONNEL PROTECTION PROCEDURES

a. Dosimetry and protective clothing requirements are given in paragraph 2.c, ER Entry Instructions.

b. Entry is permitted only after the SHD monitor has completed the survey and reported results to those about to enter (excluding non-monitored openings -

reference Paragraph 4, above).

c. All personnel shall record initial dosimeter reading in the prep area dosimeter log prior to entering the exposure room for the first time each day. Personnel shall i read dosimeters when leaving the exposure room and record a final dosimeter reading in the prep area log at completion of daily operations. Net doses over 10 mrem must be reported to the SHD Monitor.

d. Protective clothing will be removed in such a way as not to contaminate l I

" clean" areas by items from " dirty" areas.

c. All personnel will " frisk" themselves before leaving the prep area.  !

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Revised:01 Dec 94 Page 4 l

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6. SPECIFIC ACTIONS TO OPEN EXPOSURE ROOM DOORS

a. Turn up exposure room lights (this can be waived for experiment needs).

> b. Check plug door tracks for obstructions; ensure all obstacles are clear of the door (including ropes).

c. Ensure that only authorized personnel (see 2.b.) are present in the reactor prep area during exposure room openings.

d. When facility safety interlocks and opening procedures have been satisfied, insert key into exposure room door key panel and open door. DO NOT LEAVE KEY IN LOCK UNATTENDED.

e. Open door in accordance with entry procedures. Ensure all required data is logged in entry log.

f. Ensure that individuals who will be moving lead, bismuth, or other heavy materials are wearing steel-toed shoes. )

g. Limit exposure times'of all personnel entering the exposure rooms based on the results of the radiation survey.

7. ACTIVATED MATERIALS

a. PLACING MATERIAL IN EXPOSURE ROOM: Before placing any equipment or materialin an exposure room for irradiation the following will be observed:

(1) Equipment tagged as AFRRI property: a memo must be sent to both the RFD and the AFRRI property officer.The memo 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 memo must contain all nomenclature as 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 returned): a memo or statement on the reactor RUR must be sent to the RFD giving the kinds and amounts of byproduct material expected to be produced (that is the material that the experimenter wishes to be returned) and a copy or number of their radionuclide authorization number.The memo or RUR statement must be specific and contain an accurate description of the material being exposed (converted to byproduct). Other information will '

be required from personnel before any materialis allowed to be removed Revised:01 Dec 94 Page 5

from the prep or warm storage areas (see next section of this procedure ,

7.b. and 7.c.) l

. (3) Non-tagged equipment or material (not to be returned): A memo or statement on the RUR that the experimenter understands that byproduct l material produced as a result of their irradiations will be disposed of as radioactive waste, and additionally any material not specifically requested to be held, will be disposed of as radioactive waste in the next shipment.

(4) Non-AFRRI owned equipment / material: A signed memorandum from the l responsible property owner that they understand that byproduct materials generated in excess of their license will be disposed of as radioactive waste unless prior arrangements have been made with the reactor /SHD staffs t for storage. Any material not removed within a reasonable amount of i time will automatically be disposed of as radioactive waste.

b. SURVEY OF MATERIALS COMING OUT OF EXPOSURE ROOM (1) All materialleaving 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 materials will be labeled appropriately in accordance with  !

HPP 0-2 and HPP 3-1.

(2) All special equipment that has been activated such as chambers, rotators, 1 motors, meters, etc., will be stored under the control of the reactor license i

or the AFRRI byproduct license in warm storage or the prep area.

l Removal ofitems from the prep area will only be allowed in accordance with HPP 3-1.

c. DISPOSITION OF ACTIVATED MATERIALS All activated or contaminated materials will be under the control of the ,

reactor license while such materials remain in the reactor controlled area. i Removal of any radioactive materials from the reactor controlled area will be done l in accordance with HPP 3-1.  !

8. COMPLETION OF ENTRY

a. The Reactor Staff Representative will check to see that all personnel have left l

the exposure room before the plug door is closed. In the event that the warning horn in either exposure room is disconnected, for testing or experiment requirements, the exposure room plug door shall not be closed until at least two (2) licensed reactor operators visually inspect the room to ensure that no personnel remain in the room. To ensure compliance with the reactor Technical Specifications, the names of these licensed operators present at the exposure room Revised:01 Dec 94 Page 6

closing shall be entered into the reactor operations logbook and on AFRRI FORM 130. At the completion of the test or experiment, the warning horn shall

, be reconnected and tested. All actions regarding the warning horn shallin entered in GREEN ink in the reactor operations logbook.

b. The SHD monitor will not leave the area while the plug door is open without notifying the Reactor Staff Representative.

c. Lock the exposure room door control pancl; reset lights,if appropriate.

d. Resecure the prep area on departure.

I Revised:01 Dec 94 Page 7

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um.aa&uauamo&w_&&auuccewaama LOGBOOK ENTRY CHECKLIST I. Operational Logbook

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 i 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 l the entry. The operator who makes the final entry at the end of a logbook is responsible for ensuring that the ROS is notified that the logbook is ready for RFD review.

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

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

a. BLACK and BLUE-BLACK:

(1) Console locked and unlocked. The individual at the console will enter his/her name and the supervisory licensed operator's name,if necessary.

(2) Checklist number and completion time.

(3) Power level at criticality and subsequent power level changes.

(4) Reactor SCRAM.

(5) Mode of or;erations. Use appropriate stamp or entry to designate the operation:

(a) Stea6y State (b) Square Wave (c) Pulse Revised:23 Feb 95 Page1

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

(7) Change of personnel at the console. Name of personnel will be entered along with the licensed operator present in the control room,if the person at the console is not a licensed operator.

(8) The operator in charge will be designated in the logbook whenever multiple operators are signed on the console.

(9) Completion of the daily startup and shutdown checklists and weekly checklist.

(10) Signature of reactor operator to close out the log for the day.

(11) Designation of the SRO on-call and physicist in charge (PIC).

(12) Reactor calibrations and data.

(13) All changes to logbook entries (including line outs, error corrections, changes to operations mode stamp lines, and end-of-page line outs) will be initialed I or signed by the operator.

b. RED:

(1) K-excess measurements, to include experiment worth determinations. l l

(2) Actions which affect reactivity:

(a) Core movement.

(b) Fuel movement.

(c) Control rod physical removal for maintenance.

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

c. GREEN:

(1) Any reactor malfunctions noted upon discovery / occurrence with a second entry noting corrective action has been completed.

(2) Additionalitems entered at the discretion of the operator such as addition of make-up water to the reactor pool, etc.

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

Revised:23 Feb 95 Page 2

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

II. Malfunction Logbook All entries in the malfunction logbook should include the following information.

For consistency, the bold italic words should be copied into the malfunction log prior to the information.

DATE, TIME, SIGNATURE OF PERSON DISCOVERING MALFUNCTION SYMPTOM: of problem This section describes how the system is acting or malfunctioning,i.e., channel went full scale, pump failed, keyboard stopped responding to keystrokes etc.

IMMEDIATE ACTION TAKEN This section is for denoting such things as Reactor Secured, SHD notified.

RFD NOTIFIED:

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

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

Which system was malfunctioning or which component failed.

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

OPERATIONAL VERIFICATION AND/OR CALIBRATION:

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

Indicate whether the change will require staff training.

SIGNATURE RFD l

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Revised:23 Feb 95 Page 3

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DAILY OPERATIONAL STARTUP CHECKLIST Checklist number Date Time completed Supervised by Assisted by I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pmssum (80 - 110 psig) .................................. *

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

3. Air dryer o perating . . .. . . . . .. . . . . . . .. .. .. .. .. .. . . .. .. .. . . .. . . . . .. . . .. .. .. . . .. . . . . .. . .

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

II. LOBBY AREA l

Lo bby audio alarm turned o ff ......... ............ .. .. .. .......... .. .. .. ................ ...

III. EQUIPMENT ROOM (Room 2158)

1. Pmfilter differential pmssure (< 8 psid) ................................... *

2. Primary discharge pmssure (15 - 25 psig) ................................ *

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

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

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

6. Visual inspectio n o f area . .. . . . . .. . . . . .. . . . . . . . . . . .. . . .. . . . . . . . . . . . . .. . . .. .. . . . . . .

7. D o o r 2158 S1.7C UR ED . .. . . .. . . .. .. . . .. .. . . . . . . . . .. .. . . . . .. .. . . .. . . . . .. . . . . . . . . .. .

IV. PREPARATION AREA l Visual inspectio n o f area .. .... ...... .. .. . . .. .. .. .. .. .... .... .... .. .... .. .. . . .... ....

V. REACTOR ROOM (Room 3161)

1. Transient rod air pmssum (78 - 82 psig) ................................. *

2. Shield door bearing air pressure (8.5 - 9.5 psig) ...................... *

3. Visual inspectio n o f com and tank ..........................................

4. Number of fuel elements and Fuel elements

• control rods in tank storage Control rods *

5. Air particulate monitor (CAM)

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

(b) B ackup o perating .. .. . . .. .. . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . .. . . . . . . . . . . .. .. .

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

6. Stack gas monitor quality assurance checked .........................

7. D o o r 3162 SEC UR ED . . . . . .. . . . . .. . . . . .. . . . . .. . . . . .. . . . . .. . . . . .. . . . . .. . . . . . . . . . .

• Numerical Entry AFRRI FORM 61a(R) Revised: 14 Jul 95 Page1

- .. - ~- - -- -. . .-- -_ - . . . . - . -. .

N VI. REACTOR CONTROL ROOM (Roem 3160)

1. Emergency air A mr=m meet . .... ........ .... .... .... .. .. .. .. .. .. .. .. .. .... .......... ...

2. Co neole aco niem dated . . . .. .. .. . . .. . . .. .. . . .. . . . . . . .. . . .. .. . . .. .. .. .. .. . . .. .. .. .. .. .. .. . . . .

3. Stack flow and fuel temperatum mconlem dated ..............................

2

4. Lo gbo ok dated and myiewed .............. .................... .................... ......

. 5. Watermonitorbox (a) Backgmund activity (10 - 60 cpm) ............................................... *

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

(c) DM 1 msistivity ( > 0.5 Mohm-cm) ............................................. *

(d) DM2 meistivity ( > 0.5 Mohm cm) ............................................. _ . ,

l 6. Stack gas fiow rate (15 - 35 Kcfm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

8. Gas stack monitor

(a) Backgm und (2 - 20 cpm) . .... .. .. .. .. .. .... .... .. .. .. .... ...... .. .. .. .. .. .. .. .. .. . . .

• 4 (b) A larm check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

9. Radiation monitors Monitor Alarm Point R = ling Alarm Setting

} Functional (mmm/hr) (mmm/hr)

(a) R-1 (< 20) 500

(b) R 2 (< 10) 10 i

(c) R-3 (< 10) 10 4

(d) R-5 (< 20) 100 '

(e) E-3 (< 10) 10

(f) E-6 (< 10) 10 l j 10. TV monitors on .............................................................................

1

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

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

13. Waterlevellog completed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

14. Co nso le lamp tat co mpleted - ...... ...................... ........ .... .... ...... .. ...... .

1

15. Time delay o perative . . . . . . . .. . . .. .. . . . . .. . . . . . . . . . . . . .. .. . . . . . . . . .. .. . . . . .. . . . . . . . . . . . . .. .. ..

i 16. Soume level power gmater/ equal to 0.5 cps. ....................................

17. Pmstart operability checks performed ..............................................

18. Interlock Tests a) Rod raising, SS mode (e) 1 kW/ Pulse mode l

(b) Rod raising, Pulse mode (f) NM 1000 HV l (c) Soume RWP (g) Inlet Temp l (d) Period RWP l

19. SCRAM checks (at least one per md) )

j (a) % Power 1 (h) Reactor key l 3 (b) % Power 2 (i) Manual J (c) Fuel temp 1 (j) Emergency Stop (d) Fuel temp 2 (k) Timer i (e) HV loss 1 (1) CSC Watchdog i i (f) HV loss 2 (m) DAC Watchdog  ;

(g) Poollevel J 4

20. Z em po wer pulse . .. .. . . .. .. . . . . . . .. . . .. .. .. . . . . .. . . .. . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . .. . . .. ..

i ii AFRRI FORM 61b (R) Revised: 14 Jul 95 Page 2

i l

l

,, ,%^.,,,,,. "y __,,  ;

OPERATIONAL

- _ _ _ . _ _ ._ PROCEDU

~ _ ,R E N xrw'~ a'~ -

" ym.,,,_d_um 8, TAB B1 M.

u.-- .

u m+%r@uce - -

DAILY SAFETY CHECKLISP 1

Checklist number Date I

, Time completed Supervised by _

Assisted by 1

l l

I. EQUIPMENT ROOM (Room 3152) i

1. Air compresor pmssure (80 - 110 psig) .................................. *

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

3. A ir dryer o perating . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . .

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

1 II. EQUIPMENT ROOM (Room 2158)

1. Prefilter diffemntial pmssure (< 8 psid) .................................. *

2. Primary discharge pmssure (15 - 25 psig) ............................... *

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

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

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

6. Visual inspectio n o f area . .. . . .. .... . . .... .. .. .. .... . ... .... .. .. .. . . .. .. .. .... .. ..

7. D o o r 215 8 SEC UR ED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

III. PREPARATION AREA Visual inspectio n o f ama . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

IV. REACTOR ROOM (Room 3161)

1. Transient rod air pmssum (78 - 82 psig) ................................ *

2. Shield door bearing air pmssum (8.5 - 9.5 psig) ...................... *

3. Visual inspection of com and tank ..........................................

4. Number of fuel elements and Fuel elements

• contml rods in tank storage Contml mds *

5. Air particulate monitor (CAM)

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

(b) B ackup o perating . . . . . . . . .. . . . . . . . . . . .. . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . .

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

6. Stack gas monitor quality assurance checked .........................

7. D o o r 3162 SEC UR E D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

• Numerical Entry AFRR1 FORM 61b (R) Revised: 14 July 95 Page1

V. LOBBY AREA Lobby audio alarm tumed a ff ..... .. ...................................................

VI. REACTOR CONTROL ROOM (Room 3160)

1. Emuumicy air dampem mset .........................................................

2. Co nso le mco niem dated . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .

3. Stack fiow and fuel temperatum recordem dated .............................

4. Lo gbo o k dated and myiewed .. ...... ...... ........ ...... .... ............ .... .......... .

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

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

(c) DM 1 resistivity ( > 0.5 Mohm-cm) ... ............ .. ............ .. .......... .... *

(d) D M 2 resistivity ( > 0.5 M ohm-cm) ............................................. *

6. Stack gas flo w rate (15 - 35 Kcfm) .... ........ .. .... ...... ........ ...... .......... ...... *

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

8. Gas stack monitor (a) Backgro und (2 - 20 cpm) . .. .. .. , . . .. .. .. . . .. .. .... .. .. .. .. . . .. .. . . .. .. .. .. .. .. . . . *

(b ) A lann check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

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

(a) R-1 (< 20)

• 20 (b) R 2 (< 10)

• 10 (c) R-3 (< 10)

• 10

(d) R 5 (< 20)

• 20 l (e) E-3 (< 10)

• 10 (f) E-6 (< 10)

• 10

10. TV monitom on ............................................................................

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

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

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

14. Soun:e level power gmater/ equal to 0.5 cps. ...................................

AFRR1 FORM 61b (R) Revised: 14 JUl95 Page 2

OPERATIONAL,._

u~_. a -_maa; a_. PROCEDURE,C ..

.w.am; ,_~1~ '1 ,,,,,;-y,_l __'? _w - - , n_Proce_d_ure8,a. TAB In.

m DAILY OPERATIONAL SHUTDOWN CHECKLISI' Checklist No. Date Time Completed - Supervised by Assisted by I. REACTOR ROOM (Room 3161)

1. All ro d d rives D OWN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2. C arriage lights OFF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3. D o o r 3162 SEC U R ED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4. Channel test completed on both CAMS .........................................

5. D o o r 3161 lo eked with key . . . . .. . . . . .. . . . . .. .. . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

II. EQUIPMENT ROOM (Room 3152) 1

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

)

l 2. Air dryer OPER ATlON A L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .

l 3. Doors 231, 231A, and ruof hatch SECURED ................................

1 III. EQUIPMENT ROOM (Room 2158) l

1. Primary discharge pmssure (15 - 25 psig) ..................................... *

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

3. Visual inspectio n fo r leaks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4. D o o r 2158 and 2164 SECU R ED . .. . . . . . . . . . . . . . . . . .. . . .. .. .. . . .. . . . . .. . . .. .. . . . . . _. -

1 IV. PREPARATION AREA

1. ER 2 plug door CONTROL LOCKED .........................................

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

2. E R 2 lights O N and rheo stat at 10% . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i

3. ER 1 plug do or CONTR OL LO CKED ......................................... 1 l

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

l

4. E R 1 lights O N and rheo stat at 10% . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l

5. Visual inspectio n o f area . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . .. .. . . . . .. . . . . .. . . . . .. . . . . . . . . .

6. Warm sto rage d o o rs clo sed . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .

1 AFRRI Form 62(R) Revised: 14 Jul 95 Page1

V. LOBBY ALARM

. Lo bby alarm audio O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

VI. REACTOR CONTROL ROOM (Room 3160)

1. R eacto r tank lights OFF . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . . .. .. . . . . . . .. .. .

2. Console chart mcorder pens raised .................................................

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

4. Console LOCKED, and all mquimd keys mturned tolockbox......................................................................................

