ML20063F919
| ML20063F919 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 10/31/1981 |
| From: | MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | |
| Shared Package | |
| ML20063F875 | List: |
| References | |
| PROC-811031, NUDOCS 8208310385 | |
| Download: ML20063F919 (283) | |
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STA N DARD OPER ATIN G PROCEDURES l
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O UNIVERSITY of MISSOURI RESEARCH REACTOR FACILITY ,
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O ASSIGNMENT SHEET UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY O STANDARD OPERATING PROCEDURES REVISED OCTOBER, 1981 NUMBER IS ASSIGNED AS FOLLOWS:
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MURR STANDARD OPERATING PROCEDURES Revision No. Date Filed Revision No. Date Filed O
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t TABLE OF CONTENTS O
i SECTION N0. PAGE NO.
I ADMINISTRATIVE OPERATING POLICIES . . . . . . . . . S0P/I-l
-I.1 Purpose . . . . . . . . . . . . . . . . . . . . . . S0P/I-l I.2 Scope . . . . . . . . . . . . . . . . . . . . . . . S0P/I-l I.3 Reactor Operating Parameters. . . . . . . . . . . . SOP /I-l I.4 Admi ni s trati-ve Pol i cies . . . . . . . . . . . . . . S0P/I-2 II REACTOR OPERATING PROCEDURES. . . . . . . . . . . . 50P/II-l II.1 Routine Reactor Operation . . . . . . . . . . . . . SOP /II-l II.2 Fuel Handling Procedure . . . . . . . . . . . . . . SOP /II-8
, II.3 Control Blade Offset Mechanism Removal. . . . . . . SOP /II-ll II.4 Water Chemistry . . . . . . . . . . . . . . . . . . 50P/II-14 III REACTOR CONTROL AND INSTRUMENTATION SYSTEM. . . . . SOP /III-l III.1 Preparation of Reactor Instrumentation for Operation . . . . . . . . . . . . . . . . . . . S0P/III-l III.2 Front Panel Checkout of Source Range 4 Monitor Channel 1 . . . . . . . . . . . . . . . . . S0P/III-2 III.3 Prestartup Check of Intermediate Range Monitor Channels 2 and 3. . . . . . . . . . . . . . SOP /III-2 III.4 Prestartup Check of Wide Range Monitor Channel 4 . . . . . . . . . . . . . . . . . . . . . SOP /III-4 III.5 Check of Power Range Monitor Channels 5 and 6 . . . S0P/III-5 III.6 Procedure for Physically Adjusting NI Detectors at Power. . . . . . . . . . . . . . . . . S0P/III-7 III.7 Check of Process Radiation Monitors . . . . . . . . SOP /III-8 III.8 Area Radiation Monitoring System. . . . . . . . . . S0P/III-9 IV PRIMARY COOLING SYSTEM. . . . . . . . . . . . . . . 50P/IV-1 IV.1 Startup of Reactor Cooling Loop . . ........ SOP /IV-1 IV.2 Shutdown of Primary System. . . . . . . . . . . . . 50P/IV-3 IV.3 Operation of the Antisiphon System. . ....... SOP /IV-4 IV.4 Depressurization of Pressurizer . . . . . . . . . . SOP /IV-5 IV.5 Isolation, Draining, Filling and Normal i Operation of Primary Heat Exchanger Loops . . . . . S0P/IV-5 IV.6 Isolation, Draining, Filling, Normal Operation of Primary Pump Loops . . . . . . . . . . S0P/IV-7 Rev. 10/R1 App'd fra i
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TABLE OF CONTENTS (continued) g SErTION N0. PAGE N0.
V POOL C0OLING SYSTEM . . . . . . . . . . . . . . . . SOP /V-1 V.1 Pool Cooling System Startup . . . . . . . . . . . . 50P/V-1 V.2 Pool System Shutdown Procedure. . . . . . . . . . . SOP /V-2 V.3 Partial Pool Filling Procedures . . . . . . . .. SOP /V-3 V.4 Pool Lowering Procedure . . . . . . . . . . . . . . SOP /V-4 V.5 Pool Cleanup System . . . . ............ 50P/V-5 VI SECONDARY COOLING SYSTEM. . . . . . . . . . . . . . S0P/VI-l VI.1 Startup of the Secondary System . ......... SOP /VI-l VI.2 Procedure for Operation of Bypass Control Valves S-1 and S-2. . . . . . . . . . . . . . . . . SOP /VI-3 VI.3 Operation of Cooling Tower Fans . . . . . . . . . . SOP /VI-4 VI.4 Shutdown of the Secondary System. . . . . . . . . . SOP /VI-6 VI.5 Draining and Filling Secondary System . . . . . . . SOP /VI-6 VI.6 Secondary Water Treatment Procedures. . . . . . . . S0P/VI-8 VII AUXILIARY SYSTEMS . . . . . . . . . . . . . . . . . SOP /VII-l VII.1 Reactor Power Calculator. . . ........... SOP /VII-l h VII.2 Omitted VII.3 Emergency Power System. . . . ........... 50P/VII-2 VII.4 Reactor Demineralizer System. . . . . . . . . . . . S0P/VII-3 VII.5 Skimmer System. . ................. SOP /VII-38 VII.6 Primary / Pool Drain Collection System. ....... SOP /VII-40 VII.7 Primary and Pool Sample Station . . . . . . . . . . 50P/VII-42 VII.8 Liquid Waste Disposal System. . . . . . . . . . . . SOP /VII-43 VII.9 Nitrogen and Valve Operating Air Systems. . . . . . SOP /VII-53 VII.10 Compressed Air System . .............. S0P/VII-55 VII.ll Beamport Water System . . . . . . . . . . . . . . . SOP /VII-58 VII.12 Sulphuric Acid System . .............. SOP /VII 53 VIII REACTOR EXPERIMENTS . . . . . . . . . . . . . . . . SOP /VIII-l VIII.1 General Requirements. . . . . . . . . . . . . . . . S0P/VIII-l VIII.2 In-Pool Irradiations. . . . . . . . . . . . . . . . SOP /VIII-5 VIII.3 Pneumatic Tube (P-tube) System Irradiations . . . . SOP /VIII-3 VIII.4 Beamport Experiments. . . . . . . . . . . . . . . . SOP /VIII 18 VIII.5 Handling and Release of Irradiated Samples. . . . . 50P/VIII 31 Rev. 10/g1 App'd L',,x ii
TABLE OF CONTENTS (continued)
SECTION NO. PAGE N0.
VIII.6 Operating Procedures for the Nuclepore Irradiation Facili ty. . . . . . . . . . . . . . . . SOP /VIII-31 VIII.6.1 New Roll Installation . . . . . . . . . . . . . . . 50P/VIII-33 VIII 6.2 Pre-0perational Startup . . . . . ,........ S0P/VIII-36 VIII.6.3 Start Film Dri ve. . . . . . . . . . . . . . . . . . SOP /VIII-38 VIII.6.4 Irra di ate Fi l m . . . . . . . . . . . . . . . . . . . S0P/VIII-38 VIII.6.5 Termination of Film Irradiation . . . . . . . . . . SOP /VIII-40 VIII.6.6 Remove Shield Box Cover . . . . . . . . . . . . . . SOP /VIII-42 VIII.6.7 Remove Irradiated Roll from Rewind Stand. . . . . . SOP /VIII-43 VIII.6.8 Install New Core Tube on Rewind Stand . . . . . . . SOP /VIII-44 VIII.6.9 Install Shield Box Cover. . . . . . . . . . . . . . SOP /VIII-45 VIII . 6.10 Response to Nuclepore Alarms in MURR Control Room. . . . . . . . . . . . . . . . . . . . SOP /VIII-46 VIII.6.ll Shutdown Film Advancing . . . . . . . . . . . . . . SOP /VIII-50 C EP-I EP-II GENERAL FACILITY EMERGENCIES. . . . . . . . . . . . EP-I-1 REACTOR EMERGENCIES . . . . . . . . . . . . . . . . EP-II-l APPENDIX A: Reactor Startup Checksheet-Full Power Operation Reactor Startup Checksheet-Low Power Natural Convection Reactor Short-Form Pre-Critical Sheet Reactor Shutdown Checksheet Nuclear Data /Frocess Data Startup Nuclear Data Reactor Routine Patrol i Unscheduled Reductions in Power Report Radiation Work Permit Waste Tank Sample Report Secondary Water Activity Analysis Primary System Normal Operating Valve Lineup Checksheet Pool System Valve Lineup Checksheet MURR Pool Water Analysis /MURR Primary Water Analysis DI-200 Series Resin Log Q Do-Not-0perate Tag Rev. 10/81 App'd b iii n
TABLE OF CONTENTS (continued) g SECTION NO. PAGE NO.
APPENDIX B: Estimated Critical Position Procedure APPENDIX C: Toxic Materials Which Are Not Permitted in Containment O
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LIST OF EFFECTIVE PAGES Date Date Page Number Revised Page Number Revised Title Page 10/81 SOP /II-9 10/81 Assignment Sheet 10/81 SOP /II-10 10/81 Revision No. and nate Page 10/81 SOP /II-11 10/81 Table of Contents: SOP /II-12 10/81 i 10/81 SOP /II-13 10/81 ii 10/81 SOP /II-14 10/81 iii 10/81 SOP /II-15 10/81 iv 10/81 SOP /II-16 10/81 List of Effective Pages SOP /II-17 10/81 v 10/81 S0P/II-18 10/81 yi 10/81 vii 10/81 SOP /III-1 10/81 viii 10/81 SOP /III-2 10/81 SOP /III-3 10/81 S0P/III-4 10/81 S0P/III-5 10/81 S0P/III-6 10/81 SOP /I-1 10/81 SOP /III-7 10/81 SOP /I-2 10/81 SOP /III-8 10/81 SOP /I-3 10/81 SOP /III-9 10/81 S0P/I-4 10/81 SOP /III-10 10/81 SOP /I-5 10/81 S0P/III-11 10/81 10/81 S0P/III-12 10/81 O SOP /I-6 SOP /I-7 10/81 10/81 SOP /I-8 10/81 S0P/IV-1 SOP /I-9 10/81 SOP /IV-2 10/81
$0P/I-10 10/81 SOP /IV-3 10/81 SOP /I-11 10/81 S0P/IV-4 10/81 SOP /I-12 10/81 SOP /IV-5 10/81 SOP /I-13 10/81 SOP /IV-6 10/81 50P/I-14 10/81 SOP /IV-7 10/81 SOP /I 15 10/81 SOP /IV-8 10/81 SOP /I-16 10/81 SOP /IV-9 10/81 l SOP /I-17 10/81 SOP /IV-10 10/81 i SOP /I-18 10/81
) SOP /V-1 10/81 SOP /II-1 10/81 SOP /V-2 10/81 SOP /II-2 10/81 SOP /V-3 10/81 SOP /II-3 10/81 SOP /V 4 10/81 S0P/II 4 10/81 $0P/V-5 10/81 j SOP /II-5 10/81 SOP /V-6 10/81 SOP /II-6 10/81 SOP /V-7 10/81
$0P/II-7 10/81 SOP /V-8 10/81
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LIST OF EFFECTIVE PAGES (continued)
Date Date Page Number Revised Page Number Revised h SOP /VI-1 10/81 SOP /VII-36 10/81 SOP /VI-2 10/81 SOP /VII-37 10/81 SOP /VI-3 10/81 SOP /VII-38 10/81 SOP /VI a 10/81 SOP /VII-39 10/81 SOP /VI-5 10/81 SOP /VII 40 10/81 SOP /VI-6 10/81 S0P/VII-41 10/81 SOP /VI-7 10/81 SOP /VII-42 10/81 SOP /VI-8 10/81 SOP /VII 43 10/81 SOP /VI-9 10/81 SOP /VII-44 10/81 SOP /VI-10 10/81 SOP /VII 45 10/81 SOP /VII 46 10/81 SOP /VII-1 10/81 $0P/VII-47 10/81 SOP /VII-2 10/81 SOP /VII 48 10/81 SOP /VII-3 10/81 SOP /VII-49 10/81 SOP /VII-4 10/81 SOP /VII-50 10/81 SOP /VII-5 10/81 SOP /VII-51 10/81
$0P/VII-6 10/81 SOP /VII-52 10/81 SOP /VII-7 10/81 SOP /VII-53 10/81 SOP /VII-8 10/81 SOP /VII-54 10/81 SOP /VII-9 10/81 SOP /VII-55 10/81 SOP /VII-10 10/81 SOP /VII-56 10/81 SOP /VII-11 10/81 SOP /VII-57 10/81 SOP /VII-12 10/81 SOP /VII-58 10/81 50P/VII-13 SOP /VII-14 10/81 10/81 50P/VII-59 SOP /VII-60 10/81 10/81 SOP /VII-15 10/81 SOP /VII-16 10/81 SOP /VIII-1 10/81 SOP /VII-17 06/80 SOP /VIII-2 10/81 SOP /VII-18 06/80 SOP /VIII-3 10/81 SOP /VII-19 10/81 S0P/VIII-4 10/81 SOP /VII-20 10/81 SOP /VIII-5 10/81 SOP /VII-21 10/81 SOP /VIII-6 10/81 SOP /VII-22 10/81 SOP /VIII-7 10/81 SOP /VII-23 10/81 SOP /VIII-8 10/81 SOP /VII-24 10/81 SOP /VIII-9 10/81 SOP /VII-25 10/81 SOP /VIII-10 10/81 SOP /VII-26 10/81 SOP /VIII-11 10/81 SOP /VII-27 10/81 SOP /VIII-12 10/81
$0P/VII-28 10/81 SOP /VIII-13 10/81 SOP /VII-29 10/81 SOP /VIII-14 10/81 SOP /VII-30 10/81 SOP /VIII-15 10/81 SOP /VII-31 10/81 SOP /VIII-16 10/81
$0P/VII-32 10/91 SOP /ViII-17 10/81 SOP /VII-33 10/81 SOP /VIII-18 10/81 50P/VII-34 10/91 50P/VIII-19 10/81 SOP /VII-35 10/81 Sno/VIII-20 10/91 O
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LIST g EFFECTIVE PAGES (continued)
Date Date O ee9e nem8er aev4 sed ee9e nemuer aev4 sed SOP /VIII-21 10/81 EP-I-10 10/81 SOP /VIII-22 06/80 EP-I-11 10/81 SOP /VIII-23 10/81 EP-I-12 10/81 SOP /VIII-24 06/80 EP-I-13 10/81 S0P/VIII-25 10/81 EP-I-14 10/81 SOP /VIII-26 10/81 EP-I-15 10/81 S0P/VIII-27 10/81 EP-I-16 05/80 S0P/VIII-28 10/81 EP-I-17 04/75 SOP /VIII-29 10/81 EP-I-18 04/75 SOP /VIII-30 06/80 SOP /VIII-31 10/81 EP-II-1 10/81 SOP /VIII-32 06/80 EP-II-2 10/81 SOP /VIII-33 10/81 EP-II-3 10/81 SOP /VIII-34 10/31 EP-II-4 10/81 S0P/VIII-35 10/81 EP-II-5 10/81 SOP /VIII-36 10/81 EP-II-6 10/81 SOP /VIII-37 10/81 EP-II-7 10/81 SOP /VIII-38 10/81 EP-II-8 10/81 S0P/VIII-39 10/81 EP-II-9 -
10/81 SOP /VIII-40 10/81 EP-II-10 10/81 S0P/VIII-41 10/81 EP-II-11 10/81 SOP /VIII-42 10/81 EP-II-12 10/81 SOP /VIII-43 10/81 EP-II-13 10/81 O soe/viti-44 SOP /VIII-45 1o/81 10/81 ee-it-14 EP-II-15 to/81 10/81 S0r/VIII-46 10/81 EP-II-16 10/81 SOP /VIII-47 10/81 SOP /VIII-48 10/81 Appendix A SOP /VIII-49 10/81 SOP /A-la - 10/81 SOP /VIII-50 '
10/81 SOP /A-lb 10/81 SOP /VIII-51 10/81 SOP /A-2a 08/76 SOP /VIII-52 10/81 S0P/A-2b 08/76 SOP /A-3a 08/72 Emergency Procedures SOP /A-3b 06/80
! Index: S0P/A-4a 01/81
! i 10/81 SOP /A-4b 04/81 11 10/81 SOP /A-Sa 05/74 S0P/A-Sb 04/79 EP-I-1 10/81 SOP /A-Sc 04/79 EP-I-2 05/80 SOP /A-5d 06/80 EP-I-3 10/81 SOP /A-6a 08/72 EP-I-4 10/81 S0P/A-6b 07/73 EP-I-5 10/81 SOP /A-7a 09/81 EP-I-6 10/81 S0P/A-7b 06/80 EP-I-7 10/81 SOP /A-8a 05/81 EP-1-8 10/81 SOP /A-8b 07/80 i EP-I-9 10/81 S0P/A-9a 08/72 O
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LIST OF_ EFFECTIVE PAGES (continued)
Page Number Date Revised Page Number Date Revised 50P/A-9b 06/80 SOP /A-10a 01/76 SOP /A-10b 06/80 SOP /A-11a 05/81 SOP /A-11b 06/80 SOP /A-11c 05/74 SOP /A-11d 05/74 SOP /A-12a 03/80 S0P/A-12b 06/80 SOP /A-12c 05/74 S0P/A-12d 05/74 SOP /A-13a 09/78 SOP /A-13b 06/80 SOP /A-14a 08/72 SOP /A-14b 06/80 SOP /A-15a 08/72 S0P/A-15b 06/80 Appendix B-SOP /B-a 10/71 SOP /B-b 10/71 SOP /B-c 10/71 SOP /B-d 10/71 g S0P/B-e 10/71 SOP /B-f 10/71 Appendix C-SOP /C-a 04/75 S0P/C-b 11/77 l
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. Section I .
ADMINISTRATIVE OPERATING POLICIES I.1 Purpose To establish methods of operation for the reactor and associated systems which assure safety and performance within the technical specifications set forth for the University of Missouri Research Reactor.
I.2 Scope These procedures are not to be construed to constitute a part of the technical specifications. In event of any discrepancy between the information given herein and the technical specifications, limits set forth in the technical specifications apply.
O to these procedures and to any other special operating or Changes maintenance procedures which have safety significance must be reviewed by the Reactor Procedures Review Subcommittee (RPRS).
Changes which are editorial or have no safety significance may be made by the Reactor Manager, Reactor Operations Engineer or the ]
Shift Supervisor but must be documented and subsequently reviewed ]
by the RPRS.
I.3 Reactor Operating Parameters The reactor will be operated under conditions and limitations as set forth in the technical specifications, Appendix A to License
! R-103.
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I.4 Adr'nistrative Policies O
I.4.1 Standing Orders New procedures prior to becoming part of these Standard Operating Procedures, procedures to be in effect for a short period, and special instructions relating to operation of the reactor, will be issued as Standing Orders. All effective Standing Orders, as well as a listing of current orders, will be maintained in a log in the reactor control room. Standing Orders that are no longer applicable or that are incorporated into the Standard Operating Procedures will be cancelled and removed from the log. All Standing Orders will be approved by signature of the Reactor Manager or his authorized delegate. ]
I.4.2 General Operating Policies ]
A. Safety Safe operation of the reactor will take precedence over other considerations. h B. Supervisory Authority The importance of one coordinator for all reactor activities is recognized for safety and effective control of operation.
The Reactor Manager will have complete operating authority ]
over all activities related to reactor operation.
C. Operating Crews The minimum number of reactor operators for reactor operation will be two licensed persons. One of these will be licensed as a senior operator. There will be one licensed operator in the control room at all times whenever the reactor is not considered secured, as defined in Part 1.1 of the Technical Specifications. Exception: It is not necessary to have the control room manned during refueling. These activities may be directed from the reactor bridge.
D. Console Log A log will be maintained in the control room by the reactor operator providing a detailed diary of reactor operation. 9 Rev. 10/81 App'd,' 6 ~' S0P/I-2
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E. Changing Reactor Reactivity Operations affecting changes in core reactivity, other than normal steady state power control, i.e. refueling, startup, etc., will be directly supervised by a senior operator.
F. Malfunction of Reactor Systems While at Power Any malfunction or abnormal operation of a control or reactor system should be immediately brought to the attention of the Shift Supervisor. The decision as to whether to continue operation of the reactor depends upon the severity of the mal function. It remains with the Shift Supervisor as to what immediate action need be taken. However, the duty operator is authorized, in the absence of the Shift Supervisor from the control room, to place the reactor in a safe shutdown mode if he deems it necessary. It is important that the reactor systems, while the reactor is critical, not be experimented with, or rea.ctor control systems tested, unless permission to ]
do so is explicitly granted by either the Reactor Manager or ]
his designated representative. ]
Q G. Reactor Operating Parameters The reactor shall be operated in strict accordance with the Reactor License R-103 and the operating limits in Tables III and IV.
I.4.3 Startup I
A. Startup Following a Scram lhe reactor will not be started up following a scram until the cause of the scram has been determined and safe corrective actica taken. If, after thorough investigation, the cause of the unscheduled reduction in power cannot be determined and all systems are found to be normal, the reactor may be l
! started up with the approval of the Reactor Manager or his authorized delegate.
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B. Occupancy of the Reactor During reactor startup or transient operation, occupancy of the control room and containment building will be limited to the reactor staff, experimenters and those observers as approved by the Reactor Manager or duty shift supervisor.
C. Operator Change During Transients Control of the reactor will not be transferred from one operator to another during power transient operations.
D. Control Blade Operation
- 1. The control blades shall not be moved in gang control after the reactor is critical except to reduce power (II.l.3), shutdown the reactor, or as part of the automatic shimming operation.
- 2. The ganged control blades, or any single control blade, will not be withdrawn simultaneously with the regulating blade. ]
E. Hot Startup A startup within two hours of any shutdown, in which re-start capability is in doubt, shall be called a hot startup. A ]
hot startup shall only be made by the Shift Supervisor, senior ]
reactor operator, or a licensed reactor operator under the ]
direct and close supervision of a senior reactor operator. ]
The approach to critical may be made entirely in gang control ]
of the control rod drives. ]
F. Startup Checksheet
- 1. A Startup Checksheet will be completed before nuclear operation af the reactor. Separate Startup Checksheets will be used for low and full power operation. Operation above 50 KW will require completion of the full power checksheet. Operation at or below 50 KW with forced convection cooling will also require completion of the Full Power Checksheet. The completed checksheets will be approved in writing by a senior reactor operator before withdrawing the control rods for the startup. A short 9
Rev. 10/81 App'd k SOP /I-4
form Pre-startup Checksheet is provided and may be used for a pre-startup reactor system checkout if the following three conditions are satisfied:
i a. The systems and instrumentation other than those referred to in the short form Pre-startup Checksheet have been in continuous operation since the completion of the last comprehensive Startup Checksheet and the routine systems check has revealed no abnormalities.
- b. A Full Power or Low Power Pre-startup Checksheet has been completed within eight hours prior to the time a short form checksheet is to be used, or the reactor has been operating at some time within the previous eight hours, and a Shutdown Checksheet has not been completed during this period.
- c. No anomaly with regard to any systems not covered by the short form checksheet has occurred since completion of the last comprehensive Startup Checksheet.
- 2. A Startup Checksheet is not required for a return to power within a period of two hours following a shutdown from
- full power, providing the status of any system covered by the Full Power or short form Pre-startup Checksheets has not changed since the last power operation, or if the Shift Supervisor determines that no system has been affected by the cause of the shutdown.
G. Estimated Critical Position (ECP)
A procedure for determining estimated critical position has been included in the Appendix of the S0P and shall be used with the following provisions:
1 1. The Shift Supervisor shall assure that he has a reliable i
estimated critical position, established by calculation or experience, and record it on the startup checksheet prior to each startup.
! 2. The estimated critical position shall be either furnished by or approved by the Reactor Physicist on any startup O foiiewin9 e shotdown in wnich fuei hendiin9 nas teken Rev. 10/81 App'd T- SOP /I-5
place. The limits as specified in Table II shall apply to ECP's furnished in this event. h
- 3. The Shift Supervisor may call upon the Reactor Physicist at any time to establish a predicted critical position.
The responsibility of assuring that operations has a reliable ECP shall rest with the Reactor Physicist.
- 4. The use of the I1URR Estimated Critical Position Procedure shall be at the discretion of the Shift Supervisor, except if the estimate of ECP based upon past history is off by more than that shown in Table I, the control rods will be driven in and the ECP calculated.
- 5. If the reactor is not critical at ECP as calculated by the Reactor Physicist or by the procedure (plus the values shown in Table I or after fuel handling as in Table II),
the reactor will be shutdown, and if not present, the Reactor Physicist notified. The reactor is not to be restarted without approval of the Reactor Manager or ]
Reactor Operations Engineer unless the discrepancy between ]
ECP and actual critical position has been unquestionably resolved.
Table I ECP Acceptable Limits 11"-16" 0.75" 16"-22" : 1.25" 22"-26" 2.50" Table II ECP Acceptable Limits 11"-16" 0.40" 16"-22" : 0.70" 22"-26" 1.25" g Rev. In/R1 App'd & SOP /I-6
H. Instrumentation Minimum nuclear instrumentation for startups shall be one source channel, two intermediate range channels each with period trips, two power channels each with flux trips, and one wide range channel with high flux trip.
I. Use of the Public Address System ] .
Immediately prior to actual movement of the control rods, an ]
announcement will be made over the public address system that ]
a reactor startup has been commenced. A second announcement ]
will be made when the desired power level is obtained. If ]
during the startup the determination is made that power will ]
be held constant at any level for a period of greater than ]
five minutes an additional announcement will be made to inform ]
building personnel. ]
J. Health Physics Monitoring of Reactor ]
Experiments During a Reactor Startup ]
When a change is made to a beamport or other reactor ]
experiment which could lead to significant alterations in area ]
radiation levels as reactor power is increased, a Health ]
Physics Technician will be assigned to continuously monitor ]
that experiment throughout the startup. Direct communications ]
will be maintained between the Control Room and the Health ]
Physics Technician. The Control Room will inform the Health ]
Physics Technician at the following power levels: ]
- 1. During a Normal Reactor Startup ]
- a. When the reactor reaches criticality. ]
- b. When reactor power reaches 50 KWs. ]
in Mode II). 3
in Mode II). ]
- 2. During a Reactor Hot Startup ]
- a. When the reactor reaches criticality. ]
O in Mode It). ]
- c. When reactor power reaches 10 MWs. ]
Rev. 10/81 App'd,he- SOP /I-7 I
If direct communications are lost or if one of the above ]
reports is not acknowledged, reactor power will be maintained ] h at a steady level until the problem is corrected. The Health ]
Physics Technician will make his final report to the Control ]
Room after a complete survey is conducted at the desired power ]
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I.4.4 Normal Operation A. Normal power level will be 9.90 to 10.00 MW as indicated by ]
the total power meter. ]
B. The control room shall be occupied by at least one licensed operator during steady state operation of the reactor and a second licensed operator will be in the Facility Building and at a location where communication with the control room can be maintained.
C. Prior to assuming control of the reactor, the oncoming oper-ator will read the control room log book and shall be briefed on current operation, g D. During shift operation, the Shift Supervisor for the new shift will review the log book and be briefed on current operations by the crew he is to relieve. Upon completion of the log book review, the Shift Supervisor will note the same in the log book.
E. A complete set of Nuclear data will be taken once an hour ]
during steady state operation. ]
F. A complete set of Process data will be taken every two (2) ]
nours during steady state operation.
G. During routine operation, a routine patrol of the facility will be made every four (4) hours according to an approved routine patrol checksheet.
H. Normally, the calorimetric determination of the power level can be read directly from the digital readout and entered in the Nuclear Process Data. The cause of any difference between the primary and secondary calorimetric calculations which exceeds 5% (0.5 MW) during steady state full power $
Rev. 10/81 App'd /f SOP /I-8
operation should be determined. The primary power calculation will normally be used to estahlish the 10 MW power level, however, the nominal steady state power level shall not exceed 10 MW. The reactor shall not be operated at a power level which causes the steady state secondary calorimetric to exceed 10.5 MW unless it is confirmed that the secondary calorimetric is in error or out of commission.
The primary system DI flow bypasses the core and yet it flows through the primary flow orifice. Therefore, the primary flow as read on the recorder should be decreased by the primary DI flow before the value is used in calculating the power level.
The recorder values should be logged on the log sheets without correction.
I. Steady state reactor powers of 1 MW and greater will be determined by the method stated above. If a discrepancy of greater than 5% occurs between the power indicated by Channels 4, 5, or 6 and the heat balance power, the appropriate channel p should be adjusted. Channels 4, 5, and 6 are adjusted by V proper positioning of the drawer amplifier feedback poten-tiometers. After adjustment of a potentiometer, the change in indicated power shall be logged in the console log and the new pot setting logged on the Startup Nuclear Data Sheet.
The Shift Supervisor's approval must be obtained before adjustment of any Power Range Monitor. Adjustments shall only be made after a determination of the power level by heat balance.
J. Minimum nuclear instrumentation for normal operation shall be two (2) intermediate range channels with period trip, two (2) power range channels each with high flux trips and one (1)
! wide range channel with high flux trip.
l K. During reactor operation the control room shall be occupied I only by persons authorized by the Reactor Manager or Shift
! Supervisor.
i Rev. 10/81 App'd b .__ 50P/I-9
I.4.5 Shutdown g
A. Shutdown operations will be accomplished under conditions designed to assure safety of the reactor and personnel .
B. Shutdown of the reactor will be in accordance with approved ]
procedures. ]
C. Conditions causing automatic shutdown of the reactor will be investigated as to cause, and corrective action taken prior to restarting the reactor.
D. Unscheduled rhutdown sheets will be filled out for all unplanned rod run-ins and scrams that occurred while at power or after all drive full in lights have cleared when pulling ]
rods to take the reactor critical. ]
E. Entry into controlled access high radiation areas following reactor shutdown shall t'e preceded by a radiation survey.
F. The Shift Supervisor shall have a shutdown checksheet ]
performed if the control room will be unattended for an ]
extended period cf time. ]
G. An entry in the console log book that the reactor has been h secured after an operating or testing period shall be made by the reactor operator assigned to the console.
I.4.6 Experiments A. The Reactor Manager tvfil have opvating authority ever all experiments performed within the reactor containnent or wnich
~
may affr:ct reactor operations.
B. All experimental programs will be evaluated by the reactor operating organization and by the Foactor Manager.
C. Experimenters are required to inform the reactor control room of any activity which may affect reactor operation.
D. All experimanters wili be required to complete an indoctrin-atica training course on the relationrnip between his experitent and reactor operations, emergency procedures, arid radiation safety.
O Rev. 10/a App'd h- SOP /I-10
E. All reactor users shall complete a Reactor Utilization Request form. This request must be reviewed and approved by the Reactor Manager. ]
F. If an experiment appears to involve new or unevaluated hazards, a review of the proposed experiment by the Reactor Advisory Committee may be requested by the Reactor Manager. ]
G. The Reactor Manager may require, as deemed necessary for safe operation, that experimental data or operating instructions be on file with the reactor operations organization.
H. All changes in beamport experiments, and intentional flooding or draining of the beam tubes to be performed with the reactor at power will be done only after written approval is initially obtained from the Reactor Manager and after a ]
procedure for so doing has been established. Whenever ]
practical, beamports shall be flooded or drained only after the reactor has been shutdown for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I. The insertion and removal of experiments in the center test hole position will be done with the reactor shutdown.
I.4.7 Radiation Work Permit A Radiation Work Permit will be completed by the Job Supervisor ]
and Health Physics prior to conducting any work which in the opinion of the Shift Supervisor involves significant potential for exposure of personnel to radiation or the spreading or release of airborne or surface contamination.
A copy of this form is included in the Appendix of the SOP.
The form is used as follows:
A. The top portion of the RWP and the tear-off strip at the bottom (with the exception of the number) will be prepared by the Job Supervisor. The time and date spaces should contain the supervisor's estimate of the duration of the job (0800-2400 September 2, 1970; 0800-0900 each Friday, 0000-2400 September 10-12,1970, etc .) . The supervisor should be as specific as possible in describing the job. This will aid Health Physics in determining the protective measures necessary.
Rev. 10/81 App'd S0P/I-ll
,/-
B. After the supervisor has completed the top portion of the RWP, he will sign and date the form and deliver it to Health Physics, who will number the RWP, conduct the necessary surveys and determine the protective measures necessary for the job. Health Physics will then complete the remainder of the RWP indicating the survey results and the protective measures required. He will then sign and date the RWP and return it to the supervisor.
C. The supervisor will post the approved RWP at the job site for ready reference by the personnel doing the work. He will remove the tear-off strip and hang it up on the hook in the control room.
D. When the job has bee completed and the job site has been cleaned up and decontaminated, the supervisor will sign off the RWP and deliver it to Health Physics. After Health Physics has verified that the job site is clean and decon-taminated, he will sign off the RWP and maintain it in his RWP file. The supervisor will remove and discard the tear-off strip from the hook in the control room.
I.4.8 Radiation Safety The Shift Supervisor is directly responsible for the overall safety of personnel on his shift and indirectly responsible for all personnel whose safety may be affected by activities conducted under his supervision. Radiation safety is a very important part of this responsibility. It should not be construed that surveys, monitoring, or other measurements to check for contamination or radiation are to be made by operations personnel, but rather that the Shift Supervisor is responsible to insure that through coordination with the Health Physics personnel, adequate protection is provided for evolutions conducted during his shift.
O Rev. 10/81 App'd E- S0P/I-12 E
l.
I.4.9 Physical Protection of Special Nuclear Materials In accordance with 10 CFR 73, special requirements must be met in safeguarding Special Nuclear Material. The safeguards provided and the procedures applicable to maintaining the security of Special Nuclear Materials are contained in the facility Security Plan and Security Procedures.
I.4.10 Equipment Tag Out Procedure I.4.10.1 Purpose The purpose of tagging equipment is to prevent damage to equipment or personnel or to provide supplemental information concerning a special operating procedure.
I.4.10.2 Tagging Equipment A. Three tags will U used. See Appendix A for a sketch of the danger tags. The tag color designates its purpose as follows:
Red - Danger to personnel Yellow - Danger to equipment White - Supplemental information concerning an operating procedure B. The Shift Supervisor's approval must be obtained before equipment is tagged.
C. All tags and the tag log must be filled out and tags attached to equipment by a licensed operator. The tag log must contain a description of the equipment tagged, reas6n for tagging, date, and initials of operator initiating the tag.
I.4.10.3 Removing Tags A. The Shift Supervisor's approval must be obtained before any tags are removed.
B. When the tags are removed, the date of removal and the initials of the individual clearing the tags shall be entered on the tag log.
Rev. 10/81 App'd Jc SOP /I-13
O Table III Normal Reactor Operating Ranges Parameters Normal Operating Range Units
- 3. Primary Coolant Flow, 5 MW Operation 1900 50 gpm Primary Coolant Flow,10 MW Operation 3800 100 gpm
- 4. Reactor Outlet Coolant Temperature 136 F ]
- 5. Reactor Inlet Coolant Temperature 120 F ]
- 6. Pressurizer Pressure 67 3 psig ] h
- 7. Pressurizer Level CENTERLINE + 4 to - 8 inches ]
- 8. Pool Coolant Flow, 5 MW Operation 600 : 100 gpm ]
Pool Coolant Flow,10 MW Operation 1200 100 gpm ]
- 9. Pool Outlet Temperature (llot Leg) 105 F ]
- 10. Pool Level 29' - 7" : 3" feet-inches]
- 11. Resistivity, Outlet of DI-300 >500K ohms-cm ]
- 12. 5-1 Temperature Deinand Set 120 F ]
- 13. S-2 Temperature Demand Set 100 F ]
l O
1 Rev. 10/81 App'd r SOP /I-14 l
i
O O O Table IV Values of Trip Settings for Alarm, Run-In and Scram Conditions Scram Run-In Alarm Units
- 1. Short Period 9 11 --- sec ]
- 2. Low Count Rate --- --- <1.0 cps ]
- 3. liigh Power 120 115 --- % full power ]
- 4. RC Inlet Temp 152 --- 148 F ]
- 5. RC Outlet Temp 173 --- 165 F ]
- 6. RC System Low Flow 1675 --- 1750 gpm ]
5 MW Operation RC System Low Flow 21675 --- 21750 gpm ]
10 MW Operation
- 7. Heat Exchanger Low 41675 --- --- gpm ]
- 8. Rx System Low Press 361 --- --- psig ]
Switch PS 944A/B
I' Core Low AP,10 MW 43300 --- --- gpm ]
- 10. Low Pressurizer Level 14 below {
10-13 below {
inch ]
11 . Ili Pressurizer Wtr --- ---
12-15above{ inch ]
Level 2For 10 MW operation, Alarm and Scram Received from Either Loop 3 3 Pressurizer Pressure with normal system flow j
4AP corresponding to this flow value Rev. In/ajApp'd.dx S0P/I-15
(/
Table IV (continued)
Scram Run-In Alarm Units
- 12. Low Pressurizer Press 61 --- 64 psig ]
- 13. Ili Pressurizer Press 79 --- 76 psig ]
- 14. Pool Low Flow, 5 f1W 440 --- 480 gpm ]
Pool Low Flow,10 MW 2440 --- 2480 gpm ]
- 15. Pool Loop fli Temp --- ---
115 F ]
- 16. Low Pri Demin Flow --- --- <42.5 gpm ]
- 17. Low Pool Demin Flow --- --- <42.5 gpm
- 18. Bldg Air Plenum lli 1.0 --- ---
mr/hr ]
Ac tivi ty
- 19. Reactor Bridge 50.0 --- ---
mr/hr ]
- 20. RC lli Conductivi ty --- --- 2.0 pmhos ]
- 21. PC lli Conductivity --- ---
2.0 pmhos ]
psi ]
psi ]
Lo Refl AP,10 f1W 2.75 --- --- psi ]
- 24. Low N2 System Press --- --- 115 psig ]
- 25. Low Seal Trench Level --- --- 5.1 feet ]
- 26. Ili/Lo Level in T-300 --- ---
6200/2500 gal ]
- 27. Ili/Lo Level in T-301 --- ---
6000/<100 gal ]
Rev. 10/81 App'd, C;~ SOP /I-16 j
4 O O O
O O O Table IV (continued)
Scram Run-In Alarm Units
- 28. Fission Product --- --- 40K cps ]
Monitor 111 Activity
- 29. Off-Gas 111 Activity --- --- Ssee below cpm ]
- 30. Secondary Coolant --- --- 10 cps ]
Ili Activity 31 . Anti-Siphon Line Hi --- >6 --- inches ]
Level (above v1vs)
- 32. Pool Level Low >23' 29'-1" --- inches
- 33. Reg Blade --- <10% or <20% or >60% % withdrawn ]
bottomed
- 34. Vent Tank Low Level --- 9 --- inches ]
(below {}
- 35. Secondary Coolant --- --- <1800 gpm ]
Low Flow
- 36. Ch 4, 5 or 6 Downscale --- - . - <5 % full-scale ]
- 37. Valve 546 A or B --- --- off closed
- 38. Valve 509 off open --- ---
- 39. Valve 547 --- --- off open
- 40. Valves 507 A/B off open --- closed with ]
P501 on
- 41. Valve S-1 --- --- 90% open or ---
90% shut 1
SThis setpoint is determined by the semiannual calibration Rev. 10/dl App'd Cr. s S0P/I-17 y -
Table IV (continued)
Scram Run-In Alarm Uni ts
- 42. fluclear Instrument 6 inoperative --- anomaly ---
]
- 43. Anti-Siphon System --- --- 31 psig ]
Pressure Low Anti-Siphon System --- --- 44 psig Pressure liigh
- 44. Thermal Column Door --- --- open ---
- 45. Truck Entry --- door seal ---
deflated
- 46. Evacuation or manual / auto ---
manual / auto ---
Isolation
- 47. Rx System Low 3/61 --- --- psig ]
Pressure (PT-943) 6Any channel will scram on NI Inoperative except SRM ]
Rev. 10/81 App'd S0P/I-18 M[s .
8 O O
\
O Section II REACTOR OPERATING PROCEDURES II.1 Routine Reactor Operation 11.1.1 Procedure for Reactor Startup For full power, closed pressure vessel operation, the reactor will be brought to its scheduled operating power level according to the procedure outlined below.
A. Take a complete set of full power process data.
B. Obtain from the Shift Supervisor an estimate of the critical banked control blade position.
C. Take a complete set of nuclear data on the Startup Nuclear Data Sheet.
D. Complete the applicable startup checksheet required by Section I (I.4.3.F).
E. Obtain from the Shift Supervisor permission to commence a reactor startup.
F. Announce via the public address system that a normal reactor ]
startup has been commenced. ]
G. Withdraw the four control blades in gang, stopping to take a set of startup nuclear data at five-inch increments. Indicate in the console log book that startup has commenced.
H. When the blades have reached a position within 2 inches of the estimated critical position, discontinue pulling in gang and take a set of startup nuclear data.
I. Continue the startup, withdrawing only one blade at a time ]
until the reactor power level is increasing on g less than ]
a 30-second period. ]
J. At the point where the reactor is indeed critical and on a positive period, a console log entry shall be made stating that fact.
Rev. 10/81 App'd b: S0P/II-l
=<
K. Bring the reactor critical at a steady state power level of approximately 50 KW unless a lower power level is desired for tests, calibration runs, etc. The lowest steady state power level reached and any ensuing steady state power will be logged on the Startup Nuclear Data Sheet for a record of reactor operating time.
L. Withdraw the fission chamber to full out.
M. Verify that all nuclear instrumentation is responding normally.]
N. Take a complete set of nuclear data on the Startup Nuclear Data Sheet. Indicate on this sheet the critical control and reg blade positions and the primary and pool temperatures.
O. Continue the startup, withdrawing only one blade at a time until the reactor power is increasing at no_ less than a 30 second period. At power levels greater than 100 KW, maintain the control blades such that the maximum difference in posi-tion between any two blades always remains less than 1 inch.
P. As the reactor power level approaches 1 MW, increase the period until a stable period remains that is no_ less than 100 seconds for all power increases greater than 1 MW.
g Q. Bring the reactor critical at a steady state power level of 2.5 MW if in 5 MW mode of operation or 5.0 MW if in 10 MW mode of operation. At this power level:
- 1. Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read out directly from the digital calorimetric meter. Note the actual power level in the operations console log book.
In the case of the calorimetric meter being out of commission during a startup, the power level may be determined by manual calculation.
- 2. Note the time of arrival and departure from this power level on the Nuclear Startup Data Sheet.
R. Continue the reactor power increase by withdrawing only one control blade at a time, maintaining the reactor period at
_no less than 100 seconds.
]
O Rev. 10/81 App'd V SOP /II-2
S. As the scheduled power level is reached, adjust the control blades until the reactor is critical at the desired steady state power in either the manual or automatic control mode.
T. Switch IRM recorder from fast to slow speed and secure the SRM ]
recorder and scaler. ]
U. After the temperatures stabilize, take a complete set of ]
nuclear and process data. ]
V. Announce to experimenters the reactor power level, schedule ]
and note arrival in the log book. ]
I1.1.2 Procedure for Hot Startup ]
A hot startup shall only be made by a senior reactor operator, or ]
a licensed reactor operator under the direct supervision of a ]
senior reactor operator. Gang control of the rod drives may be ]
used for the entire approach to critical and to override Xenon ]
buildup if required. ]
A. Take a set of startup nuclear data.
O 8- obte4a ea estimate or tbe criticei beakea coatro1 biede position from the Shift Supervisor.
C. Obtain permission from the Shift Supervisor to commence a reactor startup.
D. Announce via the public address system that a hot reactor ]
startup has been commenced. ]
E. Withdraw the four (4) control blades in gang, .stopp.ing to ,
take a set of startup nuclear data at five inch increments. - -
Insure the stable period is no less than 30 seconds.
F. At 50 KW or when channel 1 indication is greater than 10+5, ]
withdraw the fission chamber to full out position. ]
G. Continue the startup, insuring that the maximum difference in position between any two (2) blades always remains less than one (1) inch.
l H. Stabilize reactor power at a power level of 2.5 MW in Mode II I
or 5 MW in Mode I. At this power level:
- 1. Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read Rev. 10/81 App'd d- S0P/II-3 7
out directly from the digital calorimetric meter. Note the actual power level and the time of arrival in the console log book.
- 2. Note the critical rod heights, power level, primary and pool temperatures, and arrival / departure times on the Startup Nuclear Data Sheet.
I. Continue the reactor startup by withdrawing only one control ]
blade at a time, maintaining the reactor period at n_o,o less ]
than 100 seconds. ]
J. As the scheduled power level is reached, stabilize power in ]
either manual or automatic control and couplete the following: ]
recorder and scaler. ]
- 2. Note the time of arrival in the console log book and in ]
the Startup Nuclear Data Sheet.' ]
- 3. Take a complete se. of nuclear and process data as soon ]
as the temperatures stabilize enough to get a representa- ]
tive AT on the primary and pool . ]
- 4. Announce to experimenters the reactor power level. ]
11.1.3 Assuming Automatic Reactor Control A. Conditions to be met prior to " auto" operation.
Prior to assuming automatic control for reactor operation, the following conditions must be met:
- 1. The period as indicated by both IRM-2 and IRM-3 must indicate not less than 35 seconds.
- 2. The WRM selector switch must be in the 5 KW red scale position or above.
