ML20100M782
| ML20100M782 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 12/31/1995 |
| From: | Mckibben J, Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9603050519 | |
| Download: ML20100M782 (259) | |
Text
{{#Wiki_filter:._ o, j Research Reactor Center Research Park Columbia, Missouri 65211 II Telephone (573) 882-4211 UNIVERSITY OF MISSOURI-COLUMBIA l l February 28,1996 Director of Nuclear Reactor Regulation A'ITN: Document Control Desk Mail Station P1-37 U.S. Nuclear Regulatory Conunission Washington,DC 20555
REFERENCE:
Docket 50-1.86 University of Missouri Research Reactor License R-103 Enclosed is one copy of the Reactor Operations Annual Report for the l University of Missouri Research Reactor. The reporting period covers 1 January 1995 through 31 December 1995. If you have any questions, please feel free to call. Sincerely, I Walt A. Meyer Jr. 4 Reactor Manager i bjb enclosure l l l l l 9603050519 951231 6 DR ADOCK 0500 i t 1 11 2.8 7 7 M l l 9 _ _ _ . _ _ g +1
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JNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT 1 January 1995 - 31 December 1995 RESEARCH REACTOR FACILITY
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f . i UNIVERSITY OF MISSOURI ! RESEARCH REACTOR FACILITY l - 1 ! REACTOR OPERATIONS ~ 1
- ANNUAL REPORT 1 January 1995 - 31 December 1995 l
i i Compiled by the Reactor Staff Submitted February 1996 by
&' V .
Walt A. Meyer, Jr. Reactor Manager Reviewed and Ap roved , v J. Charles McKibben Associate Director
TABLE OF CONTENTS Section Eaga I. Reactor Operations Summary I-1 through 8 II. MURR Procedures II-1 through 10 A. Changes to Standard Operating Procedures B. Changas to MURR Site Emergency Procedures and Facility Emergency Procedures C. Chantres to Health Physics Standard Operating Procedures D. Changes to MURR Shipping Procedures III. Revisions to the Hazards Summary Report III-1 through 59 IV. Plant and System Modifications IV-1 through 2 V. New Tests and Experiments V-1 VI. Special Nuclear Material Activities VI-1 through 2 VII. Reactor Physics Activities VII-1 through 3 VIII. Radioactive Effluent VIII-1 through 3 IX. Environmental Monitoring and Health Physics Surveys IX-1 through 6 X. Personnel Radiation Exposures X-1 through 3 i s
SECTION I REACTOR OPERATIONS
SUMMARY
1 January 1995 through 31 December 1995 The following table and discussion summarizes reactor operations in the period 1 l January 1995 through 31 December 1995. Full Power Percent Date Full Power Hours Mecawatt Days of Total Time of Schedule
- Jan. 1995 680.32 283.61 91.44 102.41 Feb. 1995 612.95 255.94 91.21 102.16 Mar. 1995 673.11 280.56 90.47 101.33 l Apr. 1995 644.04 268.57 89.57 100.32 May 1995 656.85 273.83 88.29 98.88 Jun. 1995 585.71 244.29 81.35 91.11 Jul. 1995 647.10 269.75 86.98 97.41 Aug. 1995 677.13 282.28 91.01 101.93 Sep. 1995 668.97 278.85 92.91 104.06 l Oct. 1995 662.66 276.29 88.95 99.62 Nov. 1995 616.03 255.63 85.56 95.83 Dec. 1995 666.94 278.05 EfL6_4 100.40 Total for one 7,791.81 3,247.65 88.95% of 99.62% of year period time for 12 mos. sched. time for at 10 MW 12 mos. at 10 MW
- MURR is scheduled to average at least 150 hours per week at 10 MW. Total time is the number of hours in a month or year.
There were fourteen unscheduled shutdowns recorded during the period 1 January
} 1995 through 31 December 1995. Of these unscheduled shutdowns, six were scrams ~
and eight were rod run-ins. Eight of the unscheduled shutdowns were manually initiated scram or rod run-in to allow investigation and/or repair ofvarious reactor equipment. Of the remaining six unscheduled shutdowns, four were spurious, one was due to loss of site electrical [ power, and one was due to bumping a control rod offset mechanism during a sample evolution. Three of the manual shutdowns were initiated to investigate fluctuating indications on the Wide Range Monitor (Channel 4). In each instance, rescating the picoammeter module appeared to correct the erratic indications. The cause of these problems appears to be high resistance in the picoammeter module connectors in the ~ I-1 k p . . . . , - . . _ . .