5. D iffuser pumps O FF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

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

8. R adiatio n mo nito rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

MONITOR READING HIGH LEVEL ALARM l SETTING (mmm/hr)

a. R-1 (< 20)

• 20

b. R-2 (< 10)

• 10

c. R-3 (<10)

• 10

d. R-5 (< 20) 20

e. E-3 (<10)

• 10  ;

f. E-6 (< 10)

• 10

g. R-6 (< 10)

• 10 i

l 1

• Numerical Ent2y i

i I

AFRRI Form 62(R) Revised: 14 Jul 95 Page 2

OPERATIONAUPROCEDDREL--

.~.c -we , ,

. a, . un m au .naaa auw ; IP2555ireif9 u- ~ .

AIR PARTICULATE MONITOR (CAM) PROCEDURE GE NE R AL This procedure specifies how to test the CAM to ensure proper operation of this monitoring device. A channel test will be performed on both reactor room CAMS at the beginning and end of each day.

SPECIFIC

1. OPER ATING and TRACING Check that the primary CAM is operating and tracing with the correct time indicated on the chart and check that the secondary CAM is operating.

Ensure the flow rate is >6 cfm and not off scale.

2. CH ANNEL TEST WITH SOURCE

a. Place the switch on the front of the CAM to " test" and verify a reading of 1000 cpm +/-20%. Reset the switch.

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

l l

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

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

d. Annotate completion of the channel test on chart paper with initials, time, and date performed for primary CAM. Annotate comoletion of the channel test on secondary CAM chart oaper only when crimary CAM is bypassed.

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

4. BY-PASS of PRIM ARY CAM Revised:08 Aug 95 Page1

When the primary CAM is by-passed, the secondary CAM chart recorder needs to

' be activated, then perform items 1,2a, and 2d.

s i

i i

)

l l

1 I

I Revised:08 Aug 95 Page 2  !

ATTACHMENT B i 10 CFR 50.59 Safety Evaluations of Modifications, Changes, and Enhancements to Procedures or Faci!ities Replacement Of CAM Electronics Replacement Of Reactor Security Computer Substitution Of in-Plant Perimeter Monitoring TLDs Section On Malfunction Log Entries Added To Procedure 8, Tab A  !

HPP 3-1 Changed For CAM Level Reading For Exposure Room Entry.

HPP 7-3 Changed To Add Chart Recorder Settings -  :

1 Section Added To Prep Area Frisking Procedure Procedure 11 Changed To Reflect Change Of CAM Chart Recorder Usage  !

Damper Roset Switch Added To Reactor Foyer I

Procedure 1, Tab A, CAM Level Reading for Exposure Room Entry Changed j Stack Gas Monitor Stack Sample Tubes Replaced

!- Remove Stack. Gas Monitor Printer h Replace Stack Gas Monitor Electronics

{ - Revision Of Daily Operational Startup Checklist l I ~ Revision Of Daily' Operational Shutdown Checklist ,

l- Revision Of Daily Safety Checklist

[ Revise Air Particulate Monitor (CAM) Procedure j

! Revise Facility Modification Procedure

{

i I

L i

L r

I 1

FACILITY MODIFICATION CUMMARY CHEET 1995 NUM INITIAL TYPE LOCATION PROPOSED CHANGE NS DATE CHANGE COMPLETED APPROTED APPROTED

1. DATE DATE (RFD) 013 (RRFSC) 7 1 3 Jan 95 Facility P11 Replacement of CAM Electronics 2 3 Aug 95 4 Jan 95 1 Mar 95 2 3 Jan 95 Facility PSP Replacement of Reactor Security computer 2 4 Jan 95 4 Jan 95 1 Mar 95 3 9 Feb 95 Facility HPP 4-6c Substitution of Navy TLDs for in plant 2 9 Feb 95 9 Feb 95 1 Mar 95 perimeter monitoring 4 23 Feb 95 Procedure P8-Tab A Add Section on Malfunction Log Entries 2 1 Mar 95 23 Feb 95 1 Mar 95 to Procedure 8, Tab A 5 12 May 95 Procedure HPP 3-1 Change CAM level reading for exposure 2 31 Oct 95 1 Jun 95 18 Oct 95 room entry 6 15 Feb 95 Procedure HPP 7-3 Change to add chart recorder settings 2 31 Oct 95 1 Jun 95 2 Jun 95 7 25 May 95 Procedure PROC. A2 Add section on Prep Area frisking 2 18 Jul 95 2 Jun 95 2 Jun 95 8 25 May 95 Procedure PROC. 11 Change use of secondary CAM chart 2 2 Jun 95 1 Jun 95 recorder 2 Jun 95 9 25 May 95 Facility n/a Damper reset switch added to reactor 2 25 May 95 25 May 95 2 Jun 95 foyer.

20 25 May 95 Procedure PROC. 1, Change CAM level reading for exposure 2 24 Jan 96 1 Jun 33 18 Oct 95 Tab A room entry 11 25 May 95 Facility n/a Replace tubes from stack monitoring 2 25 May 95 25 May 95 't Jun 95 system 12 20 Jun 95 Facility SAR Remove stack gas monitor printer 1 21 Jun 95 18 Oct 95 13 12 Jul 95 Facility SAR Replace stack gas monitor electronics 1 12 Jul 95 18 Oct 95 14 14 Jul 95 Procedure PROC. 8, Tab B Revision of Daily Operational Startup 2 14 Jul 95 14 Jul 95 18 Oct 95 Checklist 15 14 Jul 95 Procedure PROC. 8, Revision of Daily Operational Shutdown 2 14 Jul 95 14 Jul 95 18 Oct 95 Tab I checklist 16 14 Jul 95 Procedure PROC. 8, Revision of Daily Safety Checklist 2 14 Jul 95 14 Jul 95 18 Oct 95 Tab B1 17 8 Aug 95 Procedure Proc. 11 Revise Procedure Air Particulate Monitor (CAM) 2 9 Aug 95 9 Aug 95 18 Oct 95 18 9 Aug 95 Procedure Proc. A3 Revise Facility Modification Procedure 2 9 Aug 95 9 Aug 95 18 Oct 95

i

. I 4 1 Facility Modification Worksheet 2 (

No 10 CFR 50.59 Analysis Required l Replacement of the CAM Electronics l Proposed Change I

^^^

l Modification to: Procedure Facility Experiment l Submitted by: Date

1. Description of change:

Replacement of the CAM electronics module. The old electronics have become outdated and the electronics are being replaced as part of preventive maintenance. 'Ihe new electronics module is a one for one replacement.

1 i

i

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in R .59 a)(2 .

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, forward a copy of changes necessary to 14gistics.

NONE.

4. Determine what othergrocedures, NE. logs, or training material may be affected and record below.

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

Updated drawings will filed.

Gay Prae s a ll J w insinIlh on i! ""Y I$t0-

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

Action Sheet: Submitted Not RequireF Reviewed and approved by RFD fM Date RRFSC Notified MM/M' b Date 01 MAR 1995

/

Revised: 15 May 91 Page 6

t i

j Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required

Replacement of the Reactor Security C7 =+=r

! Proposed Change Modification to: Procedure Facility Experiment George 03 JanM Submitted by: Date

1. Description of change:

The reactor security computer system is being upgraded with a new and more user friendly ,

computer interface. The new system is designed as a one for one rf=- ==t. 'Ihe new computer will allow the operator to control alarm points, schedules, badges, and it will deliver alarm messages to the security desk in AFRRI. 'Ihe D600 unit which is the microprocessor controller specified in the reactor physical security plan will not change. The new computer interface will communicate with the D600 unit.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not pg* an unresolved safety question as defined in 10 i CFR 50.59(a)(2).

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

NONE. Same as before

4. Determine what other procedures logs, or trainina material may bp affected and record below. Security guards were, tramed to clear aTarms. Further traimng for reactor staff to be scheduled.

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

NONE i

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

Action Sheet: Submitted Not RequireF Reviewed and approved by RFD d _

Date RRFSC Notified M@ld Date 01 MAR 1995

'/ (

Revised: 15 May 91 Page 6 pr- --

1 Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change Modification to: Procedure Facility X Experiment Submitted by: h 66ni Date 23 7% Tf

1. Description of change:

54shMe 13aat Ocs< A% Jylled Doslak -Fev

% EWM .%c d esi & s os<.cl fev + k %

yl% f gu d h TLDs (.m+ mviavt d () Ioen W

&l nu / kFegr. BA

~AstLavierabhrud desish.Ws au cya.Ily dt.k.( l- ra din.W .

a He < > +4ay ke+k. usr Tu?-tco fu

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). \/yt.7 tid

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics. p/g

4. Determine what other procedures, logs, or training material may be affected and record below, h4 6/ 125 D R.C. W 4.Nk Minsv 4 b do S HO ltf9 l1-/a.C.

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

Nene.

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

Action Sheet: Submitted Not Required I Reviewed and approved by RFD Date f RRFSC Notified cA-l'7#///

w Date 01 MAR 1995 Revised: 27 May 93 Page 6

SAFETY AND HEALTH DEPARTMENT HEALTH PHYSICS PROCEDURE 44.D Date 08 Feb 95 IN PLANT RADIOLOGICAL MONITORING Supersedes 08 Nov 94

1. General

a. Purpose To describe the surveys and sampling performed to document radiation and contamination levels existing outside of Reactor Controlled Areas and the TLD monitors located throughout the facility. This data can also be utilized for the assessment of occupational exposures in case of dosimetry loss or unexpected dose readings.

b. Responsibility i

(1) SHDH: Responsible for collecting and issuing the facility and perimeter inplant TLD's and for performing the various health physics surveys and sampling.

(2) SHDD: Responsible for providing calibrated instrumentation, radioanalysis support, and facility in-plant TLDs.

2. References

a. Regulatory (1) 10 CFR, Parts 20 and 30.50 (2) USNRC Licenses 19-08330-02 and 19-08330-03

b. Technical (1) Hendee, Radioactive isotopes in Biological Research, pg. 242,1973 (2) USNRC Regulatory Guide 8.23, Radiation Safety Surveys at Medical Institutions,1981 >

1

t HPP 4 s.D 08 Feb 96

3. Definhions

a. Facility in-plant TLDs: TLDs supplied by the Naval Dosimetry Center which are used within the AFRRl complex to monitor for gamma or neutron radiation.

b~. BorWaterinifilah01LDei!UIINiTiiiiilliiillfby1hDIdlNDenimetriCenterwhich~are haiedicrf.9(roof i end_ bull @gJLo!Imot(SRRIWWWWradia%

c. Facility background TLD: TLDs supplied by the Naval Dosimetry Center which are used as the background control for the facility in-plant TLDs.

d. Perimeter background TLDs: TLDs supplied by the Eberline, Inc. which are used as the background control for the perimeter in-plant TLDs and the environmental TLDs.

e. Survey: An assessment of radiation levels or radioactivity concentrations and/or levels by a means (i.e., smears, direct reading instruments) appropriate to the specific set of conditions.

4. Procedures

a. Facility in-plant TLDs (1) Fifty faciity in-plant TLDs are maintained at locations as shown in enclosure 1(a-d). Two TLDs are located on the waste compactor and desk, respectively, in the Radiological Waste Facility. Four TLDs are used for quality control purposes.

At least one TLD is maintained for control (background) purposes in room 1427.

(2) SHDH shall distribute TLDs to their respective stations within 5 working days of receipt from SHDD. The date of their distribution shall be entered into the appropriate spreadsheet file at that time. Quality control TLDs shall be dosed to 30 and 100 mrom respectively (see HPP 5-7) at the time the TLDs are distributed to their stations.

(3) The TLD cycle shall coincide with everfother SHD personnel dosimetry change schedule (approximately every 13 weeks). SHDH shall collect all facility in-plant TLDs within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. The date of TLD collection shall be entered into the appropriate spreadsheet file at that time. Two additional quality control TLDs shall be dosed to 30 and 100 mrom respectively within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of TLD collection.

2

l i

HPP 4 aD HMN 1

(4) SHDH shall retum the TLDs to SHDD for shipment and processing at the Naval Dosimetry Center.

(5) Upon receipt of the dosimetry report, SHDD shall immediately forward the results for the in-plant and control TLDs to SHDH. Hi4WTTHOM j pliseedshiet _, year) shall be used to tabulate the results in a summary format. TLDs that are lost or damaged shall i have results entered into the spreadsheet as ' lost". l l

(6) The dose under the " Deep Dose Equiv Photon" column of the report shall be entered for all TLDs. TLDs #48 through 57 shall have the dose under the ' Deep Dose Equiv Neutron" column of the report entered. The spreaddest indicates when to notify the RSO should any action levels or limits be exceeded.

(7) Attach a copy of the dosimetry report to the spreadsheet report and route through the RSO before committing to file,

b. Perimeter in-plant TLDs ,

(1) Sixteen perimeter in-plant TLDs are maintained at locations on the roof and building perimeter of AFRRI as shown in enclosure 2.

~

(2) TLDs shall be distributed by SHDH to their respective stations within 5 working ,

days of receipt. The date of distribution shall be entered into the appropriate spreadsheet at that time. Quality control TLDs (#66 and 67) shall be dosed to 30 l and 100 mrom respectively (see HPP 2-1 and 5-7) at the time the TLDs are i distributed to their stations.

(3) The distribution and retrieval of the TLDs shall coincide with the Facility in-  ;

plant TLD change. SHDH shall collect all perimeter in-plant TLDs within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Quality control TLDs # 68 and 69 shall also be dosed to 30 and 100 mrom, respectively within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> collection period. The date of collection shall be entered into tN appropriate spreadsheet file at the time of collection.

(4)'SHDH~shall'une the~QUATTRO PRO spWW+TJERIMIXX.TLD.(whWr~e'XX indicates the; year of the report) to tabulate and calculate the not doses to the TLD stations. TLDs that are lost or damaged shall have " lost' entered into the I spreadsheet where the results would normally have been entered. Ensure that the badge # indicated on the Eberline and Naval:Doelmstry!CenterTLD reports ,

coincides wKh the TLD # listed in the spreadsheet when TLDs have been lost or '

damaged. The spreadsheet indicates when to notify the RSO should any action levels or limits be exceeded.

3 i I

w - - _- ___ _ . . _ _ __ _ _

(.-- - ..- . - - - - - _ - . . - - - - - . - . - - . ---- - -.

HPP 44.D t

es Feb ts (5) Attach a copy of the TLD report to the spreadsheet report and route through i ' the RSO before es,T,,,,;;;; ,g to file.

4 l c. Radiation Area and Continuous Air Monitors-i 4

Radiation Area Monitors and Continuous Air Monitors are located throughout the AFRRI complex. These instruments shall be maintained and calibrated according to HPPs 7-2 and 7-3, respectively.

) d. Routine Surveys

(1) The surveys listed in onclosure 3 shall be conducted at the frequency indicated.

j Survey types denoted by "D','S", and "P" indecate a survey with a direct reading j portable survey instrument, a smear survey, and sampling /radioanalysis, a respectively.

(2) All routine radiological surveys shall be conducted according to guidance set forth in HPP 8-1, " Radiological Survey Techniques' and any other reference HPP specified in enclosure 3. The surveyor shall also perform the following functions and make written notations as appropriate on the survey form.

(a) Review previous SHDH survey results to determine pattoms or problem 1

areas. Survey posted storage locations, benches, centrifuges, hoods, lead pigs, radioactive and regular waste containers, sinks and the floor outside the entrance to the lab.

!" (b) Any count rate or exposure rate above background observed during a direct reading survey shall be identified as to its source. If necessary, smears j shall be taken to determine if removable contamination exists.

j. (c) Consult with lab personnel regarding type and activity of isotopes used and i

locations of use/ storage in the lab. Observe lab personnel for proper handling i

of radionuclides (i.e., no mouth pipetting), proper dosimetry being wom, and any consumption of food / drink within the lab.

' (d) If a survey instrument is required to be maintained in the lab, verify an operational and calibrated survey meter is present.

(e) Ensure that the warm drains are open in rooms where radioactive animals are housed and that cages and the entrance to the room are properfy posted as a radioactive materials area and, if appropriate as a radiation area.

4 1

1

HPP 44.D Os Feb s5

, (f) Check labelling and postings of lab entry door, hoods, radioactive waste receptacles /cubitainers, sink drains, radioactive material containers, refrigerators, and any area with extemal radiation readings greater than 5 mrom/hr in any accessible area. Replace any wom, damaged, or faded j

labelling and postings.

(g) Ensure that radionuclide storage areas (i.e., refrigerators, lead caves) do not cause the presence of radiation levels above 0.5 mrom/hourin any areas adjacent to the storage area.

(h) Check all radioactive waste documentation cards to ensure they are complete and accurate.

(i) Take additional and/or random smears based on observations, conversations with lab perscnnel, and areas having a high potential for contamination (e.g., pipetting areas, water baths for radioactive samples).

(j) If contamination or unexpected radiation levels are found when performing a direct reading survey, inform lab personnel and date and note who was informed. Expand the scope of the survey to ensure that the detectable .

radiation levels are limited to a well defmed area.

(3) Radioactive Animal Surveys (a) Activated / injected radioactive animals shall be surveyed by SHDH at the time they are moved into VSD for housing or necropsy.