- 3. The power trace pointer (black) on the WRM recorder must be reading greater than the auto control prohibits set l point (red).
l 4. The reg blade position must be greater than 60% with-drawn, such that 60% annunciator alarm is energized.
B. Procedure To place the reactor into the automatic control mode: h l
Rev. 10/81 App'd b SOP /II-4
- 1. Set the low level trip (red pointer) in the wide range recorder so that the auto-control prohibit trip is at 75%
of the desired operating power.
- 2. Using the power schedule switch (1S9), bring the setpoint indicator to approximately 3% below 6 desired power level of >1000 watts as would be indicated on the black scale of the wide range monitor.
- 3. Bring the reactor to the desired power level on a period ]
>35 seconds, utilizing the reg blade in such a manner as ]
to insure that it is greater than 60% withdrawn when the ]
desired power level is reached. ]
Note: Caution and good judgement should be exercised on the part of the Reactor Operator when preparing to assume the automatic control mode in that prior operating experience has revealed discrepancies in readings between the WRM-4 power indication and the demand power for auto control as set by the power schedule switch. The Operator is to be cautioned that the indicated demand power displayed by the power set meter may lead the WRM-4 power level reading by as much as 5%. This difference is particularly predominant in the lower percentile range on the meter.
- 4. Depress the blue " auto" control switch S-2 located on the operator console. The " reg rod out of auto" alarm will reset on the annunciator. The reg blade will attempt to reduce the actual reactor power to the level indicated on the power level set meter, by automatically driving down-ward into the core. This initial action on the part of the reg blade is to be observed and verified by the Reactor Operator. Eventually, the reg blade will stabilize at its critical position, and bring the reading on the wide range recorder into agreement with that as indicated by the power level set meter. At this point, the reactor is in automatic control mode.
Note: Since the auto control mode was attained at a reactor O power =3% less then the eesired levei, the difference can now be made up with a slow manipulation of the power schedule switch.
Rev. 10/81 App'd /[ m S0P/II-5 M _ _ _
- 5. While closely observing both the reg blade position and ]
the wide range monitor Channel 4 response, raise the power ] h level set until the reactor power stabilizes at a desired ]
level as indicated by the wide range monitor instrumenta- ]
tion. ]
To Discontinue Automatic Operation Depress the blue manual switch (S-1). Control will then revert to the manual mode and will be indicated by both the " manual" switch 5-1 being lighted and the annunciator alarm " reg rod out of auto" being actuated.
Manual Override By actuating the regulating rod control switch (155), the Operator may override the automatic control system. Operation will there-after be in the manual mode unless the operator deliberately returns the system to the automatic control mode as outlined above.
Note: Either a reactor scram or a rod run-in condition will auto- h matically return control to the manual mode.
11.1.4 Procedure for Changing Power Levels For power level maneuvers at powers in excess of 1 MW:
A. Place IRM recorder in fast speed.
B. Place the reactor in the manual control mode by depressing the blue manual switch (S-1).
C. Take a complete set of nuclear data.
- 1. To increase the reactor power, each control blade or the reg blade may be withdrawn individually until the reactor power level is increasing on no less than a 100 second period.
- 2. To decrease the reactor power, all four control blades may be inserted in gang to reduce power as rapidly as required. However, to recover reactor criticality at h
Rev. 10/81 App'd E / - SOP /II-6
the desired power level, each control blade must be withdrawn individually if its position is within 2.00" of its previous critical position. Maintain all blade posi-tions such that the difference in position between any two blades is not greater than 1.00".
D. Recover criticality at the new power level.
E. Replace the reactor control in the automatic mode, if desired.
F. Take a complete set of nuclear data.
G. Switch the IRM recorder from fast to slow speed.
H. Record the power change in the log book and on the Startup Nuclear Data Sheet as required.
For power level maneuvers at power less than 1 MW:
A. For increasing or decreasing power, the same procedure as outlined in parts A-H above apply, with the exception that power level increases up to 1 MW may be made on periods n_o o less than 30 seconds.
11.1.5 Procedure for Control Blade Shimming -
A. The Automatic Shimmin'; Unit can be considered operational and will shim the regulating blade out should it reach 5.20", but it should not be used for routine shimming.
B. For manual shimming in auto control, each control blade will be withdrawn or inserted individually while the regulating blade automatically adjusts to maintain a constant power level.
C. The control blade posiitions will be adjusted such that they all read the same position across the board after the shimming operation has been completed.
D. During the shimming operation, the Reactor Operator will closely observe the nuclear instrumentation and the movement of the control blade (when in automatic control), to verify that the system response to the shimming operation is normal.
Rev. 10/81 App'd k b SOP /II-7
/
II.1.6 Reactor Shutdown Procedure 3 g
A. The procedure for a routine reactor shutdown regires only that the manual rod run-in circuit be activated. However, prior to shutting down the reactor:
- 1. Turn on the source range recorder and time and date the chart.
- 2. Insert the fission chamber until a count of approximately 105 cps is obtained on the SRM recorder.
- 3. Place the IRM recorder in fast speed and time and date the chart.
- 4. Take a set of nuclear and process data. ]
B. Depress the manual rod run-in button on the control console.
Enter the time of shutdown in the log book.
C. Follow the reactor power decrease by changing the range selector switch so as to keep channel WRM-4 on scale.
D. Complete the Reactor Shutdown Checksheet.
E. Ascertain that the reactor system is secured and enter same in log book, h II.2 Fuel Handling Procedure II.2.1 General ]
A. All fuel transfers will be authcrized by the Reactor Manager ]
or his designated representative. ]
B. If a fuel assembly is determined by the Shif t Supervisor to ]
be damaged, authorization must be obtained from the Reactor ]
Manager prior to loading that element in the reactor. ]
C. The Special Nuclear Materials Custodian (Reactor Physicist) ]
shall provide a step by step fuel movement procedure anytime ]
fuel is handled. 3 D. Fuel, new or irradiated, shall only be handled one element at ]
a time. ]
E. The reactor will be snutdown prior to handling fuel in the ]
reactor. Fuel may be handled in the weir area while the ]
reactor is operating. ]
Rev. 10/81 App'd C SOP /II-8
D F. Containment integrity is required anytime irradiated fuel is ]
d being handled. ]
G. Health Physics coverage shall be necessary when the pool is ]
below normal operating level, inspecting irradiated fuel, ]
shipping irradiated fuel and handling suspected ruptured ]
irradiated fuel . ]
H. One Senior Reactor Operator and one Reactor Operator must be ]
present to handle fuel . Only a Senior Reactor Operator, a ]
Reactor Operator, or a Reactor Operator trainee under the ]
direct supervision of a Senior Reactor Operator may handle ]
fuel. The Senior Operator is in charge of the fuel handling ]
evolution and is responsible for the proper conduct of the ]
evolution. 3 I. The fuel element fuel plates on the convex and concave ends ]
are very fragile. When moving an element, it is important to ]
approach an obstacle with the side plate facing the obstacle ]
to prevent accidental damage to a fuel plate. ]
Two fuel handling tools are provided. One is a short manually ]
th J.
operated tool to be used with the pool at refuel level . The ]
other is a long air operated tool used with the pool at normal ]
operating level . ]
K. Latching and unlatching the manually operated fuel handling ]
tool: When latching a fuel element, the red indicator will ]
come up when the tool has engaged properly. A locking key is ]
then inserted in a groove which prevents the unlatching handle ]
from moving. However, 00 NOT lift this handle when moving the ]
element. To unlatch the element, remove the locking key and ]
hold down on the top of the tool with one hand and lift the ]
unlatching handle with the other. This prevents the tool from ]
accidentally lifting the element off its seat when loading ]
into the reactor. 3 L. Latching and unlatching the air operated fuel handling tool: ]
When latching a fuel element, you will have to get a feel ]
(with practice) for when the tool is in its proper place on ]
the element. Slowly release the air operator handle. The ]
Rev. 10/81 App'd b- SOP /II-9
tool should move downward slightly as the tool pulls down into ]
the element. Verify the element is latched by observing ]
that the red indicator on the horizontal cylinder is fully ]
retracted. When unlatching the element, push down on the ]
tool while slowly pushing down the air operator handle to the ]
locked released position. When in the reactor, never lift the ]
tool off the element. Always allow the tool to float up off ]
the element. It will not float up if the element is attached ]
but can easily be worked off the element by pushing down and ]
turning until it floats off. Failing to release the element ]
in this manner may result in accidentally lifting and leaving ]
the element a few inches off of its seated position without ]
realizing it. ]
II.2.2 Procedure for Handling Fuel In or Out of the Core ]
A. Obtain a fuel handling sequence from the Reactor Physicist. ]
B. Inspect the fuel handling tool . ]
C. Place the bridge ARMS to upscale position. ] h D. Insure the pool is at the normal operating level or pump the ]
pool to refuel level as necessary. ]
E. Remove the pressure vessel head. ]
F. Turn on the Source Range Monitor Scaler and Chart Recorder. ]
Drive in the fission chamber to =1000 counts. ]
G. Attach a fuel element to the handling tool . ]
H. The operator handling the fuel element tool shall verify that ]
the element is fully latched and verbally report this to the ]
supervising Senior Reactor Operator. ]
Note: A positive latch is achieved only when the red plunger ]
on the air-handling tool is fully retracted and flush with the ]
cylinder. Any protrusion of the. olunger means the fuel element]
is not latched. ]
I. Remove and visually identify the fuel element and place it in ]
the position specified on the loading sheet. ]
J. Verify the element is seated in its new position. If in the ]
reactor, utilize board and reference mark. ] h Rev. 10/81 App'd F - SOP /II-10
K. A Reactor Operator or Senior Reactor Operator shall initial ]
the loading sequence sheet after each step. ]
L. A Senior Reactor Operator will inspect the core prior to ]
replacing the pressure vessel head. ]
M. Install the pressure vessel head. (If the pressure vessel ]
head is to be left off at this point, install the aluminum ]
protective head on the pressure vessel.) ]
N. Record that the reactor has been defueled or refueled indi- ]
cating the identification numbers of the cores involved and ]
the fact that the new core has been inspected. ]
- 0. Post the fuel element locations data sheet in the control ]
room. ]
P. Turn the bridge ARMS back downscale. ]
Q. Secure the SRM and pull the fission chamber to full out. ]
II.2.3 When starting up the reactor after any fuel change in the core, ]
the predicted critical position shall be verified by the Reactor Physicist. If the reactor has been loaded with a new mixed core, g
V a 1/M plot shall be made on the subsequent start-up.
II.3 Control Blade Offset Mechanism Removal II.3.1 Conditions Prior to Removal A. The control rod offset mechanism will not be removed except by authorization of the Reactor Manager.
B. The removal of the assembly will be supervised by the Shift Supervisor or a Senior Operator.
C. When one offset mechanism is to be removed:
- 1. The core will be defueled of two fuel elements;
- 2. The balance of the other three rods will not be raised from their fully lowered position without approval of the Reactor Manager.
D. When more than one offset mechanism is to be removed, the core will be defueled of at least two elements for each offset mechanism removed.
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E. A Health Physicist or a Health Physics Technician is to be present when the pool water is lowered and when the mechanism is brought out of the water.
F. During the process of actually removing the offset, the core neutron levels will be continually monitored using the fission-pulse channel SRM-1. The reactor control room may be unattended during the removal operation. All reactor systems will be shutdown.
II.3.2 Caution Should be Taken During Removal as Follows:
A. Due to the potentially high radiation level produced by the ]
activated blade, place the bridge ARMS to the upscale posi- ]
tion to prevent a building isolation alarm while the blade is being handled out of water.
B. Extreme caution should be used during Step II.3.3.L so that ]
undue stress is not placed n offset mechanism while breaking ]
it loose from guide pins. Also, extreme caution should be ]
used while maneuvering the offset mechanism away from the g pressure vessel.
11.3.3 The Detailed Procedure for Removal is as Follows:
A. Electrically disconnect the rod drive mechanism.
B. Remove the four bolts at the base of the rod drive mechanism and with either the rod magnet fully inserted or withdrawn, remove the rod drive mechanism.
C. Remove the four bolts at the base to the rod drive shaft housing assembly. Also remove the " blade full-in" microswitch.
D. Remove clamp-on drop time reed switch. Insure that the reed switch position is marked on the upper housing.
E. Remove the "U" clamp attaching the upper housing to the bridge l floor plate.
F. The upper housing unit may now be lifted free. Mark the upper housing when more than one mechanism is to be removed.
Loosen the bolts on the lower housing bracket and remove same.
G.
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o H. Unscrew lift rod assembly and lift up as far as it will go.
Remove lift rod and lower housing as one unit.
I. Using bolt removal tool, loosen offset mechanism hold down bolt on rear of assembly.
J. Insert offset mechanism pulling tool into hole in counter balance arm and raise blade to full out. Insert "T" section of lift tool into lifting lug at top rear of offset.
K. Attach the lifting tool to the crane.
L. Jog the crane while lifting by hand until the offset mechanism lists free of the side guide pins. Observe closely the strain necessary to break the offset free. If the offset mechanism does not break loose from its reflector platform after applying a reasonable amount of tension, relieve the tension on the lifting tool and determine the reason for the difficulty before t
continuing the attempt to lift the mechanism.
M. After the offset mechanism has cleared the guide pins, care-fully raise it until the top of the blade mount is about 1/8" below the pressure vessel intermediate flange.
Note: After the mechanism clears the guide pins, the blade is still partially within the gap so caution must be observed to hold the mechanism steady while raising it to the flange above or the blade may be damaged.
N. With the blade now clear from its gap, carefully move the mechanism away from the pressure vessel " spool" flange and raise the mechanism to the surface.
Caution: The lower portion of the mechanism and the lower tip of the blade will be very radioactive, so insure close Health Physics coverage is provided before raising the blade to the pool water surface.
II.3.4 Installation of the Control Blade Offset Mechanism The procedure for installing the blade and offset mechanism is essentially the reverse of the above, with a particular emphasis on the following points:
A. Before inserting the mechanism, check the clearance of the blade gap with the gapping tool.
Rev. 10/81 App'd I,'~- SOP /II-13
- 8. After disengaging the lifting tool from the locking "T", the Shift Supervisor or Senior Operator will exercise the blade over its full length of travel until he is convinced that the blade moves freely and is able to travel through the gap totally without resistance.
C. During the subsequent pull for the rod drop test, determine the position at which the reed switch activates. It must not be greater than 5.2".
II.4 Water Chemistry II.4.1 Water Chemistry Program The water chemistry program is designed to minimize the corrosion rate and induced activity. The table below lists the systems, specifications, and other pertinent data. The results of all chemistry are logged in the Water Chemistry Log.
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O Water Chemistry Program System Analysis Limit Procedure Source of Sample pH 5-7 II.4,4.A Inlet to FPM Primary conductivity 2 umhos II 4.4.B 2 samples required
- radioisotope analysis pH 5-7 II.4.4.A Pool conductivity 2 umhos II.4.4.B DI influent line
- radioisotope analysis pH 5-7 II.4.4.A DI Water conductivity 2 umhos II.4.4.B Connection at tank
- radioisotope analysis pH 7.0-7.4 II.4.4.A Seconda ry Dip sample from 2600 to II 4*4*0 3 conductivity 2900 umhos basin sump ]
Coolant chromates 15-30 ppm II.4.4.C H 6.8-7.2 II .'4.4. A Seal conductivity NA II.4.4.B Bulk dip sample Trench chromates 25-50 ppm II.4.4.C pH 7.0 min II.4.4.A Connection in SF-1 Chill conductivity NA II.4.4.B cooling room Wa er inhibi tor 2000 ppm min CS Test Kit l
- A radioisotope analysis of the pool and primary waters is conducted by the laboratory section weekly, for evidence of fission products plus any other abnormalities. See analysis sheet Appendix A.
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11.4.2 Waste Tank Analysis g
A waste tank analysis is performed by the laboratory group for evidence of activity prior to release to the sanitary sewer. See ]
Section VIII.8.5. A pH of each sample is measured to determine ]
its acidity. If the waste water is very acidic (pH less than 4) ]
and the liquid waste is to be held, a caustic solution should be added and circulated to prevent excess corrosion of the waste tanks.
11.4.3 Taking a Sample Normal water samples taken for water chemistry shall be taken in a 500 ml capped poly bottle. The WT and secondary samples require 1 liter samples. An additional 100 ml sample should be drawn in ]
a urine sample bottle for all WT samples and for any secondary ]
sample that requires radiochemical analysis. ]
A. Rinse and clean the sample container with DI water. ]
B. When taking the sample, purge the sample line to rid any stagnant solution.
C. Fill the sample container completely. Do not permit the sample to be air mixed while drawing the sample.
D. Cap the container immediately to prevent atmospheric contamina tion.
E. Note the time, date and source of the sample.
II.4.4 Test Procedures A. A measurement of pH is made on the portable pH meter located in Room 275. Turn the operation control to " STANDBY" and ]
allow at least a 5 minute warmup. Measure the temperature of ]
a standard buffer and set the temperature control to correspond. Immerse the electrodes in the buffer. Place the operation control in " READ" position. Use the standard- ]
ization control to set the meter reading to the exact pH of ]
the buffer. Switch the operation control to " STANDBY". Rinse O
Rev. 10/81 App'd P ' SCP/II-16
the electrodes with distilled water and wipe dry with a soft abosrbant toweling. Measure sample temperature and adjust the temperature dial to match. Place the electrodes in the first sample and swish around to rinse the electrodes ,
of impurities. Dump this sample and place the electrodes in a second sample; switch operation to " READ". The instrument will not indicate the pH of the sample. Swish the sample around the electrodes to get a representative indication; if possible, measure more than or.e sample in a consecutive manner until a constant pH is indicated. Contamination of the electrodes will induce an error in the indicated pH.
When measuring pH, the sample will become contaminated by standing open to atmosphere. Read pH immediately. After the measurement has been performed, turn the meter to standby and store electrodes in DI water.
B. Conductivity Test A measurement of conductivity is made on the portable con-d"ct ""'t '" "
- 275- '"r" i"'tr"**"* " "" nd allow O approximately 5 minutes warmup time. Rinse the cell with DI water. Place the cell in the solution to be tested. Move the cell up and down into the solution to remove air bubbles inside the cell casing or shield. Immerse the cell to a ]
depth of 1.75". The conductivity probe automatically compen- ]
sates for temperature. Dump the first sample and place the ]
cell in a second sample. Read the conductivity, setting the dial to the lowest scale possible. Measure more than one I sample, rinsing the cell in the sample to obtain best results.
When measuring high purity water, great care must be exercised to avoid contamination of the sample. The container and the conductivity cell must be thoroughly cleaned. If the sample cannot be tested promptly, the sample container should be full and capped. C02 absorption from the air can cause large increases in the specific conductivity of high purity water exposed even for a short time in an open container. Cells ]
O snouid be stored in pure weter. ]
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Section III REACTOR CONTROL AND INSTRUMENTATION SYSTEM III.1 Preparation of Reactor Instrumentation for Operation III.1.1 General Power to the process instrument panel is provided by the 480 V circuit through a step down transformer located behind the panel.
Power to the process panel including the neutron monitoring equipment will be maintained continuously. Adjustments and calibrations other than outlined in this procedure will be per-formed by the reactor instrument technician, or his authorized delegate.
After any maintenance is performed on a Nuclear Instrumenta- ]
tion detector or its associated cables, that channel of N.I.'s ]
shall be response checked before commencing a reactor startup. ]
The response check can be performed with either a gamma or neutron ]
source. The successful response check shall be noted in the ]
control room log book. ]
III.l.2 Procedure for Securing Electrical Power to Console and Instrument ]
Panel ]
A. Place all N.I drawers to zero/zero 1. ]
B. Remove VR units from N.I. drawers. ]
C. Turn Power Switch to "0FF" on 2PS1 and 2PS2. ]
D. Turn Power Switches 2CB1A and 2CB1B to "0FF". ]
E. Prop open back-up doors. ]
F. On Emergency Lighting Panel: 3
- 1. Open E15 ]
- 2. Open E18 ]
G. Place Elgar Line Conditioner Switch to "0FF". ]
Rev. 10/81 App'd
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III.2 Front Panel Checkout of Source Range Monitor Channel 1 ]
O A. Verify that the power to the recorder is on. ]
- 3. Set the function switch to " operate". ]
C. Verify that " drawer inoperative" lamp on the front panel of ]
the module is extinguished. ]
D. Set function switch to " standby". Verify that the " drawer ]
inoperative" lamp is glowing and that the " instrument anomaly" ]
illuminates on the annunciator board. -]
E. Set function switch to "zero". Verify that the "down-scale level" trip indicator is glowing, that the LCR meters and recorder both indicate 10-1 and that the " period" meters indicate -30 seconds.
F. Set function switch to 10s. Verifs chat the LCR meters and recorder indicate 8 x 104 - ).5 x 105 and that the "down-scale level" trip' goes out.
G. Set function switch to 10. Verify that LCR meters and the recorder indicate 9.8 - 10.2. .
fl. Set function switch to " period" position, and "rarap" switch to " fixed". Verify that " period" meters indicate +3 seconds.
I. Release "rar.p" switch, turn " reset" cwitch to " ramp" position for about two (2) seconds, and set function switch to
" operate" positiorc.
J. The. SRM' is now ready for use. Reset the annunciator.
K. Turn on scaler power.
Note. The scaler readout made is to be set at the discretion ]
of'the startup operator. ]
III.3 Pre-startup Check of Intermediate Range llonitor Channels 2 and 3 A. Verify that power to the recorder is on and that the IRM ]'
reco'rder selector switch on the control console is in ]
position 2 or 3 as required. ].
B. Set functi'an switch to " operate".
C. Verify that " drawer inoperative" (DS16A) lamp is extinguisned.
D. Verify that 'oeriod trip" lamps are extinguished. $
Rev. 10/81 App'd (' .
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E. Set function switch to " standby". Verify that the " period trip" indicators are not glowing.
F. Verify that lamp DS16A is glowing and a Nuclear Instrument Anomaly. annunciation occurs.
G. Set function switch to zero No. 2. Verify that the ampere meters and recorder all indicate 10-10 and the " period" meters read -30.
H. aet function switch to zero No. 1. Verify that the ampere meters and recorder all indicate 10-10 and the " period" meters read -30.
I. Set function switch to " period". Hold " ramp" switch to
" fixed". Verify that " period" meters indicate +3 and " period trip" lamp (DS17A) lights.
J. Release " ramp" switch. Move " reset" switch to the " trip" position, then hold it in the " ramp" position until ampere meters indicate 10-10; then release ",eset" switch.
K. Set function switch to the 10-8 position. Verify that the ]
O ampere meters and the recorder all indicate 8 x 10-9 to 1.2 x 10-8,
]
]
L. Set function switch to the 10-4 position. Verify that the ]
ampere meters and recorder all indicate 8 x 10-5 to ]
1.2 x 10 '+ .
M. Set function switch to 1.5 x 10-3 position. Verify that the ]
ampere meters and recorder all indicate 1.2 x 10-3 to ]
1.8 x 10-3 ]
N. Set function switch to " period" position.
O. Hold " ramp" switch (S3) to " variable".
- 1. Verify that when the control console period meter reads 11 1 seconds, the short period rod run-in lamps (DS17A) lights and short period rod run-in annunciation occurs.
- 2. Verify that when the control console period meter reads 9 1 seconds, the short period scram lamp (DS16B) lights and the short period scram annunciation occurs.
P. Turn reset switch to " ramp" for approximately 2 seconds, then to trip and release.
Rev. 10/81 App'd .s 50P/III-3 i /
Q. Place function switch in " operate" position.
R. Set compensation voltage so that indication is >10-9 if ]
possible. ]
S. Reset annunciator on control console. ]
T. This IRM is now ready for operation.
III.4 Prestartup Check of Wide Range fionitor Channel 4 A. Record the last heat balance setting of the drawer potenti-ometer. Compare potentiometer setting with last recorded heat balance setting.
B. Verify that power to the recorder is on. Time and date the chart if necessary.
C. Set function switch to operate and momentarily rotate " reset" switch (S2) to left or right.
D. Verify that " drawer inoperative" indicator (DS16A) is out.
E. Set function switch to " standby". Verify that " drawer inoperative" light (DS16A) is energized and that a nuclear instrument anomaly occurs. h F. Set function switch to zero No. 2. Verify that the power meters and recorder indicate 0 2 and that "downscale trip" light (DS17B) is energized and a downscale alarm is received on the annunciator.
G. Set function switch to zero No. 1. Verify that power meters and recorder both indicate 0 2% and that "downscale trip" light (DSl7B) is energized and a downscale alarm is received on the annunciator.
H. Momentarily rotate " reset" switch to left or right to clear rod run-in and scram trips.
I. Set function switch to " trip test".
J. Using the variable pot on the front of the module drawer, set trip adjust potentiometer to obtain an indication on the front panel meter equal to 114% 1", the desired setting for rod run-in. Verify that rod run-in light (DSl7A) is energized and that Channel 4-5-6 High Power Rod Run-In O
Rev. 10/81 App'd bW SOP /III-4
q annunciation occurs. Also verify the correct response of the console power meter and recorder at this signal level.
K. Set trip adjust potentiometer (Rl) to obtain an indication on the front panel meter equal to 119% 1%, the desired setting from High Power Scram. Verify that scram light (DS16B) is energized, and that Channel 4-5-6 High Power Scram annunciation occurs. Also verify the correct response of the console power meter and recorder at this signal level.
L. Return meter reading to less than 115%.
M. Set function switch to operate.
N. Clear rod run-in and scram trips by rotating " reset" switch to left and right.
O. Reset the annunciator.
P. WRM-4 is now ready for operation.
III.5 Check of Power Range Monitor Channel 5 and 6 A. Select Test / Feedback Module corresponding with the mode of O
V operation intended (the modules are marked and color coded with the colors used on the Mode Indicating Lights) and place the correct module in the drawer.
B. Place the Power Selector Switch 1S8 in the applicable position for the operation intended.
C. Record the actual setting of the drawer amplifier feedback ]
potentiometer on the Startup Nuclear Data Sheet. ]
D. Set the potentiometer to the calibration value determined by the Electronics Technician and marked on the potentiometer.
E. Set function switch to " operate". Verify that " drawer inoperative" lamp is extinguished.
F. Verify that power level trip indicators are extinguished.
G. Set function switch to " standby". Verify that power level trip indicators are extinguished, that " drawer inoperative" light (DS16A) is energized, and that a nuclear instrument anomaly annunciation occurs.
O Rev. 10/81 App'd n' = a 50P/III-5
H. Set function switch to "zero". Verify that both percent pcwer meters (on the console and instrument cubicle) and the recorder indicate 0 2%. Verify that a downscale light is received on the drawer and that a downscale alann is received on the annunciator.
I. Set function switch to 110%. Verify that the console percent power meter and the recorder indicate 110% 2% and the drawer meter indicates 110% 5%.
J. Set function switch to 75%. Verify that the console percent power meter and the recorder indicate 75% 2% and the drawer meter indicates 75% 5%.
K. Set function switch to 10%. Verify that the console percent power meter and the recorder indicate 10% 2% and that the drawer meter indicates 10% 5%.
L. Place function switch in " cal" position. Rotate reset switch to lef t or right to clear rod run-in and scram trips.
Reset annunciator board. Using the potentiometer provided on the front of the drawer, apply an input current equivalent g to the desired trip point for rod run-in (114% 1 %) . Veri fy that rod run-in light (DS17A) is energized and that Channels 4-5-6 High Power Rod Run-In annunciation occurs.
M. Apply an input current equivalent to the desired trip point for scram (120% 1%). Verify that scram light (DS16B) is ]
energized and that Channels 4-5-6 high power scram annuncia-tion occurs.
N. Return test signal to minimum setting. Set selector switch to operate.
O. Rotate reset switch to reset position and release. Veri fy that all trip indicators are extinguished. Reset the annunciator.
P. Set the potentiometer to the setting corresponding to the last value determined by heat balance. This should be the setting determined in Step A.
Q. This PRM is now ready for operation.
O Rev. 10 / en App'd 6 SOP /III-6
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III.6 Procedure for Physically Adjusting NI Detectors at Power Caution A. The aluminum clad lead shield for the detector cables makes the dry wells very heavy and difficult to handle. Be extremely careful to hold the dry well firmly while the clamps are being loosened. The crane and a rope may be ]
used to support the dry well during this evolution, but ] '
, NEVER raise the well with the crane. When raising a dry ]
well, lift it by hand and then restore the rope tension ]
with the crane. ]
B. Physical movement of an NI detector dry well will usually ]
affect the readings of adjacent channels. ]
III.6.1 Adjusting Channels 2 or 3 Note This procedure calls for extreme caution as a small step change can induce short periods with a resulting run-in and/or scram.
O A. Place IRM recorder to fast.
B. Place IRM selectar switch to channel not being adjusted.
C. Adjust channel.
D. Place IRM recorder to slow.
E. Log change.
f i III.6.2 Adjusting Channels 4, 5 or 6 A. Reduce power to about 9 MW. ]
B. Maintain power at 9 f1W in manual control. Use Channel 5 for ]
control if Channel 4 or 6 is being adjusted and use Channels 4 and 6 for control if Channel 5 is being adjusted.
C. Place the pot of the channel being adjusted to midrange.
D. Adjust the detector position to place the channel at the desired level.
E. Increase power to original level. ]
i F. Log final new pot setting.
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Check of Process Radiation Monitors III.7 g
III.7.1 Operational Check of Fission Product and Secondary Coolant Monitors A. Set function switch to operate.
B. Verify that drawer inoperative lamp is extinguished.
C. Set function switch to standby. Verify that the drawer inoperative lamp (DS16A) is energized.
D. Set function switch to zero. Verify that the front panel meter indicates 10-1 20%.
E. Set function switch to 105 Verify that the front panel meter indicates 105 20% and the respective hi activity annunciator channel trips.
F. Set function switch to 10. Verify that the front panel meter indicates 10 20%.
G. Set function switch to operate.
111.7.2 Operational Check of Stack Monitor A. The operator conducting the test in the West Tower shall ]
establish communication with the control room via the intercom ]
or walkie talkie and notify the front lobby receptionist of ]
the test (if applicable).
B. Place the mode switch for the iodine detector in the "T" (test) position.
C. Verify that the recorder pen indicates 3600 cpm 10%, and that the stack monitor high activity annunciation is received.
Also verify that the local meter reads within 10% of the test reading marked on the meter face.
D. Return the iodine mode switch to the "N" position.
E. Press the " reset" button until the iodine meter and recorder readings return to normal, do not drive them to the down-scale position. Reset the annunciator.
F. Place the mode switch for the particulate / gas monitor in the ]
"T" position. ]
O Rev. 10/81 App'd ,b SOP /III-8
G. Verify that the particulate recorder and gas recorder pens ]
indicate 3600 cpm 10% and that the stack monitor high ]
activity annunciation is received. Also verify that the local ]
meter reads within 10% of the test reading marked on the meter face.
H. Return the particulate mode switch to "0P" position.
I. Press the " reset" button until the particulate meter and recorder readings return to normal; do not drive it to the downscale position. Reset the annunciator.
III.8 Area Radiation Monitoring System The area radiation monitoring system will be in operation con-tinuously and is to be turned off only during maintenance on the system. When handling samples or during maintenance place the Bridge Upscale Switch in the upscale position. Insure Bridge Upscale Switch is returned to normal position after handling samples.
O The station trip points shall be set as follows:
Station 1-BP South Wall 2 X acceptable background Station 2-BP West Wall 2 X acceptable background Station 3-BP North Wall 2 X acceptable background Station 4-Fuel Vault 10 mr/hr Station 6-Room 114 2 X normal operating background Station 7-Reactor Exhaust 1 mr/hr or 10 X normal operating ]
Plenum background ]
Station 8-Reactor Bridge 50 mr/hr or 10 X normal opera- ]
ting background ]
Station 9-Reactor Bridge Backup 1 K - 10 K mr/hr At least once per month the system will be checked according ]
to the following procedure. ]
A. Insure that power is on. Power should be on at all times.
B. Using the master meter on the power and control unit, verify that the alarm relay voltage is +150 VDC +20 and the high voltage is set at 520 10 VDC.
Rev. 10/81 App'd M b S0P/III-9
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i C. Place channel selector switch on position 1.
D. Operate the check source push button and verify that when the i trip point is reached, the power and control unit alarm lamp lights and the unit audibly alarms and also the probe alarm lamp (Beam Hole Floor South) lights and it too gives an audible indication if applicable. The trip setpoint is lowered by a mechanical adjustment button at each meter.
E. Set trip point back to original setting.
F. Repeat steps C through E for Channels 2, 3, 4, and 6 observing that the lamps on the power and control unit and the indi-vidual stations illuminate and give an audible indication.
G. The source check of Channels 7, 8, and 9 which along with performing the above-mentioned functions, also initiates a reactor scram and produces a containment building isolation.
H. The purpose of the building isolation system is threefold: ]
- 1. To ir. form the personnel in the containment area that a ]
condition exists which warrants the evacuation of the ]
containment area.
To place the reactor in a safe (shutdown) condition so
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]
g 2.
that it may be left unattended. ]
- 3. To completely seal and isolate the containment area ]
automatically. ]
The purpose of the facility evacuation system is the ]
same as the building isolation system with one exception: It ]
also informs the personnel throughout the facility that a ]
condition exists which warrants the evacuation of the entire ]
facility to a predesignated area. ]
Note For normal startup checks, testing of the manually initiated reactor isolation and facility evacuation trips will be performed in conjunction with the above checks with the horns silenced and the isolation valves and doors closed.
To conduct source check:
- 1. Select desired channel; check trip point setting.
- 2. Reset scram and rod run-in trip actuators. g
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p 3. Notify all persons within the facility of intentions to perform the check.
4 Press source check push button and monitor point of trip, verifying the following to have occurred:
- a. Scram and rod run-in trip actuator amplifier tripped.
- b. Building air plenum high activity scram alarm indicated on annunciator.
- c. Evacuation or isolation scram alarm indicated on annunciator.
- d. 16" isolation valves indicate closed.
- e. Containment isolation horns have sounded.
- f. Isolation doors M0-504 and M0-505 indicate closed.
- g. Supply and return fans have secured.
- h. Red flasher light outside outer containment door is fl ashing,
- i. Alarm buzzer on ARMS module is alarming.
- 5. If more than one check is required,
- a. The horn cutout switch may be used to silence the Q containment horns.
4
- b. The 16" isoletion valves cutout switch may be turned to the off position, leaving the valves closed.
- c. The motor operated isolation doors may be left in the closed position.
- 6. When the checks have been performed as required, reset the tripped Channel 7 or 8 trip.
7 Trip the backup door radiation monitor with the attached source. Verify that the items in 4 above are initiated by the monitor trip.
- 8. Close the 16" isolation valve cutout switch, verify the valves indicate open.
i
- 9. Open isolation doors M0-504 and M0-505 by depressing the ]
open push button for 5 seconds after the fans start.
- 10. Perform a visual inspection of the ventilation system on the fifth level .
O ii. Turn the AaMS detector chenne, selector switch to Chennei 5.
Rev. 10/81 App'd 'n SOP /III-ll l t
- 12. Insure isolation horn cutout switch turned on.
Note If additional ARM checks are to be made, repeat steps A through C.
- 13. Notify all persons within the facility that checks are completed and that they should regard all further alarms.
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(v3 Section IV PRIMARY COOLING SYSTEM IV.1 Startup of Reactor Cooling Loop IV. l .1 Procedure A. Prior to placing the primary system on the line:
- 1. Verify that no primary system maintenance has been performed since the last shutdown of the primary system.
If maintenance has been performed on the system, insure that all valves disturbed are in their normal positions.
The Shift Supervisor will determine if a valve lineup ]
checksheet needs to be completed. ]
p Note: For Mode II or III operation, close the inlet valve (510B or 510F) of the heat exchanger not being used and tag out the pump breaker which will not be used.
- 2. Verify the proper lineup of the following systems in accordance with their respective S0P sections:
- a. Nitrogen and Air System - Section VII.9 and 10 ]
- o. Demineralizer System - Section VII.4 ]
I c. Prirrary/ Pool Drain Collection System - Section VII.6 ]
- 3. Verify or perform the following:
- a. P501A/B shaft cooling water supply valves are open.
- b. There are at least 2000 gallons of water in T300,
- c. Power is available to P501 A/B, P533 and P513A.
- d. Primary system flow recorder and temperature recorders l
are energized and the primary demineralizer flow recorder is energized. Time and date the recorders,
- e. Place heat exchanger bypass switch 2S41 in the position required for the heat exchanger combination to be used.
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B. Verify antisiphon vent valve closed. ]
C. Close antisiphon system manual drain valve. ]
D. Set the antisiphon system air regulator to 35 psig and open ]
the air inlet valve. ]
E. Place master switch 1S1 to test. ]
F. Open valves 527E and F. ]
G. Place valve 545 switch to auto / closed. ]
H. Place valve 527A switch to auto / closed. ]
I. Place valve 527B switch to auto / closed. ]
J. Place pump P-533 switch to on, P-533 may or may not start, ]
depending upon demand. ]
K. After P-533 has completed charging, place valve 526 switch ]
to auto / closed. ]
L. Place valve 507A/B switch to manual /open. Valves 543A/B will ]
automatically close at this time. ]
M. Immediately place valve 527C switch to open. The primary ]
system is now pressurized. ]
N. Cycle valves 546A/B switches to manual / closed. ]
- 0. Immediately start pump 501 A or B. Verify proper flow. ]
P. Cycle valves 546A and 8 open and then closed one at a time and ]
l Verify the increase and then decrease in primary system flow ]
as each valve is cycled. ]
Q. Start the remaining pump 501A or B. Verify proper primary ]
system flows. ]
R. Start pump 513A and verify proper flow. 3 S. Open the antisiphon system, drain valve and blow the system ]
dry. Close the valve, wait 10 seconds and repeat. This may ]
have to be done three or four times to insure that all the ]
water is drained. ]
T. Close the antisiphon system drain valve. ]
U. Insure that the antisiphon system pressure is between 35-40 ]
psig; then close the air inlet valve. ]
l Rev. 10/81 App'd b. SOP /IV-2 i,
q V. Place the following valve controls in the indicated positions: ]
V Valve Mode Position Valve Mode Position V507A/B Auto Closed V526 Auto Closed V546A/B Auto Open V527A Auto Closed V543A/B -- Open V527B Auto Closed V545 Auto Closed V527C -- Open W. Verify that all the valve position indicating lights are ]
operating with the valves in the positions listed in Step V. ]
If not, replace the appropriate light bulb. If this does not ]
clear the malfunction, shutdown the primary system as per IV.2 ]
and verify proper valve operation by a visual examination of ]
the actuator linkage during operation. In the case of V543A ]
or B indication failure, perform CP-24 Compliance Check. ]
Note: If the malfunction is determined to be an electrical ]
indication problem not used in the safety systen, the reactor -]
may be operated with repairs being made at the next maintenance]
O snutdown. ]
X. For 10 MW, 2 pump operation, balance loop flows as follows:
- 1. Check the flow in the two heat exchanger loops and adjust the 540 valves to balance the flow.
- 2. Check the AP across each of the pumps and adjust the bypass valves to balance the flow delivered by each pump.
IV.2 Shutdown of Primary System Note: The primary system should remain in operation for fifteen minutes after reactor shutdown to remove decay heat.
IV.2.1 Procedure A. Place master switch 1S1 in test.
I B. Close valve 527C.
C. Secure pump P533.
D. Secure P513A.
O e. If botn Pumps e501A end/or e50iB are runain9, secure them simultaneously to reduce check valve slam.
I' Rev. 10/31 App'd "' S0P/IV-3 L /
F. Verify that valves 546A/B open on the loss of flow.
G. Place the 507A/B mode switch to manual. ]
H. Verify that V507A/B close and that valves 543A/B open. ]
I. Open the drain valve on the antisiphon system and then slowly ]
open the vent valve and bleed the pressure to zero. Reclose ]
the valves when depressurized. ]
J. Place the following valve controls in the indicated positions:
Valve Mode Position Valve Mode Position V507A/B Manual Closed V527A Manual Closed V546A Manual Open V527B Manual Closed V546B Manual Open V545 Manual Closed V543A/B -- Open V526 Manual Closed K. Verify that valves 507A and B have operated and sealed closed ]
by cycling V507A/B while noting the system pressure drop. ]
There will always be some pressure drop due to pressure ]
trapped on the pump side of V507A/B; if not, repair of V507A ]
or B actuator or valve is required prior to any reactor start- ] $
up. 3 L. Close valves 527E/F.
M. Verify that all the valve position indicating lights are ]
operating with the valves in the positions listed in Step J. ]
If not, replace the appropriate light bulb. If this does not ]
clear the malfunction, determine the cause and make repairs ]
prior to any reactor startup. For V543A or B, perfonn CP-24 ]
Compliance Check. ]
l Note: If the malfunction is determined to be an electrical ]
indication problem not used in the safety system, the reactor ]
may be operated with repairs being made at the next maintenance]
shutdown. ]
N. Secure the primary flow and temperature recorders and the primary demineralizer flow recorder. Time and date the recorders.
- 0. Secure power to pumps P501 A/B, PS13A, and P533.
l P. Secure shaft cooling water supply to pumps P501 A/B. h 0
Rev. 10/81 App'd /c_ , SOP /IV-4
IV.3 Operation of the Antisiphon System IV.3.1 General Operating Philosophy The antisiphon system is designed to provide sufficient air (under pressure) to break a siphon of the primary coolant system in the event of a pipe rupture. To perform its function, this system must be maintained at a pressure greater than 27 pisg, and the water level above the antisiphon valves must be less than six inches. The procedures below will be followed to insure that the antisiphon system is operated within the above limitations.
IV.3.2 Decreasing Pressure in the Antisiphon System The system contains a pressure switch which will initiate an annunciator alarm when the system prest.ure falls below 30 psig.
Upon receipt of the low pressure alarm an attempt shall be made to establish normal system pressure by admitting air through the air valve and regulator on the bridge. If system pressure cannot d be maintained above 27 psig, th?. reactor shall be shutdown until the problem is corrected.
IV.3.3 Increasing Pressure in the Antisiphon System After the primary coolant system has been placed in service, open the system drain valve and check that the system is drained of all water. The system's pressure will then be returned to the ]
middle of the operating band (-36 psig) and this pressure will be ]
recorded on the routine patrol sheet.
On each subsequent routine patrol, read the system pressure and compare it to the base pressure recorded after the startup.
If the pressure has increased by more than 4 psi, action must be taken to insure that the pressure increase is not due to in-leakage of primary coolant water. If the pressure has increased by more than 4 psi, carry out the following procedures:
A. Open the drain valve and observe the water flowing from the O dreia iine.
I Rev. 10/81 App'd Es SOP /IV-5
B. Drain until you no longer receive a solid stream of water, then close the drain valve. h C. If the amount of water drained is significant, record this fact on the routine patrol sheet and in the console log.
D. Return the system pressure to normal (~36 psig) by venting ]
or adding air. ]
E. Record the new base pressure on the routine patrol sheet.
A new base pressure will be established during the first routine patrol of every day that the reactor is operating. To establish the new base pressure, carry out steps A through E above.
IV.3.4 Antisiphon High Level If an antisiphon high level rod run-in is received, carry out steps A through E of IV.3.3. When the high level alarm has ]
cleared, the rod run-in may be reset. Do not withdraw ~ rods until a thorough check of the system has been made to determine the source of the water leak.
IV.4 Depressurization of Pressurizer IV.4.1 Procedure A. Shutdown primary system in accordance with Section III.2.
B. Place valve position switch for V545 to open.
C. Allow pressure in pressurizer to reduce and then place valve position switch for V545 to close.
IV.5 Isolation, Draining, Filling and %rmal Operation of Primary Heat Exchanger Loops l
The following procedure is written with two sets of valve and com-ponent numbers depending on the heat exchanger being isolated.
IV. 5.1 Isolation of Primary Heat Exchanger 503A (5038)
A. Shut and tag the following valves to isolate the components indicated: g
- 1. FT912A (912E) by closing valve 568A (5688).
Rev. App'd S0P/IV-6 10/81 _
- 2. DPS928A (9288) by closing valves 595C and 5950 (595E q
V and 595F).
- 3. HX503A (5038) by closing valves 510B and 540A (510F and 5408).
IV.5.2 Draining of Primary Heat Exchanger 503A (503B)
A. Connect with flexible hose drain valve 515A (515Y) to the Primary / Pool Drain Collection System Tank funnel in pipe tunnel or suction of Drain Collection Pump.
B. Open vent valve 518AA (518AI) and drain valve 515A (515Y) and allow the loop to slowly drain or be pumped down. If drain collection pump is used, start it at this time.
C. Insure that the drain rate is controlled such that Primary /
Pool Drain Collection System does not overflow the pool . As the pool level rises to the yellow band, lower it in ]
accordance with Section V.4.2. ]
D. Shut drain valve 515A (515Y) after system has been drained O and shut or tag vent valve 518AA (518AI) if necessary to leave it open.
- 1. Insure drain collection pump is secured prior to shutting 515A (515Y).
IV.5.3 Filling of Primary Heat Exchanger 503A (5038)
A. Connect the pool TH drain line at valve 518Q to the primary TH drain line at valve 518S with a flexible hose.
B. Open vent valve 518AA (518AI) and check closed drain valve 515A (515Y). Run transparent tubing from vent valve 518AA (518AI) to the drain collection funnel .