I Channel 4 drawer caused by inability to consistently rescat the picoammeter module. The periodic problems experienced with the picoammeter seating properly is an operational one and not a reactor safety concern. High resistance or a momentary g open in the picoammeter module connection which is part of the feedback loop for the 3 Channel 4 operational amplifiers always results in higher than actual power indication. Electronics Technicians are ordering the necessary parts to replace the picoammeter module connectors. This replacement is currently scheduled as a l February 1996 maintenance activity. There were two Licensee Event Reports (LERs) submitted to the NRC in 1995. One in April regarding a problem with the source range nuclear instrument and one in January 1996 regarding degraded operability of the regulating blade during a 5 minute h period in December 1995. Neither of the events reported in the LERs represented a safety concern to the reactor or the public. g January 1995 The reactor operated concinuously in January with the following exceptions: five shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. l Major maintenance items for the month included: replacing cooling tower cell #2 5 north distribution valve stem; rebuilding pool pump 508A. E February 1995 l The reactor operated continuously in February with the following exceptions: four g shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. Major maintenance items for the month included: installing a new Rosemount flow transmitter for pool loop 'A'; repairing the amplifier for the indicating pen drive on the primary temperature recorder. l March 1995 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On March 20, a manual rod run-in was initiated during a normal reactor startup due to inadequate change in count rate on the Source Range Monitor. The reactor was suberitical with rods withdrawn to 10 inches at the time of the rod run-in. E I-2 I
l Technical Specification 3.4.a. requires an operable source range nuclear instrument during reactor startups. An electronics technician investigated the problem and determined that the cabling between the detector and amplifier was degraded. The co-axial cable was replaced and the instrument tested satisfactorily. A normal startup was subsequently completed and no further problems of this type have occurred. I A License Event Report detailing the source range nuclear instrument problem and corrective action was sent to the Nuclear Regulatory Commission April 19,1995. Major maintenance items for the month included: installing (for preliminary testing) new drywells for fission chamber and compensated ion chamber detectors. Anril 1995 The reactor operated continuously in April with the following exceptions: four I shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On April 13, a manual rod run-in was initiated after receiving a fire main low pressure alarm and indication. A break was discovered in the water supply main from the nearby pumping station. This water main supplies the emergency pool fill system 1,000 gpm capacity required by Technical Specification 3.10(c). The break was quickly isolated and sufficient water pressure was returned via alternate University wells. The reactor was refueled, and prior to commencing operation, an l emergency pool fill compliance test procedure was completed satisfactorily. The broken main was repaired and water service was returned to its original configuration laterin the week. l Major maintenance items for the naonth included: replacing the stack monitor motor, pulley, and belt; installing a new Gamma-Metrics Wide Range Monitor I detector in the reactor pool (separate from required nuclear instruments for preliminary testing); completing the biennial change-out of control blade offset mechanism "A". l 1 May 1995 The reactor operated continuously in May with the following exceptions: five I
) shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. The biennial emergency training drill involving outside emergency support organizations was completed this month.
Maintenance items for the month included: shipping eight depleted fuel elements in the BMI-1 cask; replacing the drive motor on the outer personnel airlock door; and - replacing the detector on nuclear instrument channel #5 (power range monitor). n - I-3
I I June 1995 i The reactor operated continuously in June with the following exceptions: five shutdowns for scheduled maintenance and/or refueling; one unscheduled shutdown. On June 15, a spurious poolloop low flow scram occurred while reactor power was being reduced by manual rod run-in. The power reduction was initiated as per Standard Operating Procedure to allow entry into the mechanical equipment room to perform a secondary system valve manipulation. The scram appeared to coincide 4 with the simultaneous starting of a secondary pump and the automatic closing of the secondary blowdown valve. There was no indication of any actual reduction of pool l flow. It appears that the secondary system pressure surge was transmitted through N the new pool plate type heat exchanger and caused a spurious cpike on the pool flow E . 'B' transmitter, an older model which had no electronic dampening. On June 19, the
- older model 'B' flow transmitter was replaced with a new model which has dampening, and the spurious signal problems have not meurred.
l Maintenance items for the month included: rephcing 527F valve and actuator assembly (primary demineralizer outlet); replacing the outer personnel airlock door motor; removing the original pool heat exchangers 521A/B (tube-shell type) and installing new pool heat exchanger 521 (plate type); rebuilding pool ' pump 508B; installing new Rosemount differential pressure flow transmitter (912F) for pool 'B' flow; shipping eight depleted fuel elements. g July 1995 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling; two unscheduled shutdowns. i l On July 13, a reactor scram occurred due to the loss of site electrical power. The Univercity Power Plant experienced several grid-wide interruptions. Power was X eventually restored and the reactor was refueled and returned to norrnal operation. W On July 24, a manual scram was initiated when the reactor operator observed the Channel 4 indication spike up 15% and return to its previous indication while another operator was closing the Channel 5 instrument drawer afkr a gain l potentiometer change. The powerlevelindications for Channel 5 and 6 dropped about 15%. Review of the Intermediate Range Monitor (IRM) chart indicates that the IRM indication also dropped about 15%. g Electronics technicians checked the nuclear instrument cabinet cabling to the 3 power range drawers to ensure no cabling was pinched when the Channel 5 drawer was closed. They checked each NI drawer to ensure that the voltage regulatoi and l I-4
feedback and test modules were seated. They also checked the voltage from the common power supplies 2PS1 and 2PS2. The picoammeter module in the WRM (Channel 4) drawer appeared to not be fully seated. The module plug and the drawer pins were engaged, but the module could slightly rock. The Channel 4 problem could be duplicated by the physical vibration of shutting the Channel 5 drawer, until the picoammeter module was rescated. When this module was fully seated, the "up" spike problem on Channel 4 could not be duplicated. The spurious power level spike on Channel 4 was most likely caused by a momentary open or high resistance in the plug-pin interface for the picoammeter feedback module. The picoammeter feedback module and the Channel 4 range switch provide the feedback loop for the D.C. amplifiers that provide the Channel 4 meter and trip unit output. These amplifiers are operational amplifiers which are very sensitive to the resistance of the feedback loop. Any high feedback loop resistance or momentary open would cause a spike to occur at the output of the ' amplifier. The drop in indication on Channels 5 and 6 and the IRM chart were most likely the result of regulating blade response to the spurious spike on Channel 4. Channel 4
- output is delivered to the Servo Amplifier which drives the regulating blade. The Semo Amplifier detects the error between Channel 4 indicated power and the power demand set point potentiometer and activates the regulating rod to withdraw or insert based on the direction of the error, to reduce the error to zero.