(b) The cages of such animals shall bear a " Caution - Radioactive Materials" tag which clearly indicates the date of inadiation or injection, and in the case of injected radioactive material, the activity and nuclide injected.

(c) The door to the VSD room housing a radioactive animal shall be posted

, with an AFRRI Form 121, " Radioactive Animals Survey" , a " Caution -

Radioactive Materials

• sign, and if appropriate, a " Caution - Radiation Area" sign.

(d) If the animal has been injected with H-3 or C-14, the four maximum dose rate columns on AFRRI Form 121 shall be filled out as "N/A, H-3/C-14 injected".

5

i

?

j. HPP 4 s.D MMM j e. Non-Routine Surveys i

j Non-routmo and unusual incident surveys shall be conducted by SHDH personnel.

The RSO shall dete

mine the type of survey required and the instrumentation to l be used.

i

! f. Survey Documentation f

(1) Results of all surveys which require radmanalysis shall be documented on j AFRRI Form 144 (enclosure 4).

l 1 (2) Surveys listed in enclosure 3 that have HPP's 4-4 or 4-6 as a reference shall l be documented in SHD files as follows:

l

~

(a) A fkmr plan of the Rad Waste Facility areas (including the pump house) where radioactive materials and large sources are present shallindicate where direct and smear surveys are to be taken.

(b) A floor plan of the LINAC facility areas where radiation levels may exist due to activation shall indicate where direct and smear surveys are to be taken.

(c) A listing of the radiation levels in the immediate areas of the Cobalt Pool purification system, specifically the profilter and resin containers.

(d) Direct neutron and gamma surveys of the top, side, and plug area of the Cf-252 irradiator shall be performed.

(e) Direct neutron and gamma surveys of the top and sides of the Pu-Bo source shall be performed. The highest reading obtained from the survey of the sides shall be recorded.

(f) A listing and/or floor plan of the laboratory areas where radioactive materials and radioactive animals are present shall indicate where direct and j smear surveys are taken. Any radioactive material storage area that is not an i integral part of a posted area shall also be indicated on the floor plan.

(g) A listing and/or floor plan of "public' areas throughout the institute shall indicate where smear surveys are taken.

I 6

HPP 44.D 08 Feb SE l

(3) The location of any surveys or sampling taken in addition to those documented in (a) through (g) above shall be recorded on the respective floor plan / listing or if I appropriate, part B of AFRRI Form 144. Rad 6oactive animal room surveys shall be documented using AFRR1 Form 121.

(4) Results of leak testing, X-ray unit surveys, and shielding surveys require documentation via a Memorandum for Record (MFR). Documentation of leak tests shallinclude the results and whether or not action levels (as specified in HPP 0-2) )

were exceeded. Documentation of the X-ray survey shallinclude, at a minimum, a detailed description of the survey performed, what instruments were used, and l what radiation levels were present.

(5) Documentation required for non-routine and unusualincident surveys shall be specified by the RSO on a case by case basis.

g. Survey Evaluation (1) The SHDH individual who performs a survey is responsible for ensuring the l radionnalysis results are evaluated with respect to the action levels in HPP 0-2. 1 (2) Smear and sampling surveys that indicate contamination or radioactivity levels above action levels shall be followed up with a complete survey of the lab / area of i concom. SHDH shall inform personnel who work in the area as to the results of such surveys I

(3) Direct reading surveys which indicate radiation levels above background that cannot be identified as to their source shall be brought to the attention of Chief,  ;

SHDH.

l 5. Enclosurea

a. Enclosure 1(a-d): Facility in-Plant TLD Locations

b. Enclosure 2: Perimeter in-Plant TLD Locations *

c. Enclosure 3: Routine Radiological Surveys lI L C yC Wv$L

d. Enclosure 4: AFRRI Form 144, Part B

e. Enclosure 5: AFRRI Form 121, Radioactive Animals 7

l l

l l

l

l 1

l Facility Modification Worksheet 2 l

No 10 CFR 50.59 Analysis Required Proposed Change Modification to: Procedure XXX Facility Experiment E

Submitted by: Date 23 Al 95 l

1. Description of change:

The change to this procedure adds a section on malfunction log entries. This section specifies a format to follow for consistency in entering malfunction entries. The new .

keywords to be used are SYMPTOM, RFD NOTIFIED, DIAGNOSIS, SOLUTION, l OPERATIONAL VERIFICATION AND/OR CALIBRATION.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 l CFR 50.59(a)(2).

NONE.

l

3. If change involves a facility modification, attach a drawing if appropriate. If structt:ral facility drawings need updating, forward a copy of changes necessary to Logistics.

l

4. Determine what other procedures, logs, or training material may be affected and record below.

NONE

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

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

Action Sheet: Submitted Not Required XXX

1. I 2 3 FEB 1995 Reviewed and approved by RFD d-[M D ate RRFSC Notified dr7S/6t v Date 01 NAR 1995

[

Revised: 15 May 91 Page 6

.. l

. .: ,g,,

l LOGBOOK ENTRY CHECKLIST l I. Operational Logbook

1. The reactor operations logbook is a before4he-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 Reador Facility Director (RFD) will review each logbook upon its completion; he will make an appropriate entry in the back of the logbook and sign the entry. The operator who makes the final entry at the end of a logbook is responsible for ensuring that the ROS is notified that the logbook is ready for RFD review, J

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

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

a. BLACK and BLUE-BLACK:

(1) Console locked and unlocked. The individual at the console will enter l his/her name and the supervisory licensed operator's name, if necessary.

(2) Checklist number and completion time.

(3) Power level at criticality and subsequent power level changes.

(4) Reactor SCRAM.

(5) Mode of operations. Use appropriate stamp or entry to designate the operation: i (a) Steady State (b) Square Wave (c) Pulse Revised:22 JUL 91 Page1 i

m , - . .

s j (6) Operation of remor associated fadlities such as lead shield doors,

pneumatic tube systems, etc., ucless such operations cause a change of reactivity

!' (see 5.b.(2) below).

l (7) Change of personnel at the console. Name of personnel will be entered

! along with the li<ennad operator present in the control room, if the person at the

! console is not a licensed operator.

1 j (8) The operator in charge will be designated in the logbook whenever 4

multiple operators are signed on the console.

) (9) Completion of the daily startup and shutdown checklists and weekly 4 checklist.

1 (10) Signature of reactor operator to close out the log for the day. ,

j (11) Designation of the SRO on-call and physicist in charge (PIC).

{ (12) Reactor calibrations and data.

\ (13) All line outs, entry errors, changes in mode of operation stamp lines, and j end of page line outs will be initialed or signed by the operator.

i b. RED:

l (1) K excess measurements, to include experiment worth determinations.

{ (2) Actions which affect reactivity:

l (a) Core movement, t

j (b) Fuel movement.

1 (c) Control rod physical removal for maintenance.

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

c. GREEN:

j (1) Any reactor malfunctions noted upon discovery / occurrence with a second

) entry noting mrrective action has been completed.

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

] addition of make-up water to the reactor pool, etc.

! (3) Any Technical Specification required equipment taken out of service for

! any reason. A second entry is made when the unit is returned to service.

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

i l Revised:22 JUL 91 Page 2 i

1 _. _ _ _ _ _ _

II. Malfunction Logbook

- All entries in the malfunction logbook should include the following information. ,

For consistency, the bold italic words abould be copied into the malfunction log prior to the information.

DATE, TIME, SIGNATURE OF PERSON DISCOVERING MALFUNCTION SYMPTOM: of problema This section describes how the system is acting or malfunctioning. I.E. channel went fuH scale, pump failed, keyboard stopped responding to keystrokes etc.

IMMEDIATE ACTION TAKEN This section is for denoting such things as Reactor Secured, SHD notified.

RFD NOTIFIED:

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

DIAGNOSIS : of problem A narrative description of what was discovered to be causing the problem. I.E. i

_ Which system was malfunctioning or which component failed.

SOLUTION: / repair l

A narrative description of what was done to correct the problem This could '

include both physical changes or administrative changes. I.E. A component was replaced and the unit was recalibrated, an additional backup system installed, an administrative prohibit on ... was initiated.

OPERATIONAL VERIFICATION AND/OR CALIBRATION:

A description of what actions were taken to verify that the new unit / repair would indeed perform the intended function for which it was intended. I.E. A -

calibration signal, system actuated multiple times, system tested, system calibrated with a source, Indicate whether the change will require staff training.

SIGNATURE RFD Revised:22 JUL 91 Page 3 l

Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change HPP 3.I ,

"A%de I,nh,Hw &ib/ier " '

Modification to: Procedure X Facility Experiment Submitted by: O'82ESAI Date /2 /%v 95

1. Description of change: f)..je a

C. h M } e ot.\ ruk t CA f m niYre.h &

ncn- m4 rec? cpingt -

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). gg

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forwaro a copy of changes necessary to Logistics. #/M

4. Determine what other procedures, logs, or training material may be affected and record below. gg

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

/1lrne.

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

Action Sheet: Submitted Not Required  !

Reviewed and approved by RFD L

V Date 14 JUN 1995 RRFSC Notified -

m [92~/N Date JUN 2 1995 U

(J _

Revised: 27 May 93 Page 6

G Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change llfP 7- 3, "Airbon e $a d'eoclittilV Sanidrs 4 Plo>ridis

Modification to: Procedure >f Facility Experiment

Submitted by

O'8BIEA/ Date /546 75 i

l 1. Description of change:

l p,,ccLe v4W& nf4ct 7;ge Q)

G /ocsee~c/. resp

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2).

h04

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to legistics. v/8

4. Determine what other procedures, logs, or training material may be affected and record below. gyA r. Proulee. j , T/16 A 4 ,c % <- R . & <y "

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

NM \

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

Action Sheet: Submitted Not Required [

Reviewed and approved b FD N</ Date 01 JUN 1995 RRFSC Notified >[YM Date JUN 2 tom D' -

() ~~

Revised: 27 May 93 Page 6

1 i

SAFETY AND HEALTH DEPARTMENT HEALTH PHYSICS PROCEDURE 7-3.C Date 15 Feb 95 i AIRBORNE RADIOACTIVITY SAMPLERS Supersedee 06 May 94 AND MONITORS I 1. General

a. Purpose and Scope: This HPP describes the operation, calibration, and

! maintenance procedures required for the Continuous Air Monitors (CAMS), Reactor l Stack Gas Monitor (SGM), and portable air sampling equipment.

i b. Responsibility

(1) SHDH is respeavilt br performing a daily check on all CAMS except those i required by NRC license R-84.

j (2) SHDD is responsible for maintenance and calibration of all portable air sampling equipment, and maintenance, calibration, and channel testing of all j CAMS not required by the R-84 license. SHDD shall provide calibration support l to RSDR for R-84 license required CAMS and the Reactor SGM.

(3) LOGI is responsible for routine preventive maintenance and electronic calibration support for CAMS and the Reactor SGM upon request.

(4) RSDR is responsible for performing daily checks and channel tests of R-84

license required CAMS and the Reactor SGM.

f

2. References

a. Regulatory (1) 10 CFR 20.1202,1203,1204,1301, and 1302.

1 (2) Appendix B to 10 CFR 20'.1001 - 20.2402.

(3) NRC License R-84, Technical Specircations l (4) AFRRI Instruction 3020.2 "AFRRI Emergency Evacuation and Fire Plan' 1

HPP 74.C is Feb es

b. Technical (1) Bames, David, " Radiation Hazards and Protection" 1963 (2) DF dated 20 Sep 78, J. A'rras, 'TRIGA Emergencies, Dose Estimates" (3) DF dated 01 Mar 83, W. Webber, ' CAM Alarm Settings" (4) CF-970T Series Air Sampling Pump Manual (5) Nuclear Measurements Corporation Model AM-221B-P Radiation Monitoring System Instruction Manual (6) DF dated 29 Nov 71, J. Arras, " Reactor Dock CAM Readings" (7) DF dated 20 Aug 80, L Slaback, " Reactor Emergency Alarm Points'

3. Definitione i

a. Continuous Air Monitor (CAM): A CAM consists of a mobile rock-mounted chart l recorder, air pump, shielded G-M detector, adjustable alarm settings, flow rate I indicator, analog count rate meter, and associated electronics. The unit also has a control valve to maintain constant' air flow as well as to adjust for a specified air flow rate. The CAM is designed to monitor and record airbome gaseous and particulate radioactivity on a continuous basis.

Il

b. Stack Gas Monitor (SGM): The reactor stack gas monitoring system uses a multi-nozzle probe to sample the exhaust air in the reactor ventilation system which is drawn through a detector chamber to determine the average concentration of Ar-41 in the exhaust air.

c. Portable Air Samplers: Units designed to collect particulates from the air onto a filter for subsequent radioanalysis.

d. Channel Test: The introduction of a signal (i.e., exposure of the CAM detector to a radiation field) to verify the instrument is operable.

1

HPP 7-3.C 15 Feb 95 i i

4. Procedures

a. CAM Operation '

UTEG8M10 canons entsettinggj Location High Alarm Low Alarm Fall Alarm Chart / Pen (cpm) (cpm) (cpm) Recorder

• Reactor 10K 4K On Dock Primary Reactor 10K 4K Off Dock-Backup Prep Area 74 - 50 Off Exposure 50K -

50 Off Room 1 1

Exposare 50K -

50 Off Room 2 ERC 1" 2K - 50 Off i ERC 2 2K -

50 Off M KWMN'.E

!Licciated.

" Used in front lobby during potential radiological emergencies.

(2) Daily Check SHDH shall perform a check as described below on the CAMS specified in 1.b.(1)

(a) Change the CAM filter by opening by the detector cover and removing the filter using tweezers. Replace it with a NMC glass fiber filter (part #0965942) and place the used filter in a box / bag labelled as radioactive material which is located in the drawer of the CAM. Used filters may be stored in the CAM drawer but should be disposed of as radioactive waste at least monthly.

(b) Check the CAM with the intomal test pulser by flipping the switch located on the face of the monitor from OP to TEST. The observed count rate on the analog meter must be within i 20% of 3600 counts per minute.

3

i l '

l HPP 7 8.C 15 Feb 95 (c) It may be necessary to gently tap on the chart wheel or meter face to ensure that the pin and meter needle have freedom of motion.

l (d) Retum the switch to OP.

4

{ (e) Observe the flow rate value on the magnehelic gauge. If it is off-scale or

less than 6 CFM, notify Chief, SHDD.

I I E i (g) Whenever chart paper is' removed from the CAM, it and its storage box shall l be labelled with the date of removal, the location, and serial number of the 4 CAM. Put the expended chart paper in the box which contained the new roll I

of chart paper and place it in room 1120 (warm storage) for storage.

1 (j) Any CAM found to be malfunctioning or inoperable shall be immediately

{ tagged out of service and Chief, SHDD shall be notified.

)

i (3) Calibration and Channel T,esting i

3 (a) Frequency

1. All R-84 license required CAMS shall be calibrated overy 6 months not i to exceed 9 months, and channel tested every 3 months not to exceed 4 l months. RSDR shall contact SHDD to arrange for any calibration support j necessary to meet the required frequency.

2. All other operational CAMS within AFRRI shall be calibrated every 6 months, and channel tested every 3 months, not to exceed 4 months.

)

l 1. A flow calibration shall be performed on all CAMS every 6 months.

l 1

! (b) Electronic Calibration t ,

l 1, An electronic calibration shall be performed before overy isotopic calibration. This calibration, along with preventive maintenance, is '

j performed by an outside contractor.

j 2,, Observed values indicated by the analog meter and the chart recorder

{ shall be within i 20% of the input test values of 100,1000, and 10000 cpm.

i l 4 i

l i

I l

I l

i i

COttTINDOUS AIR MONITOR DAILY CBBCK Test Pulser Flow Rate Date/ Initials (cpm) (cfm) i I

i l

l Enclosure la to HPP 7-3 l

l l

7 Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change hreeedure Ac2, "A<smel 8ssaa Thu,J 8 fr<s Area e g -

Modification to: Procedure X Facility Experiment Submitted by: Ne d/un Date 26/0 f.8

(/ '

1. Description of change:

YS .Spcc/hc .5e cWNAl d ^)

Y QM Skt Yeh /$ge& ,

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or pocedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 '

CFR 50.59(a)(2). pg '

3. If change involves a facility modification, attach a drawing if appropriate. If structural approved by RFDfacility drawings and forward need a copy updating, of changes modification necessary to Imgistics. A/of drawings mu

4. Determine what other procedures, logs, or training material may be affected and record below.

Mbhf

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

671 6

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

Action Sheet: Submitted Not Required K 01 JUN 1995 Reviewed and approved by RF Date RRFSC Notified . , [ k [/  % Date JUN 2 1995 h [ ,

Revised: 27 May 93 Page 6

W

_5HfN.. i5WG,WWW6656.6.i[E.?A9?fMs"a" IBM s: 2 w_

w 3E...E7??S$!$m!ElBiW6sds#_IiEE n PERSONNEL PASSAGE THROUGH THE PREP AREA GENERAL Access to the Reactor Prep Area is limited to personnel who are granted access in accordance with the reactor physical security plan and Operational Procedure 1.