C. Place the N2 and valve operating systems in operation as per Section VI.9.3.
D. Place the master switch 151 in " test".
E. Open valve 509.
F. Open drain valves 518Q and 518S.
Crack pen V51 (51 F) nd allow the heat exchanger to fill O G.
slowly.
Rev. 10/81 App'd I ._ S0P/IV-7
//
v
H. When a steady stream of water effuses from the vent line, close the vent valve 518AA (518AI) and valve 510B (510F). h Caution: If the heat exchanger is to be left in the isolated and filled condition, crack open (and yellow tag) the vent valve 518AA (518AI) to prevent pressure buildup in the solid loop.
I. Close drain valves 518Q and 518S.
J. Close valve 509 and return 1S1 to off.
K. Secure the N2 and valve operating systems if no longer needed.
IV.5.4 Restoration of Normal Operation of Primary Heat Exchanger 503A (5038)
A. Remove all drain or fill connections.
B. Check shut the following valves:
- 1. Drain valve 515A (515Y).
- 2. Vent valve 518AA (518AI).
C. Open the following valves:
- 3. FT912A (912E) 568A(5688)
D. Vent heat exchanger 503A (5038) by opening vent valve 518AA (518AI) until no air bubbles are seen escaping.
E. Startup primary loop following procedure IV.l .
IV.6 Isolation, Draining, Filling, Normal Operation of Primary Pump Loops The following procedure is written with two sets of valve and component numbers depending on the pump being isolated.
IV.6.1 Isolation of Primary Pump Loop 501 A (501B)
A. Shut and tag the following valves:
- 1. PI 916A/B (916E/F) 518A-518B (518AH-518AI)
- 2. Pump 501A (501B) 510A-510C (5100-510E)
O Rev. 10/81 App'd -
b -
SOP /IV-8
/-
J IV.6.2 Draining of Primary Pump Loop 501 A (501B)
A. Connect pump casing drain valve to Primary / Pool Drain Collection System Tank funnel in pipe tunnel or suction of Drain Collection Pump.
B. Disconnect gauge lines to discharge gauge.
C. Open discharge gauge valve 518A (518AH) and pump casing drain valve and allow the loop to slowly drain or be pumped down.
- 1. If drain collection pump is used, start it at this time.
D. Insure that drain rate is utilized such that Primary / Pool Drain Collection System can maintain level in system storage tank.
E. Shut pump casing drain valve after system has been drained and shut or tag discharge gauge valve if necessary to leave them open.
- 1. Insure Drain Collection Pump is secured prior to shutting pump casing drain valve.
O Iv.5.3 riilia9 of erimery eemn toon 501A c50,8)
A. Connect the pool TH drain line at valve 518Q to the primary TH drain line at valve 518S with a flexible hose.
B. Run transparent tubing from the discharge gauge valve 518A (518AH) to the drain collection tank funnel . Open valve 518A (518AH).
C. Start up the N2 and valve op system in accordance with Section VI.9.3.
D. Place the master switch ISl in " test".
E. Open valve 509.
F. Open drain valves 518Q and 518S.
G. Crack open the pump suction valve 510A (5100) and allow the loop and pump to fill slowly.
H. When a steady stream of water effuses from the gauge valve line, close the gauge valve 518A (518AH).
I. Open the discharge valve 510C (510E) and vent valve 518P.
O Coatiaue to fill the loop uatil e steedy stream of water effuses from the vent valve, then close vent valve 518P.
Rev .10/81 App'd, [ - S0P/IV-9
. ,-_ . - - . _ _ _ _ _ _ _ _ _ _- -- _ _ ._ - - _ ~
J. If the loop is to remain isolated, close valves 510C (510E) and 510A (5100). h K. Close drain valves 518Q and 518S and remove the flexible hose.
L. Close valve 509 and return 1S1 to off.
M. Secure the N2 and valve op system if no longer needed.
N. Remove the transparent tubing from discharge gauge valve 518AA (518AH) and connect the gauge line to the valve. Open 518AA (518AH).
IV.6.4 Restoration of Normal Operation of Primary Pump Loop 501 A (501B)
A. Remove all drain or fill connecticns.
B. Check shut the primary pump casing drain valve.
C. Check open suction and discharge gauge valve.
D. Open the following valves:
- 1. PI 916A/B (91EE/F) 518A-518B (518AH-518AB)
- 2. Pump 501 A (5018) 510A-510C (5100-510E)
E. Startup primary loop following procedure III.l .
O O
Rev .10/81 App'd '
SOP /IV-10
A V
Section V POOL COOLING SYSTEM V.1 Pool Cooling System Startup V . l .1 If pool system maintenance has been performed since the last pool system shutdown, insure that all disturbed valves are in their ]
normal positions. The Shift Supervisor will determine if a valve ]
lineup checksheet needs to be completed. ]
V.l.2 For Mode I operation, both heat exchangers 521 A/B and both purrps 508A/B mus't be in operation. For Mode II or Mode III operation, either heat exchanger 521A or 52iB chall be used with either pump 508A or 508B. The inlet valve of the heat exchang+r not ir ,
service shall be shut and the outlet valve shall be left in its throttlad position. This is necessary to prevent the excessive pressure that could occur in an isolated heat exchanger. The pump which will not be used shall be tagged out (at breaker) to prevent inadvertent operation.
V .1. 3 When the appropriate position for the pool system valves has been established, then the pool system can be started up according to the following procedures:
A. N2 and air system should be in service (SOP VII.9). ]
B. Visually check for a proper pool level; the pool should be filled to a level satisfying either LC-910 (normal pool level controller) or LC-966 (intermediate refuel pool level controller).
C. Check reflector AP scram setpoints to be set for the mode of operation planned: Mode I (10 MW) 2.54 and 8.00 or Mode II (5 MW) and Mode III (50 KW) 0.63 and 2.00.
i O
Rev. 10/81 App'd SOP /V-1
l D. Visually check for proper in-pool loadings:
- 1. fiake certain experiments are securely loaded and are seated within their proper loading facilities.
- 2. Make certain the flux trap facility appears normal and the test hole guard web is properly in place, or the test hole sample holder is correctly and securely positioned.
E. Turn on the pool flow and temperature recorders and time and ]
date. ]
F. Verify that the local pump stop switches in room 114 are ]
unlocked. ]
Note: If the breaker is closed, the selector switch is in the ]
auto mode and the stop switch is unlocked; the off indicator ]
in the control room for P508A/B will be lighted. ]
G. Place HX bypass switch 2S40 in the position required for the ]
HX lineup intended. ]
H. Master control switch 1S1 should be in the test positior:. ]
I. Place valve V509 switch to the manual /open position. ]
J. Turn on pool pump P503A/B as appropriate by turning the ] g control switches to on. Verify proper flow. ]
K. Start cleanup pump P513B and verify flow. ]
L. Adjust pool flow if required by throttling the HX outlet ]
valves (522A and 5220) as necessary. ]
M. With normal flow and pressure, place V509 switch to auto / ]
closed. ]
N. Verify that all the valve position indicating lights are oper- ]
a ti n g . If not, replace the appropriate light bulb. If this ]
does not clear the malfunction, shutdown the pool system as per]
V.2 and verify proper valve operation by a visual examination ]
of the actuator linkage during operation. ]
Note: Determine the cause of the failure and make repairs ]
prior to any start up. ]
- 0. If not required for other evolutions, turn master control ]
switch 1S1 to the on position. ]
O Rev. 10/81 App'd j- SOP /V-2 i
V.2 Pool System Shutdown Procedure V.2.1 The pool cooling system should remain in operation for a short period of time (5 minutes minimum) after a normal reactor shutdown in order to remove core decay heat from the reflector and experimental facility. The procedure for attaining a normal pool system shutdown mode is as follows:
A. Place master switch 1S1 in test.
B. Turn off cleanup pump P5138.
C. Turn off P508A/B using the control switches in the control room. To minimize check valve slam, secure both pumps ]
simultaneousiy. ]
D. Verify that valve V509 closes automatically. ]
E. Place V509 in the manual / closed position. ]
F. Verify that all the valve position indicating lights are ]
operating. If not, replace the appropriate light bulb. If ]
this does not clear the malfunction, determine the cause and ]
make repairs prior to any reactor start up. ]
G. Turn off the pool flow and temperature recorders. ]
H. Secure power to P508A/8. ]
V.3 Partial Pool Filling Procedures (Pool at Refuel Level or Above)
V.3.1 To increase the water level in the pool with demineralized water from T301 or T300, one of the two following procedures can be used; however, all water in T301 should be used first.
A. Filling may be accomplished with the skimmer system (Section ]
VII.S.1) with or without the skimmer pump operating and the ]
reactor either operating or shutdown. Required operational pool makeup will be accomplished in this manner.
- 1. Check capacities of tanks T300 and T301 and check proper valve lineup.
l 2. Observe the pool level and check that the skimmer pump is secured.
O Rev. 10/81 App'd '- S0P/V-3
- 3. Remotely open valve 565B from the primary / pool drain collection system control panel . Insure valve does indicate open.
- 4. The skimmer pump may be started at this point. However, ]
it will fill by gravity if desired. ]
- 5. When proper pool level is obtained, secure the skimmer pump and remotely close valve 565B. Insure it does indicate closed.
B. The second approved method of filling the pool is via the 4" line from tank T300/301 to the pool pump suction and discharge line.
- 1. Check capacities of tanks T300 and T301 and check proper valve lineup.
- 2. With the pool system in the normal shutdown mode, filling the pool through a pool pump can be avoided by opening valve V522C and permitting T301 or T300 to drain by gravity feed alone.
- 3. Close valve V522C when the filling operation is completed. g V.4 Fool Lowering Procedure V.4.1 Lowering Pool Water Level to Refuel Bridge Two methods of lowering pool level may be used:
A. By use of the skimmer system (SOP /VII.5.4).
B. By use of the pool pumps P508A or P508B as outlined below.
V.4.2 Before a lowering of the pool level using P508A/B is commenced, place pool system in service as follows:
A. Isolate one pool heat exchanger utilizing the local inlet ]
gate valve. ]
B. Place master switch in ISl to test. ]
C. Place V509 to manual /open. ]
D. Start P508A or B.
O Rev.10/81 App'd I SOP /V 4
g E. Pool lowering procedure is as follows:
- 1. Health Physics personnel shall be present while lowering pool level to insure that a high activity sample or component is not uncovered causing excessive personnel exposure.
- 2. Check pool area to insure all samples, spacers, and other radioactive materials are low enough to guarantee adequate shielding.
- 3. Turn skimmer pump P-532 off.
- 4. Insure that T-301 is valved in service.
Note: A visual observation of the in-pool facilities must be maintained while a pool pump is on and during the draining operation. Specific control over hazards and a radiation survey must be maintained curing the course of the draining operation. The pool level will not be lowered below the intermediate refuel level without the specific approval of the Reactor Manager.
,f's 5. Open manual valve V522C in room 114 to full open. Note
\J the reduction of flow as the valve is opened.
- 6. With V5220 full open, slowly throttle down on the uniso- ]
lated heat exchanger inlet gate valve until the flow ]
indicated by the flow recorder in the control room shows ]
approximately 200 gpm. ]
- 7. When the pool level is at the desired level or a T-301 high level alarm is received, secure P-508 and immediately close V-522C.
- 8. Reopen the inlet valves of both heat exchangers. ]
- 9. Insure that Health Physics clears the bridge area for access.
V.5 Pool Cleanup System l
V.5.1 To put the pool cleanup system into normal operation, the following f procedure is used:
i hy A. Check valves V515T, V515N and V515P open.
i t
Rev. 1 0/81 App'd b:'- SOP /V-5
/
~ , - - - . , - - - , .-r--, - - _- ---,,y..- - - - - - . - - - - - - --
B. Check valves V515M, V515X (P513B bypass) and V515Q closed for normal operation. O Note: Opening V515M and closing V515T bypasses flow around valve V509, HUT-504 and P508A/B to the input of P5138.
Opening V515Q and closing V515P returns processed water to the suction side of P508A/B rather than back to the top sida of the pool .
C. Make certain that one of three possible domineralizer units is valved into the cleanup system according to the procedures described in Section VI.4.0.
D. Turn on demineralizer flow recorder. Time and date the strip chart.
E. Turn on P513B from the control room by turning the F5138 control switch to the on position.
F. Verify a 50 5 gpm flow rate on the pool cleanup loop flow recorder.
G. Indicated flow rate shocid be 50 5 gpm and the indicated water purity should be less than 2.0 umhos/cm from the g demineralizer.
V.5.2 Discharging Excess Water from the Primary or Pool System with T301 Full The use of this procedure must be specifically approved by the Reactor Manager. 3 On rare occasions it may be necessary to discharge water from the primary or pool system when tank T301 is full. Under these conditions, the water is dumped to a special holdup tank or to the liquid waste system. Conditions which would require this special procedure include (but are not limited to):
A. Lowering the pool below refuel level; B. Lowering the pool to refuel level with T301 already holding more than 1,000 gallons of water; C. Draining the primary or pool piping in room 114 with the pool already at refuel level (T301 full or near full).
O Rev. 10/81 App'd b5 SOP /V-6
( To minimize the total activity dumped under these conditions,
( the water is discharged through the valved penetration downstream of the pool DI effluent filter. The water is pumped by cleanup pump P513B or by the drain collection system pump.
To discharge excess water, carry out the following:
A. Determine the volume of water to be discharged and where it is to be dumped.
B. If the water is to be dumped into the waste system (WT-3),
check to insure that WT-3 is empty or has sufficient capacity remaining to accept the water. To pump WT-3, use 50P VII.8.7B ]
or S0P VII.8.98. ]
C. If the water is to be dumped to a holdup tank, insure that the tank has the capacity to take the water and has been checked to be leak tight and clean.
D. If the resin bed on pool service is near depletion or has shown a reduced DF, consider changing to a newly regenerated bed for pool service.
O E. Check that valve V515AC is closed and remove the blank flange from the valve.
F. Connect a clean plastic or rubber hose to the flange on V515AC and run it to WT-3 or the holdup tank.
G. If pump P513B is to be used, close V515T and open P515M.
If the drain collection pump is used, close V515T and V515P, but do not open P515M.
H. Start the pump to be used for the discharge and open V515AC.
If P5138 is used, throttle V515P to get the desired discharge flow rato.
I. When the desired volume of water has been discharged, close V515AC and secure the pump.
J. Return the valve lineup to normal .
K. Drain the plastic hose to a plastic lined barrel and flush the hose with DI water (into the barrel) to decontaminate the hose.
L. Clean up any spilled water to eliminate the possible spreading of contamination.
Rev. 10/81 App'd 7' '_ _ SOP /V-7
l l
l l
l l
NOTE: THIS PAGE INTENTIONALLY LEFT BLANK O
O Rev. 10/81 App'd f' f -
50?/V-8
Section VI SECONDARY COOLING SYSTEM VI.1 Startup of the Secondary System A. Before attempting to start up the secondary system, it should be determined that:
- 1. Water level in the cooling tower basin is between 5 and 10 inches.
- 2. All personnel are clear of cooling tower equipment and fans.
- 3. Oil level in the gear reducers to the fans is normal.
B. The following manually operated valves in the cooling tower should be in positions indicated:
O Open Closed S-17 S-9 S-ll3 S-129 S-18 S-10 S-105 S-128 S-19 S-ll S-106 S-101 S-20 S-12 S-107 S-126 S-21 S-118 S-108 S-121 S-22 S-119 S-109 S-123 S-155 S-120 S-110 S-125 S-5 S-117 S-lli S-127 S-6 S-114 S-ll2 S-7 S-ll5 S-102 S-8 S-ll6 S-163 C. The following valves in equipment room 114 passageway and waste tank room should be in the positions indicated:
Rev. 10/81 App'd j r S0P/VI-l
/
Open Closed 5-152 S-151 S-103 5-169 S-153 S-150 5-160 S-170 S-104 S-159 D. The following valves in equipment room 114 should be in the positions indicated:
Open Closed 5-161 S-26 S-132 S-144 S-162 S-41 S-133 S-145 S-131 S-43 S-27 S-154 S-130 S-34 S-28 S-134 S-23 S-35 S-29 S-135 S-24 S-45 S-137 S-136 S-25 S-140 S-138 S-39 S-141 S-139 S-30 S-142 S-157 S-31 S-143 S-158 h E. For operation of the chiller units with feed water from SP-1, SP-2, SP-3 or SP-4, the following valves in room 278 should be in the positions indicated as follows:
Open Closed S-53 S-55 S-51 S-148 S-54 S-56 S-52 S-146 S-57 S-58 S-147 S-149 F. Turn on Bailey Meter recorder Model E101 in the reactor control room to monitor secondary flow and temperature during operation.
Time and date chart. Secondary outlet temperature for each heat exchanger can ba monitored in the control room with the digital readout and selector switch.
G. Verify that the circuit breakers for SP-1, SP-2, SP-3 and SP-4 on MCC-2 in the cooling tower are closed and that the control switch on the panels is in auto mode.
Rev. 10/81 App'd W S0P/VI-2
H. Start two secondary pumps for 10 MW operation, or one pump for 5 ff4 operation.
Caution: Two pumps cannot be started at the same time because ]
the basin level will be drawn down faster than the makeup ]
water can be supplied, which will result in the actuation of ]
a low sump level trip. After one pump is started, it is ]
- necessary to wait at least 10 minutes before starting the ]
second pump. ]
Verify that the correct flow occurs and that the pumps operate normally. The secondary system is now fully opera-tional..
Note: The pumps should be operated alternately with neither pump carrying a major share of total on-line time. For single pump operation, use SP-3 whenever possible. The check valve on SP-3 is rated for higher flows than those on SP-1 or SP-2.
I. Place the Calgon water treatment units in automatic control ]
locally. ]
1 O a. eumns se-1 se-2. se-3 and se-4 may be operated ioca117 during maintenance by means of controls provided at each of l
the pump positions.
K. Periodically check and adjust valves S-17, S-18, S-19, S-20, S-21 and S-22 located atop the cooling tower to assure equal flow through each.
VI.2 Procedure for Operation of Bypass Control Valves S-1 and S-2 The controllers for operating the contr31 valves S-1 and S-2 are located on the instrument cubicle in the control room as an f
integral part of the primary and pool water temperature recorders respectively. Provisions are made for both manual and automatic
! control operation modes:
A. Manual Operation
- 1. Energize process system and controller.
- 2. Adjust the valve position with the manual control button on front panel until pool and reactor coolant temperatures stabilize at the desired values.
Rev. 10/81 App'd y- SOP /VI-3
/
B. Manual to Automatic Transfer Control can be transferred from manual to automatic operation h at any time.
- 1. Turn control transfer switch on front panel to auto position.
C. Automatic to Manual Transfer
- 1. Turn control transfer switch on front panel to bal position.
- 2. Adjust manual control on front panel until deviation meter on front panel indicates no deviation. With no deviation present, red meter pointer is aligned with red index line of setpoint tape indicator.
- 3. Turn control transfer switch on front of panel to man position. The system temperature is now controlled by manual control.
Note: Caution must be used in going from the automatic mode to the manual mode in that if the indicated valve deviation is not brought into balance with the valve adjustment button on the controller prior to turning to g the manual mode, and if there is a large difference between the manual position demand and the position of the valve in the stabilizer auto mode, a significant positive or negative reactivity change could occur. This would be due to the valve leaving its position in the auto mode and traveling as rapidly as possible to the position demanded by the manual setpoint when the manual mode is selected.
The bal mode permits the manual control position demand to be equated to the stable position of the valve while being operated in the auto mode before the manual mode is selected.
VI.3 Operation of the Cooling Tower Fans The cooling tower fans required for operation is a function of both the reactor power level and/or climatic conditions. Control over the use of these fans rests with the Shift Supervisor who will O
Rev. 10/81 App'dy !' SOP /VI-4
maintain process coolant temperatures within standard operational limits as specified in the t1URR Technical Specifications and Section I of the Standard Operating Procedures.
Prior to starting the fans, the oil level in each fan shall be checked and marked off on the startup checksheet. This is to be checked prior to lighting off the fans or ten minutes after the fans have been secured. After an idle period during the winter months, the blades shall be checked to make certain ice accumulation on the surface of the blades will not cause an imbalance while the fans are in operation. Such an imbalance could result in damage to the fan units. A vibration switch installed near the gear reducer wili stop the fan if excess j vibration occurs, but this switch shall not be relied upon to prevent damage from ice accumulation.
VI.3.1 Deicing the Cooling Tower During very cold months, the water dispersion slats may become ]
mostly covered with ice. The following procedure should be used: ]
O A. Notify the Shift Supervisor of the need to deice. ]
B. Maintain communication either with radios or the intercom box ]
at the cooling tower. ]
C. Have the control room operator secure the cooling tower fan ]
for the tower bay in which deicing is desired. All three ]
cooling tower bays may be deiced at the same time but it must ]
be remembered that some cooling capacity is lost when deicing. ]
D. Allow enough time for the fan motor to coast to a stop and ]
then place the fan motor main breaker forward / reverse switch ]
to reverse. ]
E. Notify the control room to start the fan. It will now be ]
running in reverse to force heat out through the ice covered ]
slats. ]
F. Periodically check to see if ice is clear; about every 30 ]
minutes. When clear, use the above procedure to place the ]
fan in forward rotation. ]
Rev. 10/g1 App'd b ,. SOP /VI-5
,,.,r- -- - - - , . . , , -~, , ,, - .- - - - - . , - . _ - - . _ , - -
VI.4 Shutdown of the Secondary System g
Upon completion of shutdown of the reactor, reactor primary and pool loop cooling systems, the secondary cooling loop can be shutdown as follows:
A. Shutdown secondary pump or pumps. If more than one secondary pump is operating, they should be secured simultaneously to minimize check valve slam. This is done from the control room instrument panel.
B. Verify that system flow recorder indicates no flow and that the chiller pump, SP-4, has automatically started to provide coolant flow to the chiller units. During winter months when the air conditioning units will not be in service, SP-4 will be placed out of commission and verification of its aperation during these months will not be necessary.
C. Turn off cooling tower fans.
VI.5 Draining and Filling the Secondary System The following procedure will be used in draining and filling the secondary (shell) side of heat exchangers HX-503A and B and HX-521A and B.
VI.5.1 To Drain HX-503A (5038)
A. With the reactor shutdown, shutdown the primary and pool cooling systems per SOP IV and V.
B. Shutdown the secondary system per paragraph VI.4.
C. After radiation surveys have been made in equipment room 114, enter room 114 and perform the following:
- 1. Close valves S-23, S-27, S-31 and S-39 (S-24) (S 41) to isolate HX-503A (503B).
- 2. Connect a drain line to S-136 (S-137) and run it to the nearest clean water drain.
- 3. Open S-136 (S-137) to drain the heat exchanger.
- 4. Open 5-141 (S-142) to vent the heat exchanger.
O Rev. 10/81 App'd 3c , . 50P/VI-6
D. This operation will allow water to drain from the shell side of HX-503A (5038).
VI.S.2 To Drain HX-521A (5218)
A. With the reactor shutdown, shutdown the reactor primary and pool cooling systems per S0P IV and V. ]
B. Shutdown the secondary system per paragraph VII.4. ]
C. After radiation surveys have been made in equipment room 114, enter room 114 and perform the following:
- 1. Close valves S-26, S-43, S-35 and S-28 (S-25) (S-45).
- 2. Connect a drain line to S-139 (S-140) and run it to the nearest clean water drain.
- 3. Open S-139 (S-140) to drain the heat exchanger.
- 4. Open S-143 (S-144) to vent the heat exchanger.
D. This operation will allow water to drain from the shell side of HX-521A (521B).
VI.5.3 To Fill HX-503A (5038)
A. If system integrity has been broken, check that it has been properly restored.
B. Close drain valve S-136 (S-137).
C. Slowly open valve S-23 (S-24) while venting through S-141 (S-142).
D. When an air-free flow of water is indicated at S-141 (S-142),
close S-141 (S-142).
E. Open S-27, S-31 and S-39 (S-41).
F. " Jog" SP-1, SP-2 or SP-3 and insure a good air-free flow from all other secondary system vent valves, S-145, S-154, S-149, S-146 and S-144. Then close all vent valves and S-27.
f G. Run SP-1, SP-2 or SP-3 and check system for leaks and for proper operation.
I
!O Rev. 10/81 App'd b > SOP /VI-7 i
VI.5.4 To Fill HX-521A (521B) g A. If system integrity has been broken, check that it has been properly restored.
B. Close drain valve S-139 (S-140).
C. Slowly open valve S-26 (S-25) while venting through S-143 (5-144).
D. When an air-free flow of water is indicated at S-143 (S-144),
close S-143 (S-144) .
E. Open S-28, S-35 and S-43 (S-45).
F. " Jog" SP-1, SP-2 or SP-3 and insure a good air-free flow from all other secondary system vent valves, S-145, S-154, S-149, S-146 and S-144. Then close all vent valves and S-28.
G. Run SP-1, SP-2 or SP-3 and check system for leaks and for proper operation.
VI.6 Secondary Water Treatment Procedures VI.6.1 Secondary Water Sjstem Responsibility The responsibility of the secondary water treatment is within the operations group of the reactor, with one individual given prime responsibility and a co-worker to learn and be closely associated ]
with the total operation. The secondary water treatment system ]
is designed to minimize corrosion, deposition, microbiological growth, and other major chemical problems which are present in the l
l secondary cooling water system.
VI.6.2 Secondary Water Conductivity Control To control conductivity (total dissolved solids), water is sampled and monitored by the conductivity unit located in the tunnel of room 114. If the conductivity is greater than the system setpoint, l an automatic blowdown is initiated. The fresh water makeup, which l replaces the water lost through the blowdown, lowers the conduc- ]
ti vi ty. See Section II.4 for specifications. ]
O l
Rev. 10/81 App'd 6. SOP /VI-8
VI.6.3 Secondary Water pH Control To control pH, water is sampled and monitored by the pH unit located in the tunnel entrance of room 114. If the pH increases above the system setpoint, the acid injection valves automatically open and acid is gravity fed into the tower sump. The acid used is concentrated sulfuric acid supplied from the 250-gallon day tank in the cooling tower. See Section II.4 for specifications. ]
VI.6.4 Sample Paths for pH and Conductivity A. During normal operation of the secondary system, the automatic ]
pH and conductivity control units receive their sample water ]
through valves S104 and S151.
B. During operation of the secondary system with the air condi-tioning units secured and isolated, close S104 and open S103.
This provides a representative sample for these units to control pH and conductivity. To shift the automatic blowdown
(~ system during operation with the air conditioning units isolated, close S102 and open S101.
C. During shutdown periods, either secure the pH and conductivity ]
control units or run at least one large secondary system pump. ]
Sample response time from the cooling tower basin is much too slow with only P-4 running.
VI.6.5 Secondary Water Corrosion Prevention A. The prevention of corrosion in the secondary water system is ]
accomplished by automatic addition of a corrosion inhibitor ]
preparation containing zinc chromate (Dearborn 566) to the ]
cooling tower. Chromates are added to maintain 15 to 30 ppm ]
by slug feedings of 1/4 gallon inhibitor every routine to the ]
B. It may be necessary to " slug" feed chromates to the secondary ]
system, such as after a drain and fill of the system. To ]
raise the chromate concentration 5 ppm, add 1/2 gallon of the ]
Rev. 10/81 App'd /E 7 S0P/VI-9 j /
zinc chromate inhibitor directly to the cooling tower sump. ]
Insure that SP-1 or SP-2 is running when this is done. ]
VI.6.6 Secondary Silt, Algae and Mud Control ]
Silt and mud buildup is controlled by the daily slug feeding of a ]
chemical silt dispersant to the cooling tower basin. One gallon ]
of dispersant is added daily to ensure solids remain suspended a ]
sufficient amount of time to allow the secondary blowdown to ]
remove them from the system. This reduces secondary conductivity ]
and minimizes the buildup of silt in low flow areas, a fouling ]
condition. ]
Microbiological and algae growth is controlled by the addi- ]
tion of two microbiocides/algaecides. The addition frequency is ]
determined by weather conditions and reactor operations. For ]
normal operating conditions, one gallon of chemical is added every ]
three days alternating between the two types of microbiocides ]
each time. Chemicals presently being added are: ]
A. Dearborn 712 - microbiocide ] g B. Dearborn 717 - microbiocide ]
C. Daarborn 726 - silt dispersant ]
l O
Rev.10/81 App'd SOP /VI-10
O Section VII ]
AUXILIARY SYSTEMS i
VII.1 Reactor Power Calculator The automatic power calculator uses an input signal from the primary and pool aT summers and calculates a power heat balance using analog type computer circuitry. The power level is read out continuously on a digital meter which gives the reactor power in megawatts. The flow signals used to calculate the power are input manually through a potentiometer built into the system for both pool and primary flows.
I VII.l.1 Setting the Potentiometers The flow potentiometers are set at the fraction of total recorder Q flow that is being used. The primary flow recorder has a full scale reading of 2000 gpm for each loop, thus the total recorder flow available is 4000.
To determine the pot setting, add the indicated flow in loops A and B and subtract the cleanup flow from this total.
This number is the total core flow. Divide the total core flow by 4000. The resulting fraction should be set into the pot.
The pool flow recorder has a full scale reading of 800 gpm for each loop and the pool cleanup flow is extracted before the pool water flows through the heat exchangers. To determine the pot setting for pool flow, add the indicated flow of j
loops A and B and divide by 1600. The resulting fraction should l be set into the pot.
i O
Rev. 10/81 App'd M -
SOP /VII-l
-,,,,_v, , - y-, - - --. - , - . , -_ - __
Checking Operability of Calculator VII.l.2 g
The accuracy of the power calculator shall be checked daily after the first set of process data is taken provided steady state temperature conditions have been reached. This check is made by hand calculating the reactor power using the process instrumentation. The results of this calculation shall be recorded in the comments section of the process data log.
VII.2 Has been deleted.
VII.3 Emergency Power System VII.3.1 Testing of the Emergency Power System At least once a week the emergency generator will be started automatically and permitted to run for at least 30 minutes. ]
This event will be noted in the console log. An amber light ]
mounted on a side panel in the control room will energize whenever the emergency generator is running. In addition to g this, the emergency generator will be operated for a period of about 30 minutes prior to each startup after a shutdown exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. At least once a month commercial power to the auto transfer switch will be interrupted at unit substation l B in order to allow the emergency generator to start and l
immediately assume full load conditions.
l l
l VII.3.2 Prior to Starting 1
A. Check engine oil level.
B. Check that fuel pump controls are in auto and on.
VII.3.3 To Start Engine Locally A. Place the Remote-Stop-Run switch to run position.
B. When the engine comes up to speed (1800 rpm), check water l flowing to drain from engine cooling system.
C. Check fuel settling bowl full of gasoline. g Rev. 10/81 App'd r . - 50P/VII-2
D. Check oil pressure gauge reading properly.
E. Check ammeter reading a low positive charge rate.
F. Check that engine temperature does not become excessive
(>212 ). If engine temperature does become excessive under a no load condition, this means that the cooling system is not functioning and the engine should be stopped immediately until cooling water can be issued to the engine.
VII.3.4 To Stop Engine Run engine for 30 minutes and then return Remote-Stop-Run switch to the remote position. Engine will then return to its normal (standby) status.
VII.4 Reactor Demineralizer System VII.4.1 Normal Operation There are four beds of mixed resin loaded for normal operation of the reactor. Two beds are normally in service, one on the O pool system and one on the primary system. The third mixed bed is stored in the remaining DI column in a standby condition ]
(see VII.4.6). The fourth bed shall be stored in the resin ]
storage tank after being taken off service. The normal cycle for a resin bed will be from the DI column to the storage tank; from the storage tank to the regenerator; after a regeneration, l from the regenerator to a DI column.
Note: The resin stored in the storage tank shall be held before regeneration a sufficient time for the shorter half life isotopes to decay.
Note: The respective valves on each DI column are all numbered the same. The subsequent instructions will apply to any of the DI columns.
Note: Standard procedure shall be to transfer to the DCT the tritium water from each resin bed when it comes off service as per Section VII.4.3.9. The unit will be refilled with DI ]
water and logged as such.
Rev. 10/81 App'd f ,~, SOP /VII-3
VII.4.1.1 Placing the Reactor Cleanup System in Service O
Service through the DI column on reactor water is through F201, through the DI column downflow and out the DI column, then through F203 or F202 to the deionized reactor water effluent.
To place the system in service from a complete shutdown condition, carry out the following steps:
A. Insure all valves on the DI column are closed.
B. Check the resin-filter log book and the status board to determine the exact status of all beds.
C. Open valves F4 and F6 on filter F201.
D. Open valves 012 and 015 on the desired DI column to service the reactor.
E. Open valves F9 and F10 on outlet filter F203 (or valves F7 and F8 on outlet filter F202).
F. Remotely open valves 527E and 527F from the control room.
l Vent the DI column and the filters if they had been drained since the last system shutdown.
G. Turn on DI flow recorder; time and date same, h H. Start pump P513A.
I. Adjust for proper flow by throttling F201 outlet valve F4 and P513A bypass valve V515W. Insure that the pump discharge pressure does not exceed 110 psig.
Note: The bypass valve F5 shall remain closed except to check the condition of the filters.
VII.4.1.2 Placing the Pool Cleanup System in Service Service through DI column to deionized pool water is through F200, then downflow through DI column, out of DI column, through F204 or F205 and discharges approximately 3 feet below normal pool surface.
To place the pool cleanup system in service from a fully shutdown condition, carry out the following:
A. Insure all valves on the DI column are closed.
O Rev. App'd i, 3. SOP /VII-4 10/a1
B. Check the resin-filter log book and the status board to determine the exact status of all beds.
C. Open valves F1 and F3 on filter F200.
D. Open valves DIl and DI4 on the desired DI column to service the pool system.
E. Open valves Fil and F12 on outlet filter F204 (F13 and F14 on outlet filter F205).
F. Turn on DI flow recorder; time and date.
G. 1. If P508 is in service, normal operation, open V515T, I
close V515M.
- 2. If P508 is secured, open V515M, close V515T.
H. Start P513B.
I. Adjust for proper flow by throttling F200 outlet valve F1 and P513B bypass valve 515X.
Note: The inlet filter bypass valve F2 shall remain closed except to check the condition of the filters.
VII.4.2 Transferring Cleanup Services to the Standby DI Column If for any reason, such as high conductivity, the standby DI column need be placed on pool cleanup service, the following procedure shall be used. (See MURR Print 344 for valve identification.)
VII.4.2.1 Placing Standby DI Column on Pool Service (DPW)
Extreme care should be exercised when placing a DI column in parallel to insure proper valving and that the DI column has i been placed in standby in accordance with Section VII.4.6. ]
A. Insure all valves on the DI column are closed.
B. Check the resin-filter log book and the status board for the exact status and location of all resins.
C. Open valve DIl slowly on standby DI column.
D. Open valve DI4 slowly on standby DI column to place unit in parallel with on-line unit.
E. Close valves DIl and DI4 on unit to be secured.
Rev. 10/81 App'd . ib .. SOP /VII-5
F. Record in the resin-filter log boo < and the status board g the exact location and condition of all resin beds.
VII.4.2.2 Placing Standby DI Column on Reactor Service (DRW)
Extreme caution must be exercised to insure the column is not vented too rapidly which can cause a low pressure scram.
A. Insure all valves on the DI column are closed.
B. Check the resin-filter log book and the status board for the exact status and location of all resins.
C. Open valve 012 slightly on the standby DI column to allow tne pressure to equalize between the reactor cleanup loop and the DI column. Then open valve DI2 fully.
D. Slowly open valve DIS to place the standby unit in paral-lel with the operating unit.
E. Close valves DI2 and 015 on the unit to be secured.
F. Record in the resin-filter log book and the status board the exact location and condition of all resin beds. g VII.4.3 Resin Transfers Any time depleted resin is being transferred use OCW.
Any time regenerated resin is being transferred use DI.
VII.4.3.1 Resin Loading The T300 pump should be used during resin transfer and fast ]
rinses only. Sufficient flow should be available with gravity ]
flow from T300 for all other regeneration activities. ]
Each DI column will be loaded with a total of 12 cubic feet of resin which will be comprised of 7 cubic feet of anion resins and 5 cubic feet of cation resins. This resin will first be loaded into the regenerator where it will undergo a caustic and acid treatment to regenerate the resins. The resins will then be transferred in the form of a resin and h water slurry to its respective DI column.
Rev.10/81 Ap p ' d, j ' '/ . - SOP /VII-6 i
To load the resins into the regenerator, first educt the caution, then educt the anion. The cation level should be just above the acid header. Prior to educting resins into the regenerator, drain most of the excess water from the regener-ator to allow an increased educting flow rate. To properly educt resin into the regenerator, enough water must be added to the resin to create a slurry mixture. To educt:
A. Insure that all valves are closed on adjacent systems. ]
B. Connect the quick-disconnect hose to the DCW supply and open the master DCW valve.
C. Open valves RE7, RE3, RE18 at the regeneration station.
D. Open RE15, close RE16.
E. Open RE13 and RS.
F. Place the resin suction line in the slurry of resin and open valve RE12. Stir the resin in the container while it is being educted.
Note: If the eduction process stops (due to back-pressure in the regenerator from being full), secure the lineup by Q shutting RE13, RES, and RE12. Open RE9 and allow the regenerator to drain off water then proceed to step (F).
G. Repeat this process until the desired level of resin is obtained, then secure all valves.
H. To aid in filling the educting container for making a resin slurry, close RS, leave RE12 open and allow water to flow into the container via the educting line.
I. Once proper level of resin has been established, close RE7, open RE9, and allow the regenerator to fill until all resins are completely covered with water.
Note: Allowing the resins to become dry can destroy them.
J. Close all valves (RE9, RE13, RE12, RE15, DCW supply, RE8, RE18). See S0P VII.4.5.
VII.4.3.2 Resin Dump (From Regenerator R200)
O This operet40n snouid be hendied w4tn extreme cere because of the radiation levels which may be seen from the activated Rev. 10/81 App'd- -
SOP /VII-7
/ _
resin. Obtain an approved RWP and all equipment necessary.
Health Physics should be present during the operation with the proper radiation monitoring equipment. Also, care should be exercised with the handling and disposal of the resin and con-tainers. To flush resin from the regenerator, place the resin receivers beneath the resin dump line and:
A. Insure all valves are closed in adjoining systems.
- 8. Perform an air sparge as follows:
- 1. Open valves RE7, RE9 and RE15 and drain for 4 minutes.
- 2. Close valves RE7 and RE9.
- 3. Open valve RE25. ]
- 4. Open valves RE8 and RE10 to an air flow rate of 10-15 ]
cfm for 10 minutes, insuring a good loose mixture. ]
C. When securing the sparge, first close RE8 and allow the pressure to increase to 50-60 psig in the regenerator, then close RE10.
D. Crack open valve REll and allow the excess pressure in the unit to slowly force the resin into the containers. The g advantage of this procedure is the limited use of water.
It may be necessary to repressurize the unit or add more water to complete the dump.
E. When all the resin is out of the regenerator, close REll.
Open RE9 and allow the excess pressure to be vented from the regenerator.
F. Close all valves when finished (RE8, RE10, RE15, RE9, RE25).
G. Log in the resin log the exact status of the resin.
l 1
VII.4.3.3 Transferring Resin from a 01 Column to the Regenerator Caution: Prior to transferring resin, perform steps outlined in Section VII.4.3.9 (3H water drain) and VII.4.5.3 (air sparge).
TO INSURE A COMPLETE TRANSFER OF ALL RESIN, IT IS IMPERATIVE THAT A G000 SPARGE BE PERFORMED PRIOR TO TRANSFER. h Rev.10/81 App'd -
SOP /VII-8
A. Check that WT2 has sufficient capacity to accept transfer water.
B. Check the resin log and status board for exact location and status of all resins.
C. Check that all the regenerator and resin sluice line valves are closed.
D. Check closed all the valves on the DI column from which the resin is being transferred.
E. Check that valves DI3 and DI6 on the other two DI columns are closed. Open valve RE16.
F. Open valves DI3 and DI6 on the DI column to be trans-ferred. Open valves RE7 and R1. A flow path for the resin slurry is now established from the DI column to the regenerator. All that is needed now to transfer the resin is the admission of the water as a transport media.
G. Connect quick-disconnect hose to the DCW supply, open the master DCW valve. Open valve RE18 and then open valve R2 g which admits the water. Verify that the resin is flowing through the bullseye. Check to insure that there is no resin in the drain water.
H. When the transfer has been completed, close all the valves ]
opened above (DI3, DI6, RE7, R1, RE18, R2, RE16). ]
I. Make an entry in the resin-filter log and update the status board.
VII.4.3.4 Transfer of Resins from Regenerator to Standby DI Column To transfer regenerated resins, use DI supply water; if the resins are depleted, DCW may be used.
Verify adequate level in T300 >5000.
A. Check resin log and status board for exact location and
- condition of all resins.
B. Insure all valves closed on adjoining systems and DI O columns.
Rev. 10/81 Ap p ' d, C' ~~ S0P/VII-9
/-
/
C. Connect the quick-disconnect hose to the DI water supply.
Insure that the master 01 valve is closed.
D. Check valve 0113 open and valve DI14 closed. ]
E. Open valves RE3, RE18 and the master 01 supply valve. ]
F. Open valves 013 and DI9 on the DI column to receive the resin.
G. Slowly open valve R3 and allow the resin slurry to trans- ]
fer. Start T300 pump. (Verify resin flow in the bulls- ]
eye.) ]
H. When all resins are transferred, close valves DI9, DI3 and ]
R3. Shut off pump. The unit is now ready to be mixed and ]
filled as per Section VII.4.6. ]
I. Close all other valves, DI13, RE3, DI supply. ]
VII.4.3.5 Transfer of Resin from a DI Column to the Resin Storage Tank Caution: Prior to transferring recin, perform steps outlined in Section VII.4.3.9 (3H water drain) and VII.4.6.3 (air g sparge).
TO INSURE A COMPLETE TRANSFER OF ALL RESIN, IT IS IMPERATIVE THAT A GOOD SPARGE BE PERFORMED PRIOR TO TRANSFER.
A. Check the resin log and status board for exact location ]
and status of all resin. ]
B. Check that all regenerator, resin sluice line and resin ]
storage tank valves are closed. ]
C. Check closed valves DI3 and DI6 on the DI columns not ]
involved in the transfer. ]
D. Check valve DI13 open and valve DI14 closed. ]
E. Connect quick-disconnect hose connection to DCW supply and ]
open the master DCW valve RE27. ]
F. Open valves RS3 and RSS. Also open valves DI3 and DI6 on ]
the 01 column being transferred. ]
G. Open valve RE18 and then open valve R2 and verify flow of ]
resin through the bullseye. ]
H. When the transfer has been completed, close all valves ]$
opened above (DI3, DI6, R2, 0113, RS3, RSS, RE18, RE27). ]
Rev. 10/81 App'd b x SOP /VII-10
I. Make an entry in the resin-filter log and update the ]
status board. ]
VII.4.3.6 Transfer of Resin from the Resin Storage Tank to the Regenerator A. Check the level of WT2 to insure it has sufficient capa-city available.
B. Check the resin log and status board for the exact loca-tion and status of all resin.
C. Check that all regenerator, resin sluice line and resin storage tank valves are closed.
D. Check closed valves DI3 and DI6 on all DI columns. Open valve RE16; close RE15.
E. Open valves RE7, R1, RS2 and RS7.
F. Connect the quick-disconnect hose connection to the DCW supply and open the master DCW valve (RE27).
G. Open valve RE18 and open R2. Verify a flow of resin through the bullseye.
Q H. When the transfer has been completed, close all valves ]
opened above (RE7, RE16, RE18, R1, R2, RS2, RS7, RE27). ]
I. Make an entry in the resin-filter log and update the status board.
I VII.4.3.7 Transfer of Resin from the Regenerator to the Resin Storage Tank A. Check the resin log and status board for exact location and status of all resins.
! B. Check that all regenerator, resin sluice line and resin storage tank valves are closed.
C. Check that valves DI3 and DI6 on all DI columns are closed.
D. Check valve DI13 open, valve DI14 closed.
E. Open valves R3, RS2 and RSS.
'O Rev. 10/81 App 'd - - SOP /VII-11
F. 1. If resin to be transferred has been regenerated,
- a. Connect the quick-disconnect hose to the master DI supply,
- b. Verify adequate level in T300 ~ 5000 gallons,
- c. Open the master DI water valve. ]
- d. Start T300 pump. ]
- 2. If the resin is depleted, ]
- a. Connect the quick-disconnect hose to the master ]
DCW supply and open the master DCW valve. ]
G. Open valve RE18 and then open RE3 to transfer the resin ]
slurry. Verify resin flow in the bullseye. ]
H. When the resin has been transferred, close all the valves ]
opened above (RE3, RE18, R3, RS2, RSS and master water ]
supply), and shut T300 pump off if used. ]
I. Make an entry in the resin-filter log and update the ]
status board. ]
VII.4.3.8 Transfer of Resin from the Resin Storage Tank to a DI Column g A. Check the resin log and status board for exact location ]
and status of all resins. ]
B. Check that all regenerator, resin sluice line, and resin storage tank valves are closed.
C. Check closed valves DI3 and 016 on the 01 columns not in-volved in the transfer.
D. Check valve 0113 open and valve DI14 closed.
E. Open valves RS3, RS6, R1 and RS.
F. Open valves 013 and 019 on the DI column to receive the resin.
- 1. If resin to be transferred has been regenerated, l
- a. Connect the quick-disconnect hose to the master DI l
supply.