In this particular case, the "up" spike on Channel 4 would cause the regulating blade to drive in, reducing reactor power. The cause of this spurious spike on Channel 4 indication is similar to previous problems involving momentary opening or high resistance in the Channel 4 amplifier feedback loop associated with the WRM (Channel 4) range switch and the picoammeter relays themselves which resulted in spurious scrams or rod run-ins. Electronics technicians will add a precaution to their maintenanw procedure for Channel 4 to include verification that all modules are firmly seated. Major maintenance items for the month included: installing an 8" valve on the secondary side of pool heat exchanger 521; loading new pool deionization bed 'F'; shipping eight depleted fuel elements in the BMI-1 cask. Aurust 1995 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns this month. l I-5
I I Major maintenance items for the month included: replacing the compensated ion chamber detector for nuclear instrument channel #2 (intermediate range monitor); l shipping eight depleted fuel elements in the BMI-1 cask; replacing both the high and low speed drive motors for the intermediate range monitor chart recorder. Septemher1995 E The reactor operated continuously in Sectember with the following exceptions: four shutdowns for scheduled maintenance ar d refueling; one unscheduled shutdown. g On September 28, a rod not in contact with magnet rod run-in occurred when a reactor operator acciilentally bumped the offset mechanism for control blade 'C' while g performing a normal P-6 sample handling evolution. We have reiterated to the 3 operations staff the need to be extremely careful while working or handling samples near the offset mechanisms because they are extremely sensitive to contact by tools or sample holders. The mactor was subsequently refueled and returned to normal operation. Major maintenance items for the month included: repositioning secondary valves S-211 (heat exchanger 521 discharge) and S-222 (spool piece drain). October 1995 I The reactor operated continuously in October with the following exceptions: seven shutdowns for scheduled maintenance and refueling or flux trap changes. g There were no unscheduled shutdowns this month. 3 Major maintenance items for the month included: installing a new Gamma- , Metrics source range monitor; replacing the dual scram trip unit for intermediate range channel #2; biennial change-out of control blade offset 'C'; removing the old llI source range monitor detector and drywell; removing secondary pool heat exchanger Nl bypass valve S-2 and replacing it with a 6 inch bypass line. ul November 1995 The rea.ctor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and refueling; and four unscheduled shutdowns. On November 4, a spurious pool loop low flow scram occurred at the same time a h reactor operator was measuring pool water temperature (Te) millivolt output with a multimeter. The pool water temperature module and the pool loop flow square root l I-6
converter modules and alarm trip units are located in the same process instrument rack. The scram source isolation monitor indicated a yellow leg pool loop low flow scram, however, no actuallow flow condition was indicated on pool flow charts or indications. Electronics technicians replaced the dual scram trip unit which serves the primary and pool loop yellow leg flows (FT's and 912A and 912F). This unit, when tested, would generate spurious scrams whenever the pool loop flow scram setpoint potentiometer knob was touched. Primary and pool flow compliance checks were performed satisfactorily. The reactor was refueled and no further problems of this type have occurred. During a startup on November 5, a manual rod run-in was initiated from 5 MW to investigate small (0.5 F) fluctuations in primary temperature (Tc) indication. Electronics technicians recalibrated the millivolt transmitter for reactor water Te (RTD 901A). A satisfactory compliance check was performed and a reactor startup was commenced. During the subsequent startup, the reactor was shutdown by manual scram to investigate erratic Wide Range Monitor (Channel 4) indications. Reseating the Channel 4 picoammeter module corrected the erratic Channel 4 indications. A Channel 4 pre-startup check was completed and the reactor returned to operation. On November 14, a manual rod run-in was initiated when the reactor operator discovered a malfunction in the position indication mechanical-electrical transducer for control blade "D". When control blade "D" was shimmed out at 22.00 inches its position indication stopped incrementing. The shift supervisor physically verified that rod "D" position did not exceed one inch difference from the other three rods as required by Technical Specification 3.2.b. Electronics technicians replaced the transducer and tested the indication satisfactorily. The reactor was then refueled and returned to normal operation. Major maintenance items for the month included: replacing the dual scram trip unit for flow transmitters 912A and 912F; installing, testing, and later removing a pneumatic tube terminal end into the south side of the graphite reflector; mplacing the position indication mechanical-electrical transducer for contml blade "D". Dg tember 1995 The reactor operated continuousl3 n December with the following exceptions: four shutdowns for scheduled maintenance and refueling; four unscheduled shutdowns. On December 26, a spurious Wide Range Monitor (nuclear instrument Channel 4) high power rod run-in occurred during a normal startup. Reactor power was less than l i I-7
I 50 kW at the time. No actual high power condition was indicated on any l instrumentation. The rod run-in was reset and observation of allinstrumentation indicated no abnormalities. A reactor startup was subsequently completed and the g reactor returned to normal operation. W On December 27, a manual rod run in was initiated by the Shift Supervisor when he suspected that the regulating blade was not operating properly. Electronics l technicians discovered a bad bearing and a missing pin in the gearbox input shaft coupling. The bearing and pin were replaced and the regulating blade was tested satisfactorily and returned to normal operation. A Licensee Event Report was written regarding this failure and submitted January 26,1996. The Technical g Specification definition of" operable" leaves any degraded condition of the regulating 3' blade a technical specification violation On December 30, a spurious reactor loop high temperature scram occurred. No g actual reactor high temperature was indicated on any instrumentation; all reactor loop temperatures indicated normal at the time. The scram source isolation monitor g indicated a green leg primary high temperature scram fmm RTD 980A or B--even y though operators observed normal temperature on the 980 A & B indications. The scram most likely was the result of a momentary dimming of the filaments in one of the 980 trip unit bulbs. The 980 A/B trip units utilize a photo transistor switch that l provides a trip if the light source intensity decreases or is intermittent. Electronics technicians replaced the bulbs in each of the photo trip units. A satisfactory compliance check on 980A and 980B was completed and no further problems of this type have occurred. ll During the subsequent startup the Shift Supervisor initiated a manual rod run-in, while the reactor was subcritical, after noting small fluctuations (1-3%)in the Wide g Range Moniter (Channel 4) indication. Electronics tecimicians reseated the Wide Range Monitor drawer voltage regulator and picoammeter modules, and removed and 3 cleaned the range switch. The drawer was returned to service and no further 3 problems of this type have occurred. Mgjor maintenance items for the month included: removing the 6D wedge and l installing 60 wedge in the graphite reflector position #6; replacing pool flow (detector) element 921A; removing 50 plates from the pool heat exchanger; replacing the I uninterruptible power supply (UPS) battery bank; replacing the secondary water a make-up float valve; replacing a bearing and a roll pin in the gearbox input drive shaft coupling of the regulating blade; replacing the photo trip unit bulbs in primary l temperature indications 980A & 980B. I I-8 I I
) SECTION II MURR PROCEDURES f 1 January 1995 through 31 December 1995 , A. CHANGES TO THE STANDARD OPERATING PROCEDURES 2nd edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.)