The Reactor Facility Director is responsible for maintaining an unescorted access roster for the Reactor Prep Area and for providing a Prep Area briefing to all persons listed on that roster. This administrative procedure does not recapitulate the operational procedure. Rather, it presents specific guidelines for Reactor Prep Area passage, and frisking for individuals who are authorized access.

SPECIFIC

1. ROUTINE PASSAGE:(EXPOSURE ROOM DOORS CLOSED)

a. Personnel who are authorized unescorted access to the Reactor Prep Area may pass through the Prep Area as necessary.

b. Personnel who are being escorted through the Reactor Prep Area may pass through the Prep Area only with their escort.

c. Only appropriate personal dosimetry that has been issued by SHD or AFRRI Security is required for routine passage through the Reactor Prep Area. There is no requirement to wear a pocket chamber in addition to the AFRRI issued TLD for routine passage.

2. CONTROLLED PASSAGE:(EXPOSURE ROOM DOOR OPEN)

a. Only personnel associated with the experiment / operation being performed are normally authorized access to the Reactor Prep Area during an exposure room opening. These personnel will be required to wear the AFRRI TLD dosimeter (issued with their AFRRI badge), pocket chamber (if dose rate at face of door is 2 mr/hr or more), and AFRRI wrist dosimeter or finger ring dosimeter if they enter the exposure room.

All personnel who enter an exposure room will log their pocket chamber reading in the pocket chamber log prior to entering the room for the first time that day and will enter the final pocket chamber reading following their exit from the exposure room at the end of the day. Each individual who enters an exposure room is responsible for monitoring his accumulated dose throughout the day to ensure the he/she does not exceed the AFRRI daily Revised:25 May 95 Page1

5 4

exposure limits of 50 mrem / day or 100 mrem / week. Extremity dosimetry is required only if work is to be performed on an experimental array or within j 1 meter of the core projection.

b. Personnel authorized unescorted access to the Reactor Prep Area or

, personnel being escorted through the Reactor Prep Area may pass through j the Prep Area when an exposum room is open with permission from the j reactor staff person in charge during the opening if the following guidelines i are met:

i .

! The person desiring passage must stopjust inside the Prep Area door i upon seeing that an exposure room dooris open and request i permission from the reactor staff member in charge before proceeding.

At that time, the reactor staff and safety staff members monitoring the exposure room opening will determine if the radiation level at the outside entrance to the exposure room in direct line of sight with the core projection is less than or equal to 2 mrem /hr. If this reading is less than or equal to 2 mrem /hr, the reactor staff member may grant passage permission. There is no reouirement to wear a pocket chamber in addition to the AFRRIissued TLD for control naecane. If the reading is greater than 2 mrem / hr, passage will be denied.

3. OPEN PASSAGE:(NON-ROUTINE)

The Prep Area may be opened for passage by personnel traveling between buildings at AFRRI when maintenance is being performed on the normal connecting hallway.This is not a routine occurrence and warrants written approval from the Reactor Facility Director with concurrence from the Chairman, Safety and Health Department. In addition, the Prep Area must be monitored at all times by appropriately trained personnel. Prior to the opening of the Reactor Prep Area for open passage, the Safety and Health Department shall conduct a radiological survey of the area and certify that no radiuion areas exist within the Prep Area and that the non-painted areas of the Prep Area floor are free of contamination.

There is no requirement for personnel who pass through the Prep Area to wear pocket chambers or frisk themselves during periods of open passage. Open passage will be suspended during exposure room openings.

4 FRISKING Frisking unon exit from the Prep Area is only reouired for the following conditions-

n. Personnel who have entered the yellow painted work zone aren.

b. Personnel who have been in either exoosure room.

c. Personnel who may have handled potentially contaminated material.

Revised: 25 May 95 Page 2

, d. Unon reo_ nest of reactor staff or SHD n_ ersonnel.

The frinkina n. rocadure is nonted at both exits frdm the Pren Aren near the surve.v Instruments. '

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4 i l Facility Modification Worksheet 2 i

I No 10 CFR 50.59 Analysis Required j . Proposed Change

koee/oee ll, Ate Adieu 4fe /%.]fr(cAx) AsceLe

• Modification to: Procedure X Faculty Experiment  ;

Submitted by: Nc Clea Date 25% f_6 '

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' l I 1. Description of change. ,

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2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). Boge.

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics. #

4. Determine what other procedures, logs, or training material may be affected and record below. //ovd

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

/l/pH'd

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

Action Sheet: Submitted Not Required /\

01 JUN 1995

/ Date Reviewed and approved by RFp RRFSC Notified

//

7/ ' NMf k Date JLN 2 1995

- e/ .

Revised: 27 May 93 Page 6

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N N E D C 81 N N N I N $ @ l5 [$$ $ @ LIE E E R E F R $ @ [ 6 M AIR PARTICULATE MONITOR (CAM) PROCEDURE GENERAL This procedure specifies how to test the CAM to ensure proper operation of this ,

monitoring device. A channel test will be performed on both reactor room CAMS '

at the beginning and end of each day. -

SPECIFIC i

1. OPERATING and TRACING Check that the primary CAM is operating and tracing with the correct time indicated on the chart and check that the wenndarv CAM is onerating.

Ensure the flow rate is >6 cfm and not off scale.

2. CHANNEL TEST WITH SOURCE

a. Place the switch on the front of the CAM to " test" and verify a reading of 3600 cpm -W- 20% for nrimary CAM on the chart and 1000 com for the secondary CAM. Reset the switch.

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

c. Slowly bring a radioactive source near the detector. Observe the meter on the front of the CAM. The yellow light will activate at approximately 4,000 counts per minute. The red light will activate at approximately 10,000 counts per minute; the alarm will sound and the dampers will close. Reset the alarm, close the chamber door and return the source to the CAM drawer.

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

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

4. BY-PASS of PRIMARY CAM l 1

Revised:25 May 95 Pag

When the primary CAM is by-passed. the secondary CAM chart recorder needs to be activated. then perform items L 2a. and 2d.

Revised:25 May 95 Page 2

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)

! Facility Modification Worksheet 2 4

No 10 CFR 50.59 Analysis Required i

Proposed Change kiwi /bry An m e r des d Saifed

! Modification to: Procedure Facility X Experiment Submitted by: beorge. Date 28N#)'78 l

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1. Description of change:

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2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). &e

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics.

4. Determine what other procedures, logs, or training material may be affected and record below. &g

5. List of associated drawings, procedures, logs, or other mat--:.als to be changed:

S e.

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

Action Sheet: Submitted Not Required Reviewed and approved by RFD

) Date 25 MAY 1995 RRFSC Notified d%" R.972 k Date 0 2 JUN 1995 U .

Revised: 27 May 93 Page 6

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Facility Modification Worksheet 2

) No 10 CFR 50.59 Analysis Required

Proposed Change kweilurel,TM6A, eocSsr [vs' usure km Sky l Modification to

Procedure X FacGity Experiment Submitted by: /Ved/uu Date 184 f 6

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! 1. Description of change:

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2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and doc: not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). pogg,

3. If change involves a facility modification, attach a drawing i' appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics. N/g

4. Determine what other procedures, logs, or training material may be affected and record below. ggge.

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

A/0n E.-

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

Action Sheet: Submitted Not Required I O 1 JUN 1995 Reviewed and approved by RED Date RRFSC Notified -7[0kN Date OCT I 8 loo:;

G U .

Revised: 27 May 93 Page 6

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REACTOR EXPOSURE ROOM ENTRY I

1. REFERENCES l

a.10 CFR 20, " Standards for Protection Against Radiation"

b. USNRC licenses: R-84,19-08330-02

c. AFRRIInstruction 6055.8

d. AFRRI Health Physics Procedure 3-1

2. G ENER AL

a. PURPOSE: This procedure specifies all safety and security procedures for activities involving entry into the AFRRI TRIG A Reactor exposure rooms, currently designated exposure rooms 1 and 2 (rooms 1123 and 1122).

b. AUTHORIZED ENTRY: Both AFRRI picture badge and U-badge personnel, may enter a reactor exposure room under the supervision of the Reactor Facility Director (RFD) or his representative. Visiting personnel (V badge) require special authorization by both the Chairman, Safety and Health Department (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. All personnel who are granted unescorted access to the prep area or warm storage will receive a special prep area safety briefing prior to being granted access. Only personnel who have been granted permanent unescorted access will be given card access to the prep area. The RFD is responsible for maintaining a roster in the prep area for personnel who have been granted permanent unesconed access. Other personnel requiring unescorted access to the prep area or warm storage for a specific purpose or time period may be granted special access in writing by the RFD with concurrence of SHD. However, these personnel who are granted special access from the RFD will not be given card access to the prep area.

c. ER ENTRY INSTRUCTIONS - All personnel will:

Revised:25 May 95 Page1

(1) Know the Reactor staff representative is in charge of all operations in the prep area. Obtain permission to enter either exposure room from the Reactor staff representative.

(2) Wear AFRRI TLD whole body badge and pocket dosimeter.

(3) Wear wrist or finger dosimeter if work is to be performed on an 4 experimental array er within one meter of the core projection.

(4) Wear bootics, eye protection, gloves and coat.

(5) Check and log pocket dosimeter reading on log in prep area prior to entry.

(6) Familiarize themselves with approximate radiation levels in the room, based on radiological surveys performed and data obtained by SHD.

(7) Ensure that all materials removed from the exposure room are properly labeled and entered on the exposure room entry log (AFRRI FORM 130) and the activated materials controllog.

(8) Glove and lab coat requirements may be waived by the SHD monitor or reactor representative 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 requirements,

d. DEPARTURE FROM REACTOR EXPOSURE ROOM ENTRY PROCEDURES: Any departure from the following procedures will require a special work permit (SWP). Exceeding any radiation dose limits will require a written justification from the supervisor of the research project which must be approved by the Head, SHD.

3. SHD EXPOSURE ROOM SURVEY

a. EXPOSURE ROOM CAM:

(1) Prior to opening either exposure room, the respective CAM must read 2000 cpm or less. If the CAM reads 2000 cpm or greater, change the filter on the CAM and put it in the radioactive materials bag in the CAM drawer. If 10 minutes or more have elapsed since the end of the reactor run, the door may be opened to the first step to facilitate radio effluent clearance in the room. Then check the CAM after 1 minute and,if the reading has not increased by more than 100 cpm, proceed with the exposure room opening. Ifit has increased by more than 100 cpm, change the filter and wait two more minutes and repeat as necessary. If the CAM alarms during or immediately after a run, change the filter and reset the CAM.

(2)If either exposure room CAM or the Prep Area CAM is found malfunctioning or inoperable, notify the Reactor Representative or Revised:25 May 95 Page 2

Reactor Operations Supervisor (ROS) and Radiation Safety Officer (RSO)immediately. No opening shall be initiated if the exposure room to be opened does not have an operable CAM.

b. DOSE RATE AT FACE OF DOOR: If the dose rate at the face of the plug door in the direct line of sight of the reactor tank bulge reads greater than 100 mrem /hr, the door will be closed sufficiently to preclude access. The plug door will be reopened upon agreement of the SHD and RFD representatives for revaluation of radiation levels. When the dose rate at the face of the door is below 100 mrem /hr, the opening procedure may continue.

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 readings will be entered in the room entrance log (AFRRI FORM 130) and kept in the prep area. The levels will be measured at:

(1) The reactor door face in the direct line of sight of the reactor tank bulge (2) At the contamination line in the entrance of the room (3) The middle of the room (4) 30 cm from the tank wall or shield (5) Contact with the tank wall or shield (6) The area (s) where individual (s) will be working for an extended period of time and any other place deemed necessary by the reactor representative.

d. ROUTINE ENTRY: Entry is routinely permitted only when the maximum reading in any occupiable area is 1 rem /h or less. Entry may be permitted iflevels are 1-5 rem /h, but no work will be permitted in fields over 1 rem /h. If personnel are working in a specific area for an extended period of time, the dose rate in that area will be measured.

(1) Readings over 100 mrem /hr (closed window) will be specifically identified.

All dose rate readings will be reported to the Reactor representative and entry personnel. When appropriate, after consultation with the SHD and Reactor representatives, stay times will be assigned for entry personnel.

AFRRI limits of 100 mrem / week and 50 mrem / day are to be used as the basis of stay time determinations.

(2) All exposure room entries will be checked by the SHD monitor for compliance with radiation safety aspects of applicable Reactor Use Requests (RURs). If not, non-compliance will be reported to the RFD and to SHD.

Revised:25 May 95 Page 3

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e. FILLING OUT THE SURVEY OF EXPOSURE ROOM ~ OPENING LOG:

The exposure room opening log sheet must be filled out completely for each opening of an exposure room. Care must be taken to fill out each blank on the

entry log sheet. If a section is not applicable to the particular opening, N/A should  !

- be filled in the blank.

l 4. NON-MONITORED OPENING: i

a. Personnel may enter the exposure rooms without a SHD monitor present if  ;

ALL the following conditions hold:

j (1) The reactor has not been to power in that ER since the last survey.

(2) Survey meter readings at the door indicate safe entry conditions (should j be less than 1 mrem /hr).

I (3) The ER CAM should be observed, and its reading should be less than 2000 com (see paragraph 3a(1).

(4) The last survey indicates that the maximum dose rate in any area where

! work is to performed did not exceed 100 mrem /hr.

, b. An entry will be made in the exposure room log by a reactor staff member, i with a note that the survey has been waived.

j c. SHD must be notified if any radioactive materials or equipment are to be removed from the prep area.

I 5. PERSONNEL PROTECTION PROCEDURES

a. Dosimetry and protective clothing requirements are given in paragraph 2.c, l ER Entry Instructions.

b. Entry is permitted only after the SHD monitor has completed the survey and reported results to those about to enter (excluding non-monitored openings -

reference Paragraph 4, above).

c. All personnel shall record initial dosimeter reading in the prep area dosimeter log prior to entering the exposure room for the first time each day. Personnel shall read dosimeters when leaving the exposure room and record a final dosimeter reading in the prep area log at completion of daily operations. Net doses over 10 mrem must be reported to the SHD Monitor.

d. Protective clothing will be removed in such a way as not to contaminate

" clean" areas by items from " dirty" areas.

e. All personnel will " frisk" themselves before leaving the prep area.

Revised:25 May 95 Page 4

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6. SPECIFIC ACTIONS TO OPEN EXPOSURE ROOM DOORS l

. a. Turn up exposure room lights (this can be waived for experiment needs). j

b. Check plug door tracks for obstructions; ensure all obstacles are clear of the door (including ropes).

c. Ensure that only authorized personnel (see 2.b.) are present in the reactor I prep area during exposure room openings.

d. When facility safety interlocks and opening procedures have been satisfied, insert key into exposure room door key panel and open door. DO NOT LEAVE KEY IN LOCK UNATTENDED.

e. Open door in accordance with entry procedures. Ensure all required data is logged in entry log.

f. Ensure that individuals who will be moving lead, bismuth, or other heavy l materials are wearing steel-toed shoes. l

g. Limit exposure times of all personnel entering the exposure rooms based on  ;

the results of the radiation survey.

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7. ACTIVATED M ATERIALS l

a. PLACING M ATERIAL IN EXPOSURE ROOM: Before placing any equipment or materialin an exposure room for irradiation the following will be observed:

(1) Equipment tagged as AFRRI property: a memo must be sent to both the RFD and the AFRRI property officer.The memo 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 memo must contain all nomenclature as well as an adequate description of the equipment in order for it to be identified on the property book. 4 (2) Non-tagged AFRRI equipment or material (to be returned): a memo or statement on the reactor RUR must be sent to the RFD giving the kinds  !

and amounts of byproduct material expected to be produced (that is the I material that the experimenter wishes to be returned) and a copy or number of their radionuclide authorization number.The memo or RUR statement must be specific and contain an accurate description of the ,

material being exposed (converted to byproduct). Other information will l be required from personnel before any materialis allowed to be removed Revised:25 May 95 Page5

from the prep or warm storage areas (see next section of this procedure 7.b. and 7.c.) .

(3) Non-tagged equipment or material (not to be returned): A memo 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 additionally any material not specifically requested to be held, will be disposed of as radioactive waste in the next shipment.

(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 disposed of as radioactive waste .

unless prior arrangements have been made with the reactor /SHD staffs l for storage. Any material not removed within a reasonable amount of time will automatically be disposed of as radioactive waste,

b. SURVEY OF MATERIALS COMING OUT OF EXPOSURE ROOM (1) All materialleaving the exposure rooms must be surveyed for activation or l contamination. Survey meter readings will be used to determine dose levels. Smear surveys may be used,if the SHD representative deems them necessary. All materials will be labeled appropriately in accordance with HPP 0-2 and HPP 3-1.

(2) All special equipment that has been activated such as chambers, rotators, 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 ofitems from the prep area will only be allowed in accordance with HPP 3-1.

c. DISPOSITION OF ACTIVATED MATERIALS All activated or contaminated materials will be under the control of the reactor license while such materials remain in the reactor controlled area.

Removal of any radioactive materials from the reactor controlled area will be done in accordance with HPP 3-1.