- b. Verify adequate level in T300. Open DI master supply valve.
l C. Open the master DI water valve. ]h
- d. Start T300 pump. ]
Rev. 10/81 App'd b SOP /VII-12
O THIS PAGE INTENTIONALLY LEFT BLANK )
i O
O Rev.10/81 App'd I'- SOP /VII-13 y
- 2. If the resin is depleted,
- a. Connect the quick-disconnect hose to the master 9 DCW supply and open the master DCW valve.
Open valve RE18 and then open RE13. Verify the flow of ]
resin through the applicable bullseye. Whan the resin has ]
been transferred, close all of the valves opened above ]
(R1, RS3, RS6, D113, DI3, DI9, RE18, RE13, RS, and master ]
water supply valve), and shut T300 pump off if used. Make ]
an entry in the resin-filter log and update the status ]
board. ]
VII.4.3.9 Collection of DI Column Water Containing Tritium (3H)
DI columns which have been on pool or primary service will contain water with a large concentration of tritium. As soon as these beds come off service, transfer the 3H water to the DCT and refill with DI water by carrying out the following procedure, g Note: Air supply valves to each of the DI columns (vent) are labeled as follows: 01200, valve DIl0; DI201, valve Dill; DI202, valve DI12. All other valves have the same numbering sequence on each DI column.
A. Check the status and operability of the primary / pool drain collection system. If necessary, pump down the collection tank.
B. Check the resin-filter log and status board for exact lo-cation and status of all resins.
C. Check all valves closed on the respective DI column re-generator R200 and storage tank.
D. Check all valves closed on other DI columns except DIl and DI4 on the pool service unit, DI2 and DIS on the reactor service unit.
E. To insure all 3H water is transferred, the bed will be filled and flushed with DI water.
O Rev. 10/81 App'd h . S00/VII-14
- 1. Connect the quick-disconnect hose to the master DI ]
supply. ]
- 2. Verify adequate level in T300 ~ 5000 gallons. ]
- 3. Open DI valve. ]
F. Open air valve RE25, bleed any oil or water from the air line via valve RE52. Adjust air regulator to 50 psig.
Nofity the reactor control room of intentions to begin the transferring of water to the drain collection tank.
G. Check valve DI13 closed.
H. Open valve DI9.
I. Open valve DIl0 (01200) or Dill (D1201) or DI12 (D202) de-pending on column to be transferred, to pressurize the DI col umn.
J. Slowly open DI14 to commence the transfer; monitor the transfer at the bullseye.
K. When transfer is complete, close DI14, close DIl0, Dill, or DI12 respectively.
O t. . 09ea oI8 eaa veat e11 pressure fro ene coiu a. The column will now be refilled and flushed two times by the following procedure.
- 1. Open the DI supply, valves RE18 and 013. Insure DI8 open.
- 2. Open R2 and fill the respective DI column with DI water until it starts to exit via DI8.
- 3. Close R2, DI8, DI3. This flush water will now be transferred to the primary / pool collection tank.
- 4. Check D113 closed and DI9 open.
- 5. Open valve DIl0 (DI200) or Dill (01201) or DI12 (01202) to pressurize the DI column.
- 6. Slowly open 0114 and monitor the transfer until all water has been transferred. Repeat the process for the second flush.
- 7. Close DI14, DI9, DIl0, Dill or DI12.
- 8. Open DI8 and vent all the pressure from the column.
Caution: It is extremely important that valve DI14 be closed after the transfer of DI water to the drain Rev. 10/81 App'd b - SOP /VII-15
[. '
collection system. Failure to close this valve before proceeding further could result in the addition of raw water to the drain collection system.
The unit now needs to be refilled; NEVER LEAVE IT DRY.
M. Open 013.
N. Open R2 and refill the column until water starts to exit via 018.
O. Close R2, DI3, and DI8.
P. Close all other valves opened (DI supply, RE18).
Q. Log in the resin log the exact status of the DI column.
The DI column is now ready for transfer.
VII.4.4 Preparation of Regenerate Solutions Required by Regeneration VII.4.4.1 Acid Regenerate Selections for Regeneration A. Determine the required draws.
B. Fill mixing tank to proper water level for the required g draws.
C. Add acid via the measuring tank for the required draws.
VII.4.4.2 Acid Solution Strength A. Specific gravity should be 1.172 @ 66*F. ]
l VII.4.4.3 Caustic Regenerate Solutions for Regeneration l
l A. Determine the required draws. ]
B. Fill mixing tank to proper water level for the required ]
draws. ]
C. Add acid via the measuring tank for the required draws. ]
VII.4.4.4 Caustic Solution Strength A. Specific gravity should be 1.275. ]h Rev.10/81 App'd. ' - SOP /VII-16
O\S C+ V CA V 'X \ G \ S~~L C
~O Av s
~"
200
~
J .
= E 2 S Oz, HO 2
IDRAW 7. 5 gal 37.5 gal 2 DR AWS 15 gal 75 gal
, 3 DRAWS 22.5 gal !!2.5 gal o D 300 ,.
I DRAW 15 gal 75 gal 2 DRAWS 30 gal 15 0 gal !
3 DRAWS 45 gal 225 gal !
1 l .
SPECIFIC GRAVITY 117 2
~
- \ O~E
- ALWAYS ADD ACID TO WATER
'o Rev. 6/80 App' #g- 50P/VII 17
CHEV CA_ V X \'G \lS~~RLC O\S e
C AJ S , 'C -
J'2C0 .
50 lb bag HO 2
l] RAW 3 bags 50 gal 2 DRAWS 6 bags IOO gah 3 ;JRAWS 9 aags' 15 0 gal l
J 300 -
e'
~
I DRAW 44 bags 75 ga:
15 0 ga:
2 DRAWS 8Vz bags 3 DRAWS 12F+ bags 225 gd l .
l S?ECIFIC GRAVITY 1275 N
~ ^~
VII.4.4.5 Mixing of Caustic Soda Regenerate Solution f]
Note: USE PROTECTIVE EQUIPMENT WHEN MIXING CHEMICALS. The ]
caustic tank volume is 10 gallons per inch. To mix an 8N sol- ]
ution, add 25 lbs. of mercury cell grade Na0H to each inch of ]
water. ]
A. Add the necessary volume of DCW by opening the DCW tank ]
supply valve. ]
B. Add the necessary volume of Na0H in small volumes. ]
VII.4.5 Resin Regeneration: Deionizer 200 Series Prior to operating any valves on any part of the 200 series units:
A. Check the resin-filter log and the status board to deter-mine the exact location and status of all resin beds.
B. Check all valves closed except those valves in service on O tne on-iine al coiumns.
C. Check WT2 level to insure it has sufficient capacity to accept the effluents.
D. Check the status of 01300 and the level of T300 to prevent ]
a situation of low level with a depleted 01300. Do not ]
regenerate with less than 5000 gallons in T300. ]
E. Check that the solubridge is off to prevent damage to the conductivity cell.
VII.4.5.1 Sodium Chloride (Nacl) Treatment of 200 Series Resin Beds Normal operation of the DI system introduces in the anion resin (C0 3) carbonates which are not exchanged in the normal (Na0H) sodium hydroxide regeneration. A Nacl treatment will remove the carbonates and may be performed, if deemed neces-sary, prior to a regeneration with the normal acid and caustic treatment. The Nacl treatment is performed with a 4-5". solu-tion of Nacl at temperatures of 100-110 F.
Rev. 10/81 App' Ib SOP /VII-19
/
A. Check the resin-filter log and status board for the exact g location and status of all resins. Check that WT2 has sufficient capacity for the treatment.
B. Check that all regenerator resin sluice line and resin storage tank valves are closed.
C. Check closed all valves except those valves in service on the DI columns.
D. Insure conductivity solubridge is turned off.
E. Connect the quick-disconnect hose to the DCW/DHW line.
F. Open valves RE17, RE2, RE7, RE16; check closed RE15.
G. Open valves RE27 and RE28 to obtain a combined flow rate of 6-6 gpm at a temperature of 100-110*F. Continuously monitor the temperature to insure it does not exceed 110 F.
Caution: 1. The resin can b1 damaged by excessive tem-peratures (>140 F).
- 2. Insure that the hot water treatment heatup rate is slow enough to avoid thermal shock h to the resin.
H. Allow a heatup time long enough to insure the entire resin bed is at the desired temperature (outlet temperature of water should be 100-110 F). While the resin column is being warmed to desired treatment temperatures, a 20% Nacl solution may be mixed for the treatment, j I. place a " clean" 55 gallon drum beneath the Nacl suction i line.
J. Fill the drum with approximately 50 gallons of water at a l
temperature of 100-110 F.
K. Add 50 lbs. of sodium chloride (Nacl), stir and insure Nacl goes into solution. With the resin bed at the de-sired treatment temperature and the Nacl mixed, commence the treatment.
L. Secure the heatup flow by closing RE17, close RE16, open RE15 and RE9 to allow the column to drain for 4 minutes to create an expansion chamber at the top of the regenerator.
This will help prevent an excessive pressure buildup.
Rev.10/81 App'd M -
SOP /VII-20
(] M. After draining for 4 minutes, close RE15 and RE9, open RE16 and RE17 and re-establish a flow rate of 5-6 gpm at 100-110*F.
Note: Excessive gas volume may build up, and may be vented by opening RE9.
N. Open and throttle valve RE55 to educt Nacl to the resin at a rate of 3/4-7/8 inch per minute (1.2-1.4 gpm) for 40 minutes. Continually observe the resin column for indica-tion of offgasing; observe the draw down rate, the eductor flow and maintain proper temperatures. The temperature, flow rates, and peracentage of Nacl must remain within their limits to obtain the desired results.
O. After the i.otal volume of 20% Nacl solution has been educted, close valve RE55 and allow the bed to rinse for a minimum of 40 minutes. If, however, at the end of the treatment excessive offgasing is still being observed, re-peat the procedure after the 40 minute rinse with another O 50 lbs. of NeCi 8y rePeetia9 stens a throu9h 0. If off-gasing is not observed, proceed with step P.
P. Close DHW valve RE28, RE17 and RE2. Open RE18 and open RE3 for a 25-30 gpm flow. Allow the bed to rise an addi-tional 30 minutes.
Q. Close valves RE27, RE18, RE3, RE7, RE16 to complete the Nacl treatment.
R. Log in the resin-filter log the exact status and location of all resin beds.
VII.4.5.2 Backwash A. Connect the quick-disconnect hose to the DCW supply and open the master DCW supply valve (RE27).
B. Open valve RE18.
C. Open valve RE8 and RE16; close RE15.
D. Open valve RE4 gradually to give a flow rate of 15 gpm.
Rev. 10/81 Ap p ' d /,h,o - SOP /V11-21
(
l
E. During the backwash, frequently inspect through the sight g glass to insure that proper separation is being achieved.
It may be necessary to vary the flow rate to obtain a good separation.
F. Backwash for 30 minutes minimum.
G. Close valves RE8, RE4, RE18, RE27, and RE16. ]
Note: Periodic hot water regenerations may be necessary to remove silicates which are not removed during cold water regenerations.
VII.4.5.3 Caustic Soda Treatment A. Open the master DCW supply valve RE27 and open RE18.
B. Secure the solubridge.
C. Open RE2, RE7 and RE16. Close RE15.
D. Open RE17 and adjust flow rate to 7 gpm.
E. Close breaker on MCC2 for caustic pump.
F. Open caustic pump suction and discharge valve. $
G. Check closed RE61, RE63, RE66 and RE67.
H. Open RE6 and RE65. ]
I. Start pump and timer with pushbutton on control panel. ]
J. Throttle RE64 to maintain caustic flow of 1.25 gpm for 40 ]
minutes. ]
K. Ten minute rinse between draws. ]
L. To prevent caustic eduction during rinse, close RE6. ]
M. Open RE6. ]
l N. When last caustic draw is completed, close RE6, RE64 and ]
I RE65 and let unit rinse as is for 30 minutes. ]
- 0. Secure the caustic pump at MCC2 and close its discharge ]
valve. ]
P. After 30 minutes, close RE17, RE2 and RE7; secure DCW. ]
VII.4.5.4 Caustic Fast Rinse A. Open RE18, RE3, DI water supply from T300 pamp, and RE7. ]h B. Turn on T300 pump. ]
Rev.10/81 App'd , y w - SOP /VII-22
\
C C. Throttle to 30-35 gpm. ]
D. Check closed RE2 and RE17. ]
E. Monitor the rinse by performing an alkalinity test as per ]
"F" listed below. ]
F. Alkalinity Test: Obtain a 58.3 ml sample from RE23 of ]
rinse water, add 2-3 drops of methyl orange indicator. ]
While stirring, add 0.4N sulfuric acid, one drop at a ]
time, until color changes from yellow to permanent faint ]
pink or red. Each drop of acid solution equals 1 grain ]
per gallon (17.1 parts per million, ppm) of alkalinity. ]
At a resistance of 25K ohms, the alkalinity will be one ]
grain or less. ]
Note: If the solubridge is used to check the conductivity ]
of the rinse water, it must be turned off before the acid ]
draw to prevent damage to the cell. ]
G. Close valves RE3, RE7 and RE18. ]
O V H. Close the DI supply valve and RE16. ]
1 VII.4.5.5 Intermediate Backwash ]
Inspect the resin through the sight glasses for proper separa- ]
tion. If the resin has not been properly separated, proceed ]
with a DI water backwash for 10 minutes as per VII.4.5.2. ]
When the separation is adequate, proceed with step VII.4.5.6. ]
Sulfuric Acid Treatment ]
VII.4.5.6 A. Switch disconnect to DI water. ]
- 8. Open DI supply valve. ]
C. Secure solubridge. ]
D. Open RE3, RE7 af.d RE16. ]
E. Adjust RE19 for 3 gpm downflow. ]
F. Open RE1 and RE14. ]
G. Adjust RE17 for 4-5 gpm and vent the acid vent tank until ]
full of water. ]
Rev.10/81 Ap p ' d '.b % SOP /VII-23
H. Check shut RE56, RE59, RE60 and RE62. ]g I. Open acid pump isolation valves and close its breaker on ]
MCC2. ]
J. Open RES and RE58. ]
K. Start acid pump and timer at control panel . ]
L. Throttle RE57 for 1.5 gpm for 30 minutes. ]
M. Monitor the vent tank while the acid treatment is in prog- ]
ress to insure air does not pass through to the regener- ]
ator. It may be necessary to vent excess air from the ]
vent tank during the treatment. ]
N. When the acid injection is completed, close valve RES and ]
RE58 immediately. ]
- 0. After each draw, rinse for 10 minutes. ]
P. Open RES and RE58 for next draw. ]
Caution: Do not allow air to be injected into the re- ]
generator during the acid treatment. Air bubbles will ]
carry acid up into the anion resin and reduce its capa- ]
city. ]h Q. Continue rinsing without changing the valve lineup for 30 ]
minutes. ]
R. Close the acid pump suction and discharge valves, secure ]
the pump's electrical power at MCC2 and thoroughly rinse ]
the acid pump with DCW inside and out. ]
S. Close RE57. ]
VII.4.5.7 Acid Fast Rinse A. Open DI supply valve. ]
B. Open RE18 for maximun flow. ]
C. Start T300 pump. ]
- 0. Throttle RE18 flow to 30-35 gpm. ]
E. Close RE1 and RE14. Then drain the acid vent tank and re- ]
fill through REl. ]
F. Close RE17 and RE19.
]O Rev.10/81 App'd (- SOP /VII-24
C) G. Monitor the rinse by performing an acidity test as per ]
VII.4.5.8. Rinse until the acidity is less than 1 grain ]
or until the resistance measured is 25K. ]
H. Close RE3, RE7, RE16 and RE18. ]
I. Close the DI water supply valve; shut T300 pump off. ]
VII.4.5.8 Acidity Test Obtain a 58.3 mi sample of rinse water; add 2-3 drops of ]
methyl orange indicator. While stirring, add 0.4N sodium hy- ]
droxide (l'a0H), one drop at a time, until the color changes ]
from pink to permanent yellow. Each drop of Na0H solution ]
equals 1 grain per gallon (17.1 ppm) of acidity. A resistance ]
of 25K will be equal to 1 grain or less of acidity. ]
VII.4.5.9 Mixing Resins by Sparging O prior to sparging, open RE25, then open the air bleed valve j RE52 and blow any oil or water from the air supply line. ]
A. Open RE7, RE9 and RE15 and let the water drain for 4 ]
minutes. ]
B. Close valves RE7 and RE9. ]
C. Open valve RE8. ]
- 0. Open valve RE10 slowly to give 15 cubic feet / minute of ]
compressed air at 50 psig. A brisk bubbling sound should ]
be heard from within the tank. Sparge for 10 minutes. ]
Note: If a brisk bubbling is not heard, ]
- 1. Close valve RE10. ]
- 2. Add 20-25 gallons of water via RE4. Connect the ]
quick-disconnect hose to the DI supply, open the ]
master DI valve and open RE19. ]
- 3. After water is added, close RE19, RE4 and DI valve and ]
then repeat step D above. ]
Note: If the water level is too high, water will be ]
forced out via valve RE8. Proceed with the following. ]
- 1. Close valves RE8 and RE10. ] ,
Rev.10/81 App'd ^w SOP /VII-25 c
- 2. Open valves RE7 and RE9 and drain for an additional 2 ]g minutes. ]
- 3. Close valves RE7 and RE9. ]
- 4. Open RE8 and RE10 as per "C" and "D" of VII.4.5.9. ]
E. Close RE8, RE10 and RE15. ]
VII.4.5.10 Water Fill of Regenerator A. Connect the quick-disconnect hose to the DI line, and open ]
the DI supply valve. ]
B. Open valve RE9. ]
C. Open valve RE19. ]
D. Open valve RE3 and slowly fill the regenerator at approxi- ]
mately 5 gpm until water vents via valve RE9. ]
E. Close RE9, RE19 and RE8 if continuing to next step (RE3, ]
RE18,DImaster). ]
VII.4.5.11 Resin Transfer After Regeneration h i
Transfer the regenerated bed to the standby DI column by the ]
]
l procedure in paragraph VII.4.3.4.
VII.4.6 Placing a 01 Column in Standby Af ter completing the transfer to a DI column, the unit shall ]
be placed in standby by air sparging the column, draining, and ]
refilling with DI water. ]
VII.4.6.1 Refilling with DI Water Care must be exercised to insure a proper water level is ob- ]
tained prior to an air sparge. If the water level is too ]
high, water and resin can be discharged through the unscreened ]
vent line. Insufficient water may result in the bed not being ]
properly mixed. To insure the proper water level, the bed is ]
first filled with DI water, then drained for 4 minutes by the ]
following procedure. ]
Rev.10/81 App'd 2 : SOP /VII-26
l l
O l
THIS PAGE INTENTIONALLY LEFT BLANK O
O Rev. 10/81 App'd d* \ SOP /VII-27
/l
A. Check that all valves are closed on adjoining systems, g B. Open momentarily RE68 to vent the pressure off the flex-ible hose and connect the quick-disconnect hose to the master DI supply line.
C. Verify adequate level in T300.
D. Open the master DI water supply valve, open valve RE18.
E. Open DI3 and DI8 on the respective DI column.
F. Open R2 and allow the DI column to fill slowly ~ 10 gpm.
G. When water flows from the column vent line, close R2 and DI3.
The column is now full of water and ready to be partially drained for the sparge.
VII.4.6.2 Air Sparging Procedure ]
A. Open DI8, DI9 and DI13 and drain excess water from the DI ]
column for 4 minutes, then close DI9 and 0113. ]
B. The DI column should now have the proper water level for ]h air sparging. ]
C. Open the master air valve RE25 and bleed excess moisture ]
from the air line via RE52. ]
D. Open DI7 and allow the air to mix the resin gently at a ]
flow rate of about 10 cfm at 50 psig. ]
l Note: If water flows from the vent line or if a brisk ]
bubbling sound is not heard, close all valves and repeat ]
the procedure of Section VII.4.6.1 ]
E. Sparge the DI column for 10 minutes and then close DI7 ]
slowly, then close RE25. ]
l F. To refill DI column, open R2 and RE18. ]
G. Slowly open DI3 and add water to the DI column at a rate ]
of 5 gpm. Caution must be exercised during the refilling ]
to prevent disturbing and separating the resin. ]
H. When the unit is full (water coming out the vent line), ]
close DI8. ]
I. Open DI9 and 0113 fully to rinse to the drain for approxi- ]
l mately 5 minutes. ]
Rev .10/81 App'd SOP /VII-28
After rinsing, close DI9 and 0113 and open DI8 slowly to ]
Q J.
insure the unit is completely full. ]
K. Close all valves (DI8, R2, RE18, RE25, and DI supply and ]
DI3). Record the status of all resin beds and columns in ]
the resin-filter log and bring the status board up to ]
date. ]
The unit has now been regenerated, mixed, refilled and is now ]
considered to be in standby. To place in service, see the ]
proper procedure VII.4.2. ]
VII.4.7 Resin Regeneration: DI300 VII.4.7.1 DI Unit Description DI300 is a 300 gallon tank with 14 cubic feet of anion and 10 cubic feet of cation resins. It is used to supply deionized water to make up tank T300 and directly to 01200 for regenera-O tion operations. T300 sunniles makeun to the primery and pool systems and deionized water to the laboratories and water for DI200 regeneration.
VII.4.7.2 Filters The DI300 unit has a filter unit (F300) on the inlet to DI300 and a filter unit (F301) on the outlet to T300. Each unit is loaded with six 5-micron filter elements.
VII.4.7.3 Volumes of Regenerate Solutions Required H2SO4: 90 gallons of 6 normal solution (see mixing instruc- ]
tion sheet). ]
Na0H: 75 gallons total of 8 normal solution (see mixing in- ]
struction sheet). ]
VII.4.8 Regeneration Procedure i
Rev. 10/81 App'd , c4m S0P/VII-29
c VII.4.8.1 Regenerate Mixing Instructions g See Sections VII.4.6.2 and VII.4.6.5.
CLOSE VALVE 7 AND THE OUTLET VALVE 13 ON F301 TO ISOLATE T300 FROM DI UNIT DURING REGENERATION.
Insure R200-T300 isolation valves R30 and R31 are closed.
Note: Insure that the solubridge is off during the acid and caustic draws and during the initial (displacement) rinses after each draw. Power to the cell during these periods could damage the cell.
VII.4.8.2 Sodium Chloride (NaC1) Treatment of DI300 ]
The capacity of DI300 frequently decreases over time due to ]
fouling of the anion resin with carbonates (C03) which are not ]
exchanged in the normal (NaOH) sodium hydroxide treatment. A ]
Nacl treatment will remove the carbonates and shall be per- ]
formed after a performance analysis on the bed indicates a ]$
significant reduction in capacity. The Nacl treatment is per- ]
formed with a solution of Nacl at temperatures of 100-110 F. ]
A. Insure conductivity solubridge is turned off. ]
B. Check closed valves 1, 3, 4, 6, 7, 8, 9, 10, 11, 12, 13, ]
14, 17, 18, and 19. ]
i C. Check T300 supply valve RE31 and R200 supply valve RE30 ]
both closed. ]
- 0. Open valves 2 and 5. ]
l E. Throttle valves 15 and 16 to a flow rate of 10-12 gpm at ]
100-110 F. Continue to heat up the resin bed until the ]
effluent is a minimum of 100*F. While the resin column is ]
being warmed to desired treatment temperature, a 207. Nacl ]
solution may be mixed for the treatment. ]
l F. Mix in a clean 55 gallon drum 50 lbs. of Nacl to obtain ]
about 50 gallons of solution at a temperature of 100-110 F ]
(insure all Nacl in solution). ]
Note: Mix Nacl in barrel placed on landing above DI300. ]
l l Rev.10/81 App'dM~- SOP /VII-30
$I
O G. With the resin bed at desired temperature, commeiice dump- ]
ing Nacl by throttling valve D120 to obtain a drawdown ]
rate of 1-1/2 to 1-3/4" per minute (2.4-2.8 gpm) for 20 ]
minutes. ]
As the draw rate continues, observe the mixing flow to be 10- ]
12 gpm at 100-110 F. After the first barrel of 20% solution ]
is dumped, close valve DI20, continue slow warm rinse, mixing ]
a second barrel of 20% solution as per step F. ]
H. Repeat step G, then proceed to step H. ]
I. After the second barrel of Nacl has been educted, secure ]
valve D120 and allow to slow rinse at 10-12 gpm and 100- ]
110*F for 20 minutes. ]
Note: Should it become difficult to dump, open valve 10 ]
and vent any collected gases. The bed may require venting ]
many times due to the C03 displacement. ]
J. Close DHW valve 16. ]
K. Open valve 1 to 25-30 gpm and allow to rinse excess Nacl ]
O out for 30 miautes. 3 L. Close valve 2. ]
M. After final rinse is complete, close valves 1 and 5. Re- ]
move garden hose and store barrel. ]
VII.4.8.3 Backwash A. Check all valves closed.
B. Open master stop valve in DCW supply line.
C. Open valve 4.
D. Open valve 3 gradually (over a period of about one minute) to give a flow of about 18 gpm.
E. Backwash for 30 minutes minimum.
F. Close valve 3 and 4.
VII.4,8.4 Caustic Soda Treataent A. Insure that there is caustic soda mixed according to ]
Section VII.4.6.5. ]
Rev.10/81 App'd h w SOP /VII-31 y :
B. Close the caustic pump breaker at MCC2 (if sufficient flow g can be maintained without it, the pump may be left off) and open the pump suction and discharge valves.
C. Check valves RE63, RE61, RE6, RE66, RE64, RE65 and RE67 closed.
D. Open valve 5 and then valve 2 to give a flow of 7-8 gpm.
Now open valve 6.
E. Open valves RE64, RE65 and RE67 to inject caustic solu-tion.
F. Turn on the caustic pump with the pushbutton on the control panel at the 01200 station. The pump will run for 30 minutes automatically. The caustic draw can be accomp-lished without the pump if the pump is not operable. If the pump is not used, manually time the caustic draw for 30 minutes. The preferred method of doing the draw is to use the pump because the flow control is much more stable with the pump on.
G. Maintain caustic flow at 2.5 gpm using RE65 (about 1/a g inch per minute of ta'nk level) for a total draw of 75 gallons (7.5 inches of level).
H. When the caustic injection is complete, close valve 6, RE64, RE65 and RE67. Let the unit rinse for 30 minutes.
I. Secure the breaker for the caustic pump at MCC2.
Note: The strength of the effluent regenerate can be de-termined by either measuring the specific gravity (1.0428 to 1.0869) or the normality (1.2 to 1.8) which is a 4-8%
Na0H solution.
711.4.8.5 Caustic Soda, Fast Rinse A. Close valve 2.
B. Open valve 1 to give a ficw of 30 gpm.
C. Rinse until the rinse water tests 10 to 12 grains of alka-linity above that of the DCW supply. Do not rinse for more than 1-1/4 hours total . h
- 0. Close valves 1 and 5.
Rev.10/81 App'd 'hm SOP /VII-32
(7 VII.4.8.6 Alkalinity Test u.)
To test alkalinity of the DCW supply or the rinse water, ob-tain a 58.3 cc sample of the water and add 2-3 drops of methyl orange indicator. While stirring, add 0.4 normal sulfuric acid solution, one drop at a time until the color changes from yellow to pink or red. Each drop of acid solution equals 1 grain per gallon (17.1 ppm) of alkalinity.
VII.4.8.7 Acid Solution Treatment A. Insure that about 12 inches of acid is mixed according to section VII.4.6.3.
B. Check that the acid pump hose connections are closed and open the suction and discharge valves. Close the acid pump breaker at MCC2 (if sufficient flow can be maintained without it, the pump may be left off).
O C. Check RE58. RE59. aes2. ae57. RE58 ead RE80 closed.
D. Open valve 5 fully and open valve 8 to give a flow of 8.5 gpm.
E. Open valve 11 to give a 2-3 gpm increase in flow. Now open valve 9.
F. Open valves RE57, RE58 and RE60 to inject acid solution.
G. Turn on the acid pump with the pushbutton on the control panel at DI200 station. The pump will automatically shut off in 30 minutes. The acid draw can be accomplished without the pump if the pump is not operable. If the pump is not used, manually time the draw for 30 minutes. The preferred method of doing the draw is to use the pump be-cause the flow control is much more stable with the pump on.
H. Maintain acid flow at 3 gpm with RE58 which should cor-respond to about 1/4 inch per minute of tank level for a total draw of 90 gallons (7.5 inches of level).
I. When the acid injection is complete, close RE57, RE58 and RE60 and then close 9. Let rinse for 30 minutes.
Rev. 10/81 App'd, l6- S0P/VII-33 i V
J. Open the acid pump breaker at MCC2, close the suction and g discharge valves and flush the acid pump thoroughly with DCW.
Note: The strength of the effluent regenerate can be de-termined by either measuring the specific gravity (1.025-1.052) or the normality (1.01-1.6) either of which is equivalent to a 4-8% H 2SO4 solution.
VII.4.8.8 Acid Fast Rinse A. Close valves 8 and 11.
B. Open valve 1 to give a flow of 30 gpm. Rinse until rinse water tests 1 grain per gallon or less of acidity (see Section VII.4.8.9). Do not rinse for more than 40 minutes.
C. Close valves 1 and 5.
VII.4.8.9 Acidity Test $
Obtain a 58.3 cc sample of the regenerate effluent and add 2-3 drops of methyl orange indicator. While stirring, add 0.4 normal sodium hydroxide (Na0H), one drop at a time until color changes from pink to yellow. Each drop of sodium hydroxide solution equals 1 grain per gallon (17.1 ppm) of acidity.
VII.4.8.10 Mixing Resins A. Open valves 4 and 5.
B. Open valve 10 fully and let water drain for 4 minutes.
C. Close valves 4 and 5.
D. Open valve 12 slowly to give 20 cubic feet per minute of air at 50 psi. (A brisk bubbling sound should be heard from within the tank.) Let the air mix the resins for 15 minutes.
E. Close valve 12. h Rev. 10/81 d _
SOP /VII-34 App'9
VII.4.8.11 Water Refill
(]~
A. Open valve 1 to give a flow of 22 gpm maximum.
B. Let the water fill the tank until it flows from the vent line.
C. Close valves 1 and 10.
VII.4.8.12 Resistivity Check A. Check valve 3 closed.
B. Open valve 5.
C. Open valve 1 to give a flow of 30 gpm.
Note: Rinse only long enough to obtain an increase in re-sistance. If it stops, repeat VII.4.8.10; varying the flow rate may also help the rinse requirement. Use mini-mum DCW for rinse.
D. Let the water run to waste until the purity instrument ,
O E.
shows a minimum resistivity of 500K ohms.
Close all valves, then open the outlet valve on F301.
F. The demineralizer is now ready for use.
G. Log regeneration complete.
VII.4.8.13 Providing DI Water to T300 DI water may be sent to T300 with or without the use of the reverse osmosis unit as a 01300 makeup supply. Due to the fact that DCW, after passing through the R.0. Unit, is much more pure than raw DCW, the R.0. Unit is normally utilized to prolong the life of the DI300 resin regeneration. However, there are provisions for bypassing the R.0. Unit when sending DI300 water directly to 01200 (see VII.4.8.13a, b, and c).
VII.4.8.13a Providing DI Water to T300 with Reverse Osmosis Makeup A. Check shut valve 7 and open R08.
B. Open T300 supply valve (Reach Rod).
1 I '
Rev. 10/81 App'd[b- S0P/VII-35
/
C. Open isolation valve for auto valve.
Turn on conductivity meter and place auto valve in auto.
g D.
Caution: Auto valve should be open, if not or if reading is near set point, place normal, bypass switch to bypass.
(This is so the R.0. Unit will not cycle on and off as the auto valve opens and closes. When the reading on the con-ductivity meter is low so the valves do not cycle, place normal, bypass switch to normal .)
E. Place R.0. Unit in operate mode and push start / reset switch. (Pressure should come up to 180-200 psig.)
_TO SECURE SENDING WATER A. Place R.0. Unit in STANDBY.
B. Close R08, T300 supply valve, and isolation valve for auto valve.
Caution: The following valves should be left open while the unit is in STANDBY Mode.
R02 g R05 DI300 DCW Supply Valve When the unit is not in use, 00 NOT TURN OFF - PLACE IN STANDBY ONLY. O_0_ NOT SECURE SUPPLY WATER.
Note: If for any reason the unit must be turned off or the supply water secured, this condition MUST NOT exist for more l than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or damage will occur to the filter membranes (see technical manual for details).
Normally, the water inlet temperature will not require ad-j justment and is set at approximately 25 C. Allow at least 30 j minutes of running time to stabilize temperature prior to de-termining if an adjustment is needed.
No regular maintenance is required to operate this unit.
For any repair or maintenance, refer to the technical manual.
O YYe fw% *O
VII.4.8.13b Providing DI Water to T300 Without Reverse Osmosis Unit Makeup A. Check valve 3 closed.
B. Open valve 1, open the T300 supply valve RE31.
C. Check valve 7 closed and place the low conductivity cutout circuit into operation using the procedure posted at the DI300 station.
D. Record the resistivity and water meter readings on the log.
E. Insure that the resistivity reading does not drop below 500K ohrns while making water for T300.
F. Upon completion of making DI water, log the resistivity and water meter readings on the log. Close master T300 valve, close valves 1 and 17. If the low conductivity cutout circuit was used, secure it.
G. If the resistivity drops to 500K ohms, the life of the bed can sometimes be extended by following steps VII.4.8.10 through VII.4.8.12. _
O H. When the resistivity reading cannot be brought above I00v.
ohms, it is necessary to regenerate the unit. " -
O d t.^ - SOP /VII-37 Rev.10/81 App'6
VII.5 Skimmer System g
V t I . 5.1 Normal Startup of the Skimmer System The scimmer system is operated to remove floating debris from the pool at the normal operating level. If necessary, it is also possible to operate this system with the pool at refuel level by securing the skimmer box with valve 548A and recirculating the water with suction taken through valve 548B from approximately 1 foot below the refuel level.
The skimmer system is put into routine operation according to the following procedure:
A. Verify that no maintenance has been performed on the skimmer system since the last shutdown of the system. If maintenance has been performed on the system, verify that a system valve lineup checklist has been perfonned; if not, do so before proceeding.
B. Energize pump P532 by turning off-on switch located on the instrumentation panel in the control room to the on position. Vent the pump until it shows a steady discharge pressure.
VII.5.2 Pool Pump Down with the Skimmer System A. Prior to pumping the pool down, insure that there is sufficient reserve volume in tank T301 to receive the water.
B. If the pool level is to be lowered below the skimmer suction box, change the suction lineup to the lower suction by closing valve 548A and opening V548B.
C. The skimmer pump discharge normally returns to the pool via valve 515H. Pumping the pool down is accomplished by closing valve 515H and opening valve 524 to redirect the discharge to T301. A single control switch on the drain collection system control board operates valve 515H and valve 524. This switch is normally left in the open g
Rev. 10/81 App'd Mi-, 50P/VII 38
position having 515H open and 524 closed. To pump the pool down, flip the switch to the closed position, applying closing air to valve 515H and opening air to valve 524; then turn on the skimmer pump. When the pool level has been lowered to the desired level, secure the skimmer pump and return the switch to the open position and check to see that valve 515H returns to open, and valve 524 indicates shut.
VII.5.3 Raising Pool Level During Operation A. Prio'r to raising pool level, insure that the isolation valve for T301 is open and there is sufficient water in T301 to raise the pool to the desired level.
B. If T301 has insufficient water, crack open T300 isolation ]
valve and allow T300 water to flow by gravity to T301. ]
Caution: Do not allow T300 water level to drop below 2000 ]
gallons while the reactor is in operation. ]
O -
a
]
C. Pool level is raised by opening valve 565B, which valves ]
T301 or T300 (as selected) to the suction of the skimmer pump. The height of T300 or T301 provides sufficient head to overcome the pool head at the pump suction and the pool with gravity fill from the tank. The control switch for valve 565B is on the drain collection system control board in the control room, and is normally left in the closed position. To add water to the pool at a faster rate, start the skimmer pump as per VII.S.1 after valve 565B ]
has been opened. When pool level has increased to the desired level, secure the skimmer pump and shut 5658.
Note that the valve indicates shut.
Rey, 10/81 App'd N SOP /VII. 39
(/
I VII.5.4 Replacement of Skimmer Filter 531 g
The 1 micron skimmer filter 531 will be replaced when the pump discharge pressure exceeds 70 psig. At this point the AP across the filter as indicated by the AP gauge 926 should read greater than 20 psi. The used filter cartridge will be treated as radioactively contaminated material and will be handled and disposed of accordingly.
VII.5.5 Normal Shutdown of the Skimmer System Secure skimmer pump P532 by turning off-on switch on the instrument panel to the off position. Nonnally, there should be no need to change any of the valve settings after shutdown.
With P532 off and the local switch locked out, the system can be considered secured.
VII.6 Primary / Pool Drain Collection System VII.6.1 Purpose h The primary / pool drain collection system is used to collect all potentially radioactive water which is near reactor grade (2.0 umhos/cm or less). This water is recycled to the pool system and is never distributed to the building DI water supply. The collection of such effluents substantially reduces activities being discharged via the liquid waste collection system.
VII.6.2 System Operation The system may be operated either in automatic or manual.
Normal operation shall be in the automatic mode. The sequence of events in automatic are as follows:
A. The high level sensor detects high level at 2-1/2 feet, or 135 gallons, and the following events occur:
- 1. The pump automatically comes on (the " pump on" light indicates the pump is running). O Rev. 10/81 App ' d .):A SOP /VII 40
7 2. The pump discharge valve 565A opens (insure the (G "open" light indicates the valve open).
- 3. The high level light indicates high level in the tank.
- 4. The high level alarm sounds. The alarm will clear as soon as the level recedes below the sensor. The high level alarm cutout may be employed if the high level is to exist for some time.
B. After the system pumps below the low level sensor, the following events occur:
- 1. The pump stops (insure " pump off" light comes on).
- 2. The pump discharge valve 565A closes (insure valve indicates closed).
If it is desired to pump the collection tank before the level has risen to the high level sensor, the high level alarm can be simulated by depressing the auto / manual switch. This switch causes the control circuit to see a dummy high level signal which will cause the pump to start and the discharge
() valve to open. The tank will be pumped to the low level sensor which will cause it to stop as in auto control.
If for any reason it is desired to secure pumping of the collection tank before the low level sensor is reached, depress the manual override switch. This switch simulates a low level to the control circuit. The pump will stop and the discharge valve will close.
Note: When the collection system operates, an increase in pool DI water flow should be noted.
VII.6 3 System Startup The primary / pool drain collection system should be in operation any time evolutions involving operation of reactor or pool water systems is being performed. The following steps will prepare the system for operation:
A. Turn on the panel control power located behind the instrument cubical.
Rev. 10/81 App'd h et- SOP /VII 41 6
B. Place the valve operating system (air /N2 ) in service as per Section VI.9.3. ]
C. Verify that the pool level is sufficiently below the overflow so that water from the collection tank will not overflow the pool when pumped.
VII.6.4 System Shutdown After all systems have been secured and the building shutdown check is in progress, A. Verify that the level of the pool is low enough to accept water for the collection tank. If the pool level must be lowered, do so in accordance with Section VII.5.2. ]
B. Manually pump the water in the collection tank to its low level cutout as per Section VII.6.2. ]
C. Secure the valve operating system as per Section VII.9.5. ]
D. Secure the electrical power to the control power panel by opening the switch behind the instrument panel.
VII.7 Primary and Pool Sample Station VII.7.1 Sampling Frequency Both the primary and pool influent waters are sampled on a weekly basis, and an activation analysis is conducted by the ]
laboratory section for evidence of fission products and any activation products. At least once every six weeks, or at the water chemist's discretion, the effluent waters of both systems shall be sampled and delivered to the laboratory section for analysis of all radioactive ions. This data will j permit determination of a DF factor for the DI resin beds on l the radioactive ions present in the primary and pool water.
1 O l
l Rev. 10/g1 App'd '
.cs SOP /VII-42
/
t
p VII.7.2 Obtaining a Sample U
Any of the four samples required may be obtained as described below. Under normal conditions, Health Physics coverage should not be necessary to draw a sample. High activity in the primary or pool system could, however, present a radiation hazard for this evolution. A chirper is mounted on the hood ]
indicating a radiation hazard. If it chirps at a rate greater ]
than 10 times a minute during this evolution, close the sample ]
valves and call for HP coverage. ]
A. Turn on hood vent fan and chirper. ]
B. Check all sample valves closed. ]
C. Open the appropriate pool or primary sample valve and ]
verify flow by checking the flow indication bubble. ]
D. After purging for greater than 30 sec obtain a 500 ml ]
sample in a clean poly bottle from the sample discharge ]
valve. ]
E. After drawing sample rinse bottle with D.I. water and make ]
" appropriate entries in the primary / pool sample sheet. ]
F. Check all sample valves closed, and secure the fume hood ]
fan and chirper. ]
G. Log the event in the Operations Log Book. ]
VII.8 Liquid Waste Disposal System VII.8.1 Description A. All drains for potentially contaminated liquids are delivered to the liquid waste retention system (hereafter referred to as the Waste Tanks - WT) in the below grade area of the laboratory portion of the building. The liquid is pumped to the WT from two waste collection sumps provided for collection of potentially radioactive liquids.
B. The WT system consists of 2 collection sumps, 2 sumps, 2 sump pumps in each sump, one "Y" strainer, three 4680 gallon tanks, 2 waste tank pumps, 2 Cuno filters and Q associated piping, valves and fittings.
Rev. 10/81 App'd .S. S0P/VII 43
C. Each WT has valved drains which connect via a common suction header to the waste tank pumps. This header also has connections for chemical addition, DCW, and LP air.
D. The waste pumps should always discharge through the Cuno filters to any waste tank to the sanitary sewer system, or to the secondary system. The discharge header has a pressure gauge on both sides of the filter, a sample line, a buliseye, and a low pressure pump cutout switch (set at 5 psig).
E. Each tank has a sight glass for level readings. An air ]
sparge line is installed along the entire length o' WTl ]
and 2. Each tank has an unvalved vent to atmosphere. WTl ]
or WT3 can receive waste directly from the hot waste sumps, ]
depending on the valve line up. Both tanks have sludge ]
settlement standpipes, but the normal sump discharge is to ]
WT3. WT2 receives effluent directly from the DI200 ]
regeneration system. ]
F. Normally, WT3 will be used, with WTl available as a standby.] g The discharge line has a low pressure cutout switch to ]
automatically shut off the running pump upon icw discharge ]
pressure. ]
Caution: Will not shut off when pumping to sec. due to ]
sec. system back pressure. ]
l VII.8.2 Dry Active Waste l We must make every effort to remove as much waste as possible ]
in the form of drive active waste. We have three methods: ]
(1) Sludge Settlement ]
l (2) Cuno Filters ]
(3) Chemical Precipitant Treatment ]
A. Sludge Settlement WTl and WT3 are fitted with gravity drair.s to WT2 through ]
18" standpipes. This will allow WTl or WT3 to act as ]
settling tanks. When the sludge buildup warrants, the ]
O Rev. 10/81 App'd I SOP /VII 44
sludge is dumped via a 3" drain line at the north end of ]
V WTl or the south end of WT3 into barrels. This sludge is ]
dried and removed as dry active waste. ]
B. Cuno Filters The waste water will normally be pumped through the two Cuno filters. When the AP is high across them, they are replaced with new filters, and the old ones are disposed of as dry active waste. See Section VII.8.ll.
C. Chemical Precipitant Treatment Radioactive particulates will attach themselves to carriers which can then be readily filtered out of the WT water.
Without these carriers, even the most efficient filters could not remove this radioactive particulate. After filtering, the filters are shipped as dry radioactive waste (see Section VII.8.12).
VII.8.3 Dumping Criteria O A. The liquid waste is collected and held until an analysis is made to determine that the specific activity of all radioactive isotopes in the waste is less than the limit specified in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20) for dumping liquid waste to the sanitary sewer. If the 10 CFR 20 limits are not exceeded ]
and the total activity of radionuclides does not exceed ]
4 mci, the Shift Supervisor may authorize the water to be ]
pumped to the sanitary sewer. Any tank containing water ]
with an activity greater than 4 mci will be discharged ]
only with the approval of the Reactor Manager. In addi- ]
tinn to the dumping limit on each isotope,10 CFR 20 also ]
limits the total activity which the University can dump to the sanitary sewer to one curie per year. This latter limit and a general desire to minimize the activity dumped to our environment, dictates that the waste be retained as long as possible to permit the activity to decay off prior to discharge.
Rev. 10/81 App'd SOP /VII- 45
[
B. When the liquid waste exceeds the limits of 10 CFR 20 for dumping, one of two methods will usually be atilized to dispose of the waste. The most desirable option is to retain the water until the activity has decayed off to permit dumping. The second option is to chemically treat ]
the waste with a carrier solution that causes the radio- ]
nuclides to precipitate which facilitates them being ]
filtered out (refer to Section VII.8.12). Pracipitates ]
will then be removed either by pumping from one tank to ]
another or circulating the tank through the WT filters. ]
As the filtering process proceeds. it may be necessary to
]
change the filters to a smaller mesh size and continue the ]
filtration until the desired activity reduction is achieved.