As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following: Revision No.14, dated 4/27/95 Revision No.15, dated 6/12/95 Revision No.16, dated 10/19/95 B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES (Dated January 1985; Revised and reprinted May 13,1988) As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following: Revision No.19, dated 6/19/95 Revision No. 20, dated 10/18/95 Revision No. 21, dated 12/27/95 C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES Hote: New manualissues 10/29/90 HP-2, Revision No. 2, dated 9/27/95 HP-29, Revision No. 3, dated 9/27/95 HP-8, Revision No.1, dated 9/27/95 HP-31, Revision No. 3, dated 12/18/95 HP-9, Revision No.1, dated 9/26/96 HP-34, Revision No. 2, dated 12/18/95 HP-12, Revision No.1, dated 9/26/95 HP-36, Revision No.1, dated 9/25/95 HP-22, Revision No.1, dated 9/26/95 HP-40, Revision No. O, dated 4/25/95 HP-25, Revision No. 2, dated 9/27/95 HP-41, Revision No. O, dated 12/18/95 HP-28, Revision No. 4, dated 12/18/95 11-1
I D. CHANGES TO MURR SHIPPING PROCEDURES: SAS-0, Revision No. 2, dated 12 July 1995 SAS-2, Revision No.1, dated 9 Aug 95 h SAS-3, Revision No.1, dated 17 Aug 95 SAS-4, Revision No. 3, dated 4 Nov 94 I I I I I I I I I I I I I II-2 I I
STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) Revision Number 14 Revision Date: 4/27/95 I Page Number Page Number I SOPNII-20 SOPNII-28 SOPNII-21 SOPNII-29 SOPNII-22 SOPNIII-17 SOPNII-23 SOPNIII-34 i SOPNII-24 SOPNIII-38 SOPNII-25 SOPNIII-40 SOPNII-26 SOPNIII-41 SOPNII-27 I I I I E } II-3
VII.7.2 Obtaining a Samole Samples 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 to indicate a radiation hazard. 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 seconds, obtain a 500 ml sample in a clean poly bottle from the sample discharge valve. When the poly bottle is full, shut the primary / pool isolation valve first to verify no leakage through the sample valve manifold. E. Shut the sample discharge valve, rinse the outside of the bottle with DI water and make appropriate entries in the primary / pool sample sheet. F. Check all sample valves closed, and secure the fume hood fan and I chirper. l G. Log the eventin the Reactor Console Log. ] VII.8 LIQUID WASTE DISPOSAL SYSTEM VII.8.1 Descriotion A. All drains for potentially contaminated liquids are delivered to the liquid waste retention system (hereafter referred to as the Waste Tanks - WT) l 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 I collection of potentially radioactive liquids. I Rev. 4/27/95 App'd NAM SOP /VII-20
I VII.8.1 Liouid Waste Discosal System Descriotion - (Cont'd) B. The WT system consists of two collection sumps, two sump pumps in g each sump, one "Y" strainer, three waste tanks, two waste tank pumps, E two filter banks (one stainless steel Filtration Systems bag filter ] ! housing and two " Big Blue" Cole-Parmer filters, hereafter referred to as Filter Bank #1 and #2, respectively), and associated ]
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l J piping, valves and fittings. 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. l D. The waste pumps should always discharge through a filter bank to ] any waste tank or to the sanitary sewer system. The discharge header g has a pressure gauge on both sides of the filter, a sample line, and a low 5 flow paddle switch. The low flow paddle switch automatically shuts ] off the nmning pump upon low flow. ] l E. Each tank has a sight glass for level readings. An air sparge line is installed along the entire length of WT1 and 2. Each tank has an unvalved vent to atmosphere. WT3 (and WT1, if needed) can receive waste directly from the hot waste sumps, depending on the valve line-up. l' Each tank has sludge settlement standpipes, but the normal sump discharge is to WT3. WT2 receives efIluent directly from the DI200 g)' regeneration system. F. The following manually operated valves should be shut when ] the system is in a secured line up: ] WD1 I' WT1A WT5 WT-20 WT 51 ] WT-1B WT-7 WT-22 WT61 WD2 ) g WT 2A WT8 WT 24 WT62 ] E WT-2B WT9 WT-25 WT63 ] WT-3A WT-3B WT16 WT-18 WT26 WT-27 WT65 ]
]
l I Rev. 4/27/95 App'd SOP /VII-21 I
VII.8.2 Drv Active Waste We must make every effort to remove as much waste as possible in the form of dry active waste. We have three methods: (1) Sludge Settlement (2) Filtration ] (3) Chemical Precipitant Treatment A. Sludge Settlement WT1 and WT3 are fitted with gravity drains to WT2 through 18" standpipes. This can allow WT1 or WT3 to act as settling tanks, although only WT3 is currently used as a settling tank. When the sludge buildup warrants, the sludge is dumped via a 3" drain line at the south end of WT3 (or the north end of WTI)into barrels or drying troughs. This sludge is dried and removed as dry active waste. B. Filtration ] The waste water will normally be pumped through a waste system filter bank. 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.8.11. 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 SMP-33. I I I Rev. 4/27/95 App'd bMM SOPNII-22 )