8. COMPLETION OF ENTRY

a. The Reactor Staff Representative will check to see that all personnel have left the exposure room before the plug door is closed. In the event that the warning horn in either exposure room is disconnected, for testing or experiment requirements, the exposure room plug door shall not be closed until at least two (2) licensed reactor operators visually inspect the room to ensure that no personnel remain in the room. To ensure compliance with the reactor Technical Specifications, the names of these licensed operators present at the exposure room Revised:25 May 95 Page 6

closing shall be entered into the reactor operations logbook and'on AFRRI FORM 130. At the completion of the test or experiment, the warning horn shall be reconnected and tested. All actions agarding the warning horn shallin entered in GREEN ink in the reactor operations logbook.

b. The SHD monitor will not leave the area while the plug door is open without notifying the Reactor Staff Representative.

c. Lock the exposure room door control panel; react lights, if appropriate.

d. Resecure the prep area on departure.

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Revised:25 May 95 Page 7

ll Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change Q. toc m C M E~,7 of r74dc %, rer,% A. t_T l s

Modification to: Procedure Facility h Experiment Submitted by: detven Date vn.5/s r

1. Description of change: sts  % ,w2 ,L

~

Rt ,o c ocA F% m ri e. k.

s , n t.m.s 3 1

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). /vo 4

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics. l

4. Determine what other procedures, logs, or training material may be affected and record below, pea a E. l

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

pod

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

Action Sheet: Submitted Not Required %

Reviewed and approved by RFD N11 Date 7 kMd RRFSC Notified Date 2 JUk 1995 O CV Revised: 27 May 93 Page 6

rc Facility Modification Worksheet 1 10 CFR 50.59 Analysis Proposed Change Reelacement of Stack Gas Monitor printer with Chart Recorder Submitted by: ce rge/Mcclung 20 June 1995 Date

1. Description of change: The Stack Gas Monitor printer is removed. A Chart Recorder will be used to record effluent counts.

The Stack Gas Monitor will no longer print a report of average Ar-41 concentrations every six hours.

Unusual events will be displayed in real time on the chart recorder.

2. Reason for change: printer is no longer serviceable.

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

Analysis attached? Yes X

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

Procedure Facility X Experiment Revised: 27 May 93 Page 3

e Facility Modification Worksheet 1

5. Specify what sections of the SAR are applicable. In general terms describe the necessary updates to the SAR. Note that this description need not contain the I final SAR wording.

Section 3, paragraphs 3.6.3 and 3.6.3.2 are affected by the change. )

The SAR will be modified to reflect no automatic printout of average Ar-41 concentrations. It will also be modified to include use of the chart recorder continuous printout of effluent counts.

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

The chart recorder has been operated in parallel with the stack gas monitor ]

printer for several years. It has operated as intended and provides for j a continuous means of recording effluent counts at the sampling point.  !

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1 Revised: 27 May 93 Page 4

Facility Modification Worksheet 1

7. Specify associated information.

New drawings are: Attached Not required x Does a drawing need to be sent to Logistics? Yes No x Are training materials effected? Yes x No Will any logs have to be changed? Yes No x Are other procedures effected? Yes x No l

List of items affected:

APRRI TRICA Reactor Operations Manual Safety Analysis Report Procedure C006, " Stack Gas Monitor Calibration" l

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8. Create an Action Sheet containing a list of associated work specified in item #

7, attach a copy, and submit another to the RFD (modification of drawings must be approved by the RFD).

Action Sheet: Submitted x Not Required y

, bb

' ) (A r < L j /

J)s Reviewed and approved by RFD -

i

' /-b s t Date 6/ L/ / 3 7 RRFSC Concurrence M '

Date OCT l 8 1995

, ,/

Revised: 27 May 93 Page 5

50.59 ANALYSIS l

supported Action: Replacement of Stack Gas Monitor Printer with Chart Recorder The Stack Gas Monitor (SGM) continues to sample and measure the ,

effluent, as required by the Technical Specifications. The actual concentrations of Argon-41 at the sample point are still calculated and stored in computer memory. This information is available for recall on the SGM CRT at any time. The information will no longer 1 be automatically printed every six hours. The affluent counts can be monitored on the auxiliary reactor console chart recorder. This device provides for a continuous readout and hard copy printout of )

the effluent counts. Interpretation of this data by a licensed operator allows the effluent situation to be evaluated at any time.

The chart recorder allows for monitoring of potential unusual releases to the environment.

i This change does not increase the consequences of, nor change the l

types of accidents previously evaluated in the Safety Analysis Report. This change does not reduce the margin of safety as l defined in the bases for any Technical Specifications.

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- - - = . - -

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50.59 ACTION SHEET i

Cupported Action: Replacement of Stack Gas Monitor Printer with Chart Recorder

1. Update SAR to reflect change to Stack Gas Monitor System.

Date Completed:

2. Update Operations Manual to include new Stack Gas Monitor configuration.

Date Completed:

3. Modify Procedure C006, " Stack Gas Monitor Calibration" to reflect necessary changes.

Date Completed:

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Facility Modification Work Sheet 1 10 CFR 50.59 Analysis Proposed Change: Replacement of the Stack Gas Monitor Electronics with Non-Computer Based Electronics Packace submitted by: Georae Date _07-12-95

1. Description of change:

R"_.Osve the electronics shelf in the Stack Gas Monitor and replace the occputer based PIOPS electronics with a newer, more reliable shelf of cnnlog based electronics. The new unit will have outputs for alarm lights and audible alarms as well as remote meters and chart recorders.

Tho new unit will still have single channel capability for monitoring Argan-41.

2. Reason for change:

Tho old PIOPS Stack Gas Monitor electronics are no longer cost effective to maintain.

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

Analysis attached? Yes XXX

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

Procedure XXX Facility _XXX_ Experiment

Facility Modification Work Sheet 1

5. Specify what sections of the SAR are applicable. In general terms describe the necessary updates to the SAR. Note that this description need not contain the final SAR wording.

Section 3.6.3 will be changed to eliminate the computer memory and printer and replace it with a strip chart recorder.

Section 3.6.3.2, first paragraph, last line, will be changed to read:

"this system will detect those effluents which have been released into the reactor stack, and is set to alarm at the limit currently specified in the AFRRI Reactor Emergency Plan."

Table 3-3 will be changed for the Stack Gas Monitor Readout to eliminate the " printout in reactor room (Room 3161)".

See attached for proposed version.

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

The new unit will be isotopically calibrated for sodium upon installation cnd then recalibrated for Argon-41 once the reactor can be operated.

Facility Modification Work Sheet 1

7. Specify associated information.

New drawings are: Attached OTHER _XXX_ Drawings will Not required be provided with new unit.

Drawings will be placed in appropriate files for maintenance, calibrations and repairs.

Does a drawing need to be sent Logistics? Yes No Are training materials effected? Yes -XX No -XX-1 Will any Logs have to be changed? Yes No _XI_

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

I SAR Section 3.6.3 SAR Section 3.6.3.2 SAR Table 3-3 Operational Procedure 10 STACK GAS MONITOR PROCEDURE Calibration Procedure C006 Electronic and Isotopic Calibrations HPP 7-3 Airborne Radioactivity Samplers and Monitors Operations Manual (under revision)

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

Action Sheet: Submitted _XX_ Not Required Rsviewed and approved by RFD >{L Date (2 k .T)i ~

v / ,

RRFSC Concurrence O M

~

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v: Date w p.ms, o-r>J t

T

[

50.59 Analysis ,

Technical Specification Change Not Required  ;

r The Technical Specification requirement under section 3.5.1 j i

b. Gas Stack Monitor. The gas stack monitor (GSM) will sample and measure the .

gaseous effluent in the building exhaust system.

i The current stack gas monitor PIOPS electronics measure Argon _41 and report the. [

information to the control room on a chan recorder and analog meter. The new analog electronics will report the information in '.he same locations. The stack gas monitor will continue to measure Argon-41 releases as required in section 3.5.1.b of the Technical Specifications, therefore, no char.g to the Technical Specifications is required.

The current stack gas moni'ar is composed of a panicle filter, a gas chamber beside a NaI detector, a pump, and corr.puter based electronics which monitor the detector. The outputs from the PIOPS electronics operate High, Alert, and Fail lamps, and an alarm bell on the Stack gas monitor, as well as a remote meter and chart recorder in the reactor control room. i The PIOPS electronics have other features which are not in use at this time.  ;

1 The new stack gas monitor will be composed of the same a particle filter, a gas chamber '

beside the Nal detector, and pump, but the computer based PIOPS electronics which monitor the detector will be replaced with analog electronics. The outputs from the analog based i electronics will operate High, Alert, and Fail lamps, and a sonalert alarm on the Stack gas monitor, as well as the remote meter and chart recorder in the reactor control room.

The sensitivity of the stack gas monitor is based on the sensitivity of the detector. Because l~

the same Nal detector will be used in the new system, the sensitivity of the new unit will not '

change from the old unit.

This change does not increase the consequences of, nor change the types of accidents previously evaluated in the Safety Analysis Report. this change does not reduce the margin i of safety as defined in the bases for any Technical Specifications.

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PROPOSED CHANGE TO THE SAR FOR THE NEW STACK GAS MONITOR l

ORIGINAL VERSION  !

3.6.3 Stack Monitoring Systems The stack monitoring systems consist of the stack flow monitor and the stack gas monitor. 'Ihese systems provide data about the radioactive effluents discharged through the l reactor stack. The stack flow monitor measurements are recorded by a strip chart recorder. .

Stack gas monitor measurements of Ar emissions are stored in computer memory, summed I and automatically printed every six hours. At the end of each day of operation the reactor j operator is able to verify that no unusual Ar releases are indicated in the computer memory  ;

or printouts for that day. l i

)

3.6.3.2 Stack Gas Monitoring System The stack gas monitor (SGM) system is a Nal scintillation detection system which 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 report the average Ard ' concentration at the sample point every six hours on a printout.  :

The stack gas monitor system is capable of activating alarms at two levels.  !

Additionally, a flashing visual light on the reactor auxiliary instrumentation console in the reactor control room will be illuminated when the stack gas monitoring system pump motor ,

is turned off. 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. I t

TABLE 3-3 j l

STACK MONITORING SYSTEMS  ;

I System Readout Radiation Alarm i

Stack Flow Strip chart recorder (Not applicable) .

Monitoring System in reactor control However, EF5 failure ,

room gives audible and visual alarm in j reactor control room i Stack Gas Meter in reactor Activates visual alarm )

Monitoring System control room and in reactor control I printout in reactor room room (Room 3161)

PROPOSED VERSION l

3.6.3 Stack Monitoring Systems The stack monitoring systems consist of the stack flow monitor and the stack gas ,

monitor. These systems provide data about the radioactive effluents discharged through the reactor stack. The stack flow monitor measurements are recorded by a strip chart recorder.

Stack gas monitor measurements of Ard ' emissions are recorded on a strip chart recorder and '

can be viewed at the end of each day by an operator to verify that no unusual Ard2releases have occurred.

3.6.3.2 Stack Gas Monitoring System The stack gas monitor (SGM) system is a Nal scintillation detection system which 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 is set to alarm at the limit currently s9ecified in the  ;

AFRRI Reactor Emergency Plan.

The stack gas monitor system is capable of activating alarms at two levels. Additionally, a flashing visual light on the reactor auxiliary instrumentation console in the reactor control i room will be illuminated when the stack gas monitoring system pump motor is turned off.

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.

1 TABLE 3-3 STACK MONITORING SYSTEMS System Readout Radiation Alarm Stack Flow Strip chart recorder (Not applicable)

Monitoring System in reactor control However, EF5 failure room gives audible and l visual alarm in j reactor control room Stack Gas Meter in reactor Activates visual alarm  !

Monitoring System control room in reactor control I room l

50.59 ACTION SHEET STACK GAS MONITOR ELECTRONICS CHANGE Item Needing Attention Date Complete Change Section 3.6.3 of the SAR Change Section 3.6.3.2 of the SAR Change Table 3-3 of the SAR Modify Operational Procedure 10 Modify Calibration Procedure C006 Sections of HPP 7-3 Change Operations Manual Calibrate new SGM electronics l

File new schematic diagrams in appropriate files Remove diagrams for old PIOPS electronics from files I

JUN-21-95 WED 9:10 NUCLEARMEASUREMENTS FAX NO. 3175434420 P.04 NMC Model CRM 51M/91, Gcaeral Description Page1 #&cdearlisadrurPrersteddort NMC Model CRM-51M/91 Count Rate Meter NMC's Model CRM 51M/91 microprocessor controlled count rate meter is provided to serve as the readout / control unit for various NMC monitors. The CRM-51M/91 may be provided in either a rack-mount con 5guration or a wa!! mount l con $guration, depending on the customers preference and needs.

The standard CRM 51M/91 module has three latching alarms with manual reset function a five decade (101 to 10' cpm) count rate range. There is a multipurpose analog meter re the front panel that displays the alarm setpoints, the detector I high voltage, 3600 cpm test readings, and normal operating count rates la counts per minute (cpm). l l

The fo!!owing text describes the general features of the CRM as well as the operation of the front pane!

switches.

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S_oecifications Physical Dinwnsions Width: 19.0 laches, 482.6 mm. -

Fenel Meter Displays: High Alarm Setpoint Height B.75 inches,223.3 mm. Alen Alarm Serpoint Depth: 1138 inches,301.7 mm Fail Alarm Setpoint Psael Centrols: High Norm serpoint Panet Displays: HV ON (Red)

Alert Norm Scepoint Power On (Green)

Instrument Fail Serpoint Chest Soures (Optional) Roseletloa less Less than 1% at 107 CPM Alare Ranet Menar Raset Power Requironwater 130 VAC,60 Hz,30 Watts.

3600 Test / Operate High Voltage On Righ Voltage Rames: 300 to 1,300 volts DC Power On Counting Range 101 to 10 8counts per minute Card Mask Adjuslawats High Serpoint (Standard)

Fail 5stpoint Alen Serpoint Operating Temperneur, Range D'C to 50"C ILgb Voltage 2460 N. Arlington Ave. P.O. Box 18248 Phone (317) 548 2415 Nuclear Measurements Corp. Indianapes, indana 4satse2.s Fax (317) ses.44a0

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Front Panel Controh Meter Displays: The normal meter display is active in the range of10 to 10' counts per minute (cpm). Alternate meter functions are the display of alarm setpoints and the high voltage applied to the detector.

Alarm IAvels: The CRM 51M/91 has three alarms. They are: 1) High (or High High) Radiation Alarm, which is actuated when the detected count rate exceeds the user-established High Alarm setpoint; 2) Alert (or High) Radiation l Alarm, which is actuated when the detected count rate exceeds the uscr established Alert Alarm setpoint; and 3)

Instrument Fail (or Lw) Alarm, which is actuated when the detected count rato falls below the user-estahfMed Instrument Fall Alarm setpoint.

If an alarm condition is encountered, the appropriate alarm circuit willlatch in the alarm state, and a relay will change state. The circuit must be manuaDy reset by pressing the Reset button on the front panel of the CRM.

To display a setpoint, press the HIOH, ALERT, or FAIL Alarm Setpoint push button on the front pancl. %e setpoint value will be displayed on the meter. The serpoint can be adjusted via potentiometer on the card mask access next to the setpoint buttons.

3600 Test: The 3600 TEST indication switch permits a quick check of the ratemeter ca!Ibration. When cahhated the ratemeter will read 3600 cpm n15%.

Check Source: When the CHECK SOURCE IN switch (Optional) is depressed, a voltage is applied to activate (insert) the check source on the corresponding monitor. When the CHECK SOURCE IN switch is released, a second voltage is applied to de energize (retract) the check source. The check source energize and de-energize voltages are factor depending on the application.

Meter Reset: The METER RESET push button is used to speed up the down scale meter needle movement by setting the meter to zero.

l High Voltage Adjust: A potentiometer on the High Voltage Card Mask provides high voltage adjustment from 300 volts to 1,300 volts DC n 5%.

High Voltage On Switch: The HI VOLT ON switch is located on the CRM front panel. Switching on this switch turns on the high voltage to the detector and illuminates a green light above this switch. l Power On Switch: The POWER ON switch is located on the CRM front panel. Switching on this switch turns on power to the unit.

Ontional Features Analog Outputs: The CRM la equipped to contain up to three analog outputs that are logarithmically related to the input count rate. The analog outputs can be used as recorder outputs to existing customer supplied equipment. %c firstis g, .s a 0-SV output option built into the CRM 51M/9L The other two buffered analog output signal options include any m* combination of: 0-imA,4-20mA,10-50mA,0-10mV,0-100mV,0-1V and 010V.

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Relays: Each CRM drives three DPDT 5 Ampere relays, installed on the Ad"53A/91 card, which provide custo access to the alarm circuits. These relays are driven by the High Radiation. Alert Radiation and Instrument Fail alarms.

The relays can be configured to be energized or de energized in the non alarm state, and eithcr latching or non-latching.

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i Facility Modification Worksheet 2 i

No 10 CFR 50.59 Analysis Required Proposed Change: Procedure Change- Operational Procedure 8, TAB B Modification to: Procedure X Facility _ Experiment _

Submitted by: John T. Nguyen Date: 14 July 95

1. Description of change:

Add (*) symbol to indicate a numeric entry required. Add a phrase " Backup operating"in section V.5 to update the current pmcedum. Delete items not required, "3152"in section I.4 and "Pdmary and Backup"in section V.S.

i,

2. The proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

j 3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, forward a copy of changes necessary to Logistics. Not Required

4. Determine what other procedures, logs, or training material may be affected and record below, see #5 a

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

Operational Pmcedure 8, TAB B

, DAILY OPERATIONAL STARTUP CHECKLIST Add "*" to section I.1; III.1,2,4,5; V.1,2,4,5; VI.5,8a,9,12.

l Add "(b) Backup operating" to section V.5

Delete "3152" to section 1.4 and " Primary and Backup"in V.5

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

Action Sheet: Submitted Not Required X Reviewed and approved by RFD & ate /4 [.)