C. It shall be standard procedure to hold all liquid waste as long as practical to minimize the total activity released.
A sample of the tank is taken and delivered to the Nuclear Science Group. Results of the analysis are recorded on the Waste Tank Sample Form and the form is sent to the g Shift Supervisor. The Shift Supervisor reviews the sample l results and makes the decision of what to do with the tank. If the Shift Supervisor decides to dump the tank, he sends the fom to Health Physics for their concurrence.
If Health ohysics concurs that the tank.can be dumped, the tank is pumped to the sanitary sewer as per Section VII.8.6. After the operator has completed pumping the ]
l tank, he enters the final volume pumped on the sample ]
form and sends the form to Health Physics Department. ]
D. If the analysis of WT2 exc9eds the 10 CFR 20 limits or if the Shift Supervisor wishes to hold the tank for further decay, WT2 can be [ umped to WTl via the filters, utilizing a vigorous air sparge. Then WTl shall be sampled at a later date and re-evaluated to determine where it should I be dumped.
O Rev. 10/81 App'd E ., SOP /VII- 46
E. It may be necessary at some time to discharge a tank of active water to the sanitary sewer by dilution of the waste. This will be used only in extre.ne need and will be performed by sp ecial procedure provided by the Shift Supervisor on a) proval of the Reactor Manager.
VII.8.4 Draining WTl to WT2 When WTl is nearly full, drain it via the standpipe drain line by opening valve W1. Insure that WT2 has room to accept the volume in WTl above the standpipe. When the level in WT1 falls to the standpipe or if WT2 fills up, close W1. Standard procedure shall be to insure that an excessive volume of water is not left in WTl over unattended periods.
VII.8.5 Draining WT3 to WT2 ]
When WT3 is nearly full, drain it to WT2 via the standpipe. ]
A. Check valves W2, 3, Sa, 6b, 7, 9, 38, 39 shut. ]
O B. Open valves W5b, 6a to start WT3 draining to WT2. ]
C. When WT3 is drained down to the level of the standpipe ]
shut W5b and W6a. ]
D. Record the evolution in the Reactor Log. ]
VII.8.6 Recirculating and Sampling of Waste Tanks ]
, Note 1: Notify Nuclear Science Group before obtaining a sample.
Note 2: Always pump through the filters by opening valves W16, W17, W18, W19, insuring valve W15 closed. Before recirculating any tank, check the following valves closed: Wl, 2, 3, Sa, 5b, 6a,15, 22, 23, 24, 25, 26, 27, 28, 38, 39. CheckopenW14,21.]
If WP2 is used, open W7 and W8 instead of W9 and W10. ]
A. Sampling WT2 ]
- 1. Open Sa, 5b, 9, 10, 16, 17, 18, 19, 24. ]
- 2. Start the waste pump (WP1) and verify flow through the bullseye.
l Rev. 10/81 App'd 6) _ S0P/VII-47
- 3. Commence a vigorous air sparge through W41.
- 4. Recirculate for 10 minutes prior to sampling. ] h
- 5. Draw off sample through W22 and discard to liquid waste drain.
- 6. Draw off a second sample through W22 for analysis.
- 7. Shut W22 and secure the waste pump.
- 8. Close W5a, 5b,10,16,17,18,19, 24, 41. ]
- 9. Deliver the sample and completed sample form to the ]
Nuclear Science Group for analysis. ]
- 10. Record taking of sample in the Reactor Log.
B. Sampling WT3
- 1. Open W6a, 6b, 9,10,16,17,18,19, 27. ]
- 2. Start the waste pump (WPl) and verify flow through the bullseye.
- 3. Recirculate for 10 minutes prior to sampling.
- 4. Draw off sample through W22 and discard to liquid waste ]
drain. ]
- 5. Draw off a sample through W22 for analysis. ]
- 6. Close W22 and secure the waste pump.
- 7. Close W6a, 6b,10,16,17,18,19, 27. ]
- 8. Deliver the sample and completed form to the Nuclear ]
Science Group for analysis. ]
- 9. Record taking of sample in Reactor Log.
VII.8.7 Pumping to Sanitary Sewer ]
Note: Can be done only with Shift Supervisor's authorization. ]
Check the following valves closed: W1, 2, 3,15, 22, 23, 24, 25, 26, 27. If pumping with WP2, open W7 and 8 instead of W9 and 10.
A. Pumping WT2 to Sewer (check closed 6a, 6b)
- 1. Open W5a , 5b, 9,10,16,17,18,19, 28 and 30. ]
- 2. Secure local blowdown switch by WT3. ]
- 3. Commence a vigorous air sparge through W41. ]
O Rev. 10/81 App'd. / SOP /VII-48
l
- 4. Start the waste pump (WP1) and verify flow through the bullseye.
- 5. Check the WT level frequently until the tank is empty.
- 6. When it is empty, shut W41 and secure the waste pump.
- 7. Close W5a, 5b,10,16,17,18,19, 28 and 30. ]
- 8. Turn on blowdown switch.
- 9. Record the volume remaining on the Waste Tank Sample Form and return it to the Health Physics Office.
1
- 10. Record pumping evolution completion in the Reactor Log.
B. Pumping WT3 to Sewer
- 1. Check valves W5a, 5b closed. ]
- 2. Open W6a, 6b, 9,10,16,17,18,19, 28 and 30. ]
- 3. Secure local blowdown switch by WT3. ]
- 4. Start the waste pump (WPl) and verify flow through the bullseye.
- 5. Check the WT level frequently until the tank is empty.
- 6. When it is empty, secure the waste tank pump.
- 7. Shut W6a , 6b,10,16,17,18,19, 28 and 30. ]
Q 8. Turn on blowdown switch. ]
- 9. Record the volume remaining on the Waste Tank Sample Form and return it to the Health Physics Office.
- 10. Record pumping evolution completion in the Reactor Log.
VII.8.8 Pumping Waste System to Secondary System ]
Note 1: Pumping from the Waste System to the Secondary System can only be done after having received permission from the Reactor Manager. ]
Note 2: Anytime a waste tank is pumped to the Secondary System it will be pumped through the Waste System filters.
Note 3: When possible, the cooling tower fans should be left in fast speed anytime the secondary water activity level is above 10-5 uCi/ml tritium.
Note 4: The Secondary System Blowdown will remain secured ]
until Tritium activity is less than 10-5 pCi/ml and all other ]
activities are within 10 CFR 20 limits for discharge to the ]
Rev. 10/81 App'd -om 50P/VII-49
sanitary sewer. A Secondary Wate- Activity Analysis fom will ]
be filled out for each secondary water analysis performed. ]
After the form (s) is(are) completely filled out, it will be ]
sent to the Health Physics Office for filing with the ]
appropriate waste tank analysis sheet. ]
Note 5: The following data will assist in determining when a ]
water sample should be taken to check activities less than ]
10-5 pCi/ml. Immediately after pumping a waste tank to ]
secondary, the secondary water activity level will be approxi- ]
mately 1/6 of the concentration of the waste tank water. With ]
the reactor at 10 MW and three cooling tower fans in fast ]
speed, the 3H concentration decreases by a factor of 100 in ]
about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ]
A. Pumping WT2 to Secondary System ]
- 1. Secure and tag secondary system blowdown solenoid ]
valve and isolation valve and log. ]
Caution: Will not shut off when pumping to sec. due ]
to sec. system back pressure. ] $
- 2. Check tne following valves closed: Wl, 2, 3, 6a, 6b, ]
15, 22, 24, 25, 26, 27, 28, 38, 39. ]
- 3. Open valves W5a, 5b, W9 and 10 if using WP1 or W7 and ]
W8 if using WP2, W16,17,18,19. Check open W14 and ]
- 21. ]
- 4. Start the waste pump (normally utilizing WP1) and open W23 and S169. Observe the bullseye to verify fl ow.
- 5. Check the waste tank level frequently until the tank is empty, also observe the Secondary Coolant Monitor in the Control Room.
- 6. When the tank is empty, secure the waste pump.
- 7. Close the following valves: S169, W23, 5a, 5b,10, ]
if WPl was used, 8 if WP2 was used, 16,17,18 and 19. ]
- 8. Record remaining tank volume on the Waste Tank Sample ]
Form and return to the Health Physics Office.
O Rev. 1 0/81 App'd E SOP /VII-50
1 t
I \
l i
n V
- 9. Record the pumping evolution completion in the Reactor Console Log.
- 10. See Notes 4 and 5, beginning of this Section. ] l VII.8.9 Pumping Waste from One Waste Tank to Another A. Pumping WT2 to WT3
- 1. Check closed Wl, 2, 3, 6a, 6b, 15, 22, 23, 24, 25, 26, ]
28, 39. ]
- 2. Check WT3 to insure that it has enough room to receive the volume in WT2.
- 3. Open W5a, 5b, 9,10,16,17,18,19 and 27. ]
- 4. Start the waste pump (WP1) and verify flow through the ]
bullseye. ]
- 5. Connence a vigorous air sparge through W41.
- 6. Check the WT level frequently until the tank is empty.
- 7. Shut W41 and secure the waste pump. ]
- 8. Close W5a, 5b,10,16,17,18,19 and 27. ]
- 9. Record pumping evolution in the Reactor Log, and on the analysis form if there is one.
B. Pumping WT3 to WT2.
- 1. Check closed Wl, 2, 3, Sa, 5b, 22, 23, 25, 26, 27, 28, ]
38, 39. ]
- 2. Check WT2 to insure that it has enough room to receive the volume in WT3.
- 3. Open W6a, 6b, 9, 10, 17, 18, 19 and 24. Insure W15 closed.
- 4. Start the waste pump (WP1) and verify flow through the bullseye.
- 5. Check the WT level frequently until the tank is empty.
- 6. Secure the waste pump.
- 7. Close W6a, 6b, 10, 16, 17, 18, 19 and 24.
- 8. Record pumping evolution in the Reactor Log and on the analysis form if there is one.
O Rev. 10/81 App'de r 'i - SOP /VII 51
(
VII.8.10 Dumping Sludge from a Waste Tank 3 g
Sludge will be dumped from WTl through valve W44 (WT2 through sludge plug and WT3 through W40) into barrels by a procedure ]
approved by the Shift Supervisor. This sludge will be dried ]
and disposed of as Dry Active Waste. ]
VII.8.11 Changing WT Filters ]
A. Obtain an RWP,12-25 micron filters, a large double plastic ]
bag. ]
B. Insure all nonnally closed WT valves are closed.
C. Place the filter drain line hoses in the floor drain. ]
Open drain valves 51 and 52 and open both vent valves on ]
housing. ]
D '. When water quits running, remove filter cannisters and place old filters in plastic bags.
E. Replace filters and hardware, reassemble cannisters and close valves 51 and 52. g F. Open DCW valve 38 and valves 9,10, and 16 to fill and ]
vent filters. Close vent valves. ]
G. Secure valves 10, 16 and 38.
H. Wash down area, dispose of collected filters in the
- designated filter barrel .
VII.8.12 Chemical Precipitate Treatment ]
A. Drain the waste tank to WT2. ]
B. Lower the waste tank water pH. ]
- 1. Check all valves at R200 closed. ]
- 2. Line up acid mixing tank valves and close the pump ]
breaker. ]
- 3. Open R200 valves RE57, RE58, RE5 and RE70. ]
l 4 Start acid pump at R200 station and throttle flow ]
with RE58.
O l Rev. 10/81 App'd a : -
SOP /VII 52
/
5 1
- 5. Add sufficient acid (6 normal) to lower pH to between ]
5.0 and 6.0. ]
- 6. Secure the acid pump and open the breaker. ]
- 7. Shut valves RES, RE57, RE58 and RE70. ]
- 8. Drain and flush the acid mixing tank. ]
- 9. Close the acid mixing tank valves. ]
C. Sparge and recirculate, bypassing the filters, for 30 ]
minutes. ]
D. Add a special carrier solution which will be provided by ]
the Laboratory Group. ]
E. Sparge and recirculate, bypassing the filters, for one ]
hour. ]
F. Raise the pH. ]
- 1. Open the WT2 manhole cover. ]
- 2. Add sufficient sodium hydroxide to raise the pH to ]
4 11.0-14.0. ]
Caution: It is better to add too much than not ]
O enough. ]
- 3. Replace the manhole cover. ]
G. Sparge and recirculate, bypassing the filter, for 30 ]
minutes. ]
H. Sparge and recirculate or pump from WT2 to WTl through ]
25 or 5 micron filters, until the filters no longer foul. ]
VII.9 Nitrogen and Valve Operating Air Systems VII.9.1 Purpose The primary function of the nitorgen (N2 ) system is to provide pressurized N2 to the pressurizer. The secondary function of the N2 system is to act as a backup to the air in the valve operating system.
O Rev. 10/81 App'd 7 S0P/VII 53 m m . -- _ _ . - . --
-1___ - . - - -
VII.9.2 System Startup g
The air system is in continuous operation and is normally lined up to provide service to all stations. The air to the valve operator header, however, is secured when the reactor is shutdown so the air valve in room 114 must be opened prior to operating any system valves.
The N2 system is operated only while the reactor is in operation. Before the reactor is made operational, light off the N2 and valve op system by the following procedure:
A. Verify that the two banks have sufficient pressure for the impending operation. Ideally one of the banks should be full (2000-2200 psig) and the other bank should have more thar. 250 psig.
B. Close the switch which energizes the electrical controls for the system.
C. Check closed the cross connect N2 to air valve V0P8.
D. Open the N2 cut out valve V0P15 in room 114, and verify aN 2pressure of 0 5 psig to the valve op header.
E. Close header bleed valve V0P35.
F. Open the air cut out valve V0P31 in room 114 and verify a valve op header pressure of 100 10 psig.
G. Open the N2 to air cross connect valve V0P8.
The N2 and valve operator systems are now ready for operation.
l I
VII.9.3 System Operation The operation of the air and N2 systems is fully automatic.
The operation of the system is monitored every four hours during plant operation. The only manual evolutions required j are those of changing the bottles on a depleted N2 bank and blowing down the dust and oil filter every four hours. If moisture is detected in the air bled from the filter, the 1
filter should be blown down until no further traces of moisture O
Rev. 10/81 App'd/ SOP /VII 54
are seen. The filter element turns a dark red color when it traps oil. The filter element shall be changed when more than 75% of its volume has turned dark red in color.
VII.9.4 System Shutdown After the reactor has been secured and no further valve operations are anticipated, the air and N2 systems are shut-down as follows:
A. Close the N2 to air cross-connect valve V0P8 to reduce N2 consumption.
B. Close the N2 cut out valve V0P15 in room 114.
C. Close air cut out valve V0P31 in room 114.
D. Open header bleed valve V0P35, bleed to atmospheric pressure, leaving valve open.
E. Secure the N2 control system by opening the electrical switch at the bottle station.
O vtt io compressed Air system VII.10.1 System Startup The air systems are in continuous operation and are normally valved to provide service to all stations.
A. Check all air valves not required closed.
B. Insure main air compressor after-cooler water supply o'perable with the chill water pump running.
C. Insure desiccant type dryer contains sufficient desiccant pellets.
D. Check the tag log and all pieces of equipment for operability.
E. Apply electrical power for each compressor by
- 1. Main air compressor
- a. Close main breaker on MCC3.
- b. Place the local switch to " auto". (Manual operation should be used for only special tests.)
Rev. 10/81 App'd 6- S0P/VII 55 6
- 2. Emergency air compressor
- a. Close breaker #3 on the Emergency Power Panel.
- b. Close the local switch disconnect at the compressor.
- 3. 16" valves
- a. Close breaker #18 on the Emergency Lighting Panel.
- b. Close local toggle switch at the compressor.
- 4. Instrument air compressor (Johnson)
- a. Close switch #31 on LPil.
- b. Close local switch at the compressor.
When any piece of equipment is placed in service, monitor the operating equipment until satisfied that it is operating properly.
VII.10.2 System Operation The main air compressor operates continuously to supply air to the facility. The pressure is maintained between 95 and 115 psig. The desiccant dryer has a viewing window for pellet level inspection; and the supply should be replenished when h the level falls below the window. The system requires that the after-cooler be in operation whenever the compressor is in operation. Should DCW to the building be secured, the main compressor must be secured to prevent damage to the equipment (EP-II.12).
The emergency air compressor is always available as a backup for the air system in containment. It is checked for proper operation weekly. The compressor assumes the load at 65 10 psig and supplies sufficient air for all door gaskets and equipment within the containment. The compressor is electrically supplied from breaker 43 of the Emergency Power Panel.
The backup air compressor for 16B isolation valve will only operate upon failure of both the main and emergency air compressors. The compressor assumes the load at 60 5 psig.
The compressor provides air only for valve 16B and will allow e
Rev. 10/81 App'd/h 50P/VII 56
the valve to be operated as required. The compressor is k electrically supplied from breaker 18 of the Emergency Lighting Panel.
The instrument air compressor is always valved for opera-tion and operates at a pressure of 70 5 psig. Should this compressor fail, instrument air may be supplied from i.he main compressor by opening the cross-connect valve located near the tompressor and closing the cut out valve for the compressor.
VII.10.3 Shutdown The main air compressor may be shutdown for maintenance during operation provided that A. Large volumes of air are not required for a particular evolution.
B. A stored air or N2 supply is connected to the backup door air cylinder in the Machine Shop, and this supply line is isolated from the main header.
O C. Operebiiity of the emersency eir compressor is checked.
Should the facility lose DCW water, the main air compressor must be shutdown as per Section EP-II.12. To shutdown the compressor, the local auto /off/ manual switch is turned to "o f f" . The compressor may be electrically isolated by opening the main breaker on MCC3.
The emergency air compressor must always be operable whenever the reactor is operating. It may be secured at its local breaker. Breaker #3 on the emergency power panel should not be secured because it supplies power to the isolation doors, door 101 and the personnel air lock doors.
With the reactor operating the compressor for isolation valve 16B may only be electrically secured when the valves are placed in the closed position. Should this be necessary, open the local switch only, because the main switch also provides power to the facility and reactor isolation systems.
The instrument air compressor may be shutdown by opening p
i O its local breaker. Its main supply may be secured at breaker Rev. 10/81 App'd.th - 50P/VII-57
- 3 of LPll . If secured and air supply is still required, the cross connect valve from the main compressor may be opened. O If any of the components or compressors above are secured or placed in a position other than normal, the component shall be tagged in accordance with the tag-out procedure.
VII.ll Beamport Water System (see Section VIII.4)
VII.12 Sulphuric Acid System VII.12.1 Receiving Bulk (Concentrated) Acid Caution: This process is extremely dangerous. Protective ]
equipment must be worn. Always have an available supply of ]
water and sodium bicarbonate. ]
Bulk sulphuric acid is delivered by tank truck and is ]
transferred to the storage tank by air pressure or gravity ]
drain. When possible the gravity drain method should be used. ]
In the event air pressure must be used, extreme caution should ]
be exercised. The tank truck can easily exceed the receiving ]
capacity of the system. Insure that the tank pressure does not ]
exceed 15 psig and closely monitor tank levels. ]
A. Check valve 1 closed and valves 2 and 3 open.
B. Crack open the Tank-0-Meter bubbler valve 7 to give an air flow of 3-4 bubbles per second. Note and record the tank level indicated on the Tank-0-Meter.
C. Remove the cap on the fill line to enable connection of ]
the transfer line from the truck. Commence filling the ta nk .
D. While the tank is filling, watch the Tank-0-Meter to insure that an air flow of 3-4 bubbles per second is maintained.
Caution: If the system is over filled acid will spill into ]
the mixing tank. The heat generated at this point could ]
result in damage to the acid handling system. ]
E. When the tank volume reaches 750 gallons, secure the transfer.
Rev. 10/81 App'd e' -
SOP /VII-58
F. Disconnect the transfer hose into the storage tank.
G. Record the final volume of the tank and report to the truck driver the amount of acid received. Close the bubbler valve.
VII.12.2 Transferring Acid from the Storage Tank to the " Day Tank" When the acid in the day tank has been used, the tank is refilled with acid from the storage tank by carrying out the following procedure:
A. Check valves 2 and 3 open.
B. Crack open the bubbler valve (7) to give an air flow of 3-4 bubbles per second.
C. Record the volume of acid in each tank.
D. Check valve 1 closed.
E. Screw down on the air regulator (6) until a pressure of 15 psig is indicated on the pressure gat.ge. ]
F. Close valve 2 and open valve 1. The indicated pressure C) wii, drop uotii tne storage tenk nes been gressurized eod the actual transfer begins. When the pressure stabilizes the transfer is underway. If the pressure rises above 15 psig, reduce it to 15 psig by adjusting the regulator. ]
G. During the transfer monitor the storage tank and day tank levels. Maintain a bubbler flow of 3-4 bubbles per second on the Tank-0-Meter.
H. When the day tank is full, close valves 3 and 1.
I. Open valve 2 to depressurize the storage tank.
J. Open valve 3 and back off on the air regulator (6).
K. Record the final volume of acid in each tank.
L. Close the bubbler valve.
VII.12.3 Mixing Acid for Regeneration To make sufficient 6N acid for regeneration purposes, follow the procedure in Section VII.4.4.3.
O Rev. 10/81 App'd k - 50P/VII 59
O NOTE: THIS PAGE INTENTIONALLY LEFT BLANK g O
Rev. 10/81 App'd (C :' ' - SOP /VII-60
- - _ . . . _ d -- __. __
O Section VIII REACTOR EXPERIMENTS VIII.1 General Requirements VIII.l.1 Reactor Utilization Request All experiments conducted in the MURR reactor facility must be approved by the Reactor Manager. The mechanism for obtaining ]
this approval and for conducting the required staff and advisory committee reviews is outlined below.
A. Reactor Utilization Request Description The approval and review machinery is begun by the prepara-tion of a Reactor Utilization Request (RUR). The RUR is prepared by the experimenter with the assistance of the MURR staff. Instructions are obtained from the Reactor ]
Manager. The RUR describes the experiment in considerable ]
detail. It also presents the activities (and isotopes) which may be produced and details the methods of handling the radioactive waste. It also lists the Special Nuclear Material and by-product licenses applicable to the experiment. The nost important part of the RUR and the one which should be given considerable effort in its preparation is the safety analysis. This part of the RUR shall analyze all possible accidents and transients to determine if the experiment involves an unreviewed safety question as defined by 10 CFR 50.59. It is important that the experimenter thoroughly research his experiment in an attempt to resolve all questions which may arise in the review process.
O Rev. 10/81 App'd b- SOP /VIII-1
B. Reviews
- 1. The initial review of the experiment is conducted by g
the MURR staff while they are assisting the experi-menter prepare the RUR. Hopefully most of the safety questions will be raised and analyzed during this review.
- 2. The RUR is then sent to the Manager of Health Physics ]
(HP) for his review. ]
- 3. The Manger of Health Physics reviews the RUR to insure that all necessary radiological control measures will be taken in the proposed experiment. He also checks the applicability and adequacy of the by-product license (s) under which the experiment is to be conducted.
However, his review is not limited to the above areas. ]
He may recommend limitations or additional analyses 3 in other areas. If the Manager HP approves of the experiment, he will indicate the additional limitations (if any) recommended and sign the RUR in the space $
provided.
- 4. The Reactor Manager will analyze the proposed experi- ]
ment to determine if it represents a new class of experiment or represents a change to an existing experiment which has safety significance. If either of the above conditions apply the Reactor Manager will l
submit the RUR to the Reactor Safety Subcommittee l
(RSSC) for their review. The RSSC conducts the reviews
! of all new experiments for the Reactor Advisory Committee (RAC). Their review is primarily directed l
toward determining if the new experiment introduces an unreviewed safety question in accordance with 10 CFR 50.59. If the RSSC finds that the experiment does not
! involve an unreviewed safety question and recommends l approval, the RUR review is completed. The RSSC may, however, refer the experiment to the RAC for its review.
O l
Rev. 10/81 App'd 'i~ SOP /VIII-2
)
i This might be done because of unusual hazards, special conditions involved or because the RSSC feels that an unreviewed safety question does or may exist.
- 5. The Reactor Advisory Committee (RAC) will normally review an experiment only if the experiment has been referred to it by the RSSC. If the RAC determines that the experiment does not involve an unreviewed safety question the review process is complete.
- 6. If the RSSC and/or the RAC feel that a proposed experi-ment introduces an unreviewed safety question the experiment must be submitted to the NRC for final ]
review. The MURR staff will generally prepare the j documents necessary for submittal to the NRC. ]
C. Approval of RUR After all of the reviews have been completed the Reactor Manager will indicate on the RUR any additional limitations ,
required beyond those listed in the data package and will iO then sign the RuR as being approved. Copies of the approved RUR will be distributed to:
- 1. The experimenter
- 2. Facility Director
- 3. Manager of Health Physics
- 4. Reactor Safety Subcommittee
, 5. MURR Staff
- 6. Reactor Advisory Committee (if RAC was involved in the review)
- 7. Reactor Service Engineer VIII.1.2 Flammable or Toxic Materials A. Definitions
- 1. Flashpoint of the liquid shall mean the temperature at which it gives off vapor sufficient to form an ignitable mixture with the air near the surface of the liquid or
- O Rev.
uiw m.
w App'd b _ - SOP /VIII-3 7
within the vessel used as determined by appropriate test procedures referenced in Section 1910.106 of the OSHA Regulations.
- 2. Liquid shall mean, for the purpose of this section, any material which has a fluidity greater than that of 300 penetration asphalt when tested ic accordance with ASTM Test for Penetration for Bituminous Materials, D-5-65.
- 3. Combustible liquids shall mean any liquid having a flashpoint at or above 140 F (60 C).
- 4. Flammable liquids shall mean any liquid having a flashpoint below 140 F and having a vapor pressure not exceeding 40 pounds per square inch (absolute) at 100 F.
- a. Class I liquids shall include those having flash-points below 100 F and may be subdivided.
(1) Class IA shall include those having flash-points below 73 F and having a boiling point below 100 F. g (2) Class IB shall include those having flash-points below 73 F and having a boiling point at or above 100 F.
(3) Class IC shall include those having flash-points at or above 73 F and below 100 F.
- b. Class II liquids shall include those having flash-points at or above 100 F and below 140 F.
- c. Class III liquids include all combustible liquids.
- 5. Safety can shall mean an approved container, of not more than 5 gallons capacity, having a spring-closing lid and spout cover and so designated that it will safely relieve internal pressure when subjected to fire exposure.
B. Limitations of Flammable and Combustible Liquids
- 1. No flammable or combustible liquids may be taken into the containment building unless they meet the require-ments of Table VIII-l below. h Rev. 10/81 App'd w SOP /VIII-4
Table VIII-l Maximum Allowable Size of Containers Class of Liquids Container Type Cl IA Cl IB Cl IC Cl II Cl III Glass or approved plastic 1 pt 1 qt 1 gal 1 gal 1 gal Metal 1 gal 5 gal 5 gal 5 gal 5 gal Safety cans 2 gal 5 gal 5 gal 5 gal 5 gal '
- 2. Storage of flammable or combustible liquids in contain-ment is prohibited unless the Reactor Manager has approved a written request to store the material in the containment building.
C. Toxic Materials The materials listed in Appendix C will not be taken into the containment building unless specifically authorized in O writing by the Reactor Manager.
VIII.l.3 Corrosive Chemicals Materials which are chemically incompatible with the reactor system components from the view point of corrosion shall be subject to special scrutiny and control. Experimenters are prohibited from placing any material in experimental positions (beamport, thermal column, P-tube, bulk pool, reflector, or flux trap) which have not been listed as to type and amount
^
on an approved RUR or in Section VIII.3.
VIII.2 In-pool Irradiations j
This section covers the irradiation of samples and any experi-l mental measurements in (1) the flux trap, (2) the graphite reflector, (3) the lead shield bulk pool facility and the bulk pool.
1 O
l 1 -
Rev. 10/81 App'd c'a - S0P/VIII-5
/
VIII.2.1 General Requirements g
All in-pool irradiations must be under an approved RUR.
Section 3.1 of the Technical Specification lists the reactivity limits applicable to in-pool experiments. The Reactor Services Engineer will coordinate the loading of all in-pool experiments to insure that none of the Tech Spec reactivity limits are violated. An in-pool irradiation loading sheet (Appendix A) will be filled out for each sample (or sample type). The completed sheets will be kept in the control room until the sample is released. These sheets will enable the operations staff to be continuously informed of the experimental loading of all in-pool facilities. The loading sheet will also document the reactivity worth of the sample (s) listed on the sheet. The Shift Supervisor shall insure that all sample handling evolu- ]
tions are properly performed and documented. Once every shift ]
the sample logs shall be reviewed and an inventory of the ]
stored flux trap size samples shall be taken. Every sample ]
shall be positively identified. It shall be the responsibility ]
of the shutdown crew to verify that all samples and/or spacers ]
are properly stored and/or accounted for. ]
VIII.2.2 Sample Encapsulation All samples to be irradiated in the reactor pool will be encapsulated in either a seal-welded or crimp sealed aluminum can or a threaded aluminum capsule. Only the seal-welded can will be used in the flux trap.
The seal-welded aluminum cans have been tested to rupture pressures of 400-700 psig, but no sample will be loaded in a seal-welded can which will generate a pressure greater than 100 psig (assuming complete decomposition of the sample).
Where practicable a sample will be doubly encapsulated to minimize the possibility of release of the sample material .
All corrosive materials must be doubly encapsulated. The primary encapsulation may be an aluminum can (seal-welded or $
Rev. 10/81 App'd g k SOP /VIII-6
threaded) or a sealed quartz vial. The quartz vials have a O
- very low rupture pressure so precautions must be taken to eliminate possible pressure build-up when quartz vials are used.
Sample cans will be weighted if necessary to insure that the sample has negative buoyancy.
VIII.2.3 Flux-Trap Irradiations Since the flux trap region has a positive temperature and void coefficient of reactivity, additional limitations are placed on all samples to be irradiated in the flux trap.
All flux trap samples will be seal-welded, leak checked and will have a negative buoyancy.
The flux trap sample holder will be loaded or removed ]
from the reactor only when the reactor is shutdown. The flux ]
trap sample holder must be securely latched in place while it ]
is in the reactor. D_0_NOT 0 under any circumstances unlatch the ]
O flux tren until tne control biedes are fuli in. ]
For verification that the flux trap is properly latched, ]
an operator other than the operator inserting the flux trap ]
will visually observe its proper latching. ]
All flux trap irradiations will be shown on a flux trap loading sheet (Appendix A) which must be signed by the Reactor Services Engineer. If the sample loading is unique the Reactor Physicist will check the Service Engineer's calculations of the total reactivity worth and will also sign the loading sheet.
If there are insufficient samples to fully load the flux trap sample holder, the holder will be loaded with aluminum spacers to insure that the samples cannot move during reactor operation. The sample hold-down rod must be securely pinned or wired to the sample holder to satisfy the Tech Spec require-ment of a secured experiment.
O Rev. 10/81 App'd . h n -
SOP /VIII-7
/
VIII.2.4 Handling of Irradiated Samples g
Every effort shall be made to naximize the decay time before an irradiated sample is removed from the pool. This is done to allow short lived activity to decay.
No radioactive material will be moved in the MURR pool which causes a working area dose rate of as much as 100 millirem per hour without the presence of a member of the Health Physics staff who is monitoring the operation. The Health Physics monitor will monitor the operation to minimize radiation exposure to personnel, terminating the operation if necessary.
Radioactive materials in the MURR pool causing working area dose rates less than 100 millirem per hour may be moved within the pool without the presence of a member of the Health Physics staff if, and only if, a licensed Reactor Operator or qualified sample handler surveys the operation.
VIII.3 Pneumatic Tube (P-tube) System Irradiations VIII.3.1 Limitations on P-tube Use A. No irradiation in the p-tube will be permitted unless it has been authorized by an approved Reactor Utilization Request (RUR).
B. The Reactor Manager will maintain a list of the approved RUR's and the limitations applicable to each RUR. This list will be kept in the control room for use by the Reactor Operator.
C. The Reactor Manager will also maintain a list of the individuals authorized to use the p-tube system and the RUR numbers they are authorized to use. An individual is placed on this list at the request of the principal experimenter for the RUR to be used. The request is made by filling out an " Experiment Utilization Request" form ]
and submitting it to the Reactor Manager via the Manager ]
of Health Physics. This form is used to certify that the experimenter has :
Rev. 10/81 App'd. h _ m S0P/VIII-8
I
- 1. Satisfactorily completed a checkout on the use of the p-tube system including the applicable emergency procedures;
- 2. Received Health Physics indoctrination in those radiation control measures applicable to p-tube irradi-ations. A few individual experimenters will be authorized to conduct p-tube irradiations at other than normal working hours (0800-1700). This authoriza-tion will be granted only to those individuals who have considerable experience in p-tube irradiations and have shown outstanding knowledge and judgement in the radiation control measures applicable to p-tube irradi-ations. The Experiment Utilization Request form is also used to initiate a request for these (night time) irradiations.
D. The experimenter shall take the following radiation control measures prior to conducting p-tube irradiations:
- 1. He shall insure that a radiation detector with audible indication is in the laboratory and is operating properly.
- 2. He shall wear his film badge and dosimeter during the irradiations. If the experimenter is doing a number of irradiations, he shall check his dosimeter period-ically to prevent overexposure.
VIII.3.2 Sample Limitations A. Any radionuclide having an atomic number from 3 through 83 plus tritium may be produced in the p-tube system. Activity will depend on the sample matrix, time of irradiation, and power level . Prior to the irradiation of a particular sample type, an estimate will be made of the activity produced by the major constituents. Sample activity will be limited to 25 mci. Flux monitor, container and cadmium shield activity will be limited to 50 mci. Higher activi-ties must be specifically authorized in the experimenter's RUR.
. Rev. 10/81 App'd ,l- % SOP /VIII 9
B. Each sample must be properly encapsulated as follows:
- 1. Solid samples will be wrapped in polyethylene or h aluminum foil, sealed in polyethylene tubing or sealed in a polyethylene vial.
- 2. Liquids will be sealed in a polyethylene vial or polyethylene tubing with the ends heat sealed to prevent inadvertent spilling. Liquids other than water and biological fluids will be doubly encapsulated with the secondary encapsulation being a high density poly-ethylene rabbit.
- 3. Powder samples will be sealed in a polyethylene vial and irradiated in a high density polyethylene rabbit.
Boron and boron compounds in powder form will be sealed ]
in high density polyethylene within the rabbit. ]
- 4. A metal liner such as cadmium sheet may be used in the rabbit providing it is in one piece and covers at least 80 percent of the rabbit's interior surface. The experimenter shall take measures to insure that the heat generated by the metal can be dissipated and will not cause damage to the sample or rabbit.
- 5. The experimenter shall insure that the sample is adequately secured in the rabbit (by polyethylene packing, etc.) so that the motion within the rabbit is minimized.
C. Material which may be irradiated in the p-tube system includes water, plant and animal tissue and fluids, bone, air filters, soils, rocks, soil extracts, coal, paper, meteorites, fibers, dried paint, safe insulation and glass. Pure elements, alloys and compounds not exempted in D below may also be irradiated subject to the activity limitations in A.
D. Unless it is specifically authorized in the experimenter's RUR, the following materials will not be irradiated in the p-tube system:
O Rev. 10/81 SOP /VIII-10 App'[d 4 -
- 1. Natural uranium; g
V 2. Special nuclear materials as defined in Title 10, Part 70, Paragraph 70.4m of the Federal Code of Regulations (i.e. , plutonium, uranium-233, or uranium enriched in isotope 233 or 235);
- 3. Pure elements: Li, Na, K, Rb, Cs, Ca, Sr, Ba, Hg, Os, H, 0, F, Ne, Ar, Kr Xe, and P;
- 4. Compounds: NHgNO 3 , CaC 2 , Ca0, perchlorates, per-manganates, Na20, and Na20 2;
- 5. Materials which chemically react with water to produce undesirable quantities of heat and pressure;
- 6. Any explosive, flammable, combustible, or toxic materials.
E. The controlling factor for determining the weight and time limits of a sample to be irradiated in the p-tube is the activity limitation of Section A. If the activity limits do not further restrict a sample's size, the following O weight limits shall apply:
V 1. For irradiation times up to 30 minutes, the maximum weight of irradiated materials in one rabbit will be 2 grams with two exceptions:
- a. A maximum of 10 grams of water or dried feces;
- b. Only 1 mg of chemical compounds in solution; t
l form of powder. The experimenter shall take mea- ]
l sures to insure the heat generated can be dissipated]
l without causing damage to the rabbit or sample. ]
- 2. For irradiation times of 30 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the f maximum weight of irradiated materials in one rabbit will be 1 gram with two exceptions:
- a. A maximum of 10 grams of water or dried feces;
- b. Only 500 pg of chemical compounds in solution.
l The weight limits above do not include the weight of the rabbit, polyethylene vial, or packing, or the cadmium (or lO otner metei) shieids.
Rev. 10/81 App'd, /' '.- S0P/VIII-ll 9
The maximum irradiation time for most samples will be one hour at power levels 1 5 MW and 30 minutes for power h l ev el s > 5 MW. Hair, fibers, paint, air filters and flux monitors may be irradiated for a maximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at power levels 1 5 MW and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at power levels > 5 MW.
The following additional limitations shall apply for irradiations > 10 minutes:
- 1. Primary encapsulation will be heat-sealed high-density polyethylene vials (Holland vials).
- 2. Liquid samples may be irradiated for up to 30 minutes provided pin holes are punched in the top of the polyethylene vial to relieve pressure.
Deviations from the above weight and time limitations must be specifically authorized in the experimenter's RUR.
VIII.3.3 Rabbit Limitations A. Two types of rabbits are presently authorized for use in the p-tube system. The most commonly used rabbit is the g low density polyethylene rabbit, ihe minimal cost of this rabbit makes it ideally suited for short irradiations in which the sample is a solid and the weight is small. These rabbits are very susceptible to radiation damage and have led to rabbit failure when they were used a number of times.
Low density rabbits will therefore be used only once in the p-tube system and will not be used for irradiations greater than 10 minutes.
B. The second type of rabbit which may be used in the p-tube system is the high density rabbit. This type of rabbit will be used for all irradiations greater than ten minutes and for most liquid and powder irradiations (see Section VIII.3.2.B). Each high density rabbit will be limited to six insertions or two hours of total irradiation, which-ever occurs first. To account for the irradiation history of high density rabbits, the experimenter will place one mark with a marking pen on the high density rabbit for h Rev. 10/81 App'd i _ 50P/VIII-12
n each insertion up to and including 10 minutes. For irradi-U ations longer than 10 minutes, a mark will be placed on the rabbit for each 10 minute period or fraction thereof.
For example, if a rabbit is irradiated for 25 minutes, it will receive 3 marks. When a rabbit has received six marks, it will be discarded. Each rabbit must be examined for cracks or other signs of potential failure before it is used.
VIII.3.4 Sample Irradiation Procedures VIII.3.4.1 When an experimenter has met the requirements of VIII.3.3 and is ready to run his experiment, he shall call the reactor control room giving his A. Name B. Laboratory room number C. Experiment file number D. Length of time he requires for tube use VIII.3.4.2 When the blowers are on, the system will be operated by the t
following procedure.
Note: The position of each control button (CB) and control light (CL) for the operation of the system from laboratories 216-228, 227-218 respectively are given on Figure VIII-1. ]
A. For laboratories (216-228, 227-218) which have switching ]
or control stations, the circuit selector (CB-1) must be ]
positioned to the control station of the experimenter's
! laboratory, i.e. 216.
B. Set the " automatic-manual" control switch (r3-2) to the tyne of cont ol desired.
C. 'f 4 donatic control of the system is used, set the timer 7.c ; sired irradiation time. Irradiation time as short as t
c ;g.onds can be used; maximum time in automatic control l
modes is not to exceed 20 minutes. Irradiations in manual l
control in excess of 20 minutes must be approved by the Reactor Manager in writing. ]
Rev. 10/81 App'd. Os SOP /VIII-13
O CL-1 CL-2 CL-3 CL-4 CL-5 N,
Systea Rabbit Rabbit Rabbit Rabbit ]
In Use Arrival Arrival In Arrival ]
Station Station Reactor ]
(216) (227) (228) (218) ]
CB-4 CB-5 CB-6 CB-3 Rabbit Manual Emergency RESET Dispatch Return Return CB-2 i CB-1 1 Automatic-off-Manual Circuit Selector ]
216-0FF-228 ]
(227) (218) ]
Figure VIII-l Control Station for Laboratories ]
216-228, 227-218 ]
O Rev. 10/81 App'd p - 50P/VIII-14
F t
Note: In rooms 216 and 218, insure that the desired timer v (2 seconds or 20 minutes) is selected and set for length ]
of irradiation time desired.
D. Press the " reset" button (CB-3). The system is now ready for use; the control light (CL-1) for " system in use" should be on.
E. Press the " rabbit dispatch" switch (CB-4).
F. Insert the rabbit. The air stream will carry rabbit through the system to the reactor.
G. Check that the rabbit trips the " rabbit in reactor" indicator light (CL-4).
H. Notify the reactor control room that the rabbit is in the reactor.
I. If the control (CB-2) is set on " automatic", the rabbit will be automatically discharged to the " catcher" located in the fume hood of the laboratory used as the operating site of the control station of the pneumatic tube system.
The rabbit arrival at the control station will be indicated
(] by the lights at either CL-2 or C1.-3 and CL-5.
J. If the control is set on " manual", the rabbit is inserted as in steps A, B, D, E, F, G and H. However, the experi-menter must depress the " rabbit return" switch (CB-5) to bring the rabbit back to the control station.
Note: The emergency return switch (CB-6) is not to be used for manual operations; its use is described in Section VIII.3.5, Emergency Procedures, below.
K. Notify the control room when the rabbit returns to the laboratory hood.
L. Place," station selector" switch to "off" position. ]
M. Press the " reset" button (see note below).
N. Place " auto-manual" switch to "off" position. (If buzzer ]
sounds, go through reset procedure again. If it still ]
sounds, notify control room.) 3
- 0. Call the control room and give the actual irradiation time O for the sempie, if different from estimete g4 en pr4or to irradiation.
Rev. 10/81 App'd . . ._ 50P/VIII-15
Note: Steps L-N reset the system for continuous air purge ]
to prevent excess Ar-41 generation. Failure to do so may ]
result in a facility license violation. ]
VIII.3.4.3 Aftt.c the rabbit has returned from the reactor, check the dose rate.
VIII.3.5 P-Tube Emergency Procedures VIII.3.5.1 The most common occurrences will be trouble with the station controls, the possibility of the rabbit sticking in the tube, and the rabbit coming apart in the pneumatic tube system.
VIII.3.5.2 Station Control Malfunction A. If the rabbit is in the reactor and is not automatically discharged, press the " emergency return" switch (CB-6) and notify the control room immediately.
B. If the rabbit is not in the reactor and station controls do not work, call the control room. The Reactor Operator g will then get in touch with the electronic technician.
Note: The experimenter is not authorized to attempt repair of the system.
C. Report to the control room the material contained in the sample, the expected activity and dose rate, and the approximate time the rabbit can remain in the reactor without creating any hazard.
VIII.3.5.3 Rabbit Stuck in Tube Any time all or any part of a rabbit fails to return to the ]
dispatch station, notify the control room immediately about the ]
problem, stating the material contained in the sample, the ]
weight of the sample, the expected activity and dose rate, and ]
the approximate time the rabbit can remain in the reactor ]
without creating any hazard or melting. ]
O Rev. 10/81 App'd l ' . __ S0P/VIII-16
A. After the control room is aware of the problem, press the ]
q V emergency return switch. Observe the rabbit in reactor ]
light (CL-4) and check with the control room to see if the ]
4 operators heard the rabbit leave the reflector region. ]
Note: CL-4 is not a true indication of rabbit location. ]
It simply indicates the electronic control signal to the ]
unit. Hearing the rabbit depart the reflector is the only ]
sure way to know it has lef t. If the rabbit was heard to ]
depart the reflector region, check the connecting station ]
to see if the rabbit was returned there. ]
B. Check the station lineup, verify the circuit selector ]
switch (CB-1) is selected to the proper station as ]
indicated by CL-2 or CL-3. ]
C. Depress the reset switch (CB-3). ]
D. Depress the dispatch button (CB-4) while observing CL-4. ]
E. Repeat steps A through D several times as directed by the ]
control room. ]
F. If the attempts fail, go to the connecting station, line it ]
Q up for service and repeat steps A though D. ]
G. If these procedures have failed, follow up action will be ]
handled by reactor operations and Health Physics personnel . ]
Note: If the rabbit is stuck outside the reactor it may be ]
found by searching the guide tubes with a radiation monitor.]
If the rabbit is stuck in the reflector, the reactor must ]
be shutdown and the p-tube removed. ]
VIII.3.5.4 Wet Rabbit If the outside of the rabbit is wet when it is returned from the reactor, notify the control room immediately.
Rev. 10/81 App'd .e' SOP /VIII-17
/ - _ _ _ _ .