I VII.8.3 Dumnine Criteria g A. The liquid waste is collected and held until an analysis is made to g determine that the specific activity of all radioactive isotopes in the E waste is less than the limit specified in the Code of Federal Regulations, Title 10, Part 20 (10CFR20) for dumping liquid waste to the sanitary sewer. In addition to the dumping limit on each isotope,10CFR20.2003 l also limits the total activity which the MURR can dump to the sanitary sewer to 1 curie per year for carbon-14,5 curies per year for H-3 (tritium), and 1 curie per year for other radioactive material, excluding C-14 and H-3. MURR will continue to use 80?c of the totallimit as an administrative limit,i.e.,800 millicurie per year for carbon 14,4 curies per year for H-3 (tritium), and 800 millicurie per year of other g radioactive material. This latterlimit, and a general desire to minimize , the activity dumped to our emironment, dictates that the waste be g retained as long as possible to permit the activity to decay off prior to 5 discharge. If the 10CFR20 limits are not exceeded and the total activity of radionuclides does not exceed 10 mci of tritium or 2 mci of other nuclides, the Shift Supervisor may authorize the water to be
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l pumped to the sanitary sewer. Any tank containing water with an : activity greater than 10 mci of tritium or greater than 2 mci of ] l other nuclides will be discharged only with the approval of the Reactor Manager. l B. When the activity ofliquid waste exceeds the limits of 10CFR20 for disposal, one of two methods will normally be
]
]
g' utilized ta lower activity to acceptable levels. The most ] gj desirable option is to retain the waste until the activity decays ] E to an acceptable level. The second option is to introduce a ] : carrier solution which tends to precipitate out the ] radionuclides. The precipitate can then be removed by ] l filtration, or pumped to a different waste tank (see SMP 33). ] I I Rev. 4/27/95 App'd \) h SOP /VII-23 I
i 4 . VII.8.3 Dumoine Criteria - (Cont'd) ! C. It shall be standard procedure to hold allliquid waste as long as practical to minimize the total activity released. Prior to disposal ] ofliquid waste, a representative sample shall be analyzed by ] a qualified staff member who will record the presence and ] 3 amount ofindividual radionuclides and tritium on the Waste ] Tank Sample Form. This Sample Form is then reviewed by a ] 1
- Health Physics Technician and then sent to the Shift ]
{ Supervisor. The Shift Supervisor reviews the results and ] q j totals the activity, and then determines the appropriate ] l ^ action with respect to disposal. Pumping to the sanitary ] : I sewer is accomplished by Reactor Operations personnel per ] + SOP VII.8.7. After completion of the pumping, the final ] ) volume disposed is entered on the Waste Tank Sample Form, ) i which is then returned to Health Physics for filing. ] D. If the analysis of WT2 exceeds the 10CFRlimits, orif the Shift l , Supervisor wishes to hold the tank for further decay, WT2 can be l pumped to WT1 via the filters. Then WT1 shall be sampled at a later ] date and re-evaluated to determine where it should be dumped. l VII.8.4 Drainine WT1 and WT2 (not currently done; procedure moved to SMP-33) l l VII.8.5 Transferrine WT3 to WT2 I l When WT3 is nearly full, transfer it to WT2 via the standpipe. Preferred transfer time is after normal working hours. NOTE 1: 10CFR20 prohibits visible solids in any sample, therefore, all waste water will be filtered through 5 and 0.5 micron filters prior to sampling as reflected in this procedure. NOTE 2: Only gravity drain will be used when transferring WT3 to WT2. A. Ensure all WT system valves are in their correct positions as per the ] normal system line-up listed under VII.8.1, Liquid Waste Disposal System Description. i Rev. 4/27/95 App'd M SOP /VII-24 (Sections VII.8.5 revised in its entirety) 1 4 i
I VII.8.5 Transferrine WT3 to WT2 - (Cont'd) l B. If required, install new 5 micron filters in Filter Bank #2 I.A.W. VII.8.11, Changing Waste Tank Filters. Update status board. C. Open valves WT-3A,24,62,63 and 65. D. After transfer is complete, shut valves WT-3A,24,62,63 and 65. E. Record transfer evolution in the Reactor Console Log. VII.8.6 Recirculating and Samoline of Waste Tanks NOTE 1: Unless directed otherwise by the Shift Supervisor, WT level should be > 160 cm prior to sampling for sanitary sewer discharge. NOTE 2: Notify Reactor Chemistry group prior to obtaining a sample. l NOTE 3: Do not air sparge WT because aerated water appears cloudy in sample container. A. Sampling WT2 l
- 1. Ensure all WT system valves are in their correct positions as per I
the normal system line-up listed under VII.8.1, Liquid Waste a Disposal System Description.
- 2. If required, install new 0.5 micron filters in Filter Bank #1 I.A.W.
I VII.8.11, Changing Waste Tank Filters. Update status board.
- 3. Open valves WT-2B,7,8,16,18 and 24.
- 4. Start Waste Pump #2 and verify flow through the bullseye.
- 5. Recirculate for at least 12 hours prior to sampling.
I Rev. 4/27/95 App'd % SOPNII-25 l (Sections VII.8.5 and VII.8.6 revised in their entirety) ) I
VII.8.6 A. Sampling WT2 -(Cont'd)
- 6. Purge sample line by obtaining a sample through WT-22 and discard toliquid waste drain.
- 7. Obtain a second sample and fill two (2) 500 ml sample bottles and one (1) specimen sample cup for analysis.
NOTE: If sample shows any indication of suspended or settled solids, additional recirculation and sampling is required.
- 8. Secure Waste Pump #2 and shut valves WT-2B,7,8,16,18 and 24.
- 9. Deliver sample and sample form to the Reactor Chemistry Group for analysis.
- 10. Record sampling evolution in the Reactor Console Log.