RRFSC Notified ./ Date i a y[

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OPERATIONAllPROCEDURE n u 8. TAB B1 ~

.= m u.z m m .am - a DAILY SAFETY CHECKLIST Checklist number Date Time completed Supervised by Assisted by I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 110 psig) ............. ....................

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

3. Air d rye r o p e r a t in g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . .

4. D oors 231,231 A, and toof hatch SECU RED .........................,

II. EQUIPMENT ROOM (Room 2158)

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

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

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

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

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

6. Visu a 1 in sp e et io n o f a r ea . .... . . . .. . . . ... . . ... . . .. ... ... .. . ...... .. . .. . . . . ... . .. . .

7. D o o r 215 8 S E C U R E D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Ill. PREPARATION AREA i

i Visu a 1 in sp e et io n o f a r ea ... ... . .. .. . .. . ...... . .. ... ... .. . .... . ... . . .... . .. . . . . . .. . . .

l IV. REACTOR ROOM (Room 3161)

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

2. Shield door bearing air pressure (8.5 - 9.5 psig) ...................... *

3. Visu a1 insp eetio n o f co re a nd t a n k ..........................................

i

4. Number of fuel elements and Fuel elements

• j control rods in tank storage Control rods *

5. Air particulate monitor (CAM)

(a) Prima ry op erating a n d t ra cin g ..........................................

(b) B a ck u p o p e ra t in g . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . .

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

6. Stack gas monitor quality assurance checked .........................

7. D o o r 3162 SE C U R E D . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..

• Numerical Entry AFRRI FORM 61b (R) Revised: 14 Jul 95 Page1

V. LOBBY AREA Lobby au dio e L rm tured o ff . ................................................ .........

VI. REACTOR CONTROL ROOM (Room 3160)

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

2. Co n sole r eco r d ers d a t e d . .. .... . . .... . ... . .. .. . ... ... ... .... . .. . . . . .. ... . . . . . . . . . . .. . . .. .. ..

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

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

5. Water monitor box (a) Ba ck gro u n d a etivit y (10 - 60 cp m) ............................................... *

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

(c) D M 1 resistivity [ > 0.5 M ohm-cm] ............................................. *

(d) D M 2 resistivity [ > 0.5 M oh m-cm) ............................................. *

6. Stack gas flow rate [15 - 35 Kcfm] . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . *

7. Sta ck lin ear flow rate (1.0 - 2.0 Kft/ min) ............................................

8. Gas stack monitor (a ) Ba ck gro u n d (2 - 20 cp m ) . .. . . . . . . .. . . . . . . . . . . . . . . . .. .. . . . . ... .. . .. . .. .. . .. . . . . ... . . *

(b ) A l a r m ch e ck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

9. Radiation monitors l Monitor Alarm Point Reading Alarm Setting

! Functional (mrem /hr) (mrem /hr) l (a) R-1 (< 20) 20 (b) R-2 (<10) 10 (c) R-3 (< 10) 10 (d) R-5 (< 20) 20 (e) E-3 (< 10) 10 (f) E-6 (< 10) 10

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

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

12. Wat er t emperature (inlet) (5 -35 C) .............................. .................. *

13. Water 1evel log completed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

AFRR1 FORM 61b (R) Revised: 14 JUI 95 Page 2

< 1:

Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required i Proposed Change: Procedure Change- Operational Procedure 8, TAB I l 4

Modification to: Procedure X Facility _ Experiment ,,, j Submitted by: John T. N guyen Date: 14 July 95

1. Description of change:

Add (*) symbol to indicate a numerical entry required and add a phrase

" Warm storage doors closed" .

2. The proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

, 3. If change involves a facility modification, attach a drawing if appropriate. If l l

structural facility drawings need updating, forward a copy of changes necessary to l Logistics. Not Required

4. Determine what other procedures, logs, or training material may be affected and record below. see #5 '

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

j Operational Prucedure 8, TAB I DAILY OPERATIONAL SHUTDOWN CHECKLIST l Add "*" to section III.1; VI.8 J

Add " Warm storage doors closed" to section IV

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

[ Action Sheet: Submitted Not Required X

~

Reviewed and approved by RFA / te k i M RRFSC Notified / I/ Date OCTb 8199b 9 9

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DAILY OPERATIONAL SHUTDOWN CHECKLIST l Checklist No. Date Time Completed Supervised by Assisted by I. REACTOR ROOM (Room 3161)

1. All r o d d rive s D O WN . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . .

2. C a t r ia g e ligh t s O F F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3. D o o r 316 2 S E C U R E D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .

4. Cha n n el t est com pleted o n bo t h CAM s .........................................

i

5. D o o r 3161 lo ek ed wit h k ey . ... ... ...... ... ... ... .... . . ... . .. ... ... .......... . . ... . .. ...

l II. EQUIPMENT ROOM (Room 3152)

1. Distillation unit discharge vaIve CLOSED .....................................

2. Air d rye r O P E R ATI O N A L . . . . . . .. . . . . . . . . . . . . . .. . .. . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . .

l 3. D oors 231, 231A, and roof hatch SECU RED ................................

III. EQUIPMENT ROOM (Room 2158)

1. Primary discharge pressure (15 - 25 psig) ..................................... *

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

3. Visu a1 in sp e etio n fo r lea k s . . . .. . ... ... ... . .. ..... . .. .... . .. ... .. .... .. . ...... ... .. . ...

l 4. D o o r 215 8 S E C U R E D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

IV. PREPARATION AREA

1. ER 2 plug door CONTR OL LOCKED .........................................

D oor closed; a nd han dwh eel PAD LO CKED ................................

2. E R 2 ligh t s O N a n d r h eo st a t a t 10% .................................... ..........

3. ER 1 plug door CO NTR O L LO C K ED .........................................

D oor closed; and handwheel PAD LOCKED ...............................

4. ER 1 ligh ts ON a nd rh eost a t a t 10% ..............................................

5. Visu a 1 in sp e et io n o f a r ea . .... ...... . .. ......... . ........ . . .......... ...... ... ... . . . . .. ...

6. Wa r m st o ra ge d o o r s clo se d ... ... .. .... ... ..... .... ... ... ...... .... .. .. .... .... .. . .. ...

1 AFR RI Form 62(R) Revised: 14 Jul 95 Page1

V. LOBBY ALARM L o b b y a la r m a u d io O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

VI. REACTOR CONTROL ROOM (Room 3160) i

1. R e a et o r t a n k ligh t s O F F . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .

2. Console chart record er p ens raised ................................................. )

3. S t e a d y-st a t e t im e r O F F . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . .

4. Console LOCKED, and all required keys returned toloekbox...................................................................................... ,

5. D i ffu s e r p u m p s O F F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

7. R eactor monthly usage su mmary completed ..................................

8. R a d ia t io n m o n it o rs . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . .

MONITOR READING HIGH LEVEL ALARM SETTING (mrem /hr)

a. R-1 (<20) 20

b. R-2 (<10)

• 10

c. R -3 (< 10) 10 l d. R-5 (< 20) 20

e. E-3 (<10) 10

f. E-6 (< 10) 10

g. R-6 (< 10) 10

• Numerical Entry AFRRI Form 62(R) Revised: 14 Jul 95 Page 2

/e Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change: Procedum Change- Operational Procedum 8, TAB B1 1 Modification to: Procedure X Facility _ Experiment _

Submitted by: .lohn T. Nguyen Date: 14 July 95 I

1. Description of change:

Add (*) symbol to indicate a numeric entry required. Add a phrase " Backup operating"in section IV 5 to update the current procedure. Delete items I not required, "3152"in section I.4 and " Primary and Backup"in section V.4. l

2. The proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).  ;

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, forward a copy of changes necessary to Logistics. Not Required

4. Determine what other procedures, logs, or training material may be affected and record below, see #5

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

Operational Pmcedure 8, TAB B1 DAILY SAFETY CHECKLIST Add "* " to section I.1; II.1,2,4,5; IV.1,2,4,5; VI.5,8a,9,12.

Add "(b) Backup operating" to section IV.5 Delete "3152" to section I.4 and " Primary and Backup"in IV.5

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

Action Sheet: Submitted Not Required X Reviewed and approved by RFD ^l  ! Date [Y A /j R RFSC Notified (( M b Date OCT bl 819[5 "6 Q

I

_. _ _ ~

DPERATIONAL PROCEDURE? , R' Procediire 8, TAB B:

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- we .au m.m n DAILY OPERATIONAL STARTUP CHE_CKLIST Checklist number Date Time completed Supervised by Assisted by I. EQUIPMENT ROOM (Room 3152)

1. Air compressor pressure (80 - 110 psig) .................................. *

2. Wa t er d rain ed from air co mpressor .......................................

3. Air d ry e r o p e r a t in g . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . .. . . . . . . .. . . . . . . . . . . . . . . . . . . . .

4. D oors 231,231 A, and roof hat ch SECU R ED ..........................

II. L O B B Y A R E A Lo b b y a u d io al a r m t u r n e d a ff . . . ... . . . . .. . . . . . . . . . ... . . .. . . .. . . . . . . . . . .. . . . . . . . . . . . . . . .. . . .

III. EQUIPMENT ROOM (Room 2158)

1. Prefilter differentia 1 pressure (< 8 psid) ................................... *

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

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

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

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

6. Visu a 1 in sp e et io n o f a r ea .. .. .. . . .. .. . . .. .. . ... ... . .. ... ... .... .. ... ... ... ... .... .

7. D o o r 215 8 S E C U R E D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

IV. PREPARATION AREA Visu a 1 in sp e et io n o f a r ea . .. . . . . .. . .. ... . ..... .. . . .. .... .. ... .... .. . .. ... . .. . . . ... .. .

V. REACTOR ROOM (Room 3161)

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

• l

2. Shield door bearing air pressure (8.5 - 9.5 psig) ...................... *

3. Visu a 1 insp eet io n o f co re a nd t a nk ..........................................

4. Number of fuel elements and Fuel elements

• control rods in tank storage Control rods

• l

5. Air particulate monitor (CAM)

(a) Prima ry op era ting a n d t ra cin g .......................................... l (b) B a ck u p o p e ra t in g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . ..

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

6. Stack gas monitor quality assurance checked .........................

7. D o o r 316 2 S E C U R E D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

l Numerical Entry AFRRI FORM 61a (R) Revised: 14 Jul 95 Page1

VI. REACTOR CONTROL ROOM (Room 3160)

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

2. Co n sole r eco r d ers d a t ed . . ....... . .. .. . . . . . . ... .. . . .. . . ..... . .. .. .. ... .. . ... . .. .... .. . .. ... ..

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

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

5. Water monitor box f

(a) Ba ekgro u nd aetivit y (10 - 60 cp m) ............................................... *

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

(c) D M 1 resistivity [ > 0.5 M ohm-cm] ............................................. *

(d) D M 2 resistivity [ > 0.5 M ohm-cm] ............................................. *

6. Stack gas flow rate [15 - 35 Kcfm] . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . *

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

8. Gas stack monitor (a) Ba ck gro u n d (2 - 20 cp m ) . . . . .. .. . .. .. .... .. .... ... . .. . .. ..... . .... . .. . . .. . . . . ... .. . . *

(b ) A l a r m ch e ck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

9. Radiation monitors Monitor Alarm Point Reading Alarm Setting Functional (mrem /hr) (mrem /hr) l j (a) R-1 (<20) 500 l 1

(b) R-2 (< 10) 10 (c) R-3 (<10) 10  :

, (d) R-5 (<20) _

100 1

(c) E-3 (< 10) 10 t

, (f) E-6 (< 10) 10

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

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

' 12. .Wat er t emperat u re (inlet) (5 - 35 C) ................................................ *

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

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

15. Tim e d c la y o p er a t ive . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

17. Prest att op erability ch eeks performed .............................................

l 18. Interlock Tests

a) Rod raising, SS mode (e) 1 kW/ Pulse mode I (b) Rod raising, Pulse mode (f) NM-1000 HV (c) Source RWP (g) Inlet Temp (d) Period RWP

19. SCRAM checks (at least one per rod)

(a) % Power 1 (h) Reactor key 1 (b) % Power 2 (i) Manual I (c) Fuel temp 1 (j) Emergency Stop {'

(d) Fuel temp 2 (k) Timer (c) HV loss 1 '" 'SC Watchdog  !

(f) HV loss 2 t I AC Watchdog (g) Poollevel 2 0. Z e ro p ower p u lse ... .... .... .... . . . ... ........ . . . . ..... . .. .. ........................

l AFRRI FORM 61b (R) Revised: 14 Jul 95 Page 2

p 1

Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change Procedure 11, " Air Particulate Monitor (CAM) Procedure Modification to: Procedure x Facility Experiment Submitted by: src omnny v . w.ci, inn Date n x,,7 m

1. Description of change:

Procedure 11 is changed to reflect new parameters for channel test on primary and secondary CAM. This is due to installation of new electronics module in primary CAM. Secondary CAM electronics module was changed in May 95. New channel test reading is 1000 cpm +/- 20%.

Both CAMS still perform in the same manner.

2. Verify that the proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does net produce an unresolved safety question as defined in 10 CFR 50.59(a)(2). Done.

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to 1.ogistics. N/8

4. Determine what other procedures, logs, or training material may be affected and record below. /[/gj;< l

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

Nu \

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

Action Sheet: Submitted Not Required x Reviewed and approved by RF Date 0 9 AUG1995 RRFSC Notified /- - Date OCT I 8 1995 8

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Revised: 27 May 93 Page 6

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OPER

. m TiONAI.PROCEDNREI!M' ^ " ^ ??"*NI"#CT Eh ??TMUIiiii.

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1 AIR PARTICULATE MONITOR (CAM) PROCEDURE ,

GENERAL This procedure specifies how to test the CAM to ensure proper operation of this monitoring device. A channel test will be performed on both reactor room CAMS at the beginning and end of each day.

SPECIFIC

1. OPERATING and TRACING j Check that the primary CAM is operating and tracing with the correct time indicated on the chart and check that the secondary CAM is operating.

Ensure the flow rate is >6 cfm and not off scale.

2. CH ANNEL TEST WITH SOURCE

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

1000 cpm +/-20%. Reset the switch,

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

c. Slowly bring a radioactive source near the detector. Observe the meter on the front of the CAM. The yellow light will activate at approximately 4,000 counts per minute. The red light will activate at approximately 10,000 counts per minute; the alarm will sound and the dampers will close. Reset the alarm, close the chamber door and return the source to the CAM drawer.

d. Annotate completion of the channel test on chart paper with initials, time, and date performed for primary CAM. Annotate comoletion of the channel test on secondary CAM chart nacer only when crimarv CAM is bypassed.

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

4. BY-PASS of PRIM ARY CAM Revised:08 Aug 95 Page1 I

When the primary CAM is by-passed, the secondary CAM chart recorder needs to be activated, then perform items 1,2a, and 2d.

I Revised:08 Aug 95 Page 2

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Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required 4

Proposed Change: Procedure Change- Operational Procedure A3

]

Modification to: Procedure X Facility _ Experiment _

Submitted by: .lohn T. Nguyen Dde: 09 Aug 95

l. Description of change:

In page 2, Par 3 a word, "following", is changed to "followed by".

1 I

2. The proposed change does not involve a change to the Technical Specifications, the facility as described in the SAR, or procedures as described in the SAR, and does not produce an unresolved safety issue as defined in 10 CFR 50.59(a)(2).

! 3. If change involves a facility modification, attach a drawing if appropriate. If l 2

structural facility drawings need updating, forward a copy of changes necessary to l Logistics. Not Required l

4. Determine what other procedures, logs, or training material may be affected and record below. see #5

5. List of associated drawings, procedures, logs, or other materials to be changed: 1 Operational Pmcedure A3, Facility Modification In page 2, Paragraph 3 a word, "following", is changed to "followed by".

6. Create an Action Sheet containing the list of associated work specified above,

attach a copy, and submit it to the RFD.

Action Sheet: Submitted Not Required X

Reviewed and approved by RFD b! [ Date 09 AUG1995 RRFSC Notified m d(( Date OCT I 81995 4

4

I ADMINISTRATIVE PROCED1)RE[ g ,1 g

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FACILITY MODIFICATION GENERAL Changes to the Reactor Facility and operational procedures must comply with requirements specified in the Reactor License, and 10 CFR 50.59. It is required that modifications to the facility or procedures as described in the Safety Analysis Report (SAR) be documented with a written safety analysis. Under 10 CFR 50.59, a licensee may make changes to the facility provided there are no changes made to the Technical Specifications, there are no unreviewed safety questions, and that a proper safety analysis is carried out, documented, and reviewed.

Applicability:

The Facility Modification Procedure applies to proposed facility changes or changes in the operating procedures.

The referenced procedure will not cover routine replacement of parts or components with equivalent parts or components.

DESCRIPTION This administrative procedure consists of these instructions, the Facility Modification Worksheet Guide, and two worksheets to facilitate a 10 CFR 50.59 review of modifications and to determine if a detailed safety analysis is necessary.