VIII.3.6 Emergency Return of Rabbit with Malfunctioning P-Tube ]
Control Box ] O Dispatch and return of the rabbit is controlled by solenoids ]
in cabinet located by the seal trench. All solenoids in use ]
are labeled by letters in the solenoid cabinet. Procedure to ]
be followed in case of a failure at the local station is as follows:
A. Remove cover to solenoid cabinet. ]
B. Turn solenoid power switch off (this de-energizes all ]
solenoids). ]
Note: This closes off all tubes which will result in a ]
high concentration of Ar"1 if the reactor is operating. ]
Room 216 - R and J Dispatch solenoids ]
Room 218 - Q and N Dispatch solenoids ]
Room 227 - B and N Dispatch solenoids ]
Room 228 - A and J Dispatch solenoids ]
Refer to solenoid schedule. ] h C. Energize the P-tube blowers.
D. Then, " manually" depress following solenoids in solenoid cabinet.
Room 216 - U and L Return solenoids ]
Room 218 - V and 0 Return solenoids ]
Room 227 - G and 0 Return solenoids ]
Room 228 - H and L Return solenoids ]
As an example, the solenoids for return to room 216 should ]
be in the following positions: solenoids R and J "up"; ]
solenoids U and L "down". ]
VIII.4 Beamport Experiments ]
O Rev. 10/R1 App'd b' SOP /VIII-18
VIII.4.1 General Requirements As with all other experiments, beamport irradiations and measurements must be authorized by an approved RUR.
A. There are four major hazards involved with beamport experiments. They are:
- 1. Chr.nges in reactor reactivity due to beamport activi-ties such as draining or flooding a beamport.
- 2. Exposure of personnel to radiation as a result of movements of shielding or inadequate shielding.
- 3. Release of radioactive gases such as Ar-41 which are produced in the beamport.
- 4. A production of explosive or toxic materials in the beamport.
B. The limitations listed below are established to minimize or eliminate these hazards.
- 1. The AEC Regulations Title 10 Part 50 Section 50.54(j) require that " Apparatus and mechanisms other than controls, the operation of which may affect the reactivity or power level of a reactor shall be manipulated only with the knowledge and consent of an operator or Senior Operator licensed pursuant to Part 55 of this chapter present at the controls."
Because of this regulation, all beamport evolutions such as draining, filling or evacuating the port will be done by reactor operations personnel . Care must also be exercised in filling a drained beamport. The air within a drained port will be activated during reactor operation and this activated air is forced out of the port during the filling operation. These activated gases present a radiation hazard to personnel l in containment and can also result in a release of radioactive gases in excess of the license limit. This potential hazard is another reason for requiring that oa'r reactor operatio"s persoa"e1 be permitted to fi11-O i
Rev. 10/g1 App'd / '
. . . ,_ SOP /VIII-19
//
v _ __ _
drain, or evacuate a beamport. Whenever practical, all changes in beamport status shall be made only after h the reactor has been shutdown for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 2. All shielding movements (including temporary movements which will be returned to normal) shall be coordinated with Health Physics personnel . This restriction is necessary to insure that no personnel radiation hazard is introduced by movement of beamport shielding.
- 3. The gamma and neutron radiation levels in a beamport can easily induce chemical reactions which would normally require extreme temperature and/or pressure conditions in the laboratory. The Technical Specifica-tions are quite restrictive on the use of or the generation of explosive materials in an experiment. An experimenter should evaluate the possibility of the generation of explosives from any materials that are placed in a teamport experiment.
Section VIII.l.2 outlines the limitation on the use of toxic and flammable materials. This section is h
written to restrict the introduction of toxic and flammable materials in an experiment or in the contain-ment building. The experimenter is cautioned, however, that a toxic or flammable may be generated in a beamport from some perfectly harmless material, and thus should analyze the possible reactions from any material he introduces into his experiment.
Note: The experimental can may be flooded or drained ]
only when the reactor is shutdown. ]
VIII.4.2 Draining, Evacuating and Flooding BP "D" Collimeter and ]
Experimental Can ]
The following procedures shall be used in filling, evacuating, ]
and draining the BP "D" collimeter and experimental can. All ]
valve changes shall be made by reactor operations personnel. ]
A copy of this procedure shall be posted at the manifold. ] h Rev. 10/81 App'd Jf c SOP /VIII 20
A. Draining the Experimental Can ]
- 1. Check all manifold valves closed. ]
- 2. Check vacuum valve BP-D3 closed. ]
- 3. Check surge tank valves BP-D10 and BP-Bil open. ]
- 4. Place experimental can drain hose in poly-bottle then ]
open experimental can drain valve BP-D7. ]
- 5. Open experimental can outlet valve BP-D6 to drain as ]
much water from the lines as possible. ]
- 6. Close experimental can drain and outlet valves, BP-07 ]
and BP-06. ]
- 7. Close surge tank valves BP-D10 and BP-Dil . ]
B. Evacuating the Experimental Can ]
- 1. Check experiment can inlet, outlet and drain valves ]
closed: BP-DS, BP-D6 and BP-07. ]
- 2. Check surge tank inlet valve BP-010 closed. ]
- 3. Turn on vacuum pump located at mezzanine level. ]
Monitor the vacuua in manifold gauge. ]
Open vacuum valve marked BP-08. ]
Q 4.
Caution: If vacuum pump stop: during reactor operation,]
00 NOT restart the vacuum pump. An introduction of ]
air into the experimental can cavity could result in a ]
release of Ar-41 to the facility exhaust. The vacuum ]
l may be re-established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor is ]
shutdown or when authorized by the Reactor Manager. ]
C. Filling the Experimental Can
- 1. Close vacuum valve BP-08.
- 2. Secure vacuum pump if not required for other services.
- 3. Open experiment outlet valve BP-06 to release vacuum.
- 4. Open surge tank inlet valve BP-D10 and vent valve BP-Dil.
- 5. Open experiment can inlet valve BP-05 and fill surge tank to 1/2 full.
I
- 6. Close experiment outlet valve BP-06, and continue to fill surge tank to 1/2 full .
j
- 7. Close experiment inlet valve BP-DS.
Rev. 10/81 App'd, 4s SOP /VIII 21
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D. Evacuating Converging Collimeter
- 1. Turn on vacuum pump.
- 2. Open isolation valve BP-D9.
Caution: D_0, NOT evacuate the converging collimeter assembly]
unless the reactor has been shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or when ]
authorized by the Reactor Manager. ]
Note: The experimental can may be flooded or drained only ]
when the reactor is shutdown. ]
VIII.4.3 Draining, Evacuating and Flooding BP "E" Collimeter and ]
Experimental Can ]
The following procedures shall be used in filling, evacuating, ]
and draining the BP "E" collimeter and experimental can. All ]
valve changes shall be made by reactor operations personnel. ]
A copy of this procedure shall be posted at the manifold. ]
A. Draining the Experimental Can ]
- 1. Check all manifold valves closed. ]
]
O 2. Check vacuum valve BP-E8 closed.
- 3. Check surge tank valves BP-E10 and BP-Ell open. ]
- 4. Place experimental can drain hose in poly-bottle then ]
open experimental can drain valve BP-E7. ]
- 5. Open experimental can outlet valve BP-E6 to drain as ]
much water from the lines as possible. ]
- 6. Close experimental can drain and outlet valves, BP-E7 ]
i and BP-E6. ]
- 7. Close surge tank valves BP-E10 and BP-Ell. ]
B. Evacuating the Experimental Can ]
- 1. Check experiment can inlet, outlet, and drain valves ]
closed: BP-ES, BP-E6, and BP-E7. ]
- 2. Check surge tank inlet valve BP-E10 closed. ]
i
- 3. Turn on vacuum pump located at mezzanine level. ]
Monitor the vacuum in manifold gauge. ]
- 4. Open vacuum valve marked BP-E8. ]
lO i
Rev. 10/81 App'd_ .~ SOP /VIII 23 f/
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Caution: If vacuum pump stops during reactor opera- ]
tion, 00 NOT restart the vacuum pump. An introduction ]
of air into the experimental can cavity could result ]
in a release of Ar-41 to the facility exhaust. The ]
vacuum may be re-established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor ]
is shutdown or when authorized by the Reactor Manager. ]
C. Filling the Experimental Can ]
- 1. Close vacuum valve BP-E8. ]
- 2. Secure vacuum pump if not required for other services. ]
- 3. Open experiment outlet valve BP-E6 to release vacuum. ]
- 4. Open surge tank inlet valve BP-E10 and vent valve ]
BP-Ell. ]
- 5. Open experiment can inlet valve BP-E5 and fill surge ]
tank to 1/2 full. ]
- 6. Close experiment outlet valve BP-E6, and continue to ]
fill surge tank to 1/2 full. ]
- 7. Close experiment inlet valve BP-E5. ]
Evacuating Converging Collimeter ]
Q D.
- 1. Turn on vacuum pump. ]
- 2. Open isolation valve BP-E9. ]
Caution: 00 NOT evacuate the converging collimeter ]
assembly unless the reactor has been shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ]
or when authorized by the Reactor Manager. ]
i VIII.4.4 Operating Procedures for Beamport F ]
The following procedures shall be used for operation of Beam- ]
> port F. All valve and tube changes shall be made by reactor ]
operations personnel. Major shielding movements and all ]
center tube adjustments or changes shall be coordinated with ]
Health Physics and reactor operations personnel. All changes ]
in the operational status of this beamport should be coordin- ]
ated with Beamport E. A copy of this procedure shall be ]
posted near Beamport F and a copy shall be put in the Beamport ]
F Log Book. ]
i Rev. 10/81 App'd, /f u -- S0P/VIII 25
{ . - _ _ . _ . _ - .
The water level in the surge tank shall be checked and ]
maintained by operations. Makeup water should be " super" ]
water. ]
The principle experimenter should send a note to opera- ]
tions asking for a change in filters and tubes. The note ]
should reach operations before the shutdown. The principle ]
experimenter is responsible for verifying the desired ]
filtering material is in a center tube before it is inserted ]
and that it is covered in his RUR. To facilitate in verifying ]
materials, all filter parts should be marked and their storage ]
should be controlled because of their activation and potential ]
contamination. ]
A. Installing Center Tubes in Beamport F ]
- 1. Center tubes shall be installed into Beamport F only ]
with the reactor shutdown. ]
- 2. Verify the Beamport F center tube sealing "0"-ring is ]
in place and in good condition. ]
With Health Physics coverage, transfer the desired 3.
center tube from storage to Beamport F and insert it
]
]
g until contact is made with the ball valve. Note the ]
change in the Beamport Storage Log. ]
- 4. Lightly tighten the center tube "0"-ring packing nut; ]
check the drain valve and vent valve closed and open ]
the surge tank line valve. ]
- 5. Open the center tube ball valve and insert the center ]
tube. The center tube packing nut may need to be ]
adjusted so the tube can be inserted with minimal water ]
leakage. ]
- 6. With the center tube fully inserted, pull the tube out ]
the distance desired by the experimenter. It must be ]
pulled out at least 1/4 of an inch to allow for thermal ]
expansion. ]
- 7. The center tube end plate shall be removed and a rod ]
inserted in the tube to verify the filter slugs are at ]
the end of the tube closest to the reactor core. ] $
Rev. 10/81 App'd V_- SOP /VIII-26
p 8. The vacuum pump shall be hooked up and started before ]
the reactor is taken critical . The vacuum should be ]
applied slowly so that suction will not pull out the ]
filter parts. ]
- 9. A beamport radiation survey shall be completed after ]
the reactor is started up at 10 MW. ]
B. Adjustments to Beamport F Center Tube ]
The center tube shall only be adjusted with the reactor ]
subcritical. Adjustments include changing the distance ]
the center tube is from the core and pulling or adding ]
parts from the center tube. ]
- 1. Take the reactor subcritical before adjusting the ]
center tube. ]
- 2. If the center tube is moved, insure it is not closer ]
than 1/4 inch from being fully inserted. ]
- 3. After adjustments are made and vacuum restored, return ]
reactor to normal operations, and perform a Beamport F ]
O radiation survey.
Removing Center Tube from Beamport F
]
C.
The center tubes may be very activated. Therefore, close ]
Health Physics assistance is required. Minimize the ]
number of personnel in Beamports D, E, and F areas while transferring the center tube.
- 1. The center tube should be allowed to decay before moving from the beamport; preferably at least three days because of the sodium activity.
- 2. Place a plastic tube (s18 feet) over the center tube and tape the exposed end.
- 3. After loosening the packing nut, pull the center tube back slowly; when it is within one to two feet of being fully withdrawn, attempt to gently close the ball valve (be careful not to score the valve or the center tube).
- 4. When the ball valve closes, stop withdrawing the center O tube; ciose tne surge tenk iine veive, then open tne vent and drain valves.
Rev. 10/81 App'd % 50P/VIII 27 i,
- 5. Completely remove the center tube, pull the plastic tube over the end and tape.
O
- 6. Transfer the center tube to a beamport storage hole, log the change in the storage book, and survey around the storage hole.
Cautions:
Insure center tube is not left fully inserted; allow at ]
least 1/4 inch for thermal expansion. ]
After the center tube is inserted, verify the drain ]
and vent valves are shut. ]
. To prevent a partially filled beam tube leaving a crack ]
for radiation, be sure the vent tank has water in it. ]
To limit handling of a very radioactive filter tube, ]
pull the tube back four feet and let it decay for >2 ]
days before withdrawing it. Have Health Physics ]
coverage. ]
To limit tritium release, limit leakage of water. ]
To prevent excessive personnel exposure, make sure ] g filter pirts are in tube and pushed forward to reactor ]
end of filter tube. Apply vacuum slowly so that parts ]
are not sucked up. Have Health Physics coverage on ]
startup. ]
l After startup, check Health Physics readings against ]
previous readings with similar filters. ]
. Make it a habit to stay out of beams, whether they are ]
open or " closed". ]
Note: The experimental can may be flooded or drained only ]
when the reactor is shutdown. ]
VIII.4.5 Draining, Evacuating and Flooding BP "B" Collimeter and ]
Experimental Can l
The following procedures shall be used in filling, evacuating ]
and draining the BP "B" collimeter and experimental can. All ]
valve changes shall be made by reactor operations personnel. ]
A copy of this procedure shall be posted at the manifold. ]
Rev. lofg1 App'd 6- SOP /VIII-28
A. Draining the Experimental Can ]
k 1. Check all manifold valves closed. ]
- 2. Check vacuum valve BP-B8 closed. ]
- 3. Check surge tank valves BP-B10 and BP-Bil open. ]
- 4. Open experiment can drain valve BP-B7. ]
- 5. Open experimental can outlet valve BP-B6 to drain as ]
much water from the lines as possible. The experi- ]
mental can water draining into the pipe trench may be ]
extremely radioactive and consideration should be given ]
to collecting and transferring it to the D.C.T. ]
- 6. Close experimental can drain and outlet valves, BP-B7 ]
and BP-B6. ]
- 7. Close surge tank valves BP-B10 and BP-Bil. ]
B. Evacuating the Experimental Can ]
- 1. Chec'. experiment can inlet, outlet and drain valves ]
closed: BP-B5, BP-86 and BP-B7. ]
- 2. Check surge tank inlet valve BP-B10 closed. ]
O 3- Tura oa vecuum 9"=9 1ocated at mezzaa'ae 1 eve -
Monitor the vacuum in manifold gauge.
3
]
- 4. Open vacuum valve marked BP-88. ]
Caution: If vacuum pump stops during reactor operation,]
0_0 NOT restart the vacuum pump. An introduction of ]
air into the experimental can cavity could result in a ]
release of Ar-41 to the facility exhaust. The vacuum ]
may be re-established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor is ]
shutdown or when authorized by the Reactor Manager. ]
C. Filling the Experimental Can ]
- 1. Close vacuum valve BP-B8. ]
- 2. Secure vacuum pump if not required for other services. ]
- 3. Open experiment outlet valve BP-B6 to release vacuum. ]
- 4. Open surge tank inlet valve BP-B10 and vent valve ]
BP-Bil. ]
- 5. Open experment inlet valve BP-B5, adding water until ]
water exits from experiment outlet line. ]
Rev. 10/81 App'd, e.% S0P/VIII-29
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]
- 7. Close experiment inlet valve BP-BS. ]
D. Evacuating Converging Collimeter ]
- 1. Turn on vacuum pump. ]
- 2. Open isolation valve BP-89. ]
Caution: DO NOT evacuate the converging collimeter assembly]
unless the reactor has been shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or when ]
authorized by the Reactor Manager. ]
VIII.5 Handling and Release of Irradiated Samples VIII.5.1 General Responsibilities The Reactor Services Engineer shall coordinate the handling and shipping of all samples irradiated in the in-pool facilities.
He shall insure that the shipping container is in conformance with the applicable regulation and that all required shipping O PePers end documents ere PrePered in e timeiy menner.
The Services Engineer shall also coordinate the sample handling with Health Physics personnel.
The Shift Supervisor shall have the responsibility of insuring that all irradiation records are complete. He will immediately notify the Services Engineer of any apparent discrepancies relating to the in-pool irradiations.
VIII.S.2 Sample Handling Procedures Detailed procedures for the handling of various samples are ]
contained in the Health Physics Standard Operating Procedures. ]
VIII.6 Operating Procedures for the Nuclepore Irradiation Facility ]
The following procedures shall be used when operating the ]
Nuclepore Irradiation Facility. ]
O Rev. 10/81 App'd bw SOP /VIII- 31 l
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SOP /VIII-32 Rev. 6/80 App'd h/5 2
m e e i. ,i s, m -c u... y l
i VIII.6.1 New Roll Installation ]
General: New (unirradiated) rolls may arrive at MURR from ]
Nuclepore Corporation in two types of shipping containers. ]
The most common shipping container is the cardboard box ]
supplied by the vendor of the film. All boxes will be identi- ]
fied with a W-XXX number which will match an Irradiation ]
Request. ]
Sometime in the future, rolls of up to 300 pounds may be ]
shipped here in the Nuclepore shipping container. ]
This procedure is applicable to installation of any size ]
roll. ]
l A. Verify the roll to be installed matches the Irradiation ]
Request. Open the container. ]
B. Hoist the roll. ]
50 lb Container Large Roll Container ]
- 1. Lay sling on floor. 1. Check the roll to see ]
- 2. Lift the roll from the which way it will unwind. ]
box. Place roll on 2. Put the sling under the ]
sling. Remove core roll. ]
tube end inserts. 3. Attach the sling to the ]
- 3. Check the roll to see hoist hook. ]
which way it will 4. Lift sufficiently to ]
unwind. slide the roll off the ]
- 4. Attach sling to the shaft of the container. ]
hoist hook. ]
- 5. Insert expanding air shaft and adapter into the core ]
tube of the roll. ]
Note: The adapter may be inserted in the core tube in ]
either direction but the splined air shaft must be ]
inserted so that with the splined end to the right on ]
the unwind stand, the film roll unwinds away from the ]
reactor. ]
- 6. Center the adapter and shaft (approximately) in the ]
]
Q core tube.
Rev. 10/g1 App'd, h S0P/VIII 33
- 7. Inflate the air shaft.
Note: When inflating the sir shaft, apply air pressure ]
] g for three or four seconds. Rapidly remove the air ]
nozzle while holding the valve open. This prevents ]
releasing the air from the shaft. ]
- 8. Hoist the roll to the unwind shaft bearing cradle and ]
lower it onto the bearings. ]
C. Close and latch the bearing caps on each end of the roll. ]
D. Remove the sling. ]
E. Couple the unwind shaft to the tension control shaft and ]
clip the coupling retainer onto the splined shaft. ]
F. Remove the covering from the roll and save it for wrapping ]
the irradiated roll. ]
G. Obtain the film width from the Irradiation Request. The ]
film width of Markrofol or Hostaphan film is given in ]
millimeters. The width of Mylar is given in inches. The ]
widths of film used, expressed in mm and inches are: ]
508 mm, 20"; 495 mm, 19.5"; 465 mm, 18.3"; and 434 MM, ] g 17.1". ]
H. Measure the film width to see that it corresponds with the ]
Irradiation Request and roll width data. ]
I. Splicing the new film to the film in the irradiation. ]
- 1. Pull the film down off the roll and, holding the film ]
web with both hands so that the web is smooth, see if ]
l the edge matches the position specified for the width ]
of the film. The position indicator is on a bakelite ]
tray attached to the polyethylene below the unwind ]
I stand. It is probable that the edge of the film will ]
not match the specified position. If not, two methods ]
! are available for moving the edge of the film. ]
l a. The entire unwind stand may be moved sideways (it ]
l has about 1-1/2" of travel). It is positioned by ]
the edge guide system located above on the left. ]
O Rev. 10/81 App'd, . SOP /VIII 34
- b. The roll may be released from the unwind shaft by ]
releasing the air and then moved from side to side ]
on the shaft. Make certain that the shaft is ]
properly inflated when the move is completed. ]
Note: The position of the edge of the film is very ]
important. If the film enters the irradiator case ]
excessively off center, the edge of the film can be ]
snagged by components internal to the irradiator ]
case with serious consequences. ]
- 2. Put a strip of 3M double backed tape across the new ]
roll along a line about at the level of the center of ]
the shaft. The tape should be cut to a length and ]
positioned so the ends of the tape are even with or ]
slightly inboard from the edges of the film. Remove ]
the end of the film below the tape, leaving no more ]
than one inch of film below tape. Strip the backing ]
off the tape. ]
Grasp the cut off end of the film which passes into ]
O 3.
the irradiator by the edges and pull it so that it ]
contacts the first idler roll below the unwind roll. ]
The film should contact the roller smoothly. Lift the ]
film around the unwind roll until it contacts the ]
double-backed tape. Press the film onto the tape and ]
cut or tear off the excess film. Leave no more than ]
l one inch of film excess above the tape. ]
- 4. If the new roll of film is wider than the in-machine ]
film, cover any exposed double-backed tape with two ]
small pieces of film. If the new roll is narrower, the ]
unattached edges of the film entering the irradiator ]
should not cause a problem. ]
l J. Unlatch and lower the small roll sensor so that it rests on ]
l the new roll. ]
K. Mark a black line across the splice with a felt-tipped pen. ]
L. Turn on unwind stand edge guide (main power must be on). ]
l O
Rev. 10/81 App'd , S a- SOP /VIII 35 L
M. If unwind stand moves to a position so that the film edge is not aligned with the mark for the width of the film,
]
]
g position the unwind edge guide sensor so that the film edge ]
is in the proper position. ]
If the unwind film roll was positioned properly when ]
the roll was installed, the unwind stand should be centered ]
so that the edge guide system has about equal travel room ]
to both right and left. If there is less than 1/2" on ]
either side, start over. ]
VIII.6.2 Pre-Operational Startup ]
A. General ]
- 1. Standard shutdown conditions will be rabbit retracted, ]
no helium addition to irradiator case, main switch off ]
on Cabinet A, and with pump Pl-B operating and Pl-A on ]
standby, (We will leave Pl-B running until it fails, ]
then change it out and run Pl-A to failure, etc.) ]
- 2. Operating the gas system under these conditions should ]
assure that all valves are continuously in their normal ]
operating position; however if the system is shutdown ]
during an outage, the valve lineup should be checked. ]
B. Electrical ]
- 1. Check that disconnect switch is closed. ]
- 2. Turn on MAIN switch on Cabinet A. ]
- 3. Check that power switch is ON on Cabinet B. ]
- 4. The 02 monitor must be on for ten minutes to allow it ]
l to come to equilibrium. ]
C. Start Helium Flow to Irradiator Case ]
- 1. Check helium supply at bottle station. ]
l a. One full bank should be on standby and the other ]
bank supplying helium to Cabinet B. ]
l
- b. If the setting of the regulator of the standby ]
bottle is not known, it may be checked and set by ]
appropriate valving. (A bleed valve is installed ]
Rev. 10/81 App'd E - SOP /VIII 36
downstream of the regulator to verify setpoints.) ]
The regulator for the inservice bank should be set ]
at 30-32 psig and the standby bank should be at ]
26-28 psig. ]
- 2. At Nuclepore Cabinet A: ]
- a. Calibrate 02 monitor ]
(1) To calibrate the 02 monitor, about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of ]
no helium flow is required to fill the irradi- ]
ator case with air. ]
(2) With air in the case, and the 02 monitor on the ]
0-25% range, turn calibration knob to bring ]
indicator to 21% mark. If it will not come in ]
- o calibration the case may have helium in it ]
or the 02 sensor must be rejuvenated (refer to ]
Beckman Manual). ]
- b. Set PIC-1 at 0.04" W.C. ]
- c. Set PIC-2 at 0.03" W.C. ]
O d. Check that one pump switch (of P1-A or Pl-B) is in ]
" HAND" position and the other in "AUT0". ]
- e. Check that the indicator for the ON pump is lighted.]
- f. Check that PISH-3 and PISH-4 are not below trip ]
point. Low trip point on each should be set at ]
full left position. High trip point at 0.15. ]
- g. Check that Low Helium light on Cabinet A is clear ]
(off). ]
- h. Open helium supply valve, and adjust flow as high ]
as possible without a low trip on PISH-3. ]
- i. Following the initial setup for helium addition, ]
re' turn periodically to recheck the helium addition ]
rate. ]
- j. When 02 concentration reaches 5 to 8% film irradi- ]
ation may start. This will require thirty minutes ]
to one hour. ]
O
! Rev. 10/81 App'd b- - S0P/VIII 37
/
VIII.6.3 Start Film Drive ] g A. Press switch TD Relay. ]
B. Set speed selector to approximately 3 m/ min and press ]
motor start switch. Immediately check through side and ]
top shield windows. ]
- 1. First, through side window. See that drive roll is ]
turning and that there is no slack film on top of drive ]
roll. ]
- 2. See that film is entering Irradiator Case at approxi- ]
mately the correct position for the width of the film. ]
Note: For 18.3", 465 mm and 17.1", 434 mm wide film; ]
the position is relatively unimportant. For 20", ]
508 mm and 19.5", 495 mm; the film must enter the case ]
within rather narrow limits. ]
C. Run film sufficiently to set the rewind edge guide sensor ]
so that it is rewinding the film properly on the rewind ]
rolls. ] g D. Decrease speed to s2 m/ min. ]
E. Shutdown the motor. ]
VIII.6.4 Irradiate Film ]
A. With the drive motor dial set at approximately 3, run the ]
film for 5 meters to move any weak film out of the irradi- ]
ation zone. ]
B. Stop the drive motor. ]
l C. Mark the film on the unwind roll: ]
Start I.R. ]
Sseed Rabbit Pos. Rod Bank ]
Film No. W Date and Time ]
l D. Check rabbit position indicator calibration. ]
- 1. With rabbit retracted and the slack out of the rabbit ]
drive system (handle moved counterclockwise), the ]
l position indicator should read 0.00 .05. If it is ]
O l
Rev. 10/81 App'd (2 SOP /VIII 38 f s
not on 0, report this to the Reactor Operations ]
Engineer or Chief Research Electronic Technician. ]
- 2. Move rabbit to full in position - about 5 turns counter-]
clockwise on the crank wheel. The rabbit will bang to ]
a stop at the full in position. ]
Move the rabbit at a reasonable speed, it weighs ]
100 lbs and could break something if rammed against the ]
stop. ]
- 3. With rabbit full in, after about a minute, the position ]
indicator should reach equilibrium at 4.00 .05 (this ]
indication is feet of travel). ]
If the reading is between 3.90 and 4.10, reset it ]
to 4.0 .05. If it is outside this range it may be ]
faulty. If deemed to be faulty, back the rabbit out ]
and stop the irradiation preparation. Advise Reactor ]
Operations Engineer. ]
- 4. After rabbit position indicator is calibrated, back it ]
out past the set point desired and continue procedure. ]
Q E. Move rabbit in to position specified by Irradiation Request.]
- 1. Approach rabbit set point cautiously and arrive at set ]
point while moving from out to in (counterclockwise on ]
operating wheel). ]
- 2. If the set point is over-shot, back the rabbit out and ]
move in to set point. ]
- 3. If set point is 4', move rabbit in until it stops. ]
Note: If the rabbit is inserted, the film must be set ]
in motion within 15 minutes. If the film is stopped ]
during a film irradiation, the rabbit must be retracted ]
within 15 minutes. ]
F. Start the drive motor and bring it to speed of Irradiation ]
Request. ]
G. Put a mark on the film. ]
H. Reset film odometer and run time. ]
I. Record appropriate start of run data on Irradiation Request.]
Rev. 10/81_ App'd , b - 50P/VIII 39 f
Observe operation for about 10 minutes to adjust any drift ]
J.
of film drive speed controller. ]
g K. As you leave the irradiator, call the control room to ]
activate tne alarms. Make certain the machine js running ]
as_ the alarms are activated. ]
VIII.6.5 Termination of Film Irradiation ]
A. Small Roll Alara ]
- 1. When the unwind roll is down to the point where the ]
remaining film on the unwind shaft is about 1/4" thick, ]
the small roll alarm will sound in the control room. ]
- 2. When the small roll alarm sounds, an operator should ]
go to the irradiator and raise and latch the roll ]
follower. ]
B. Observe the thickness of film remaining. One fourth inch ]
of film on a six inch core tube represents (about) the ]
following film length: ]
O 24 gage (6u) 670 m ]
40 gage (10u) 400 m ]
48 gage (12u) 330 m ]
60 gage (15u) 270 m ]
80 gage (20u) 200 m ]
- 1. Film which is running at 5 m/ min or less which is 83 ]
material (3 x los holes /cm 2) is 40 gage or 24 gage. ]
At 5 m/ min it can be seen that the 400 meters of 40 ]
gage film will run about one hour following the small ]
roll alarm. ]
- 2. Film running at 15 m/ min 81 material (1 x 10e holes /cm2 )]
will have only 20 minutes remaining on the roll and, ]
of course, film running at more than 15 m/ min will have ]
corresponding shorter times. ]
- 3. Material with 5 x 107 (75 material) holes /cm2 or less ]
will be at faster speeds and use thicker film and will ] g Rev. 10/81 App'd 7 d - SOP /VIII 40
therefore have to be either continuously attended ]
during irradiation or the response to the small roll ]
alarm will have to be prompt. ]
Note: If the operator can remain on the Nuclepore ]
station to allow some of this film to be irradiated, ]
it is advantageous to do so. If time does not permit ]
this, proceed to film shutdown (Step C). ]
C. When about 1/8" of film is left on the unwind roll, mark ]
the film with a black line. ]
D. After the film has proceeded 10 meters beyond the mark, ]
slow film speed to less than 5 meters / min. ]
E. Stop the film by pushing the Motor Stop switch and with- ]
draw the rabbit. ]
F. Mark the film: ]
End M77P9 (appropriate identification) ]
meters (from metering run gage) ]
time ]
O date ]
G. Fill out Irradiation Request Fonn. ]
H. Press TD Relay and motor start switch and run the film ]
until the marked film is wound on the rewind roll. ]
I. Shutdown drive motor. ]
l J. Shutdown the following system: ]
l
- 1. Control Cabinet A ]
Note: Make sure meter and time readings have been ]
recorded on Irradiation Request Forms. ]
- a. Upscale 02 monitor to 0-25% scale. ]
- b. Turn off MAIN power. ]
l
- c. Turn off lights. ]
l
- 2. Control Cabinet B ]
- a. Turn off helium at flowmeter regulator. ]
O Rev. 10/81 App ', d [- > ' SOP /VIII 41
VIII.6.6 Remove Shield Box Cover 3 g
General: At least eight hours should pass following irradia- ]
tion of a roll or advancement of the film to allow radiation ]
and contamination levels to decay to reasonable levels. Make ]
certain irradiator case pressure is negative. ]
A. Preparation ]
- 1. Remove retaining clip and disconnect rewind shaft frcm ]
rewind drive shaft by moving female splined coupling ]
away from rewind shaft. ]
Note: Coupling must be moved so that it is against ]
the shoulder on the splined shaft. ]
- 2. Turn on lights. ]
- 3. Hook up lifting yoke to eye bolts on the shield box ]
cover. ]
- 4. Connect crane hook to the lifting yoke with the load- ]
cell between the hock and the yoke, ]
- 5. Remove sufficient beamport shielding from the deck to ]
allow movement of shield box cover away from the ]
reactor about two feet. ]
B. Lift the Cover ]
- 1. Carefully raise the hook (in small steps) until the ]
load cell indicates 3600 pounds. ]
- 2. Remove the wedges (blue wedges) which hold the cover on ]
the shield box. ]
- 3. Move shield box cover away from the reactor until it ]
clears the roll and bearing supports of the unwind ]
shaft. ]
Measure the y radiation level as the cover is ]
moved away. If greater than 300 mrem /hr more decay ]
time may be in order. ]
- 4. Move the cover away and set it on the deck grating ]
near the hand rail. ]
O Rev. 10/81 App'd C s '- SOP /VIII 42
4 i
I VIII.6.7 Remove Irradiated Roll from Rewind Stand ]
General: Consider all items inside the shield box as con- ]
taminated. Experience has shown contamination to be smearable ]
but fixed sufficiently so that it does not blow around. The ]
contamination levels on the bowed roller (light colored rubber) ]
and the lay-on roller (black roller) will be quite high. The ]
pinch roll (black rubber) will also be contaminated but it is ]
l relatively inaccessible. ]
A. Make sure the splined shaft coupling is disconnected from ]
the rewind roll shaft. ]
B. Raise LAY-0N. ]
! C. Cut the film near the roll. ]
D. Secure the end of the film on the roll with scotch tape. ]
E. Wrap a layer of plastic around the roll and secure it with ]
tape. ]
F. Open the bearing caps. ]
G. Depending on roll size, follow procedure below. ]
- 1. Fifty pound roll ]
- a. Lift the roll off the unwind stand and lay the roll ]
on a piece of sponge rubber. ]
f b. Deflate the unwind shaft and remove it and the ]
adapter from the roll. ]
- c. Set the shaft and adapter on paper. ]
- d. Tuck the ends of the plastic roll wrap inside the ]
core tube. ]
l e. Lift the roll and place it in the box it came out ]
of. ]
- f. Insert core tube shipping adapter in the end of the ]
core tube. ]
- g. Close the box with duct tape. ]
i
- h. Write roll I.D. number on box. ]
l i. Have Health Physics survey the box and record ]
appropriate radiation level on the box. ]
]
Q j. Move the box to storage.
Rev.10/81 App'd Oc --
SOP /VIII 43 i . ,
- 2. Greater than fifty pound roll (up to 300 lbs) ]
- a. Have either a shipping container or a roll support ] O stand available to hold the roll. ]
- b. Place the large sling around the roll and lift it ]
off the unwind stand with the MURR c'rane. ]
- c. Deflate the unwind shaft and remove it and the core ]
tube adapter from the roll. It is convenient to ]
store the adapter and rewind shaft back on the ]
rewind stand. ]
- d. Place the film roll on the cantilevered shaft of ]
the shipping container or the roll support stand. ]
- e. Remove the sling. ]
- f. If the shipping container is used, place the ]
retainer ring on the shaft to hold the core tube ]
in place and install the shipping container cover. ]
- g. Mark the container or roll with the radiation level ]
and move the roll or container to storage. ]
VIII.6.8 Install New Core Tube on Rewind Stand ]
A. Put core tube adapter and rewind shaft inside core tube. ]
Note: Make sure core tube is wide enough for the next ]
roll. ]
B. Center the adapter and shaft in the core tube. ]
C. Inflate the unwind shaft. ]
D. Put the assembly on the bearings and close and latch the ]
bearing caps. ]
E. Paint the north end of the core tube black. ]
With measuring tape, mark the center of the core tube. ]
F.
G. Measure from inside of left bearing block to the center of ]
l the core tube. The center should be 12" 1/8" from the ]
inside edge of the left bearing block. ]
H. If necessary, deflate the rewind shaft, relocate the core ]
tube and re-inflate the shaft. ]
I. Pull the film end from the raised lay-on roll to the core ]
tube and lay it smoothly over the core tube. ]
Rev .10 /g1 App'd _k. - - SOP /VIII 44 l
J. Turn the Raise Lay-On valve so that Lay-On roller returns ]
to the core tube. As the roller starts toward the core ]
tube, pull the edges of the film to keep the film taut. ]
K. When Lay-On has returned to the core tube, trim the film ]
as necessary and fasten the film to the core tube, at the ]
center only, with a peice of scotch tape. ]
L. To make the future operation of coupling the rewind shaft ]
to its drive shaft, align and rotate the rewind shaft as ]
necessary to find the place where the coupler will engage. ]
Disengage the coupling leaving the shaft in this position. ]
Making this alignment prior to replacing the shield box ]
cover will make it easier to perfonn that job with the ]
shield box cover in place. ]
VIII.6.9 Install Shield Box Cover ]
A. Lift the shield box cover using MURR crane and Nuclepore ]
dynamometer and lifting yoke. ]
O B. Check to see tnet rewind sneft coupiing is fuiiy retracted ]
from rewind shaft onto the splined drive shaft. ]
C. Move the shield box cover into position so that the holes ]
in the shield box cover flange align with the slotted pins ]
protruding from the shield box. ]
D. Push the box cover into place. ]
Note: Once the pins are in or partially in the holes in ]
the box cover, use extreme care in moving the crane. ]
Observe the dynamometer to avoid any lift in excess of the ]
3600 lb weight of the shield box cover. A lift of the ]
shield box of only a part of an inch could cause great ]
damage to the equipment. ]
E. When the cover is seated onto the shield box, insert the ]
tapered wedges into the pins and drive them home with a ]
hammer. When the tapered pins are seated, the hammer blow ]
gives a distinctive sound. ]
F. Lower the crane hook and remove the lifting yoke. ]
O l
Rev. 10/81 App'd s v SOP /VIII 45
-- - . . __ ? - _ _ - - _ . . , _ - - . _ _ _ _ - _ .
G. Couple the rewind shaft by sliding the coupling toward the ]
rewind shaft. ]
H. Install the rewind shaft coupling retainer (plexiglass ]
semicircle s 2" long). ]
I. Run about two or three meters of film to see that the ]
rewind system functions properly (see procedure - Start ]
Film Drive,Section VIII.6.3). ]
J. Shutdown the system (see procedure - Termination of Film ]
Irradiation,Section VIII.6.5). ]
VIII.6.10 Response to Nuclepore Alanns in MURR Control Room ]
A. Alarms ]
- 1. Small roll ]
- 2. PISH-5 (will give concurrent Gas System Alarm) ]
- 3. 02 supply (mislabeled - should be High 02 ) 3
- 4. Helium supply ]
- 5. Alarm System Failure ]
B. Response to Alarms ] h
- 1. Small roll ]
Unwind roll is about out of film. See procedure - ]
Termination of Film Irradiation,Section VIII.6.5. ]
- 2. PISH-5 (with Gas System Alarm) ]
- a. Check PISH-5 reading in Cabinet C. If it is above ]
5" H2 0(low trip point), whatever had caused the ]
trip has corrected itself and the system will ]
continue to function without any safety implica- ]
tions. The only action necessary is to attempt to ]
diagnose the cause of the disturbance. PI 13 and ]
14 will tell which pump (s) are functioning satis- ]
factorily. They are normally full scale when the ]
pump is running. If both are functioning, they can ]
be returned to normal operation (one running, one ]
not running) by resetting PISH-5. If the one on ]
AUTO is running and the one on HAND is not running, ]
O Rev. 10/81 App'd P SOP /VIII 46
l there has been either a mechanical or electrical ]
failure. ]
Note: Any electrical interruption (i.e., auto- ]
! matic bus transfer shifting) will cause this alarm ]
to pick up. It may be cleared by cycling the reset ]
l switch on Control Cabinet B. ]
- b. If PISH-5 is below the trip point (5") neither pump ]
is functioning properly and it will be necessary to ]
- shutdown any irradiation in progress. Proceed to ]
the Nuclepore experiment on the Beam Port floor, ]
shutdown film drive, withdraw the rabbit, mark the ]
film and shut off the helium supply. ]
Following this, attempt to find the problem ]
with the pumps and restore suction. ]
- 3. 02 Supply (Should be High 02 ) 3
- a. This indicates that the 02 concentration in the ]
irradiator case is greater than 16%. When not ]
O irradiating film this is normal except that generally the 02 monitor will be out of service.
]
]
- b. If film irradiation is in progress: ] ,
(1) Proceed to Nuclepore experiment. ]
(2) Check range setting on 02 monitor. ]
(3) If 02 > 16%, check to see if relationship ]
between PISH-3 and 4 is normal, that is PISH-3 ]
not above set print of PT-1 and within 0.02" ]
of being same pressure at PISH-4. ]
(4) Check that Helium flow is about 4 to 7 units ]
on FI-10. Increase this flow as permissible ]
without tripping PISH-3. ]
! (5) Observe 02 concentration after increasing He ]
flow. If it starts down, proceed with irradi- ]
ation. ]
(6) If you are unable to immediately reduce 02 ]
l concentration, shutdown the film drive and ]
withdraw the rabbit. ]
Rev. 10/81 App'd, & SOP /VIII 47 i /
Note: If high 02 concentrations persist, ] g extremely high radiation levels may exist. ]
Observe Nuclepore ARMS reading if > 50 mrem ]
immediately secure irradiation. ]
- 4. Helium Supply ]
- a. Proceed to helium supply station to see if bottles ]
are full and valved on. ]
- b. If there is output pressure from the bottle station,]
proceed to Nuclepore console. ]
- c. If helium is still flowing to irradiator case there ]
is an electrical or mechanical problem with the ]
mercoid switch which senses helium supply pressure. ]
As long as helium continues to flow and the 02 3 concentration is satisfactory, the irradiation may ]
continue. ]
- d. If there is no helium flow, shutdown the drive ]
motor, withdraw the rabbit, mark the film and ]
attempt to find the reason. Notify Reactor Opera- ] $
tions Engineer. ]
- 5. Alarm System Failure ]
Proceed to Nuclepore irradiator, shutdown the film ]
drive, withdraw the rabbit, mark the film and notify ]
the Reactor Operations Engineer. ]
This alarm results if power is lost to the 24 V AC ]
supply to all shutdown and alarm relays. ]
The gas system and drive system will probably be ]
shutdown. ]
C. Alarms from Sensors Associated with Film Drive Shutdown ]
- 1. Large Roll - roll reaching limit of size of shield box. ]
- 2. Supply (Unwind) Dancer - off normal. ]
, 3. Takeup (Rewind) Dancer - off normal. ]
1 l 4. Gas System - PISH PISH-4 low trip. ]
l 5. Drive Power - film drive motor shutdown. ]
1 O
l Rev. 10/81 App'd -
SOP /VIII- 48
D. Responses to Above Alarms ]
Note: Alarms A, B, C, D - all are programmed to shutdown ]
the film drive motor and should come along with the drive ]
power alarm. ]
- 1. The response to any of the above alarms is to proceed ]
to the irradiator, retract the rabbit (within 15 ]
minutes of shutdown) and mark the film. Note the film ]
shutdown on the Irradiation Request. ]
- 2. With the rabbit withdrawn there is time to analyze the ]
problem. ]
- a. If the rewind roll has become large enough to trip ]
the large roll sensor, the proper action is to get ]
the rewind roll off after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> decay time. If ]
this is not practicable before 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> passes, ]
the trip may is bypassed inside Cabinet A and the ]
film run through as required. ]
- b. Problems with the unwind dancer reaching the off ]
nonnal trip position, which is the position with ]
O the air pistons fully extended, have resulted from ]
instabilities at film speeds above 15 m/ min. The ]
tension amplifier has been adjusted to a less sensi-]
tive response to film tension variance, however, it ]
may be necessary to personally attend the machine ]
l for 20 to 30 minutes to stop the oscillations. As ]
the roll becomes smaller the oscillations go away. ]
With the rabbit withdrawn, note the position ]
(meters of shutdown) and start the film at speci- ]
fied speed. If the film runs satisfactorily, stop ]
the drive, mark the film, insert the rabbit and ]
start the irradiation again. If the shutdown ]
repeats, stop the irradiation and withdraw the ]
rabbit. Mark the film and advise the Reactor Opera-]
tions Engineer. ]
O Rev. 10/81 App'd -
SOP /VIII 49
/
- c. Takeup Dancer (Rewind Dancer) trips may come from ]
instabilities as above or from problems in the ]
film handling system between the film drive and ]
the rewind roll. If the film path seems normal, ]
i.e., no wrap-up or film breaks evident after the ]
drive roll, restart the film drive and observe the ]
operation to see if the problem is evident. If the ]
system operates satisfactorily, stop the film drive,]
insert the rabbit, mark the film and resume film ]
irradiation. ]
If film problems are apparent, correction will ]
normally require removal of the shield box cover. ]
- d. Gas system faults, if correctable by changing set ]
points or repairing results, may allow film ]
irradiation to resume. ]
- e. A drive power alarm alone means that the motor ]
starter has opened the power circuit to the motor ]
either because the motor is over-loaded or some ] g other over-current has caused the motor starter to ]
drop out. In any case, it is a problem for the ]
electrical people. Do not attempt restart without ]
finding the source of the problem. ]
VIII.6.11 Shutdown Film Advancing ]
Caution: Ensure compressed air is supplied to control Cabinet ]
A and supply, take-up, lay-on, and pinch air pressures have ]
positive indication. ]
A. Check or turn on main power to control Cabinet A. ]
B. Turn on lamp. ]
C. If supply or take-up dancer trip is present, engage TD ]
by-pass. Immediately proceed to Step D. ]
Note: TD bypass is a shutdown override. It exists for ]
approximately five seconds and then clears itself. ]
O
/ '
Rev. 10/81 App'd- .C SOP /VIII 50
l
]
l C D. Turn on drive motor.