B. Sampling WT1 (not currently done; procedure moved to SMP-33) VII.8.7 Pumning Waste Tanks to Sanitary Sewer NOTE 1: This procedure can only be done with Shift Supervisor's and/or Reactor Manager's authorization. NOTE 2: All discharges to the sanitary sewer will be through 0.5 micron filters. A. Pumping WT1 to Sanitary Sewer (not currently done; procedure moved to SMP-33) B. Pumping WT2 to Sanitary Sewer
- 1. Ensure all WT system valves are in their correct positions as per the normal system line-up listed under VII.8.1, Liquid Waste Disposal System Description.
Hev. _4/27/95 App'd M SOP /VII-26
- (Sections VII.8.6 & VII.8.7 revised in their entirety) 1
i i I! VII.8.7 B. Pumping WT2 to Sanitary Sewer -(Cont'd) g 1
- 2. Open WD-1, WD 2, WT-2B,7,8, IS and 18. i
- 3. Start Waste Pump #2 and verify flow through bullseye.
- 4. When tank is empty, ensure pump is secured and shut WD-1, i
WD 2, WT-2B,7,8,16 and 18.
- 5. Record the volume pumped on the Waste Tank Sample Form and return it to Health Physics Office. l
- 6. Record pumping evolution in the Reactor Console Log. g)
VII.8.8 Pumninc Waste Tanks to Secondarv Svstem (moved to SMP-15) I' VII.8.9 Pumnine Waste Water from One Waste Tank to Another A. Pumping WT2 to WT3
- 1. Ensure all WT system valves are in their correct positions as per the normal system lineup listed under VII.8.1, Liquid Waste Disposal System Description. l,
- 2. Check WT3 level to ensure there is sufficient volume to accept g contents of WT2.
- 3. Open WT-2A to pump WT via the standpipe or WT-2B to pump the entire volume of WT2. Open WT-5,9 and 27.
- 4. Start Waste Pump #1 and verify flow through bullseye.
I
- 5. Commence a vigorous air sparge through W-2C (except if pumping via standpipe).
- 6. When tank is empty, ensure pump is secured and shut WT-2A or I
WT-2B,20,5,9 and 27. Rev. 4/27/95 App'd 31M SOPNII-27 (Sections VII.8.7 & VII.8.9 revised in their entirety) ] I
VII.8.9 A. Pumping WT2 to WT3 - (Cont'd)
- 7. Record pumping evolution in the Reactor Console Log.
B. Pumping WT2 to WT1 (not currently done; procedure moved to SMP-33) VII.8.10 Dumning Sludce from a Waste Tank Sludge will be dumped from WT1 through WT-44, from WT2 through ] the sludge plug, and from WT3 through 3D into barrels or drying ] troughs by a procedure approved by the Shift Supervisor. This sludge will be dried and disposed of as Dry Active Waste. k VII.8.11 Chancine Waste Tank Filters NOTE 1: In order to minimize radioactive waste, waste tank filters should not be replaced unless draining and pumping evolutions cannot be performed in a reasonable amount of time. NOTE 2: Shift Supervisor's approvalis required to change filters. NOTE 3: Wear gloves, lab coat, and shoe covers when changing filters. A. Changing Filters in WT Filter Bank #1 and/or #2
- 1. Check shut valves WT-63,62,18 and 16.
- 2. Ensure drain line hoses are positioned to drain to the floor drain.
Open drain valve WT-51 if replacing filters in Bank #1 or Bank #2.
- 3. Open vent valve WT-61 and drain the filter housings. When water stops issuing from drain lines, remove filters from Bank #1. If changing Bank #2, open WT-20,63 and 24 and place used filters in a bucket.
- 4. Install appropriate size filters as required by procedure and reassemble filter housings. Shut WT-51.
Rev. 4/27/95 App'd b SOP /VII-28 (Sections VII.8.9 & VII.8.11 revised in their entirety) 1
I VII.8.11 A. Changing Filters in WT Filter Bank #1 and/or #2 - (Cont'd) l
- 5. ReSil the filter housings by opening DCW valve 38 and valves l WT-65 and WT-16. If Bank #2 is being refilled, also open WT-20, 63 and 24.
- 6. When water issues from filter vent, shut WT-61. Shut DCW valve 38 and WT-65 and WT-16. If filling Bank #2, when water flows into E WT-2 shut WT-20,63,24 and DCW valve 38. W
- 7. Wash down area and place used filters in the filter drying cabinet.
- 8. Check self on portal monitor. g VII.8.12 Chemical Precioitate Treatment (moved to SMP-33)
VII.9 NITROGEN SYSTEM I VII.9.1 Puroose The primary function of the Nitrogen System (N2 )is to provide pressurized N2 to the pressurizer to maintain primary pressure. VII.9.2.1 N,> System Startuo l Before the reactor is made operational, light off the N2 system by the ) following. procedure: A. Verify that the regulator is set at 140 psig and the average gauge pressure of the two N2banks is at least 500 psig before placing the system in operation. B. Close the switch which energizes the electrical controls for the system. C. Open the N2 cut out valve N15 in room 114, and verify a N2 pressure of 90 to 95 psig t.o the pressurizer. The N2 system is now ready for operation. g Rev. 4/27/95 App'd M SOPNII-29 l (Section VII.8.11 revised in its entirety) ] I
VIII.3.5.2 Station Control Malfunction -(Cont'd) 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. D. The reactor operator will get in touch with a health physics technician to . monitor as required. 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. NOTE: If a boron shielded rabbit is stuck in the reflector, control room ] operators will initiate a manual rod run-in to about 500 IGV. ] A. After the control room is aware of the problem, press the " return" pushbutton. Observe the rabbit in reactor light and check with the control room to see if the operators heard the rabbit leave the reflector region. Hearing the rabbit depart the reflector is the only sure way to know it has left. If the rabbit was heard to depart the reflector region, check the other connecting station to see if the rabbit was returned there. B. Depress the dispatch button. s C. Repeat steps A and B several times as directed by the control room. D. If the attempts fail, tum control box off. Go to the other connecting station, . line it up for service and repeat steps A and B. E. If rabbit still has not returned, a chaser rabbit may be inserted in an attempt to dislodge the stuck rabbit. Before the chaser rabbitis dispatched it will be marked so that it can be readily identified, thus preventing confusion with the stuck rabbit should it return. CHASER RABBIT ID MARK SHOULD GO ACROSS ONE END CAP, ALONG THE SIDE AhT ACROSS THE OTHER END CAP. F. 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 rabbitis stuck in the reflector, the reactor may have to 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. 4/27/95 App'd SOP /VIII-17
I VIII.4.7 Operating Procedures for Beamport "F" The following procedures shall be used for operation of Beamport "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 l,l personnel. A copy of this procedure shall be posted near Beamport "F" l and a copy shall be put in the Beamport "F" log book. gl CAUTIONS:
- Ensure center tube is not left fully inserted; allow at least 1/4 inch for thermal expansion.