The instructions in the Facility Modification Worksheet Guide are used to determine which worksheet must be completed for the modification. One of three conclusions regarding the proposed facility modification will be reached:

1. The modification requires prior approval or a license amendment from the USNRC,

2. The modification may be made according to the provisions of 10 CFR 50.59(a)(1)(Facility Modification Worksheet # 1), or

3. The modification does not require a 10 CFR 50.59 safety analysis (Facility Modification Worksheet # 2).

~

Revised:09 Aug 95 Page1

I Facility Modification Worksheet Guide

1. Technical Specification Change: If the proposed modification requires a change in the Technical Specifications, a license amendment is required prior to making the change. NRC approvalis required; do not implement the change without this approval.

2. Unreviewed Safety Question: If an unreviewed safety question is created by the proposed change as defined in 10 CFR 50.59(a)(2) such that the change increases the probability of occurrence or severity of an accident described in the SAR, can malfunction in a manner that can cause an accident of a different type than described in the SAR or can decrease safety margins as defined in Technical Specifications, then NRC approvalis required. Do not implement the change without this approval.

3. If the proposed modification makes a change in the facility as described in the SAR or changes a procedure as described in the SAR, the change can be l performed under a 10 CFR 50.59 analysis with a safety review,if there are no J unreviewed safety issues (10 CFR 50.59(a)(2)). The change may be made followed by_a review by the RRFSC. Go to Facility Modification Worksheet # 1. l

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4. If the proposed modification does not make a change to the facility as described in the SAR or to a procedure as described in the SAR and does not pose an ,

unreviewed safety issue, a 10 CFR 50.59 analysis is not required. Go to Facility I Modification Worksheet # 2.

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Revised:09 Aug 95 Page 2

Facility Modification Worksheet 1 10 CFR 50.59 Analysis Proposed Change Submitted by: Date

1. Description of change:

2. Reason for change:

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

l Analysis attached? Yes

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

Procedure Facility Experiment Revised:09 Aug 95 Page 3

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Facility Modification Worksheet 1 i

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

} necessary updates to the SAR. Note that this description need not contain the

final SAR wording.

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

4 Revised:09 Aug 95 Page 4 l

Facility Modification Worksheet 1

7. Specify associated information.

New drawings are: Attached Not required Does a drawing need to be sent to Logistics? Yes No Are training materials effected? Yes No Will any Logs have to be changed? Yes No Are other procedures effected? Yes No List ofitems affected:

8. Create an Action Sheet containing a list of associated work specified in item #

7, attach a copy, and submit another to the RFD (modification of drawings must be approved by the RFD).

Action Sheet: Submitted Not Required Reviewed and approved by RFD Date RRFSC Concurrence Date Revised:09 Aug 95 Page 5

Facility Modification Worksheet 2  !

I No 10 CFR 50.59 Analysis Required Proposed Change j Modification to: Procedure Facility Experiment Submitted by: Date '

l. Description of change:

l l

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

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

3. If change involves a facility modification, attach a drawing if appropriate. If structural facility drawings need updating, modification of drawings must be approved by RFD and forward a copy of changes necessary to Logistics.

4. Determine what other procedures, logs, or training material may be affected and record below.

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

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

Action Sheet: Submitted Not Required Reviewed and approved by RFD Date RRFSC Notified Date Revised:09 Aug 95 Page 6

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r ATTACHMENT C i o

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. Appointment Letters for Current Reactor'

Land Radiation Facility Safety Committee 2

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i ARMED FORCEO RADIO':lOLO3Y RECEARCH INOTIT 8901 wlSCoNSIN AVENUE BETHESDA. MARYLAND 20889-5603 l

RRFSC 18 September 1995

. 605.01 l I

MEMORANDUM FOR RECORD .

SUBJECT:

Members of Reactor and Radiation Facility Safety Committee l

Effective this date, the following individuals are members of the Armed Forces Radiobiology Research Institute (AFRRI) Reactor and Radiation Facility Safety Committee (RRFSC). Memberships are in accordance with the Technical Specifications of Nuclear Regulatory Commission license R-84. I 4

i PERMANENT MEMBERS Thomas J. O' Brie'n, AFRRI, Radiation Safety Officer Voting Member 4

Mark Moore, AFRRI, Reactor Facility Director Voting Member

)

d APPOINTED MEMBERS

)

David G. Jarrett, COL, MC, USA, AFRRI, Chairman Voting Member Dr. Marcus Voth, The Pennsylvania State University, Voting Member Reactor Facility Director ,

4 Mark A. Miller, Naval Research Laboratories, Voting Member Radiation Safety Officer l

SPECIAL MEMBERS Charles B. Galley, CAPT, MSC, USN, AFRRI, Special Voting Member Head, Radiation Sciences Department l J mes Caldwell, Montgomery County Government, Special Non-Voting Member l Environmental Protection Department Dr. Leslie McKinney, AFRRI, Special Non-Voting Member

, Radiation Pathophysiology and Toxicology Department RECORDER i

Danny K. McClung, SFC, USA, AFRRI Special Non-Voting Member

E. KEARSLEY CAPT,MSC,USN 4

Director DISTRIBUTION:

1-each individual 1-RRFSC file I

4

RSDR 31 January 1995 MEMORANDUM FOR DIR THROUGH RFD CO

'Mi/pp CUBJECT: Additional Duty Appointment Request that SFC Danny K. McClung be appointed as Recorder (non-voting member) for the Reactor and Radiation Facility Safety Committee.

M MARK MOO Reactor acility Director -

/-

Concur Nonconcur C .G Y Captain, C, USN Head, Ra intion Sources Department i

Cencur/ onconcur R. SHEEHAN olonel, USAF, MSC Chairman, Reactor and Radiation Facility Safety Committee prove / Disapproved ERIC E. KEAR Captain, MSC, USN Acting Director cc:

SFC McClung RRFSC File

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! RRFSC 23 February 1995 MEMORANDUM FOR RECORD

SUBJECT:

Appointment of Alternate Member, RRFSC

]

4 j Mr. Steve Miller is appointed as an alternate member for the 1 3 March 1995 RRFSC meeting. The Reactor Facility Director is un-

] cvailable due to travel commitments. Mr. Miller's knowledge and j p2sition qualify him to substitute.

5

/

O R. SHEEHAN

Colonel, MSC, USAF 1

Chairman, RRFSC l DISTRIBUTION:

1-Mr. Miller 1-RRFSC file 4

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DIR 18 September 1995 MEMORANDUM FOR RECORD

SUBJECT:

Reactor and Radiation Facility Safety Committee Special Members ,

Effective this date, the appointment of the following special member to the RRFSC is rescinded:

Eric G. Daxon, LTC(P), MSC, USA.

E. KEARSLEY CAPT, MSC, USN Director i

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1 4 DIR 18 September 1995 MEMORANDUM FOR RECORD

SUBJECT:

Reactor and Radiation Facility Safety Committee Special Members Effective this date the appointment of the following member to the RRFSC is rescinded:

Mr. Kirk King, Naval Research Laboratory.

Mr. King is replaced by Mr. Mark A. Miller, also of Naval i Research Laboratory. Mr. Miller's expertise in the field of '

radiation protection qualifies him to be a voting member of the RRFSC.

(-

E. KEARSLEY CAPT, MSC, USN Director l

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ATTACHMENT D 4

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Summary of all Maintenance for 1994 I

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i l TRIGA TRACKER l

l MAINTENANCE ANNUAL I

REPORT l ******

i i 1995 i

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Armed Forces Radiobiology Research Institute 8901 Wisconsin Avenue Bethesda, Maryland 20889-5603

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i AFRRI/RSD Date 22 ' JAN 1996 i

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MEMORANDUM FOR Reactor Facility Director l Deputy Reactor Facility Director i Reactor Operator Supervisor

!' Record i

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SUBJECT:

Maintenance Annual Report -1995 4.

3 The Son of TRIGA Tracker provides the reactor staffinformation concerning maintenance

tasks, frequency, requirement, due date, and date of completion. All information is stored in a l database which is updated throughout the year as maintenance is performed. The following is the summary of the Maintenance Annual Report for 1995

J

1. The following tasks have not completed:

ID_Nu Task Requirement Due Date m-A019 Security Personnel Training Emergency 16-DEC-95 This task is also postponed until Feb 96 Plan 8.1 l

)

2. 306 items were performed during the year Attached is the maintenance report which provided a list of completed tasks in 1995 Notice that this report is sorted by task ID number and date of completion. Please review, initial and return to me for filing.

' T<

r John T. Nguyen i

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Abbreviation The folloWng are the abbreviations used in the Annual Maintenance Report ID_NUM A = Administrative C = Calibration M = Maintenance P = Reportable S = Surveillance TASKS RRFSC = Reactor & Radiation Facility Safety Committee ERT = Emergency Response Team SNM =Special Nuclear Material SCBA =Self Contained Breathing Apparatus RWP = Rod Withdravel Prevent RAM = Remote Area Monitor RTD = Resistance Temperature Detector CSC cControl Systesm Computer DAC = Data Acquisition Computer R E QUIR E ME NT TS = Technical Specifications CFR = Code of Federal Regulations EP = Emergency Plan OP = Operational Procedure Req =Requalification NRC = Nuclear Regulatory Commission internal =Not required except by internal Facility Director Memorar.dum PSP = Physical Security Plan Manual = Manufacture's recommendation in maintenance manual ASC = Annual Shutdown Checklist FREQUENCY M = Monthly O = Quarterly S = Semi-Annually A = Annually N =Non-routine

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST_DONE A001 RRFSC Meeting, full or Subcomittee TS 6.2.3.2 0 01-MAR-95 A001 RRFSC Meeting, Full or Subcomittee TS 6.2.3.2 0 02-JUN-95 A001 RRFSC Meeting, Full or Subcomittee TS 6.2.3.2 Q 18-0CT-95 A001 RRFSC Meeting, Full or Subcomittee TS 6.2.3.2 Q 18-DEC-95 A002 Emergency Directions Memorandum Internal Q 01-JAN-95 A002 Emergency Directions Memorandum Internal Q 01-APR-95 A002 Emergency Directions Memorandum Internal A002 Emergency Directions Memorandum 0 01-JUL-95 Internal Q 02-0CT-95 A004 On-Call Designation Memorandum TS 6.1.3.2 01-JAN-95 Q

A004 On-Call Designation Memorandum TS 6.1.3.2 0 01-APR-95 A004 On-Call Designation Memorandum TS 6.1.3.2 Q 01-JUL-95 A004 On-Call Designation Memorandum TS 6.1.3.2 Q 02-0CT-95 A005 Reactor Access Roster PSP A005 Q 01-JAN-95 Reactor Access Roster PSP Q 01-APR-95 A005 Reactor Access Roster PSP Q 01 ,1UL-95 A005 Reactor Access Roster PSP Q 02-0CT-95 A006 Operator Records Review 10 CFR 55, Requal Plan A006 Operator Records Review 0 03-JAN-95 10 CFR 55, Requal Plan Q 03-APR-95 A006 Operator Records Review 10 CFR 55, Requal Plan A006 Operator Records Review Q 03-JUL-95 10 CFR 55, Requal Plan Q 30-0CT-95 A007 Emergency Training of ECP Personnel EP 8.1 A 09-NOV-95 A008 Emergency Drill EP 8.2; 10 CFR 50 A 29-NOV-95 A009 ERT Training EP 8.1 A009 ERT Training Q 22-FEB-95 EP 8.1 Q 22-MAR-95 A009 ERT Training EP 8.1 A009 ERT Training Q 21-JUN-95 EP 8.1 Q 27-SEP-95 A009 ERT Training EP 8.1 Q 29-NOV-95 A010 Prep Area Access Memo Review / Update OP A2 A 04-JAN-96 A0ll Reactor Facility Audit TS 6.2.5 A 26-0CT-95 A012 Emergency Plan Review 10 CFR 50, EP 8.3 A 16-JAN-96 A013 Accountability Report for SNM 10 CFR 73 A013 Accountability Report for SNM S 31-MAR-95 10 CFR 73 S 02-0CT-95 A014 Emergency Briefing for AFRRI Personnel EP 8.l(3) A 05-DEC-94 /

Note: This task is late and postponed until Feb 96 A015 Reactor Operations Logbook Review OP 8, TAB A N 26-0CT-95 A016 NNMC Security & Fire Personnel Training EP 8.1 A 23-MAR-95 A017 Publish Schedule for Requal Lectures 10 CFR 55.59 A 18-JAN-96 A018 Physical Security Plan Review Security Plan 6a A 19-DEC-95

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST DONE A019 Security Personnel Training EP 8.1 A 16-DEC-94 Note: This task is late and postponed util Feb 96 A023 Wallet Size Recall Roster TS 6.1.3.2 N 06-JAN-95 A024 SCBA Training for ERT Members 10 CFR 20.1703 A 15-MAR-95 A025 Officer of the Day Annual Training AFRRI Inst 5200.8A A 28-JUL-95 A026 Training for Prep Area Users 10 CFR 19.12 A 12-APR-95 A027 RRFSC Minutes and Summary of Action A027 Internal Q 14-JAN-95 RRFSC Minutes and Summary of Action Internal A027 RRFSC Minutes and Summary of Action Q 26-APR-95 A027 Internal Q 26-JUL-95 RRFSC Minutes and Summary of Action Internal A027 RRFSC Minutes and Summary of Action Q 25-0CT-95 Internal Q 28-DEC-95 C001 Calibration of Cooling System Gauges Internal A 28-APR-95 C002 Calibrate Pressure Gauges / Air System Internal A 30-0CT-95 C004 Fuel Temp Channel I Calibration TS 4.2.3b A 05-0CT-95 C005 Fuel Temp Channel II Calibration TS 4.2.3b A 05-0CT-95 C005 Stack Gas Monitor Calibration Manual A 04-0CT-95 C007 Operational Channel Calibration TS 4.2.2c A 06-0CT-95 C008 Safety Channel I Calibration TS 4.2.2c A 05-0CT-95 C009 Safety Channel II Calibration TS 4.2.2c A 06-0CT-95 C010 Scram Circuit Calibration TS 3.2.2 A 29-NOV-95 C011 RWP Calibration

. TS 3.2.2 A 29-NOV-95 C012 Control Rod Calibration TS 3.1.2 & 4.la A 07-DEC-95 C013 Criticality Monitor, Elec Calibration TS 4.5 A 12-DEC-95 C014 RAM System Calibration TS 4.5 A 12-DEC-95 C015 Thermal Power Calibration TS 4.2.2c A 01-NOV-95 C016 Fuel Temp Chart Recorder Calibration TS 4.2.3b, 2.1 A 05-0CT-95 C017 Fuel Temp Prestart Action Pak Cal Manual, Annual Shutdown A 05-0CT-95 C018 Magnet Power Supply Action Pak Cal Manual, /Innual Shutdown A 05-0CT-95 C019 l Ground Fault Detector Action Pak Cal Manual, Annual Shutdown A 05-0CT-95

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST_DONE C020 A1016 Boards Calibration Manual, Annual Shutdown A 05-0CT-95 CO21 Thermocouple Quality Assurance Verificat Manual, Annual Shutdown A 05-0CT-95 CO22 RTD Probes Calibration Internal A 24-0CT-95 C023 Calibration of Pulse Ion Chamber TS 3.2.1 & 4.2.2 A 02-NOV-95 CO24 Calibration of Cerenkov Detector TS 3.2.1 & 4.2.2 A 02-NOV-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 27-JAN-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 23-FEB-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 29-MAR-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 21-APR-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 26-MAY-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M001 UPS System Test for Criticality Monitor M 26-JUN-95 10 CFR 70 M 28-JUL-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M M001 UPS System Test for Criticality Monitor 30-AUG-95 10 CFR 70 M 29-SEP-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 23-0CT-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 28-NOV-95 M001 UPS System Test for Criticality Monitor 10 CFR 70 M 28-DEC-95 M002 Stack Gas Monitor 011 Check Manual M 27-JAN-95 M002 Stack Gas Monitor Oil Check Manual M 23-FEB-95 M002 Stack Gas Monitor Oil Check Manual M 28-MAR-95 M002 Stack Gas Monitor Oil Check Manual M 21-APR-95 M002 Stack Gas Monitor Oil Check Manual M 26-MAY-95 M002 Stack Gas Monitor Oil Check Manual M 26-JUN-95 M002 Stack Gas Monitor Oil Check Manual M 28-JUL-95 M002 Stack Gas Monitor Oil Check Manual M 30-AUG-95 M002 Stack Gas Monitor Oil Check Manual M 29-SEP-95 M002 Stack Gas Monitor Oil Check Manual M 27-0CT-95 M002 Stack Gas Monitor Oil Check Manual M 28-NOV-95 M002 Stack Gas Monitor Oil Check Manual M 28-DEC-95 M003 Transient Rod Air System Manual M003 Transient Rod Air System M 30-JAN-95 Manual M 27-FEB-95 M003 Transient Rod Air System Manual M003 M 28-MAR-95 Transient Rod Air System Manual M003 Transient Rod Air System M 21-APR-95 Manual M 26-MAY-95 M003 Transient Rod Air System Manual M003 Transient Rod Air System M 26-JUN-95 Manual M 28-JUL-95 M003 Transient Rod Air System M003 Manual M 30-AUG-95 Transient Rod Air System Manual M003 Transient Rod Air System M 29-SEP-95 M003 Manual M 01-NOV-95 Transient Rod Air System Manual M003 M 28-NOV-95 Transient Rod Air System Manual M 28-DEC-95 M004 Air Damper Operation & SCBA check M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 27-JAN-95 l M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 23-FEB-95 M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 29-MAR-95 N004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 21-APR-95 TS 3.4 & 4.4 & 5.lc M 30-MAY-95