Note: Ensure take-up reel is turning. If not, immediately ]
stop machine. ]
E. Run film approximately five (5) meters at four (4) to ]
five (5) meters per minute. ]
F. Turn off drive motor. Leave speed set at running speed. ]
G. Turn off lamp. ]
H. Log entry. ]
O O
j/'- ~ SOP /VIII 51 Rev. 10/81 App'dys'--
i I
l NOTE: THIS PAGE INTENTIONALLY LEFT BLANK O
Rev. 10/81 App'd f ' SOP /VIII 52
i I
i i
3 REACT 0R E M E R G E 11 C Y PR0CEDURES i
l
.i i
O
INDEX OF EMERGENCY PROCEDURES
~
SECTION NO. PAGE NO.
EP-I GENERAL FACILITY EMERGENCIES . . . . . . . . . . . . . EP-I-1 EP-I.0 Classification of Emergencies. . . . . . . . . . . . . EP-I-l EP-I.1 Facility Evacuation Plan . . . . . . . . . . . . . . . EP-I-4 EP-I.2 Reactor Isolation Plan . . . . . . . . . . . . . . . . EP-I-8 EP-I.3 Fire Plan. . . . . . . . . . . . . . . . . . . . . . . EP-I-11 EP-I.4 Medical Emergency Plan . . . . . . . . . . . . . . . . EP-I-12 EP-I.5 Security Procedures. . . . . . . . . . . . . . . . . . EP-I-15 EP-II REACTOR EMERGENCIES. . . . . . . . . . . . . . . . . . EP-II-l EP-II.1 Failure to Scram or Rod Run-In . . . . . . . . . . . . EP-II-l EP-II.2 Reactor Scram from Causes Other than Loss of Flow or Pressure. . . . . . . . . . . . . EP-II-2 EP-II.3 Reactor Scram from Loss of Primary System Pressure or Flow. . . . . . . . . . . . . . . . EP-II-2 EP-II 4 High Radiation . . . . . . . . . . . . . . . . . . . . EP-II-2 EP-II.5 Nuclear Instrument Failure . . . . . . . . . . . . . . EP-II-3 EP-II.6 Failure of the Area or Process Monitoring System. . . . . . . . . . . . . . . . . . . EP-II-3 EP-II.7 Failure of Intercom System . . . . . . . . . . . . . . EP-II-3 EP-II.8 Control Rod Drive Failure. . . . . . . . . . . . . . . EP-II-4 EP-II.9 Electrical Anomalies . . . . . . . . . . . . . . . . . EP-II-4 EP-II.10 Failure of Experimental Apparatus. . . . . . . . . . . EP-II-6 EP-II.11 Backup Isolation Doors: Radiation Detector Alarm . . . . . . . . . . . . . . . . . . . . EP-II-6 EP-II.12 Loss of Service Water to the Facility. . . . . . . . . EP-II-7 EP-II.13 Loss of Secondary Flow . . . ............. EP-II-8 EP-II.14 Loss of Pool Flow During Reactor Operation. . . . . . . . . . . . . . . . . . . EP-II-9 EP-II .15 Loss of Pool Water During Reactor Operation. . . . . . . . . . . . . . . . . . . EP-II-9 EP-II .16 Valves 507A/B Fail to Close. . . . . . . . . . . . . . EP-II-ll EP-II.17 Pressurizer Valves Fail to Operate . . . . . . . . . . EP-II-ll O
Rev. 10/81 App'd i
INDEX OF EMERGENCY PROCEDURES (continued)
PAGE N0.
O SECTION N0.
EP-II.18 Anti-Syphon Valves . . . . . . . . . . . . . . . . . . EP-II-il EP-II .19 Emergency Core Cooling Valves 546A/B . . . . . . . . . . . . . . . . . . . . . . . . EP-II-12 EP-II.20 High Activity Levels in the Primary Cooling System . . . . . . . . . . . . . . . . EP-II-13 0
l Rev. 10/81 App ' d , .(b . ii
)
EP-I GENERAL FACILITY EMERGENCIES EP-I.0 Emergencies are classified as follows:
A. Facility Evacuation - Emergencies of any type which require all personnel in the Facility to leave the premises.
B. Reactor Isolation - Emergencies limited to the reactor containment building which require all personnel in the containment to leave containment.
C. Fire - Emergencies which may or may riot involve A or B and which may require personnel to leave the premises.
D. Medical - Emergencies involving injury to personnel but which may or may not involve situations A, B or C. These injuries may but do not necessarily involve radiation exposure or radioactivity contamination.
E. Security - Emergencies involving (1) the actual theft of special nuclear material and/or the sabotage of the O facility or (2) an attempt or threat of theft or sabotage will be handled by the procedures outlined in the Reactor Security Procedures.
Emergencies A and B are announced by a continuous sounding of the horns located throughout the Facility. There is no difference in the sound of the horns for a Facility evacuation or for a reactor isolation, however, only those horns in the containment sound when a reactor isolation occurs. Fires not associated with A or B above will be announced over the public address system with appropriate instructions for all personnel.
Security emergencies may result in the manual initiation of an evacuation to clear all personnel from the building.
!O Rev. 10/81 App'd M- EP-I-l
/
( ( (
y LP-I.0.1 Description of Radiation Alams and Personnel Response
< Facility Staff Personnel Non-Staff Personnel Response Response System Responsible for Alarm location of Sensors Audibic location Type of Alam a,
N Viroughout llorn a $ Decute reactor isolation D ecute reactor isolation g 1. Isolation System a. Ibnual Swinh in plan plan Control Room Containment
- b. Air plentan (AR}D (fifth level)
- c. Reactor bridge (ARM)
$' d. Air plenum BU monitor o becute facility becute facility
- 2. Evactution System a. Control Room Viroughout ilom a $ evacuation plan i b. Front lobby Facility evacuation plan Cause israediate area to Vacate containment;
- 3. Gas Ibnitor (portable) Variable in Containment local Bell Notify Reactor be vacated and notify Reactor Operations Operations Bell and red light Cause innediate area to Vacate containment;
- 4. l' articulate Ibnitor Variable in Containment Local be vacated and notify Notify Reactor Reactor Operations Operations
- 5. Area Radiation bbnitor a. South wall-BP Floor local; Control Rm Buzzer and red light
- Cause inanediate area to Vacate imediate area (APJO be vacated and notify
- b. West wall-BP Floor licalth Ihysics
- c. North wall-BP Floor
- d. Fuel Storage Room
- e. Ileat & changer Room
- 6. Ifand and Foot tbnitors ibin Corridor and Bu::cr and red light Notify llealth Ihysics 4 Notify IIcalth Ihysicr. 4 Personnel Airlock Door local e Bell or buzzer and red light in Control Room a Flashing red light near containment entrance
$ Control Room anntniciator buzzer and light 4 After norn11 working hours, notify Reactor Operations m
7 m
G es e
EP- I .O. 2 IMPORTANT TELEPHONE NUMBERS Office Home O Facility Director, R. M. Brugger (on Sabbatical Leave until 9-1-82) 882-4211, Ext. 230
]
Acting Director, D. M. Alger 445-4775 ]
Reactor Manager, J. C. McKibben 882-4211, Ext. 204 442-6728 ]
Reactor Operations Engineer, L. L. Schuermann 882-4211, Ext. 203 474-8350 ]
Reactor Maintenance Engineer, W. A. Meyer 882-4211, Ext. 202 474-7368 ]
Reactor Shift Supervisor, N. Tritschler 882-4211, Ext. 214 474-6214 3 Reactor Shift Supervisor, B. Bezenek 882-4211, Ext. 214 445-5680 3 Reactor Shift Supervisor, C. Anderson 882-4211, Ext. 214 696-5506 ]
Reactor Shift Supervisor, J. Tunink 882-4211, Ext. 214 474-4174 ]
Health Physics, Manager, MURR, 0. Olson 882-4211, Ext. 227 874-8167 ]
Health Physics Technician, S. Stewart 882-4211, Ext. 226 474-6326 ]
Health Physics Technician, J. Litton 882-4211, Ext. 225 443-2707 ]
Health Physics Technician, S. Growcock 882-4211, Ext. 224 875-4502 ]
University Police / Watchman's Office, UMC 882-7201 ]
Medical Center Health Physicist, P. Lee 882-7221 445-5275 ]
2 Research Park Dev. Bldg.
Radiation Safety Officer, UMca, J. Tolan 882-3721 445-7787 ]
413 Clark Hall Physical Plant Emergency 882-8211 (Day) 882-7201 (Night) ]
Emergency Room, Medical Center, UMC 882-8091 Ambulance, Medical Center, UMC 911 (Will be dispatched by ]
City of Columbia)
Boone County Hospital 449-0938 ]
Boone County Hospital, Admissions 875-3237 ]
Boone County Hospital, Emergency Room 875-3501 ]
Boone County Ambulance Service 449-0937 Missouri State Highway Patrol, Jefferson City 314-751-3313 3 FBI, Jefferson City 314-636-8814 ]
NOTE: For any emergency involving the City of Columbia, dial 911.
O Re v. 1 0/81 App'd m- EP-I-3
EP-I.1 Facility Evacuation Plan g
EP-I.1.1 The facility evacuation alarm is actuated manually from two ]
locations: (1) the reactor control room, and (2) the lobby ]
control center. ]
The following events result from a facility evacuation alarm:
A. The reactor scrams; B. The containment ventilation system isolation doors close; C. The containment exhaust isolation valves close; D. The facility horns sound; E. The flashing red light exterior to the containment personnel airlock door is energized.
Upon hearing the alarm, all personnel within the facility ]
without preassigned tasks shall proceed to points beyond the ]
exclusion area limit and remain there until released by the Emergency Director. The exclusion area is that area bounded by the outer perimeter of the reactor lab building. See the g map of the routes and the map of the area on pages EP-I-16 and EP-I-17, respectively. Once outside, the personnel are to note the wind direction indicator at the top of the building east tower and proceed to the upwind parking lot.
EP-I.l.2 Evacuation Routes A. All personnel within the containment building will exit the containment building and proceed through the east door of the laboratory building and then go to the upwind parking lot.
B. All laboratory personnel, support personnel, and guests ext.crine to the cot.tainment building will leave the ]
facility through the nearest exit (north, east, or south ]
doors) and then proceed to the upwind parking lot. ]
O Rev. 10/81 App'd, h% EP-I-.1 f
EP-I.1.3 Preassigned Tasks O
The responsibility for the overall direction in the event of an emergency shall rest with the Emergency Director. In the event of a facility evacuation, the Emergency Director shall be the Facility Director; in his absence, the Associate Director; in his absence, the Reactor Manager; in his absence, the Reactor Operations Engineer; and 17 his absence, the Duty Shift Supervisor.
In the event all of these people are absent from the facility during the emergency, the task will be assumed by the next senior licensed operator whose job title is Senior Reactor Operator or Reactor Operator. The duties of Emergency Director may be assumed by any of the above-mentioned indi-viduals upon their arrival at the facility, but only after being thoroughly briefed on the emergency and the action taken.
In the event of a facility evacuation, the following people shall report to the reactor lobby: the Facility Director, Associate Director, Reactor Manager, Manager of ]
Reactor Health Physics, Administrative Associate to the ]
Director, Machine and Electronics Shop Supervisors, and Duty ]
Shift Supervisor. ]
The Emergency Director shall proceed to the lobby control center. The Emergency Director shall ascertain the availa-bility of personnel required to execute the emergency plan and appoint a Coordinator. With the assistance of the Coordinator he shall establish that the facility is vacated l and secured. He shall investigate the cause of the alarm and the magnitude of the incident, and shall direct those activi-ties necessary to correct the emergency situation. After the emergency is terminated, he shall direct the procedures necessary to restore normal operation.
Q l
Rev.10/81 App'd '-~ EP-I-5 t
/-
~
The Coordinator shall ascertain that the reactor contain-ment building and facility laboratories have been vacated and secured. If the pneumatic blower system was in use during the emergency, he shall insure that the samples being irradiated are returned to the laboratory and then have the blowers secured at the local lighting panel (#32). He shall insure a record of the events following the emergency is maintained.
The Duty Operator shall perform the following tasks before leaving the Control Room: (Do not attempt to correct any abnormalities at this time.)
A. Verify that the reactor has scrammed as indicated by the instrumentation.
B. Verify that all shim rods have bottomed as indicated by the console lights.
C. Verify that the containment has sealed as indicated by the ventilation door and the exhaust valve lights.
D. Insure all personnel are cleared from 5th, 4th, 3rd, and 2nd levels of the containment building and exit via personnel airlock doors.
g E. If the Assistant Duty Operator is not known to be in containment, the Duty Operator shall also insure that all personnel are cleared from the beamport floor.
He shall report to the Coordinator and advise him of the status of the reactor.
The Assistant Duty Operator shall ascertain that all personnel are cleared from the beamport floor area and exit via personnel airlock doors. He shall report to the Coordinator in the lobby control center. If on routine patrol and not in the containment building, he shall proceed directly to the lobby control center.
The Manager of Health Physics shall proceed to the lobby control center and establish the radiation-safe condition of the area. He shall establish a hot-cold change area, assemble and prepare for use special Health Physics equipment, and O
Rev. 10m1 App'd hv - EP-I-6
- /
perform radiation and contamination surveys. He shall evaluate the extent of radioactivity contamination and/or radiation ex-posure received by personnel in the Facility at the time of the incident. He shall advise the Emergency Director of measures to be taken to control and to clean up radioactivity contamination which may have resulted from the incident.
The Machine Shop Supervisor or in his absence one of the Machine Shop personnel shall secure the labcratory ventilation fans. He shall establish that the mechanical equipment room and the below-grade areas exterior to the containment are vacated and secured. He shall report to the Coordinator in the lobby control center.
The Administrative Associate to the Director, if not already present, shall proceed to the lobby control center. When directed by the Emergency Director, she shall notify auxiliary organizations which have been made aware of these emergency procedures and per-form other communicative functions required. The following tele-phone numbers may be of assistance in the performance of these duties:
University Police / Watchman's Office, UMC 882-7201 ]
Radiation Safety Office, UMca 882-3721 ]
John Tolan, 413 Clark Hall Radiation Safety Office, UMC 882-7221 ]
Dr. Philip Lee, 2 Research Park Dev. Bldg.
Emergency Room, Medical Center, UMC 882-8091 ]
Tour Guides shall be responsible for the safe evacuation of visitors in their charge from the facility in accordance with the evacuation routes in this plan.
l Experimenters who are conducting experiments in the containment area shall render their experimental apparatus safe for unattended ]
operation. They shall be responsible for the safe evacuation of visitors in their charge from the facility in accordance with the evacuation routes in this plan.
All staff personnel shall remain on standby to provide the special services that may be required to restore normal operation.
l lO Rev. 10/81 App'd / '
EP-I-7 1 ( . - . . -
Note: When determined appropriate by the Emergency Director, ]
the evacuation horns may be silenced by opening breaker 15 on ]
the emergency lighting panel located in the north inner ]
corridor next to the emergency power transfer switch. ]
EP-I.2 Reactor Isolation Plan EP-I.2.1 The reactor isolation alarm is actuated automatically by either of two radiation monitors in the containment air exhaust plenum or the reactor bridge monitor. It may be actuated manually by the Duty Operator upon the detection of high levels of radia-tion by the reactor system radiation monitors or by advisement from personnel that a safety hazard exists.
The following events result from a reactor isolation alarm:
A. The reactor scrams; B. The containment ventilation system isolation doors close; C. The containment exhaust isolation valves close; The containment horns sound; g
D.
E. The flashing red light exterior to the containment personnel airlock door is energized.
Upon hearing the alarm, all personnel in the containment ]
without preassigned tasks shall exit through the personnel ]
airlock door to the front lobby. ]
EP-I.2.2 Preassigned Tasks In the event of a reactor isolation, the Emergency Director shall be the Reactor Manager; in his absence, the Reactor ]
Operation Engineer; in his absence, the Duty Shift Supervisor. ]
In the event all of these people are absent from the facility during the emergency, the task will be assumed by the next senior licensed operator whose job title is Senior Reactor Operator or Reactor Operator. The duties of Emergency O
Rev. in/81 App'd, 6 ,' ~ EP-I-8
Director may be assumed by any of the above-mentioned indi-viduals upon their arrival at the Facility, but only after being thoroughly briefed on the emergency and the action taken.
The following shall report to the lobby control center:
Reactor Manager, Reactor Operations Engineer, Shift Supervisor, ]
Duty Operator, Reactor Services Engineer, Reactor Physicist, Plant Engineer, Manager of Health Physics, Machine and Electronics Shops Supervisors.
The Emergency Director shall proceed to the lobby control center. The Emergency Director shall ascertain the availa-bility of personnel required to execute the emergency plan.
He shall investigate the cause of the alarm and the magnitude of the incident. He shall appoint a Coordinator. If in the opinion of the Emergency Director the extent of the emergency is sufficient to warrant evacuation of the facility, he shall actuate the alarm and the facility evacuation plan shall be executed. After the emergency is terminated, he shall direct r**' 9'r^ti "-
O '"" Pr cad"r*' "*ca"^r' * ' r* "
The Coordinator shall establish that containment is vacated and secured. He shall inform the Facility Director of the ]
emergency and direct the Administrative Associate to the ]
Director to carry out her communicative functions. If the ]
pneumatic blower system was in use during the emergency, he shall insure that the samples being irradiated are returned to the laboratory and then have the blowers secured at the local lighting panel (#32). He shall assist the Emergency ]
Director as required and insure a record of the events ]
following the emergency is maintained. ]
The Duty Operator shall perform the following tasks before leaving the Control Room: (Do not attempt to correct any abnormalities at this time.)
A. Verify that the reactor has scrammed as indicated by the instrumentation.
B. Verify that all shim rods have bottomed as indicated by A
V the console lights.
Rev. 10/R1 App'd W- EP-I-9 e .
C. Verify that the containment has sealed as indicated by the ventilation door and the exhaust valve lights.
D. Insure all personnel are cleared from 5th, 4th, 3rd and 2nd levels of the containment building and exit via personnel airlock door.
E. If the Assistant Duty Operator is not known to be in containment, the Duty Operator shall also insure that all personnel are cleared from the beamport floor.
He shall report to the Emergency Director and advise him of the status of the reactor.
The Assistant Duty Operator shall ascertain that all personnel are cleared from the beamport floor area and exit via personnel airlock doors. He shall inform the Manager of Health Physics of the emergency. He shall then position himself at the outer personnel airlock door and allow only authorized entry into the containment.
The Manager fof_ Health Physics shall proceed to the lobby control center. He shall establish a hot-cold change area, assemble and prepare for use of special Health Physics equip-g ment, and perform radiation and contamination surveys. He shall evaluate the extent of radioactivity contamination and/or radiation exposure received by personnel in the containment at the time of the incident. He shall determine if the Radiation Safety Officer should be notified. He shall advise the Emergency Director of measures to be takan to control and to clean up radioactivity contamination which may have resulted from the incident.
The Administrative Associateo to the Director shall advise ]
the laboratory personnel of the isolation emergency by means ]
of the public address system. She shall read the following ]
statement two times: ]
"Your attention please - Your attention please.
A reactor isolation has occurred. All non-involved personnel shall keep clear of the main g corridor and the lobby."
Rev. 10/81 App'd M EP-I-10 1
She shall perform communicative functions for the Emergency Director. The following telephone numbers may be of assistance in the performance of these functions:
Traffic Safety and Security Office, UMC 882-7201 ]
Radiation Safety Office, UMca 882-3721 ]
Radiation Safety Office, UMC 882-7221 ]
Emergency Room, Medical Center, UMC 882-8091 ]
Tour Guides shall be~ responsible for the safe evacuation of visitors in their charge from the containment and exit via the east door.
Experimenters shall render their experimental apparatus safe for unattended operation. They shall be responsible for the safe evacuation of visitors in their charge to the lobby.
They shall inform the Emergency Director if adjustment need be made to their equipment upon re-entry.
All staff personnel shall remain on standby to provide the O special services that may be required to restore normal opera-tion.
Note: To facilitate communication once re-entry into the containment building has been made and proper radiation surveys are conducted, the isolation horns may be silenced by means of a switch on the back of the control console in the Control Room.
EP-I.3 Fire Plan
[
I Fire emergencies may or may not involve radioactivity contam-ination and/or radiation exposure. If the fire is associated with a facility evacuation or a reactor isolation emergency, then the appropriate plan shall be executed. The Emergency Director shall be informed immediately of the nature and lcoation of the fire. He shall investigate the fire and determine the necessary steps to be taken to minimize the Rev. 1 0/81 App'd- m EP-I-ll
,/
hazard both to personnel and to property. The individual discovering the fire shall immediately notify the Duty Operator and describe its nature and location. He shall then return to the scene and try to bring the fire under control with portable extinguishers. The Duty Operator will send the Assistant Duty Operator to the location of the fire to deter-mine its severity and will report the situation to the Shift Supervisor. If it is determined that the fire cannot be put out immediately with the local fire extinguishers, the reactor will be imediately shutdown so that full attention can be given to the fire. The Duty Operator will then announce the fire and its location and ask that the area be avoided. At this point it can be assumed that the fire is large enough to warrant control measures. Immediately upon hearing the fire announcement, it will be the responsibility of the Machine Shop (or the Assistant Duty Operator if after normal working hours) to secure the ventilation supply and exhaust fans and close all fire doors. If the fire is in the containment building and cannot be immediately brought under control, the g
Duty Operator shall manually initiate a reactor isolation.
The Shift Supervisor, if necessary, will call the Columbia City Fire Department, 9-911; and Traffic Safety and Security ]
Office, UMC, 882-7201. Since the fire-fighting system of the ]
Facility is dry (i.e., it requires a pumper truck and hoses ]
for operation), it is imperative that the Fire Department be notified as soon as possible after the discovery of the fire.
He shall then, if deemed necessary, notify the Facility Director or his authorized delegate and make a report as to the situation.
EP-I.4 Medical Emergency Plan Injuries which may or may not involve radiation exposure and/or radioactivity contamination are classified as follows:
O Rev. 10/81 App'd IV"- EP-I-12
A. Class I: Accidents which involve contamination of the surface of the body with a possible associated dose from penetrating radiation at a level of 100 Rem or more.
Physical injury in the usual sense may or may not be involved.
B. Class Ia: Accidents which involve a dose from penetrating radiation at a level of 100 Rem or more but without con-tamination.
C. Class II: Accidents which involve contamination of the surface of the body with a possible associated dose from penetrating radiation at a level of 25 to 100 Rem. Physical injury in the usual sense may or may not be involved.
D. Class iia: Accidents which involve a dose from penetrating radiation at a level of 25 to 100 Rem but without contam-ination.
E. Class III: Accidents which may involve minor contamination to the surface of the body with a possible associated dose from penetrating radiation at a level of 2 to 25 Rem.
Q Physical injury in the usual sense may or may not be involved.
i EP-I.4.1 Upon discovery that an accident has occurred, the following action is to be taken:
A. If the area in which the accident has occurred is a "high radiation area" with an exposure dose rate of 100 mR/hr or more, or is suspected to be such an area, move the victim quickly and carefully to a location at which the exposure dose rate is 5 mR/hr or less if the victim can be moved without harm. Evacuate all personnel from the accident area and provide first aid to the victim.
B. Call the Health Physics Manager at 882-4211. If he is not ]
available, call the Radiation Safety Officer, UMca, at ]
882-3721; or the Radiation Safety Office, UMC, at 882-7221.]
C. Notify the Reactor Operator in the Control Room.
i Rev. 10/81 App'd,-r C % EP-I-13
[/ . - . . -_
EP-I.4.2 Upon arrival at the accident scene, health Physics will take the following action:
A. Assess the severity of the radiation injt:ry and classify the injury.
B. If necessary, close off and seal the accident area and turn off the ventilation to that area.
C. Notify the Emergency Room, Medical Center, UMC, at 882-8091, and arrange for medical care either at the Facility or at the Medical Center.
D. If initial treatment is to be administered at the Medical ]
Center, arrange for transportation by the Medical Center ]
ambulance, 882-6128, the Facility vehicle, or commercial ]
ambulance service. ]
E. If initial treatment is to be administered at the Facility by a representative of the Medical Center, attend the accident victim, keep him comfortable, and render first aid as required.
F. Survey all personnel who may have been contaminated in the accident. Provide first aid as required.
G. Provide decontamination of the accident victim, if possible, and all other persons found to be contaminated.
H. Save all samples of clothes, jewelry, and etc. Label the samples with name, time and date.
I. Notify the Facility Director and the Radiation Safety Officer.
J. Evaluate the radiation dose received by carefully recon-structing the accident. This assessment is more detailed than that required in item A above and may be deferred until after the care of the accident victim is transferred to the attending physician.
O Rev, 10/81 App'd h- EP-I-14
/,
EP-I.4.3 Transportation Routes to the Medical Center
)
A. Injuries which do not involve contamination of the surface of the body shall be taken directly to the emergency entrance of the Medical Center, UMC, for treatment in the Emergency Room (see Figure EP-3).
B. Injurie's'which do involve. extensive contamination of the surface of the body shall be taken to the dock area at the rear of the Medical, Center, UMC. From there the accident victim will be taken to rooms M162-163, Cadaver Ro~~.)
(sometimes called the Medical School Morgue), located in the immediate vicinity of the dock entrance (see Figure EP-3). J EP-I.5 Security Procedures Because of the sensitive nature of facility security the procedures for handling the theft or attempted-theft of special nuclear material and the procedure,s for' preventing
('])
sabotage of the Facility are contained in a separate document .
(Reactor Security Procedures) and will not be outlined in this document.
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EP-II REACTOR EMERGENCIES It cannot be overly stressed that the guideline for any emergency procedure shall be actions which safeguard personnel and equipment, in that order.
If, while operating the University of Missouri Research Reactor, a situation develops that requires an emergency action as set forth in these procedures, it must be remembered that for a transient type accident, Title 10 of the Code of Federal Regulations, Part 50.36, dictates certain actions as pertaining to safety limits and limiting safety system settings.
In the case of a transient type accident, the Shift Supervisor must determine before resuming operation if a safety limit, as illustrated by the safety limit curves set forth in the MURR Technical Specifications, has been exceeded. If in fact a limit has been exceeded, the reactor shall remain shutdown until the Commission authorizes resumption of operation.
Limiting safety system settings are those settings which will initiate automatic action to prevent exceeding a safety limit.
If a safety system setting is exceeded without receiving an automatic function trip, the reactor shall be shutdown and the Commission notified. The cause of the failure will be noted and corrective action taken before operations resume.
The following actions shall be taken by reactor operating personnel for the conditions listed.
EP-II.1 Failure to Scram or Rod Run-In If for any reason the reactor fails to scram or rod run-in automatically when called for by a protective system, the Reactor Operator shall press the manual scram or manual rod run-in to insure all rods are full in or driving in and the reactor is shutting down as indicated by nuclear instrumentation.
O Rev. 10/81 App'd fx_ EP-II-l
{l . _ _ _ _ . _ . .
EP-II.2 Reactor Scram from Causes Other than Loss of Flow or Pressure O
A. Monitor nuclear instrumentation to assure reactor is in shutdown mode.
B. Acknowledge cause of scram and take corrective action as required.
C. Notify Shift Supervisor of scram.
D. Verify control rod drives at full-in position.
E. Log entry in console log book and fill out scram report.
EP-II.3 Reactor Scram from Loss of Primary System Pressure or Flow A. Monitor nuclear instrumentation to assure reactor is in shutdown mode and verify control rods full in.
B. Acknowledge cause of scram.
C. Check that the primary system is in the normal shutdown lineup.
D. Check AT across the in-pool heat exchanger.
E. Place primary system switches and controls in normal shutdown mode.
F. Notify Shift Supervisor of scram.
G. Log entry in console log book and fill out scran report.
EP-II.4 High Radiation An operator may detect an increase in radiation levels above normal before any trip levels occur. In this event, the operator will notify the Shift Supervisor and the Manager of Reactor Health Physics. He shall closely monitor the radiation level. If necessary, the Shift Supervisor shall lower the reactor power to prevent continued rise in radiation levels.
If the alarm trip point is exceeded, the operator will initiate a normal reactor shutdown at the discretion of the Shift Supervisor, who will noti'v the Reactor Manager and the ]
Manager of Reactor Health Physiss of the condition.
O Rev. 10/81 App'd /A EP-II-2
,/ -
In the event radiation leven have reached a magnitude to cause reactor isolation, procedures outlined in EP-I.2 shall be followed.
EP-II.5 Nuclear Instrument Failure All six nuclear channels shall be operational for reactor startup and Channels 2 through 6 shall be operational during operation at power. If a Reactor Operator notices any nuclear channel not functioning correctly and the reactor has not scrammed due to instrument failure, the reactor shall be shut-down by rod run-in and the channel repaired prior to restarting the reactor.
EP-II.6 Failure of the Area or Process Monitoring System Temporary or portable monitoring equipment may be set up to monitor radiation levels in all areas except the equipment room 114, the facility off-gas ducts, and the reactor bridge without disrupting reactor operation. The Manager of Health Physics shall be notified of the failure of any radiation detection unit.
It shall be acceptable procedure to switch inputs from detectors in the facility off-gas ducts, the equipment room 114, and the fuel rupture monitors to operational monitors during temporary repair of these units. Portable monitoring equipment shall be set up to monitor radiation in the displaced area. Building air activity may be monitored by a constant '.ir monitor capable of detecting radioactive gaseous and particulate activity during temporary repairs to the facility off-gas radiation monitor.
t EP-II.7 Failure of Intercom System i A means of communication shall be maintained at all times between the reactor control room and experimenters who are O utilizing the reactor. If during reactor startup, communication Rev. 10/81 App'd,!gw EP-II-3 o
v
is lost between the Reactor Operator and the experimenters, the reactor will be held steady at the existing power until O repairs or temporary communication can be established. If communication is lost during steady state operation and repairs or temporary communication facility cannot be made in a reasonable period of time, the reactor shall be shutdown.
EP-II.8 Control Rod Drive Failure If the Reactor Operator detects a stuck or inoperative drive mechanism, he shall take the following action:
A. Scram the reactor, noting the approximate stuck position.
B. Verify the reactor is scrammed as indicated by the nuclear instrumentation.
C. Make no effort to move the stuck mechanism and note if rod drives move down as required.
Note: Rather than have the stuck blade being forced into the gap by the automatic reverse function from loss of magnetic contact, place the master switch in test and h insert the other mechanisms manually.
D. Notify the Shift Supervisor.
EP-II.9 Electrical Anomalies EP-II.9.1 Indications
) Any electrical anomaly which results in the loss of electrical
- power will cause the reactor to scram and the emergency generator to come on line. All process systems will shutdown.
l A loss of electrical power is quite obvious because of the sudden quiet and darkness in the containment building. An anomaly such as single phasing or a reduction in line voltage is not so obvious. In such conditions, the reactor may or may not scram and the systems may or may not shutdown. The opera-tor must be alert to changes which might be symptoms of an electrical anomaly. The dimming of lights, the loss of some O
Rev. 10/81 App'd /g ., . EP-II-4 v
of the containment lights and/or the failure of some of the process system are possible symptoms of an electrical anomaly.
EP-II.9.2 Action for Sustained Electrical Anomalies The following actions will be carried out in the event of an electrical anomaly which results in a loss of power, single phasing or a reduction in line voltage of sufficient duration to result in any abnormal condition other than a reactor scram.
Console Operator shall:
A. Check reactor shutdown.
B. Turn all pump and cooling tower fan switches off in the most expeditious manner.
C. Place all valve controls in their normal shutdown position and manual mode.
Assistant Duty Operator, when directed by the console operator, shall:
A. If a rabbit is in the reactor at the time electrical power O is lost, transfer the p-tube blower to emergency power and return the rabbit.
B. Trip the master supply breaker on substation "B".
C. Check emergency generator and its loads for proper opera-tion.
D. Trip the supply breakers for MCC-1 and 2 in the cooling tower.
Do not carry out Steps A and C if normal electrical power is restored before these steps are completed. Check operating equipment. Determine cause of power interruption and if another loss is anticipated.
Recovery from Complete Plant Shutdown Before restoring power to the substation:
A. Check all three phases on each substation for proper voltage.
B. If other than a complete, sudden interruption of power occurred, place the following loads in a condition such d that they may be individually monitored on lightoff.
- Rev. 10/81 App'd, b rs EP-II-5 p'
- 1. SF1
- 2. RFl 9
- 3. Vacuum pumps
- 4. Main air compressor
- 5. Air conditioners
- 6. Chill water system
- 7. SP4
- 8. Cooling tower sump pumps
- 9. Condensate return pumps
- 10. Ventilation air compressor
- 11. SF2
- 12. RF2 When starting systems, closely monitor any equipment known to be running at the time of the power failure.
A full power startup checksheet shall be completed prior to starting up the reactor.
EP-II.9.3 Recovery from Reactor Scram Only If a momentary loss of power occurred such that only a reactor scram occurred, the reactor may be operated after perfonning a Reactor Short Form Precritical c.hecksheet.
EP-II .10 Failure of Experimental Apparatus The Reactor Operator shall not hesitate to shutdown the reactor upon receiving reliable information that any equipment is operating in a manner which is hazardous to personnel.
EP-II.ll Backup Isolation Doors: Radiation Detector Alarm Backup isolation system will be initiated automatically by a radiation detector located in return fan air plenum. The backup isolation door system operates to seal the fifth level ventilation gratings beyond the motor-operated isolation doors (504 and 505), upon receiving an indication of high plenum O
Rev. 10/81 App'd, 'i- EP-II-6
I l
activity from the radiation monitor. The doors are pneumatic piston-driven with a positive pressure to open and gravity to close and respond from their own local radiation detection unit.
When the trip point on the detector unit is reached, the doors close and an audible and visual alann is energized in the control room and a reactor isolation is initiated. Upon receiving the backup door alarm and isolation, the operator shall carry out the procedure of the Reactor Isolation Plan EP-I.2.0.
EP-II.12 Loss of Service Water to the Facility City water is provided to facility services through a 3" line ]
in the basement of the cooling tower. ]
Upon loss of the water service to the facility, the ]
following steps shall be initiated: ]
A. Shutdown and secure the reactor.
B. Secure, tag out, and make the appropriate entries in the O reector iogs for.the foiiewing equipment:
- 1. Cooling pumps SP1, SP2, SP3 and SP4
- 2. Emergency generator unit
- 3. Main air compressor
- 4. Vacuum unit pumps
- 5. Air conditioning units
- 6. Hot water recirculating pump
- 7. After the reactor has been secured, secure the primary coolant system since pumps P501A/B no longer have cooling water.
- 8. Room 212 (North Counting Room) Air Conditioner (Notify Research and Applications Group.)
- 9. Room 232A (Animal Room) Environmental Control Box (Notify Dalton Research Center.)'
- 10. Room 232B (ETSRC Counting Room) Air Conditioner (Notify ETSRC Group.)
- 11. Ice Machine (inner passage way)
O Rev. 10/81 App'd /d;. EP-II-7
?
1 C. Announce to the entire facility that water service has been interrupted.
g D. Upon restoration of the water service to the facility, return all systems to their normal status.
E. Announce to the entire facility the restoration of water service.
EP-II.13 Loss of Secondary Flow A. A loss or reduction in secondar, ~10w might be attributed to failure of the secondary cooling pump, a break in the secondary cooling line, or loss of water in the cooling tower causing pump shutoff when the low sump level switch is tripped, or possibly due to restriction in the line caused by a faulty check valve on the discharge side of the running SP pump. It will be indicated on the secondary flow recorder and by a low flow alarm in the control room.
B. Flow Reduction - No Auto Reactor Shutdown
- 1. If the flow is gradually decreasing, the Duty Reactor h Operator shall send the Assistant Duty Operator to the cooling tower to assess possible pump or piping damage.
The Duty Operator shall monitor the position of 51 and reactor temperatures. If any significant change is noted in either, the reactor shall be shutdown by rod run-in, the Reactor Manager and/or Operations Engineer ]
notified and the primary and pool systems left in operation. It shall, however, be permissible under the direction of the Shift Supervisor to immediately switch SP pumps to determine whether this action corrects the deteriorating flow conditions.
- 2. If no change is indicated in temperature or valve position, reactor operation may be continued.
C. Loss of Flow If the loss of flow is due to the loss of SP pump, the following procedure shall be followed:
Rev. 10/81 App'd M m - EP-II-8
/
- 1. If the operator actually sees one or both of the on-line pump lights go out and the flow sharply decrease or drop to zero, the standby pump may be started immediately upon loss of the on-line pump.
- 2. Power must be reduced it the standby pump cannot be put on line as per 1 above and the reactor shutdown if no secondary cooling is forthcoming.
EP-II.14 Loss of Pool Flow During Reactor Operation Flow elements 921 A on the output side of heat exchanger 521 A and 921B on the output side of heat exchanger 521B monitor reactor pool water flow and are set to scram the reactor in the event the flow rate becomes less than 435 gpm for either loop. Should the pool flow rate drop below 435 gpm in either loop without generating an automatic scram, the Reactor Operator will:
A. Immediately manually scram the reactor.
O B. Snutdown the pooi system ieev4ne the pc4mery end secondery on line.
EP-II.15 Loss of Pool Water During Reactor Operation Two pool level controllers (LC910 and LC966) are set to assure that the pool level is maintained between acceptable limits during nonnal operation. When the level becomes less than a limit compatible with the reactor operational mode, the reactor will be automatically shutdown and the Shift Supervisor will be notified immediately.
When the pool level alarm sounds and the pool level con-tinues to recede, the following procedure shall be followed:
A. Verify that the reactor is being shutdown automatically.
If control rod run-in action has not been activated, then depress the manual scram button on the control console.
B. Manually turn off P508A and/or P508B from the Control Room
{ and verify that valve 509 closes.
Rev. 10/81 App'd Au~ EP-II-9 7
/,'
C.
D.
Turn off P513B from the Control Room, Place master switch 151 in the test position.
g E. Turn the operational mode switch for valve 509 to the manual position and close the valve if it has not closed automatically.
F. Close valve 547 by actuating the manual three-way valve on ]
the upper bridge level. Insure that the valve has closed ]
by the movement of the local indication actuator or the ]
light indication on the control room process instrument ]
panel. ]
At this point the pool tank should be isolated from the process leg of the pool cooling system. If the pool level continues to recede after the pool tank has been isolated:
A. Enter room 114 observing proper radiation protection procedures and open valve V522C and/or V522B. This supplies water from T301 and/or T300 by gravity flow to the pool via the pool system.
- 1. If T301, which is normally valved for service to the $
reactor and pool systems, drains completely empty before the pool leakage is arrested, a continued source of demineralized water can be made available by entering the south tower and valving T300 into the pool-reactor makeup line. Furthermore, makeup water to T300 may be routed through 0I300 at a rate of up to approximately 40 gpm.
B. Attempt to locate and secure the leak with all available ]
means. ]
C. In the event that the water level in the pool tank con-tinues to recede after step A above is completed, or if the initial leak rate is in excess of that with which the demineralized water system can keep it, and it is clear that all the foregoing efforts to check the flow of water from the pool have failed, then the following step may be taken to maintain or increase to a safe level the amount of water in the pool: h.
Rev. 10/81 App'd bw EP-II-10 s.
CV 1. Open the emergency raw water pool fill valve under the
~
floor plate at pool edge to full open (1/4 turn).
This should supply a raw water flow rate into the pool in excess of 1000 gpm.
EP-II.16 Valves 507A and 507B Fail to Close Failure of these valves only presents a problem in the event of a pipe rupture or out of pool leak in the primary system.
Check valve 502 backs up the failure of 507B preventing draining of the core and the antisiphon system prevents the core draining in case of failure of V507A.
If these valves fail to close, the Reactor Operator will switch the master switch to test, the valve auto / manual switch to manual, and turn the open/close switch to close.
EP-II.17 Pressurizer Valves Fail to Operate p All of the automatic valves on the pressurizer are oacked up by manual valves. In event of malfunction of any of these valves and they cannot be closed from the Control Room, the operator shall shutdown the reactor and then close (or have the Assistant Duty Operator close) the appropriate manual valve upstream of the failed valve.
EP-II.18 Antisiphon Valves (543A/B)
Either valve will perform the desired function. If both valves failed to open, the following steps shall be taken immediately:
A. Open manually with the wrench provided.
B. If unsuccessful, close the air supply valve and disconnect copper tubing on the valve side of the 3-way solenoid.
The valve should open but it may be necessary to use the wrench.
C. If all attempts have failed to open either valve and a void core is suspected, carry out the reactor isolation
\/ procedure.
~
t Rev. 10/81 App b EP-II-ll
EP-II.19 Emergency Core Cooling Valves 546A/B g
A. One or both valves fail to open. These valves are of paramount importance, especially after considerable operating time has been accumulated. The Reactor Operator shall check, following every scram from loss of pressure or flow, that at least one of these valves has opened.
Either valve will perform the desired function. If either valve fails to open, the following steps shall be taken immediately:
- 1. Place the master control switch in test, place the valve 546A/B auto / manual switch in manual and the open/close switch to the open position. If it has still not opened, he shall:
- a. Attempt to open the valve manually with the wrench provided.
- b. If unsuccessful, close the air supply line to the valve at the bridge and bleed air pressure from the valve by disconnecting the copper tubing on the valve side of the 3-way solenoid.
- c. If all attempts fail to open one of the valves, operate the primary and secondary cooling systems.
B. One or both valves fail to open during reactor operation.
If 546A/B open during reactor operation, a flow path for the primary coolant bypassing the core is established.
Calculations have shown that this bypass flow is about 30-33% of the initial core flow. These calculations also indicate that this reduced flow will not lead to core damage so long as normal temperature, power and pressure l are maintained. It is noted, however, that this reduced flow decreases our safety margin from the safety limit I curves by about 60%, so the reactor is to be shutdown upon receipt of indication of this accident. The core dif-ferential pressure scram from DPS929 should be initiated automatically by one or both of the 546 valves opening, g Rev. 10/81 App'd .h EP-II-12
but if indication is received that one or both of the p) x" valves have opened and the reactor has not scrammed, initiate a manual rod run-in.
EP-II.20 High Activity Levels in the Primary Cooling System Upon receiving an indication of an abnormally high level of radioactivity in the primary cooling system, the reactor shall be inuediately shutdown by rod run-in and the Shift Supervisor and Manager of Reactor Health Physics notified.
Note: Extreme caution should be observed when entering areas containing primary water or containing systems connected to the primary coolant. These areas should be entered only after they have been checked as radiologically safe. Adeque;e protective clothing should be worn while in these areas and while obtaining water samples at the fission product monitor, and the primary / pool sample station.
A. Precautionary reduction of flow. The first action is to O assume the worst case condition, namely a fuel element failure, and minimize plate ercsion due to high flow. If at 10 MW and maximum flow at the time of the abnormal radioactivity reading, secure one pump to decrease the flow by one-half. Secure only one pump at this time.
B. Determine the source of radioactivity (i.e., fission products, activation of coolant impurities, etc.) and magnitude of activity levels by:
- 1. Checking fission product monitor; i
- 2. Having primary water sample analyzed; f 3. Observing off-gas recorder if primary system should i automatically vent; I
- 4. Conducting radiation surveys in areas containing primary coolant.
(
C. Further reduction of plate erosion
- 1. If the source of activity is determined to be fission n products, a further reduction flow to approximately U
f ,
Rev. 10/81 App'd I h EP-II-13
/.
500 gpm is necessary to reduce plate erosion. To accomplish this, fully open the bypass valve (538A or 5388) around the pump (501A or 501B) that is running, then throttle valve 540 (A and/or B),
depending upon which heat exchanger loops are in service.
D. Clean up the contaminated systems
- 1. Leave the primary cooling and primary cleanup loops in operation to clean up the system.
- 2. The radiation levels in the demineralizer rooms may be very high.
E. When it becomes necessary to shutdown the primary system for leaking fuel element identification, extreme caution must be exercised to prevent a release of radioactive aerosals to the containment building. In addition, caution must be exercised to insure NOT to flood the charcoal and absolute filters during the venting operation.
Shutdown the primary system by: g
- 1. Master switch to test.
- 2. Close valve 527C.
- 3. Secure pump P-533.
- 4. Secure pump P513A.
- 5. Secure primary pump 501A or B.
- 6. Verify valves 546A/B open on loss of flow.
l 7. Place valves 507A/B mode switch to manual.
- 8. Verify that valves 507A/B close and valves 543A/B open.
- 9. Open the vent valve cautiously on the antisiphon system and bleed off system pressure via the absolute and charcoal filters.
- 10. Close vent valve on antisiphon system.
1 O
Rev. 10/81 App'd- Je - EP-II-14
O 11. eiece the foiiowia9 valve coatrois in indicated position.