l
- After the center tube is inserted, verify drain and vent valves are shut.
g
- 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 filter parts are in g tube and pushed forward to reactor end of filter tube. Apply vacuum E slowly so that filter parts are not sucked back. Have Health Physics coverage on startup.
- After startup, check radiation survey readings against previous l
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 l reactoris shutdown. The waterlevelin the surge tank shn11 he checked and maintained by Operations. Makeup water should be " super" water. The principal experimenter should send a note to Operations asking for ] I a change in filters and tubes. The note should reach Operations before the shutdown. The principal 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 g should be marked and their storage should be controlled because of their activation and potential contamination. Rev. 4/27/95 App'd IfhM SOP /VIII-34 I
/
VIII.5 HANDLING AND RELEASE OF IRRADIATED SAMPLES VIII.5.1 General Resnonsibilities The Reactor Senices Engineer shall coordinate the handling and shipping of all samples irradiated in the in-pool facilities. He shall ensure that the shipping container is in conformance with the applicable regulation and that all required shipping papers and documents are prepared in a timely manner. [ The Services Engineer shall also coordinate the sample handling with Health Physics personnel. The Shift Supervisor shall have the responsibility of ensuring that all irradiation records are complete. He willimmediately notify the Senices Engineer or his designated representative of any apparent discrepancies relating to the in-pool irradiations. VIII.5.2 Sarrrh. Mand 1Me Pmeedures Detailed procedures for the handling ofvarious samples are contained in the Health Physics Standard Operating Procedure p VIII.6 RESPONSE PROCEDURES FOR THE NUCLEPORE IRRADIATION L FACILITY Deleted in its entirety. ] [ VIII.7 THERMAL COLUMN DOOR OPERATIONS VIII.7.1 Ocenine the Thermal Column Door NOTE: Do not open thermal column door with the reactor critical.
- 1. Clear all obstructions from behind thermal column door.
- 2. Verify air off to Radiograph with Control Room.
- 3. Disconnect air supply line on thermal column door at the snap fitting.
- 4. Verify Neutron Radiograph rotating aperture drive shaft pulled back and disconnected.
Rev. 4/27/95 App'd \Mh_ SOP /VIII-38 eJ -. .- _ _ _ _ _ _ _ _ _ _ _ . - .
VIII.7.2 Shuttine the Thermal Column Door - (Cont'd) ] C. Install rubber grommet and attach rabbit drive mechanism. D. Place shield box door back on rails and shut it. Pin door fully shut. E. Recouple take-up spline coupling. F. Open Nuclepore air supply valve and reset all tension controls. G. Test run film. H. Place the experimentin its desired operational mode in accordance with approved procedures.
- 11. Inform operators of the system status.
VIII.8 RESPONSE PROCEDURES FOR THE ALPHA LABORATORY When responding to alarms from the Alpha Laboratory and the Argon Glove I Box, an initial attempt to contact the laboratory to notify any lab personnel g present shall be made. If no answer, or if otherwise determined necessary, 3 proceed with the following procedure. NOTE: Maintaining an inert argon atmosphere is the principal fire safety feature of the argon glove box. The following alarms may not have immediate safety implications, however, they indicate a degradation in the fire safety feature of the argon glove box and indicate a potential loss of glove box integrity. VIII.8.1 Resnonse to Aloha Laboratorv High Airborne Radioactivity Alarm (Exhaust g and/or Room Monitor) W
- 1. Notify shift supervisor and Health Physics Manager.
- 2. Monitor readings on facility exhaust particulate monitor in control room.
l An assessment of the off-site radiological consequences shall be made. g
- 3. If the stack particulate monitor indicates a steady increase coinciding with -E an alpha-6 alarm, secure the reactor, and turn off EF-13 and EF-14 at the breakers on the Emergency Distribution Center.
- 4. Ensure persons have evacuated the Alpha Laboratory. If no experimenter l
is present, call the on-call experimenter as soon as time permits. WARNING: DO NOT enter room, except for life saving or accident mitigation efforts, until Health Physics arrives. ] l
- 5. Secure the Alpha Laboratory exhaust and supply fans locally. g
- 6. Shut the Alpha Laboratory supply damper only.
App'd M( SOP /VIII-40 I Rev. 4/27/95 I
VIII.8.1 Resnonse to Aloha Laboratorv Hich Airborne Radioactivity Alarm ] (Exhaust and/or Room Monitor)-(Cont'd) ]
- 7. Except for life saving or accident mitigation, personnel shall ]
not reenter the Alpha Lab prior to a Health Physics evaluation ] of the airborne radiological hazard in the laboratory. ] SUBSEQUENT ACTION: Assist recovery and decontamination procedures for the Alpha Laboratory and basement in vicinity of Alpha Laboratory. VIII.8.2 Hich Oxveen in Glove Box Alarm NOTE: The continuously operated oxygen monitor (located in the DRI-TRAIN l rack)is the most sensitive indication of air leakage into the argon glove box.