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST_DONE M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M004 Air Damper Operation & SCBA check M 26-JUN-95 M004 Air Damper Operation & SCBA chec',

TS 3.4 & 4.4 & 5.lc M 28-JUL-95 M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 30-AUG-95 M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 29-SEP-95 M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 27-0CT-95 M004 Air Damper Operation & SCBA check TS 3.4 & 4.4 & 5.lc M 28-NOV-95 TS 3.4 & 4.4 & 5.lc M 28-DEC-95 M005 Millipore Water Makeup System Manual M005 Millipore Water Makeup System M 27-JAN-95 Manual M 23-FEB-95 M005 Millipore Water Makeup System Manual M M005 Millipore Water Makeup System 28-MAR-95 Manual M 21-APR-95 M005 Millipore Water Makeup System Manual M 26-MAY-95 M005 Millipore Water Makeup System Manual M 26-JUN-95 M005 Millipore Water Makeup System Manual M005 Millipore Water Makeup System M 28-JUL-95 Manual M 30-AUG-95 M005 Millipore Water Makeup System Manual M 29-SEP-95 M005 Millipore Water Makeup System Manual M005 M 31-0CT-95 Millipore Water Makeup System Manual M 28-NOV-95 M005 Millipore Water Makeup System Manual M 28-DEC-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 27-JAN-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 23-FEB-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 28-MAR-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 21-APR-95 M005 Lube Pump & Bearings of Prim. Cooling Manual M 30-MAY-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 26-JUN-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 28-JUL-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 30-AUG-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 29-SEP-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 27-0CT-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 28-N0V-95 M006 Lube Pump & Bearings of Prim. Cooling Manual M 28-DEC-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 27-JAN-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 23-FEB-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 28-MAR-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 21-APR-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 30-MAY-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 26-JUN-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 28-JUL-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 30-AUG-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 29-SEP-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 27-0CT-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 28-NOV-95 M007 Lube Pump & Motor bearings, 2nd cooling Manual M 28-DEC-95 M008 Experimental Tables and Stands Internal M008 Experimental Tables and Stands Q 29-MAR-95 Internal Q 29-JUN-95 M008 Experimental Tables and Stands Internal M008 Experimental Tables and Stands Q 05-0CT-95 Internal Q 18-DEC-95 M009 Channel Test of Criticality Monitor M009 TS 4.5, 10 CFR 70 Q 09-MAR-95 Channel Test of Criticality Monitor TS 4.5, 10 CFR 70 0 21-JUN-9

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST_DONE M009 Channel Test of Criticality Monitor TS 4.5, 10 CFR 70 M009 Channel Test of Criticality Monitor Q 28-SEP-95 TS 4.5, 10 CFR 70 Q 12-DEC-95 M010 Channel Test of RAM TS 4.5, 10 CFR 70 Q 09-MAR-95 M010 Channel Test of RAM TS 4.5, 10 CFR 70 Q 21-JUN-95 M010 Channel Test of RAM TS 4.5, 10 CFR 70 Q 28-SEP-95 M010 Channel Test of RAM TS 4.5, 10 CFR 70 Q 12-DEC-95 M0ll Clutch Adjustment Check of Shield Doors Manual M011 Clutch Adjustment Check of Shield Doors Q 27-JAN-94 Manual Q 21-APR-95 M0ll Clutch Adjustment Check of Shield Doors Manual M011 Clutch Adjustment Check of Shield Doors Q 28-JUL-95 Manual Q 23-0CT-95 M012 Pressure Relief Dampers Inspection M012 Internal Q 30-MAR-95 Pressure Relief Dampers Inspection Internal M012 Pressure Relief Dampers Inspection Q 26-JUN-95 M012 Internal Q 28-SEP-95 Pressure Relief Dampers Inspection Internal Q 05-JAN-96 M013 Lamp, Filter Check on Stc, rage Tank Manual Q 27-JAN-95 M013 Lamp, Filter Check on Storage Tank Manual Q 21-APR-95 M013 Lamp, Filter Check on Storage Tank Manual Q 28-JUL-95 M013 Lamp, Filter Check on Storage Tank Manual Q Ol-NOV-95 M014 Exercise Reactor Water Syst Valves Internal M 27-JAN-95 M014 Exercise Reactor Water Syst Valves Internal M014 Exercise Reactor Water Syst Valves M 23-FEB-95 Interna M 31-MAR-95 M014 Exercise Reactor Water Syst Valves Internal M014 Exercise Reactor Water Syst Valves M 21-APR-95 M014 Internal M 30-MAY-95 Exercise Reactor Water Syst Valves Internal M014 Exercise Reactor Water Syst Valves M 26-JUN-95 M014 Internal M 28-JUL-95 Exercise Reactor Water Syst Valves Internal M M014 Exercise Reactor Water Syst Valves 30-AUG-95 M014 Internal M 29-SEP-95 Exercise Reactor Water Syst Valves Internal

• M M014 Exercise Reactor Water Syst Valves 27-0CT-95 M014 Internal M 28-NOV-95 Exercise Reactor Water Syst Valves Internal M 28-DEC-95 M015 Cooling Tower Inspection Internal M015 Cooling Tower Inspection S 29-JUN-95 Internal S 05-JAN-96 M016 Change (tack Gas Blower Oil Manual M016 Change .;ack Gas Blower Oil Q 28-MAR-95 Manual 29-JUN-95 M016 (hange Stack Gas Blower Oil Manual Q

M016 CMnge Stack Gas Blower Oil Q 04-0CT-95 Manual Q 22-JAN-96 M017 Reg, Safe & Shim Rod Drive, Check Belts M017 Internal Q 31-MAR-95 Reg, Safe & Shim Rod Drive, Check Belts Internal M017 Reg, Safe & Shim Rod Drive, Check Belts Q 26-JUN-95 M017 Internal Q 19-0CT-95 Reg, Safe & Shim Rod Drive, Check Belts Internal Q 22-JAN-96 M018 Grease Wheel Bearings in ERI Manual 30-JAN-95

( M018 Grease Wheel Bearings in ERI Q M018 Manual Q 01-MAY-95 Grease Wheel Bearings in ERI Manual M018 Grease Wheel Bearings in ERI Q 31-JUL-95 Manual Q 30-0CT-95

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST_DONE M019 Grease Wheel Bearings in ER2 Manual Q 30-JAN-95 M019 Grease Wheel Bearings in ER2 Manual Q 01-MAY-95 M019 Grease Wheel Bearings in ER2 Manual Q 31-JUL-95 M019 Grease Wheel Bearings in FR2 Manual Q 30-0CT-95 M020 Change Air Compressor Oil Manual N020 Change Air Compressor Oil Q 28-MAR-95 Manual Q 26-JUN-95 M020 Change Air Compressor Oil Manual M020 Change Air Compressor Oil Q 04-0CT-95 Manual Q 22-JAN-96 M021 Control Rods Visual Inspection TS 4.lc & 4.2.5 A 27-0CT-95 M022 Control Rod Examination TS 4.lc & 4.2.5 A 27-0CT-95 M023 Rod Drive Installation Manual., Annual Shutdown A 30-0CT-95 M024 Control Rod Connecting Pins M024 Internal M 27-JAN-95 Control Rod Connecting Pins Internal M024 Control Rod Connecting Pins M 27-FEB-95 M024 Internal M 31-MAR-95 Control Rod Connecting Pins Internal M024 Control Rod Connecting Pins M 21-APR-95 M024 Internal M 31-MAY-95 Control Rod Connecting Pins Internal M M024 Control Rod Connecting Pins 26-JUN-95 M024 Internal M 28-JUL-95 Control Rod Connecting Pins Internal M024 Control Rod Connecting Pins M 30-AUG-95 M024 Internal M 29-SEP-95 Control Rod Connecting Pins Internal M024 Control Rod Connecting Pins M 27-0CT-95 M024 Internal M 05-DEC-95 Control Rod Connecting Pins Internal M 05-JAN-96 N025 Oil Level Check in Lead Shield Door Syst Manual A 23-0CT-95 M026 Inspect Seals around Reactor Room Doors M026 Internal S 30-MAR-95 Inspect Seals around Reactor Room Doors Internal S 29-SEP-95 N027 Still Inspection & Cleaning Manual A 23-0CT-95 M028 Console Chart Recorder Inspection Internal A 23-0CT-95 M029 Reg Rod Drive Annual Maintenance Manual A 19-0CT-95 M030 Safe Rod Drive Annual Maintenance Manual A 19-0CT-95 M031 Shim Rod Drive Annual Maintenance Manual A 19-0CT-95 M032 Trans Rod Drive Annual Maintenance Manual A 21-AUG-95 M033 Facility Interlock Checklist TS 4.2.4 & 3.2.3 M033 Facility Interlock Checklist TS 4.2.4 & 3.2.3 S 18-APR-95 S 01-DEC-95 M034 Timer Cleaning & Inspection Manual A 23-0CT-95 M035 Standard Rod Drive Removal TS 2.1 & 4.2.5 A 19-0CT-95 l

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID__NUM TASKS REQUIREMENT FREQUENCY LAST_DONE M036 Transient Rod Drive Inspection TS 4.ld M036 Transient Rod Drive Inspection S 31-MAR-95 TS 4.1d S 21-SEP-95 M037 Digital Rod Position Indicators Adjust Internal A 30-0CT-95 M038 Rod Drive Barrel Removal Manual, Annual Shutdown A 19-0CT-95 N040 Rod Drive Barrel Assembly Manual, Annual Shutdown A 30-0CT-95 M041 Change Absolute, Roughing & Prefilter Manual N 17-JAN-95 M042 Change Resin Beds on still Internal N 11-JAN-95 M044 Change Demineralizer Resins Internal N 18-AUG-95 M045 Core Dolly Oil Check Manual A 23-0CT-95 M047 CSC & DAC Computer Filter Cleaning Manual Q 27-FEB-95 M047 CSC & DAC Computer Filter Cleaning Manual Q 31-MAY-95 M047 CSC & DAC Computer Filter Cleaning Manual Q 31-AUG-95 M047 CSC & DAC Computer Filter Cleaning Manual Q 15-DEC-95 M048 Am-Be Neutron Source Check NRC 8yproduct License A 24-MAR-95 P001 Verification of Reactor Monthly Usage OP 8 M 31-JAN-95 P001 Verification of Reactor Monthly Usage OP 8 M 28-FEB-95 P001 Verification of Reactor Monthly Usage OP 8 H 31-MAR-95 P001 Verification of Reactor Monthly Usage OP 8 M 28-APR-95 P001 Verification of Reactor Monthly Usage OP 8 M 01-JUN-95 P001 Verification of Reactor Monthly Usage OP 8 M 30-JUN-95 P001 Verification of Reactor Monthly Usage OP 8 M 31-JUL-95 P001 Verification of Reactor Monthly Usage OP 8 M 01-SEP-95 P001 Verification of Reactor Monthly Usage OP 8 M 02-0CT-95 P001 Verification of Reactor Monthly Usage OP 8 M 01-NOV-95 P001 Verification of Reactor Monthly Usage 0P 8 M 30-NOV-95 P001 Verification of Reactor Monthly Usage 0P 8 M 02-JAN-96 P002 Key Inventory OP 5 A 31-JUL-95 P003 Annual Operating Report TS 6.6.lb A 27-MAR-95 P004 Indemnity Payment to NRC 10 CFR 140 A 18-APR-95 P005 Enriched Uranium Lease Agreement Agreement #1037 N 11-DEC-95 5001 Hall Alarm Panel Operable Verification EP 8.4 10-MAR-95 S001 Hall Alarm Panel Operable Verification EP 8.4 Q

S001 Hall Alarm Panel Operable Verification Q 26-JUN-95 5001 EP 8.4 0 04-0CT-95 Hall Alarm Panel Operable Verification EP 8.4 Q 22-JAN-96 S002 Inventory of Emergency Equipment 5002 EP 6.6 Q 31-JAN-95 Inventory of Emer9ency Equipment EP 6.6 S002 Inventory of Emergency Equipment Q 14-APR-95 EP 6.6 Q 24-JUL-95

SON of TRIGA TRACKER MAINTENANCE ANNUAL REPORT - 1995 ID_NUM TASKS REQUIREMENT FREQUENCY LAST_DONE S002 Inventory of Emergency Equipment EP 6.6 Q 23-0CT-95 S003 Control Rod Drop Times Measurement TS 4.2.1 & 3.1.4 S003 Control Rod Drop Times Measurement S 11-APR-95 TS 4.2.1 & 3.1.4 S 31-0CT-95 S004 Reflector Coefficient & Excess Reactivit TS 4.la; OP 8 tab D A 12-DEC-95 S005 Reactor Water Analysis for Nitrate Hach Handbook A 03-0CT-95 S007 SCBA Regulator Annual Flow Test 10 CFR 20.1703 A 22-NOV-95 S008 Reactor Water Analysis for Iron Hach Handbook A 03-0CT-95 S010 Fuel Elements Measurement / Inspection TS 4.2.5 & 5.2.2e A 27-0CT-95 S011 Power Coefficient of Reactivity TS 4.lf A 12-DEC-95 S012 Load Testing of Reactor Hoist 29 CFR 1910.179 A 09-MAY-95 S013 Reactor Water Annalysis for Nitrite Hach Handbook A 03-0CT-95 S014 Reactor Water Analysis for Aluminum Hach Handbook A 03-0CT-95 S015 Reactor Water Analysis for Ammonia Hach Handbook S015 Reactor Water Analysis for Ammonia M 27-JAN-95 Hach Handbook M 27-FEB-95 S015 Reactor Water Analysis for Ammonia Hach Handbook M 31-MAR-95 S015 Reactor Water Analysis for Ammonia Hach Handbook M 21-APR-95 S015 Reactor Water Analysis for Ammonia Hach Handbook M 05-JUN-95 S015 Reactor Water Analysis for Ammonia Hach Handbook S015 Reactor Water Analysis for Amonia M 26-JUN-95 Hach Handbook M 28-JUL-95 S015 Reactor Water Analysis for Ammonia Hach Handbook S015 M 30-AUG-95 Reactor Water Analysis for Ammonia Hach Handbook S015 Reactor Water Analysis for Ammonia M 03-0CT-95 Hach Handbook M 27-0CT-95 S015 Reactor Water Analysis for Ammonia Hach Handbook S015 M 04-DEC-95 Reactor Water Analysis for Ammonia Hach Handbook M 28-DEC-95 S016 Reactor Water Analysis for Chloride Hach Handbook A 03-0CT-95 S017 Reactor Water Analysis for Copper Hach Handbook A 03-0CT-95

ATTACHMENT E Fresh Water Use in Pump House

(

SHD/RSO 4 Aug 95 MEMORANDUM FOR RECORD THROUGH SHD

SUBJECT:

Contractor Use of Fresh Water from Pump House on 3 Aug 95 I was informed that contractors replacing the steam line in the rear of AFRRI were using the fresh water hose bib from the AFRRI Radiological Waste Facility Pump House. Apparently the lock securing the Pump House door had been broken allowing access. LOGF was immediately contacted and installed another lock to secure the door. I also informed MSG DeMilia and Mark Moore of the event. SHD had given previous permission for contractors to use the fresh water line which was contigent upon their notifying us for access. Apparently, at some point in time the contractors accessed the pump house themselves by breaking the lock.

On 4 Aug 95, MSG DeMilia requested I meet with him and Mr. Tom O' Pray (the NNMC ROICC 295-7748). Mr. O' Pray discussed the construction workers concerns about the " radioactive water" they had been bathing in and drinking for the past 2-3 weeks. I told him that although the fresh water line is in our Radioactive Waste Tank Pump House, it is completely isolated from the radioactive material waste lines and would not contain radioactive water.

I further explained that SHD performs weekly surveys in the Pump House which have always indicated there is no radiological contamination present. I then summarized that the entry of the workers into the Pump House and subsequent use of the water from the fresh water line did not expose anyone to radioactivity and therefore was of no radiological safety concern.

/ i Thomasd.O'Brien Radiation Safety Officer Safety and Health Department 37

ASD 500 02 October 1995 MEMORANDUM FOR DEPUTY DIRECTOR FOR ADMINISTRATION

SUBJECT:

Pump House Break-in I recommend that the Pump House Break-in incident be closed after the final recommendation is approved.

a.

AFRRI personnel shall not allow access to this building to non AFRRI personnel unless approved (in writing) by the Radiation Safety Officer.

Corrective actions have already been accomplished. The contractor was notified of the breaking and entering; however, without proof of who actually committed the crime, we would just be " shooting in the dark" in an attempt to collect, damages for

$114.70.

/ '

BRENT A. HAYNIE LCDR (Sel), MSC, USN Security Officer go /disap wu urtis W. Pearson m Col, USAF, MSC Deputy Director for Administration CC:

Head, Safety and Health Department MSG Demilia

-