Valve Mode Position V507A/B Manual Closed V546A Manual Open V546B Manual Open V543A/B -- Open V527A Manual Closed V527B Manual Closed V545 Manual Closed V526 Manual Closed
- 12. Cycle valves 507A/B to open and back to reduce loop ]
pressure to less than 20 psig. ]
- 13. Close valves 527E/F. ]
- 14. Open vent valve on antisiphon system to bleed any ]
additional pressure. ]
- 15. Close antisiphon vent valve. ]
- 16. Secure the primary flow and temperature recorders and ]
l the primary demineralizer flow recorder. Time and ]
date the recorders. ]
- 17. Secure power to pumps P501A/B, P513A and P533. ]
Note: A Health Physics survey is vital prior to ]
entering room 114. ]
- 18. Secure shaft cooling water to pumps P501A/B. ]
F. Leaking or ruptured fuel element identification.
The fuel element which is leaking fission products must be accurately identified and placed in safe storage before the remaining intact elements may be utilized. This will be accomplished in the following manner:
- 1. Have the Health Physics personnel move the portable gaseous and particulate monitors to the reactor bridge for continuous monitoring. HP personnel will be O prese"t-Rev. lofg1 App' W EP-II-15 f/
]
- 2. Move four elements from the core to the "X" basket $
and four elements to the "Y" basket.
- 3. Draw a grab sample from above each element and give to lab group for analysis. If one of these samples indicates fission products present, this element will be inspected first.
- 4. Move the fuel element from one of the baskets to the fuel inspection rig for visual inspection.
- 5. Install the fuel element cap on the discharge hose for the portable pool sweep pump.
- 6. Commence recirculating water through the element.
Recirculate each element for 15 minutes minimum and draw samples for the lab group to analyze.
- 7. When an absolute verification of the leaking fuel element has been made, that element will be placed in the special single element storage cask and placed in the "Z" basket area. The element will remain sealed in the cask until ready for shipment. h l
O is Rev. 10/R1 App'd, E '* ' - EP-II-16
APPENDIX A a
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~----en,,ww w --- ---- -,r--s -- --w--
REACTOR STARTUP CHECKSHEET DATE:
FULL POWER OPERATION .
Time (Started)
(or Low Power Forced Circulation)
BUILDING AND MECHANICAL EQUIPMENT CHECKLIST
(')
v'
- 1. Run emergency generator for 30 minutes and check the governor oil level.
(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or after each maintenance day.)
. 2. a. Check operation of fan failure buzzer and warning light. Shift fans.
(Required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)
- b. Test stack'moniter per 50P while in west tower.
- c. Test the stack monitor low flow alarm.
- 3. Visual check of room 114 equipment completed.
- a. P501 A and P501B coolant water valves open.
- b. 51 and S2 hydraulic pumps on (oil level normal).
- c. Pump controllers unlocked to start (as required).
- d. Insure N backup system on per SOP.
- e. Open air2 valve for valve operating header (V0P 31).
- f. N9 backup valve open.
- g. Check valves 599A and 599B open.
- h. Pipe trench free of water (on Monday startups, check the four-pipe annulus drain valves for water leakage).
- 4. Visual check of CT equipment conpleted.
- a. Oil level in CT fans normal (Monday startups).
- 5. Beamport Floor
- a. Beamport radiation shielding (as required),
- b. Unused beamports checked flooded (Monday).
- c. Seal trench low level alarm tested (Monday).
- 6. Emergency air compressor (load test for 30 minutes on Monday).
()
- 7. Reactor Pool Reflector experimental loadings verified and secured for start-up.
a.
- b. Flux trap experimental loading verified and secured for start-up, or strainer in place.
REACTOR CONTROL SYSTEM CHECKLIST
- 1. All chart drives on; charts timed and dated. IRM recorder to slow.
- 2. Fan failure warning system cleared.
- 3. Annunciator board energized; born off.
- 4. Television receiver on.
- 5. Primary / pool drain collection system in service per SOP.
- 6. Secondary system on line per S0P (as needed).
- 7. Primary system on line per S0P.
- a. Primary cleanup system on line.
- 8. Pool system on line per 50P.
- a. Pool cleanup system on line.
- b. Pool skimmer system vented.
- c. Pool reflector ap trips set per SOP.
- 9. Valves S1 and S2 cycled in manual mode and positioned as required.
- 10. Nuclear instrumentation check completed per SOP.
- a. The following trip values were obtained during the check.
IRM-2, run-in seconds Scram seconds IRM-3, run-in seconds Scram seconds WRM-4, run-in % Scram %
PRM-5, run-in % Scram %
('~') 11.
PRM-6, run-in % Scram %
Channel 4, 5, and 6 pots returned to last heat balance position.
- 12. SRM-1 detector response checked and set to indicate > l cps.
Rev. 10/81 App'd h SOP /A-la
- 13. Check of process radiation monitors (front panel checks).
- a. Fission product monitor.
- b. Secondary coolant monitor.
Note: Items 14 through 35 are to be completed in sequence immediately prior to a pulling rods for a reactor startup. W
- 14. Annunciator tested.
- 15. Annunciator alarm cleared or noted.
- 16. Power selector switch 1S8 in position required.
- 17. a. Bypass switches 2S40 and 2S41 in position required.
- b. All keys removed from bypass switches.
- 18. Master switch ISl in "on" position.
- 19. Magnet current switch on, check " Reactor On" lights.
- 20. Reactor isolation, facility evacuation and ARMS checks. (Monday start-up)
These items are to be checked with scrams and rod run-ins reset, and when appropriate items are actuated, verify that the TAA's do trip.
- a. Reactor isolation switch (leave valves and doors closed). (Monday start-up)
- b. Facility evacustion switch (check outer containment horns).(Monday start-up)
- c. ARMS trip setpoints checked and tripped, check buzzer operational locally for all channels and remotely for' channels 1 through 4 and 9.
Channel 1 - Beam Room South Wall Channel 2 - Beam Room West Wall Channel 3 - Beam Room North Wall Channel 4 - Fuel Storage Vault Channel 6 - Cooling Equipnent Room 114 Channel 7 - Building Exhaust Air Plenum (Monday start-up)
Channel 8 - Reactor Bridge (Switch in " Normal") (Monday start-up)
Channel 9 - Reactor Bridge backup (switch in " upscale") (Monday start-up)
- d. Check HV readings: volts.
e.
f.
Check 150V reading: volts.
Selector switch on ARMS in position 5.
g
- g. Trip backup monitor with antached source.
- h. Reactor isolation horns switch in " Isolation Horns On" position.
Valves and doors open.
- i. All ARMS trips set per SOP.
- j. Check ventilation fans, containment and backup doors.
- 21. Operate reg blade from full-out to full-in and set at 10"+.05".
! a. Check rod run-in function at 10% withdrawn and annuncTator at rod bottomed.
l 22. Raise blade A to 2" and manually scram.
l 23. Raise blade B to 2" and trip manual rod run-in.
l 24. Raise blade C to 2" and scram by hM1 trip.
l 25. Raise blade D to 2" and scram by IRM trip.
l 26. Annunciator board energized; horn on.
- 27. Jumper and tag log cleared or updated.
l
- 28. IRM recorder in fast speed.
- 29. Check magnet current for 90 ma on each magnet.
- 30. Cycle hM1 range switch.
- 31. Predicted critical blade position ( inches).
- 32. Pre-startup process data taken.
- 33. Visually check room 114 after all systems are in operation.
- a. Check oil reservoir for pump P501A, 501B, and P533 for adequate supply.
Add if necessary.
- 34. Routine patrol conpleted.
- 35. Reactor ready for startup. Time (Completed) g Senior Reactor Operator Rev. 10/81 App'd 4fc.
/ SOP /A-lb
REACTOR STARTUP CHECKSHEET Dete LOW POWER NATURAL CONVECTION UNIVERSITY OF MISSOURI RESEARCH REACTOR Building and Mechanical Equipment Checksheet p
s' ,
- l. Secure containment intrusion alarm system.
2, Run emergency generator for 30 minutes (when secured check operate switch to auto).
3 Check operation of fan failure buzzer and warning light. Shift fans (required once a week).
- a. Test stack monitor per S0P while in west tower.
4 Visual check of room 114 equipment completed (complete b thru f only if pool system !
will be used).
- a. Pipetrenchfreeofwater(onMondaymorningstartupscheckthefourpipea ;
drain valves for water leakage).
- b. N2 header exhaust valve open.
- c. Valve S-2 hydraulic pump on, oil level normal.
- d. All pump controllers except P-501A/B and P-513A unlocked to start.
- e. Insure N2 system on per S0P VI.
- 5. Beamport floor
- a. Beamport radiation shielding (as required).
- b. Unused beamports flooded (Monday morning).
- c. Seal trench low level alarm tested (Monday morning).
- 6. Check emergency air compressor oil level and load test on bleed down.
- 7. Reactor pool
- a. Reflector experimental loadings verified and secured for startup.
- b. Flux trap experimental loading verified and secured for startup, or strainer in place.
- c. Pool clear and free of debris, ctor control System Checklist
- 1. All necessary chart drives on; charts timed and dated.
- a. IRM recorder on slow speed.
- 2. Fan failure warning system cleared.
- 3. Annunciator board energized; horn off.
- 4. Television receiver on and cameras checked.
- 5. Pool skimmer system in service (if required).
- 6. Secondary system on line per S0P V (if required).
- 7. Pool system on line per S0P IV (if required).
- a. Pool cleanup system on line.
- 8. Primary system secured per S0P V.
- a. Pressure vessel head removed, opening clear,
- b. Natural convection flange-off.
- 9. Nuclear instrumentation check completed per SOP II.
- a. The following trip values were obtained during the check.
IRM-2, run-in seconds Scram seconds IRM-3, run-in seconds Scram seconds WRM-4, run-in % Scram %
PRM-5, run-in % Scram %
PRM-6, run-in % Scram %
- 10. Channel 4, 5, and 6 pots returned to last heat balance position.
- 11. SRM-1 detector response checked and set to indicate at least 1.0 cps
- 12. Check of secondary coolant monitor (if pool system and secondary system are to be used)
- 13. Annunciator tested.
- 14. Annunciator alarm cleared or noted Rev. 8/76 Repl. _4/75 App'd S0P/A-2a
By-pass Switch Positions
- 15. IS20 - bypass position
- 16. IS21 - bypass position g
- 17. IS22 - bypass position W
- 18. 1S23 - bypass position
- 19. IS24 - off (key removed)
- 20. 1S25 - bypass position
- 21. 2S40 in 50 KW position (unless the pool system is to be operated).
- 22. ~2S41 in 50 KW position
- 23. Power selector switch 1S8 in 50 KW position.
- 24. Turn magnet current switch on.
- 25. Turn master switch to on.
- 26. Scram reset.
- 27. Rod run-in reset.
- 28. Reactor isolation, facility evacuation and ARMS check.
- These items to be checked with scrams and rod run-ins reset, and when appropriate i items are actuated, verify that the TAA's do trip.
- a. Reactor isolation switch (leave valves and doors closed,
- b. Facility evacuation switch (check outer containment horns).
- c. ARMS trip set points checked and tripped, check buzzer operational locally for all channels and remotely for channels 1 through 4 and 9.
Channel 1 Beain Room South Wall 2 Beam Room West Wall 3 Beam Room Forth Wall 4 Fuel Storage Vault 6 Cooling Equipment Room 114 7 Building Exhaust Air Plenum 8 Reactor Bridge (Switch in "NorTnal")
9 Reactor Bridge back-up (Switch in " Upscale")
- d. Check HV readings volts
- e. Check 150 v reading volts
- f. Selector switch on ARMS in position 5
- g. Trip back-up monitor with attached source.
- h. Reactor isolation horns switch in Isolation Horns On position. Open isolation valves and doors.
- 1. All ARMS trips set per SOP.
- j. Check ventilation fans, containment and back-up doors.
Operate regulating rod full out to full in.
l 29.
- a. Check rod run-in function at 10% withdrawn and annunciator at rod bottomed.
- b. Raise regulating rod to 10" ! .05".
- 31. Raise rod "B" 2" and trip manual rod run-in.
- 32. Raise rod "C" 2" and scram by WRM trip.
- 34. Annunciator board energized; horn on.
- 35. Jumper log cleared or updated.
- 36. Tag out log cleared or updated.
l 37. IRM recorder in fast speed.
I
- 38. Cycle WRM range switch.
. 39. Reset scram and run-in circuits I
- 40. Check magnet current for 90 ma on each magnet.
- 41. Predicted critical blade position ( in.)
- 42. Pre-startup process data taken.
43.
44.
Visual check of room 114 after systems are in operation.
Routine patrol completed.
- 45. Reactor ready for startup.
Rev. 8/76 Rep 1. 8-72 App'd /
8 Senior Reactor Operator l sa m -3
Date
. REACTOR SHORT-FORM PRE-CRITICAL CHECKSHEET
- 1. Front Panel Check of SRM completed
- 2. SRM Recorder and Scaler on
- 3. Front Panel Check of IRM #2 completed
- 4. IRM #2 Trip Values Run-In sec.
Scram sec.
- 5. Front Panel Check of IRM #3 completed
- 6. IRM #3 Trip Values Run-In sec.
Scram sec.
- 7. Front Panel Check of WRM completed
- 8. WRM Trip Values Run-In %
, Scram __
- 9. Front Panel Check of PRM Ch. #5 completed - Note 1
- 10. PRM #5 Trip Values Run-In %
Scram %
- 11. Front Panel Check of PRM Ch. #6 completed - Note 1
- 12. PRM #6 Trip Values Run-In %
Scram %
- 13. IRM Recorder to Fast Speed
- 14. Cycle WRM Switch
- 15. Predicted Critical Position ( in.)
- 16. Reset Scram and Run-In Circuits
- 17. Pool and Experiments Checked and Ready for Startup
- 18. Reactor Ready for Startup Nota 1: Pot Returned to Position Obtained from Heat Balance.
Senior Reactor Operator Rsv. 8-72 Repl. 10-71 App d {h'%dk e
50P/A-3a
O NOTE: THIS PAGE INTENTIONALLY LEFT BLANK l
O
(
O Rev. 6/80 App'd rs 50P/A-3 b
App'd Rev.
D/L1/22/81 UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR SHUTDOWN CHECKSHEET DATE
- 1. Time o f re a c t o r s h u t d ow n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
U 2. All bl ades bottomed and dri ve mechcni sm full i n. . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 3. Ma g n et c u rre n t sw i t c h o f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 4. SRM set to recuired position...............................................
- 5. Reacto r primary system shutdown per S0P IV. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 6. Pool system shutdown per S0P V.............................................
- 7. Secondary system shutdown per S0P VI.......................................
- a. C o o l i n g tow e r fa n s o f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 8. Di gi ta l re a do u t swi tc h o f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 9. Annunciator board on off .........................................
- 10. Re v e rs e o s mo s i s u n i t s e c u re d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 11. Sample inventory sati sfactory and data sheets updated. . . . . . . . . . . . . . . . . . . . . .
- 12. Si integrators recorded....................................................
- 13. All bypass swi tches off and keys in key box. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 14. Master switch off on ...........................................
- 15. DCT system secured.........................................................
- 16. Room 114 check:
- a. Cool i n g flow to P501 A/ B s ecured . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- b. Val ves Sl an d S2 hyd ra ul i c moto r o f f. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
(1 c. N2 system and air to valve header secured.............................
d. Calgon units secured..................................................
- e. Room 114 pump controllers locked out. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 17. Completed and logged reactor shutdown checksheet...........................
BUILDING SHUTDOWN CHECKSHEET
- 1. Pool level normal..........................................................
- 2. ARM trip levels set per 50P................................................
- 3. Annunciatar board off........................................ .............
- 4. TV unit secured............................................................
- 5. ARM and off-gas recorder paper supply okay, charts timed and dated. . . . . . . . .
- 6. Primary / pool drain collection system secured per 50P. . . . . . . . . . . . . . . . . . . . . . .
- 7. Routine patrol completed...................................................
- 9. Ma s te r key swi tch o f f an d i n key bo x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 10. Test of containment intrusion alarm completed. System energized...........
- 11. A l l k ey s a c c o u n t e d fo r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 12. Buil di ng s h utdown and reacto r s ecured. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
U 13. Control room doors locked..................................................
- 14. Completed building shutdown checksheet.....................................
- 15. Logbook entries compl ete, crews si gned out. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Senior Reactor Operator 50P/A-4a
e THIS PAGE INTENTIONALLY LEFT BLANK O
l O
SOP /A-4b Rev. 4/2/81 App'd /PA o
Date r hbclear Data
(
Rod Position hbclear Instunnentation Power by Heat Average Channel Channel Channel Channel Channel Channel Balance in FM Time RR CR 1 2 3 4 5 6 Primary [ Secondary I
I I
O _
l f
I
! I i
l
\
- i Rev. 5/74 Repl. 7/73 App'd / S0P/A-5a
! l Date ,
Process Data l Mode i
^
LTine -
In Pool Ht. Exch.
l Pressurizer Level Pool Refl. AP PS 944A l PS 944B DPS 928A DPS 928B l DPS 929 l
Sec. Th (6)
Sec. Tc (5)
Sec. AT Sec.. Water Flow I Pool Tc Loop A (3) {
Pool Tc Lo p B (4) y {
Sec. Th Pool A (7)
Sec. Th Poo; B (8) l Rx Cond In l Rx Cond Out Pool Cond In Pool Cond Out Stack Gas l l l Stack Part.
Stack Iodine Operator Reader l l l h Heat Balance by Manual Calculation: _
Rev. 4/79 Repl. I-3-78 App'd_/($'/', 50P/A-5b
Date Process Data Mode
,e Pri. Flow A Pri. Flow B Pool Flow A Pool Flow B Demin Flow A _
Demin Flow B Pri. T c
Pri. T s Pri. AT Pool T c Pool T h Pool 4T South Wall ARMS st Wall ARMS
_ North Wall ARMS Fuel Storage ARMS l l
Room II4 ARMS 1 Blda Air Exh ARMS Rv Rridae ARMS Fission Product 1
Sec Water i TAA Yellow TAA Rod Run-In l TAA Green l l
Rx Pressure I Rx Tc Loop A l
^T Loop B l 1
1 1 _
Rev 4/79 Repl . 1/3/78 App' d . ,/_ SOP /A-Sc
O NOTE: THIS PAGE INTENTIONALLY LEFT BLANK O
O Rev. 6/80 App'd h .v'- 50P/A-5d
Date STARTUP NUCLEAR DATA APP.
h TINE BANK POS.
RR POS.
SRM PCS. SLM-1 I IRM-2 IRM- 3. WRM-4 PROCEEDINGS i
l k l
1 i t I Oritical Rod Position A B C D RR ECP Power at Critical Position Pri. Temp. in out Pool temp. in out Operator Itmarks G Date APP.
BANK RR SRM TIME PCS. POS. POS. 5I01-1 IRM- 2 IRM-3 'WRM-4 PROCEEDINGS i l 1 I l l l l l l l l t , i i t
Critical Rod Position A B C D RR ECP Power at Critical Position Pri. Temp in out Pool Temp in out Operator Remarks Rev. 9-72 Repl. 4-72 App'd DN SOP /A-6a
Core !!onday Startup Pot Settings
!rdD Last Sheet 4 5 6
!CID This Sheet Pot Changes Total !!WD Date Time Channel Setting Fuel Element Record Core Position Fuel Element 570 to Date 1 ------
2 --- --
3 ------
4 ------
5 ------
6------- -
7 - - - --
8 ------ __
Power Tir.e Time Time Time at This Level lDate Arrival! Departure Hrs !!in Pwr Level (days) ' !r4D 9
1 I
i m
a C
o b l l o
U 1
/
Rev. 7/73 Repl. 8/72 App'd 7 h/ SOP /A-6b
Date PfiEUMATIC TUBE IRRADIATIONS
'Run Clock Time Room Irradiation File No.
(] 1 In Out Name Proj. No. N,0 . Min Sec 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 (V ,17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 f-)
'~' 34 l l Rev. 9/2/81 App'd .d., /w SOP / A-7 a
O fl0TE: THIS'PAGE INTENTIONALLY LEFT BLANK-e e
- e e
4 e
e O
l Rev 6/80 App'd 6-- 50P/A-7b
Date Reactor Routine Patrol
- 1. Time of start of patrol
([jTimeanddateallcharts
- 3. Check ARMS trip settings 4 Visual check of entire pool
- 5. Anti-sipnon tank pressure +3.0 psig
- 6. North iso door seal press 18-28 psig
- 7. South iso door seal press 18-28 psig
- 8. 5th level backup doors Open
- 9. 5th level detector reading 0-3.5 mr/hr
- 10. 5th level trip point set' 3.5 mr/hr
- 11. 16" iso viv A air pressure 45-55 psig Bkr $ open,
- 12. Emerg compress on standby g, e -
- 13. Containment hot sump pumps C? erable 14x Door 101 seal pressure 18-28 psig 157 BP floor Conditions normal
- 16. Fuel vault Locked
- 17. Inner airlock door seal press 18-28 psig
- 18. Outer airlock door seal press 18-28 psig
- 19. T-300 level > 2000 gal
- 20. T-301 level < 6000 gal Level < Alarm Pt.
21 . Labyrinth sump 22*
RO UNIT (Run daily:
POWER ON \to T-300 or drain./
i ON[Run c,n 0700 routinel ifor - 4 hrs. /
- 23. R0 Unit Temp 24-28 C / standby
- 24. R0 Unit Pressure 190-200 psig / standby C
Thermostat > 50 F l 25.EGrm.(IE@6p9Nhcgugogygj.
Gas >sightglass.I Temo > 40 F I
< i T-300, 301 room Thermostat 26- The mostat s>55lF 40 F 2(~') Rm 114 particulate filter aP < 2.5" H20 On the first routine oatrol of the day or the first patrol af ter a startup, drain all water from the anti-siphon system. If draining causes the pressure to drop significantly, return to the middle of tho band (35 osig) and record the pressure here.
Rev. 5/81 App'd db S0.P/A-Ga
External Doors All locked except east
- 28. when sec on duty
- 29. CT basin water level 5-10"
- 30. Acid Day Tank Level Visible , l
- 32. P-pump (s) running
- 33. Pump strainer AP 0-7.0 psi
- 34. Discharge Pressure
- 35. Pump Strainer AP 0-7.0 psi
- 38. WT Booster Fan Running Acid Control and pH Flow 400-800 cc/ min
- 39. oH 7.0-7.4 40.
500- O cc/ min Blowdown Control /Cond. ,
- 41. Fission Product Monitor Flow 95-105 cc/ min
- 43. Pressurizer t'2 supply press90-100 psig ,
- 44. Check Rm 114 from door -
[
45.
Deltech oil filter " red < 75% dark red level and blowdown
- 46. Seal trench n mp on days
- 47. Full N2 bottles total > 3
- 48. Bank A bottle press > 250 psig
- 49. Bank B bottle press > 250 psig
- 50. Bank on service A or B
- 51. N2 header pressure 135-145 psi -
- 52. Waste Tank # 3 level
- 53. Waste Tank # 2 level l
- 54. Waste Tank i 1 level
- 35. Time of Completion of Patrol l l l
- 57. Operator initials !
l j l g If a condition is normal, enter an "N" or a cneck "v" in the applicat,le box. If the condition or reading is abnormal, enter "AN" for the condition and circle it. Circle the reading if it is abnormal. Exclain all abnormal readings or conditions in the remarks.
Remarks: -
Rev. 7/80 App'd ' -
SOF/A-Sb
UNSCHEDULED REDUCTION IN POWER REPORT NO.
Date Scram Time of Rod Run-In W
Power Level at Time of Power Reduction KW MW Indication observed on annunciator and/or other instrumentation Cause of reduction in power O
- Action taken to alleviate cause of power reduction i
t l
[
Permission to take the reactor critical received from Time required to bring reactor back to previous power level Form filled out by Form reviewed by Remarks:
O Rev. 8-72 Repl. 5-72 App'd {gg SOP /A-9 a
O t10TE: THIS PAGE ItlTEtiTI0tlALLY LEFT BLAtlK O
O Rev 6/80 App'd f61.~ s. SOP /A-9b c
Rev.1-76 Repl 4-75 App'd /$
UtlIVERSITY OF MISSOURI O RADiATI0n WDRx eERMir s.,
fiumber: Time: Date:
Location: ; . . ,f
~
Description of Work: .. . D ,' e i .o. l,p ,,;g. d ,
. ,. s . .
..,s
- 4
," .c .,
,t j } 'd A , .',.st-j 5y' G : a '*1:
. . [1)'
4 Radiation Survey Results +q 1, - ; ' 7; dProtectiveEquipmentRequirements General Area mM/IN - l;. O Gloves (cloth) .
Hot spots
- n -% 0 Gloves (Waterproof) mrem /h at
ShoeCovers(Cloth) mrem /h.at-- Shoe Covers (Waterproof)
- '" a Dosimeters mrem /h:at -- ', Finger Chambers Contamination. Survey,.Results Coveralls (Cloth) q ; O Coveralls-(Waterproof)r ,
Cap .. '
~
General Area - - ' M pCi/.100.cm 2 -
~ 7 Lf ,
, + .. . .g e
,' Half. face respirator's JJ a . ,'.:, f.% t.p. ."- / - full, face respirator . .. / .
_,,a, .: Scott. Air Pack;',b. J $ J O Continuous. Monitoring Required; .. * -
N- A.,- o N
...,\. 2. ,.
O- Intsrmittent' Monito'ririg;... Requirp -/n.s ..+09
L.
Special Instruct' ions'
- . 4 7
.f' I , .f
.r. '
v .-
- i. , .-
7 t
I l
Approved By Job Supervisor Time Date Health Physics Time Date Terminated By i
Job Supervisor Time Date Health Physics Time Date O ILocaticn TIME DATE ilature of Job SOP / A-10 a
O NOTE: THIS PAGE It4TErlTI0tiALLY LEFT BLAT 4K O
O Rev 6/80 App'd - f .1 ^ SOP /A-105
...s.. ...a..n. . . . . , . . ...a.w vre a nu.
WASTE TANK SAMPLE REPORT TAtiK f40. TAtlK LEVEL (Li ters )
TIME DATE Completed adding water to this tank.
SAMPLER TIME DATE W l. Analysis Results tiucli de Half Life Physical Form Concentration MPC Activity (uCi/ml) (pCi)
- a. H-3 12.3Y b.
f pH TOTAL CONCEtlTRATI0ft (b)
Analysis by Date Time Concentration (uCi/m). Total Volume (litersl Activity (mci) i (a) x -
= '
(b) x
- 2. Approvals Required For .
Any Discharge . ...................... !
Shift Supervisor !
Discharge of Total Activity > 4 mci or to Secondary System Reactor Manager Discharge Limit Approved . . .. ... ..........
Health Physics i
- 3. Action Taken Date Discharged Time Discharged Volume Discharged (Liters)
Tank Discharged to (check one) Sanitary Sewer Secondary System flot Discharged
,n.
RL /ks
! ~ i Rev. 5/81 App'd..~ /_ t ,~/ E SOP /A-ll a
O fl0TE: THIS PAGE INTENTIONALLY LEFT BLANK O
l O
I Rev 6/80 App'd.f.Le' SOP /A-ll b
Date Prinary System Nomal Operation Valve Lineup Checksheet m This checksheet shall be completed when required by the SOP. The operator perfoming the
("Jcheck will verify the position of each valve and indicate the verificatien by initialing the checksheet. Under the direction of the Shift Su,ervisor, a valve may be positioned other than noted on this sheet. The operator will check the valve to be in the desired position, line out the nomal position on this sheet, and write in the actual position of the valve. The reason for the valve being positioned abnomally will be noted in the coments section.
Throttled valves shall be checked to be in the position shown by the tag on the valve.
Note the valve's position in the space provided on the checksheet.
V1v No. Valve Descriptien Position 551 Vent tank regulator valves ............. Zero pressure 518A>f Vent tank vent ......................... Open 518AL Vent tank air suoply ................... Closed 598B N2 supply to 543ASB .................... Open 598A N2 supply to 546 and 547 ............... Open 518S Loop drain (in tunnel) . . . . . . . . . . . . . . . . . Closed (locked) 518T Loop drain (in tunnel) . . . . . . . . . . . . . . . . . Closed (locked) 5180 T[1 vent and FI31 cutout . . . . . . . . . . . . . . . . . Open (locked) 595L Isolation v1v for DPS-929. . . . . . . . . . . . . . . Open 56811 DPS-929 inlet / outlet test v1vs equali . . Closed 595'! Isolation v1v for PS-944A .............. Open 595N Isolation v1v for DPS-929 and PS-944B... Open
~
595B Return v1v from FP'f . . . . . . . . . . . . . . . . . . . . Open (locked) c 518X T{I vent valve .......................... Closed (locked)
V 510A P-501A suction ......................... Open 510D P-501B suction ......................... Open 518A P-501A gage cutout ..................... Open 318Ali P-301B gage cutout ..................... Open 518B P-501A gage cutout ..................... Open 518AB P-501B gage cutout ..................... Open 538A P- 501A bypass . . . . . . . . . . . . . . . . . . . . . . . . . . Throttled (locked) C!o. turns open )
538B P-501B bypass . . . . . . . . . . . . . . . . . . . . . . . . . . Throttled (locked) (No. turns open ]
510C P- 50 L\ discharge . . . . . . . . . . . . . . . . . . . . . . . . Open 510E P-501B discharge ....................... Open 518P 'III vent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 510B FN Inlet to 503A . . . . . . . . . . . . . . . . . . . . . . . Open 510F IN i nlet to 503B . . . . . . . . . . . . . . . . . . . . . . . Open 515A HX drain for 503A . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 568I DPS-928A inlet / outlet test v1vs equalit. Closed 595D IN 503A DPS inlet ...................... Open 595C IN 503A DPS outlet . ................... Open 515Y HX drain for 503B . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 595F !E 503B DPS inlet ...................... Onen 595E IN 503B DPS outlet ..................... Onen 568J DPS-92SB inlet / outlet test v1vs equali . Closed 540A IN outlet for 503A . . . . . . . . . . . . . . . . . . . . . Throttled (locked) C:o. turns ocen )
540B IN outlet for 503B . . . . . . . . . . . . . . . . . . . . . Throttled (locked) (No. turns open ]
599I PT 943 cutcut . . . . . . . . . . . . . . . . . . . . . . . . . . Open (locked)
, 51SY TC ven t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C l o s ed (l ocked)
!v ,) 595A Inle t to FP.\1 . . . . . . . . . . . . . . . . . . . . . . . . . . . Open (locked) i Rev. 3/ a Rep 1. s/~2 App'd L
h SOP /A-llc
l 518M HUT vent ............................... Closed 518L RJr vent ............................... Closed (locked) 515K HUr drain . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 568A FE 913A valve manifold ................. Inlet / outlet open; equaliz. closed 568B FE 913B valve mnifold . . . . . . . . . . . . . . . . . Inlet / outlet open; eaualiz. closed 518AE IN 503A 1 cop strainer drain . . . . . . . . . . . . Closed 518AF HX 503B loop strainer drain ............ Closed 518AA HX 503A vent . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 518AI IN 503B vent . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 528 P-533 recirc to T-300 .................. Closed 515J P-513A suction ......................... Open 518E P-513A suction gage cutout ............. Open 518F P-513A discharge gage cutout ........... Open 515L P-513A discharge ....................... Open 515W P-513A bypass .......................... Closed 568E FE-923A valve manifold ................. Inlet / outlet open; equali . closed 595H Primary sample valve ................... Open 515U V- 5 27A cutout va1ve. . . . . . . . . . . . . . . . . . . . . Open 515AA Press drain to drain collection system.. Open 515B V-527C cutout valve .................... Open 515S V- 52 7D cutout valve . . . . . . . . . . . . . . . . . . . . Open (locked) 544 V- 54 5 cutout valve . . . . . . . . . . . . . . . . . . . . . Open 599G PZR local level indicator cutout . . . . . . . Closed (locked) 599H PZR local level indicato- cutout ....... Closed 515AB Pressuriter drain to waste system ...... Closed 515C P- 533 suction . . . . . . . . . . . . . . . . . . . . . . . . . . Open (locked) 599A PS-938 cuteut .......................... Open 599B PS-939 cutout .......................... Open 599C PS-940 cutout .......................... Open a W
599D PS-941 cutout .......................... Open 599E PS-945 cutout .......................... Open 599F PS-946 cutout .......................... Open 599N FE-913A drain .......................... Closed 5900 FE-913A drain .......................... Closed 599V FE-913B drain .......................... Closed 599N FE-913B drain .......................... Closed Coments:
O Rev. 5/74 Rep 1. s/72 App' '/j Operator SOP /A-Ild i
NOTE: PLEASE RETURN TO HEALTH PHYSICS OFFICE Revised -3 31 80 ~
AND ATTACH TO INDICATED ANALYSIS SHEET.
App'd d , / e- 'l.- U ' '~
[
[ SECONDARY WATER ACTIVITY ANALYSIS Date Wt. Analysis Number (from Wt. sample sheet)
Time Initials Sample Taken from Tower Sump Isotope Half Life Activity 3
H 12.3 yr uCi/ml Analysis Performed by Time Date O
-5 Tritium activity is less than 10 Ci/ml and all other activities are within 10CFR20 limits for discharge to the sanitary sewer. Approval is given to turn on the blow-down system.
Shift Supervisor Blowdown on Time Date Initials 50P/ A-12 a
O l
NOTE: THIS PAGE INTENTIONALLY LEFT BLANK O
O Rev 6/80 Ap p' d 50P/A-12b
Date _
Pool System Valve Lineup Checksheet b)ThischecksheetshallbecompletedwhenrequiredbytheSOP. The operator perfoming the check will verify the position of each valve and indicate the verification by initialing
& checksheet. Under the direction of the Shift Supervisor, a valve may be positioned other than noted on this sheet. The operator will check the valve to be in the desired position, line out the nomal positien on this sheet, and write in the actual position of the valve. The reason for a valve being positioned abnomally will be noted in the comments section.
Throttled valves shall be checked to be in the position shown by the tag on the valve.
Note the valve's position in the space provided on the checksheet.
V1v No. Valve Description Position 598A N2 supply to 546 and 547 ............... Open Air supply valve to V-547 .............. Closed Vent valve from V-547 .................. Open 548A P-532 pool suction ..................... Open 548B P-532 pool (at refuel) suction . . . . . . . . . Closed 518U Vent valve (pool TH) . . . . . . . . . . . . . . . . . . . Closed (locked) 515X P-513B bypass .......................... Closed 515N P-513B discharge ............,.......... Open 518H P-513B suction gage cutout ............. Open 518G P-513B discharge gage cutout ........... Open 522C Pool drain / fill . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 522B Pool fill . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) ps 515Q Cleanup return to loop . . . . . . . . . . . . . . . . . Closed (locked)
V 515M Cleanup suction from pool .............. Closed (locked) 515T Cleanup suction from loop .............. Open 522F P-508A discharge ....................... Open 522E P-508B discharge ....................... Open 531B P-508B bypass .......................... Closed 518I P-508A gage cutout ..................... Open 518J P-508A gage cutout ..................... Open 518AD P-508B gage cutout ..................... Open 1 518AC P-508B gage cutout ..................... Open 599J PS- 94 7 cutout . . . . . . . . . . . . . . . . . . . . . . . . . . Open (locked) l 539A P- 508A suction . . . . . . . . . . . . . . . . . . . . . . . . . Open (locked) 1 539C P- 508B sucticn . . . . . . . . . . . . . . . . . . . . . . . . . Open (1ccked) 518V Vent valve . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) 515P Cleanup retum to pool . . . . . . . . . . . . . . . . . Open 514B EUr outlet ............................. Open 539B FE-521A inlet .......................... Open l 539D IE-321B inlet .......................... Ocen 522A IE- 521A outlet . . . . . . . . . . . . . . . . . . . . . . . . . Throttled (locked) l 52 3 IE- 5 21B cutlet . . . . . . . . . . . . . . . . . . . . . . . . . Throttled (locked) 51SN IUT vent cutout ........................ Open 518K IM vent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Clos ed (locked) 515R IUT drain . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C lo sed (locked) 5150 f N- 521A drain . . . . . . . . . . . . . . . . . . . . . . . . . . Clos ed (locked) 5152 IE- 521B drain . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (lecked) 518N Vent valve . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Closed (locked) h 51 SAG Pool sys 'T' strainer drain . . . . . . . . . . . . Closed l
SOP / A-12 c Rev. 5/74 Rep 1. 9/72 App'd A
5180 Drain valve (tunnel) . . . . . . . . . . . . . . . . . . . Clos ed (locked) 518R Drain valve (tunnel) . . . . . . . . . . . . . . . . . . . Clos ed (locked) 514A V- 509 cutout . . . . . . . . . . . . . . . . . . . . . . . . . . . Open (locked) g
) 568G FF-917 cutcut valve . . . . . . . . . . . . . . . . . . . . Open W l 599: PT-917 vent ............................ Closed l
-~~
599Y P-532 sucticn vent ..................... Auto Float l 51EI P-532 suction .......................... Open 518D P-532 gage cutout ...................... Open 518C P-532 gage cutout ...................... 0 pen 515E Skimmer filter inlet ................... Open 515D Skimmer filter outlet. . . . . . . . . . . . . . . . . . . Open 567A Drain collection purp suction . . . . . . . . . . Open 567B Drain collection pump suction drair. .... Closed 566 Drain coll sys disch ................... Open So7C Drain coll sys disch to 513B suction ... Open 593 Skimmer suction T-300/T-301 . . . . . . . . . . . . Open 51&U/AK IDC- 521A/B loop vents . . . . . . . . . . . . . . . . . . . Closed (locked) 56SC FE-921A valve manifold ................. Inlet / outlet open; equali:er closed 568D FE-923 valve manifold . . . . . . . . . . . . . . . . . Inlet / outlet open; equalizer closed 5995 FT-912D drain .......................... Closed 599T FE-912D drain .......................... Closed 599M FT-912F drain .......................... Closed 599Q FT- 912F drain . . . . . . . . . . . . . . . . . . . . . . . . . . Clos ed 568F FE-923B valve manifold ................. Inlet / outlet open; equalizer closed 595J Pool cleanup effl to sample station .... Open 595G Pool influent to sample station . . . . . . . . Open 595K Pool cleanup vent ...................... Closed 515AC Pool cleanup to blank flange ........... Closed Corsents:
Operator O
Rev. :/ Rep 1. S/72 App'd k/ SOP / A-12d L
(UFR FOOL WATER IMLYSIS Sample drawn:
Date: Time: Operator:
Activity:
27 64 Mg uCi/ml CU uCi/ml 2"Na UCi/ml 2"W uCi/ml i22 semTc uCi/ml Sb uCi/ml 182 5'Mn uCi/mi Tc uCi/ml
'H uCi/m1 pH Comments:
Analysis Perfonned:
Date: Time: Technician:
ITRR PRIMARY WATER ANALYSIS Sample drawn:
Date: Time: Operator: -
Activity:
27Mg pCi/ml Cu pCi/ml 24 87 Na uCi/ml W uti/ml ssmTc pCi/ml 232I uCi/ml 55 Mn uti/ml 1321 uCi/ml l 5"Mn uCi/ml 1331 tici/ml lI uti/ml 8
H pCi/ml pH Comments:
'l j
Analysis Performed:
O Date: Time: Technician:
Rev: September 15, 1978 App'
[Ob-[ m SOP /A-13a
O Il0TE: THIS PAGE INTErlTIONALLY LEFT BLANK O
~O 4
Rev 6/80 App' / && S0P/A-13 b
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Rev 6/80 App'd .i- SO P/ A-14 i>
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o o o N /
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/ O l DO NOT l
i OPERATE D0 THt$ TAG 6H ALL NOT SE REMOVED NOR THIS EQulPMENT Of4 RATED wlTHOUT -
THE APPROVAL OF THE SHIST 60P.
! EQUI PME N T _.__ _._ ___ . ._
OPERATE i CONDITION / POSITION _
gg ggy_ _
SEE REVERSE SIDE TAGtJO ~
- o. l~ .Z TAG-DO NOT OPERATE RESEARCH REACTOR FACILITY UNIVERSITY OF MISSOURI OR AWN BY h d. f.f.4M APPROVED SHEET NO.-._ I OF I DRG. NO.
n Rev. 8-72 Repl. 10-71 App'd o87) f . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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O Rev 6/80 App'd d' , SOP /A-15 b 1
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APPENDIX B e *
. 4 e
O O P
to O
e O O O
O e*
9 e
1
e E.C.P.
Monday morning critical position: (#1)
Monday morning primary temperature: (#2) )
l Run #1 (latest run)
Time of start-up: (#3)
Time of shutdown: (#4)
'O PrimarI temp at shutdown: (#5).
Power level (MW): (#6)
Blade Positions at Shutdown: (#7)
Run #2 Time of Start-up: (#8) #
P Time of shutdown: (#9)
Power level (MW) (#10)
O Rev .10
- 71 OmA
Run #3 Time of startup: (#11)
Time of shutdown: (#12) -
O Power level (MW): (#13)
Rod worth (total at Monday startup (Enter total worth curve with #1)
Rod worth (total at Run #1 shutdown (#14a)
(Enter total worth curve with #7)
Total negative reactivity (over Monday startup) at Run #1 shutdown. Use control blades total worth curve.
(#14a) (#14)
- = (#15)
O Difference in primary temp. between Monday startup
- and Run #1 shutdown.
1 l
I (#5) (#2)
- = (#16)
Negative reactivity at Run #1 shutdown due to temperature:
(#16)
(#17)
X 0.02055 =
9 Rev 1 71 SOP /B-b
Negative reactivity at Run #1 shutdown due to
() Xenon:
(#15) (#17) .
- = (#18)
Predicted time of reaching critical: (#19)
Length of shutdown:
~
(#20)
Negative reactivity remaining at start-up due to Xenon present at Run #1 shutdown:
(Enter Table 1 at the value #20)
(#18) (Table 1 factor) x = (#21)
Calculation of Normalized Iodine Present at Run #1 Shut Down Run #1 Length of run:
(#4) (#3)
- = (#22)
O Rev.10-71 SOP /B-c
Normalized iodine present at Run #1 shutdown.
(Enter Table 2 at the value #22)
(#6)
Table II (#22) x (#23) 5 Run #2 Length of run:
(#9) (#8)
- = (#24)
Normalized iodine produced in Run #2.
(Enter Table II at the value #24) g'
(#10)
Table II (#24)
(#25) x I S l
l Length of time from Run #2 shutdown to Run #1 shutdown:
(#4) (#9)
- = (#26) l l
Normalized Iodine present at Run #1 shutdown l
due to Run #2. (Enter Table III at Value #26)
(#25) Table III (#26) x = (#27) 1 Re 10-71
l Run #3 Length of Run:
(#12) (#11)
I
- = (#28) i
~
Normalized. Iodine produced in Run #3.
(Enter Table II at the value #28)
(#13)
Table II (#28) x = (#29) 5 Length of time from Run #3 shutdown to Run #1 O shutdown:
(#4) (#12)
- = (#30) j Normalized Iodine present at Run $1 shutdown due to Run #3. (Enter Table III at value #30)
(#29) Table III (#30) x = (#31)
Total normalized Iodine present at R1n #1 shutdown:
(#23) (#27) (#31)
+ '
- t. + = (#32)
Rev. 10-71 %
SOP /B-e
Negative reactivity due to Iodine prosent at Run il shu tdown. (Enter Table IV at the value #20)
(#32) Table IV (#20) ggg X = (#33)
Temperature of primary at predicted time of
(#34) critical:
Difference in temperature from Monday startup:
(#34) (#2)
- = (#35)
Negative reactivity at predicted time of startup due to temperature:
(#35)
X 0.02055 = (#36)
Total negative reactivity at predicted tima of startup: lll
(#21) (#33) (#36)
N + + = (#37)
Total Reactivity at startup:
, (#14) (#37)
+ = (#38)
Predicted critical from control blade worth curves.
(Enter total rod worth curve with (#38)
O Rev. 10-71fj(
SO9/B-f
- . - "-.,a .
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APPENDIX C i
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. . - - - - - - - - . - - - - - - , . - - . ------. - -.~.-..-..-.---.- ---.-. _
'O V
EXIC HATERIALS WITH RESTRICTED USE IN THE CONTAINMENT BUILDING The folicwing materials in potentially hazardous quantities and readily dispersable forms are not permitted in the cantainment building' Acetone .
Ammonia Antimony and compounds Arsenic and conpounds Bromine Carbon dioxide Carben monoxide ~
Chlorine Chlorine dioxide Chlorine trifluoride Chlorofom (trichloromethane)
Chromium, sol. chromic, chromous salts as Cr Cyanide (as CN)-Skin 2,4-D DITT-Skin l p Ethyl alcohol (ethanol)
V Ethyl ether Fluorine Formic acid Hafnium Hydrogen bromide Hydrogen chloride Hydrogen cyanide-Skin Hydrogen peroxide (90%)
Hydrogen selenide Hydroquinone Iodine Isopropyl alcohol L.P.G. (liquified petroleum gas)
Manganese Mercury Mesityl oxide Methyl alcohol (methanol)
Molybdenum: Soluble compounds-Insoluble compounds i Naphtha (coaltar)
Naphthalene Nickel, metal and soluble cmpds, as Ni Nitric acid Nitric oxide Nitroglycerin-Skin g Nitromethane Rev. App'd SOP /C-a 4/75
I l Ozone g Perchloric Acid Phosgene (carbonyl chloride)
Phosphoric acid Phosphorus Propane Sodium hydroxide Strychnine Sulfuric acid
. Trinitrotroluene-Sk.in Uranium: Soluble conpounds-Insoluble compounds I
O l
Rev. 11/77 App'd Cb SOP /C-b