- 1. Verify no increased airborne activity on the stack monitor.
- 2. Notify Shift Supervisor and Health Physics technician.
I 3. Contact TRUMP-S scientist on call.
- 4. A. Check the warning light panel outside the door and check the argon I glove box pressure indicated on the three photohelic gauges located on top of the argon glove box. (Normal range -0.1 to -2.0 inches of water).
l B. If pressure is near zero, then the possibility of a leak exists and the glove box should be visually inspected from the window to the Alpha Laboratory. i 5. Check the Alpha Laboratory exhaust monitor (alpha-6) and the Alpha Laboratory room monitor (alpha-3) for indication of elevated activity. A. If no elevated activity is indicated on either monitor, enter the laboratory by normal entry procedure, TAM-10. B. If elevated activity is indicated, see SOP VIII.8.1, Response to Alpha Laboratory High Airborne.
- 6. Check NITRAIN/DRI-TRAIN units for loss of power.
I 7. Check glove ports covered.
- 8. Check oxygen monitor reading. If reading exceeds 100 ppm, secure the argon box well heater (use range switch ifindication is off scale).
l 9. Investigate source ofleakage and temporarily seal, if possible.
- 10. Exit Alpha Laboratory by normal exit procedures, TAM-10.
I 11. Assist TRUMP-S scientist and Health Physics in determining source and corrective action. Rev. 4/27/95 App'd SOP /VIII-41
l l STANDARD OPERATING PROCEDURES l 2nd Edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) l Revision Number 15 Revision Date: 6/12/95 l I Page Number Pare Number SOP /I-19 REP-14-1 l SOP /I-21 SOP /A-la l SOPN-1 SOP /A-4a SOPN-2 SOP /A-4b l SOPN-4 SOP /A-5b SOPN-5 SOP /A-5c SOPN-6 SOP /A-14a
. SOP /A-14b SOPNI-2 SOP /A-14e SOP /A-21c i SOPNII-1 SOP /A-21d l
1 I J II-4
Table III Normal Reactor Operating Ranges Parameters Normal Operating Range Units
- 1. Thermal Power,5 hBV Operation 5 59c hBV
- 2. Thermal Power,10 hBV Operation 10 + 09c hBV
- 59c
- 3. Primary Coolant Flow,5 AnV Operation 1850 50 gpm l Primary Coolant Flow,10 AnV Operation 3700 50 gpm
- 4. Reactor Outlet Coolant Temperature 136 *F I 5. Reactor Inlet Coolant Temperature 120 F
- 6. Pressurizer Pressure 67 i 3 psig l
- 7. Pressurizer Level Centerline +4 to -8 inches l 8. Pool Coolant Flow,10 ABV Operation 1200 100 gpm 1
- 9. Pool Outlet Temperature (Hot Leg) 105 *F
- 10. Pool Level 29'7" 3" feet-inches
- 11. Resistivity, Outlet of DI-300 > 500 K ohms-cm
- 12. S-1 Temperature Demand Set 120 F
- 13. S-2 Temperature Demand Set 100 F l
l [ Rev. 6/12/95 App'd M SOP /I-19
I Table IV (continued) Nominal Values of Trip Settings for Alarm, Run-In and Scram Conditions for l 10 ABV Operation Scram Run-In Alarm Units l 63 65 psig-I
- 12. Low Pressurizer Press --
- 13. Hi Pressurizer Press 78 -- 75 psig
- 14. Pool Low Flow,10 ABY 980 --
1060 gpm ] l
- 15. Pool Hi Temp -- -- 115 *F
- 16. Low Pri Demin Flow -- 42.5 gpm I
- 17. Low Pool Demin Flow -- -- 42.5 gpm
- 18. Bldg Air Plenum Hi 10 x normal oper- -- -- mr/hr Activity ating background
- 19. Reactor Bridge 10 x normal oper- -- -- mr/hr ating background
- 20. RC Hi Conductivity -- -- 2.0 mhos
- 21. PC Hi Conductivity -- -- 2.0 mhos l
- 22. Hi-Refl AP,10 ARV psi 7.0 I
- 23. Low Refl AP,10 hnV 3.0 -- -- psi
- 24. Low N2 System Press -- -- 115 psig l
- 25. Low Seal Trench Level -- - 5 feet 6200/2500 gal
- 26. Hi/Lo Levelin T-300 -- --
6000/<100 gal
- 27. Hi/Lo Level in T-301 -- --
App'd SOP /I-21 Rev. 6/12/95 I
[ SECTION V POOL COOLING SYSTEM { V.1 Pool Cooling Svstem Startuo [ V.1.1 If pool system maintenance has been performed since the last pool system shutdown, ensure that all disturbed valves are in their normal positions. The Shift Supervisor will determine if a valve lineup checksheet needs to be completed. [ For Mode I operation, heat exchanger 521 and either one or both pump (s) ] V.1.2 508A/B must be in 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.9.2 & VII.10.2). , B. Visually check for a proper poollevel; the pool should be filled to a level satisfying either LC-910 (normal pool level controller) or LC-966 I (intermediate refuel poollevel controller). C. Check the reflector AP scram setpoints are set for the 101mV mode of ] I operation. ] D. Visually check for properin-poolloadings: [ 1. Make certain experiments are securely loaded and are seated within their properloading facilities.
- 2. Make certain the flux trap facility appears normal and the test hole
[ strainer 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. I Rev. 6/12/95 App'd W SOP /V-1 sw*
V.1.3 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 Il and the stop switch is unlocked; the offindicator in the control , room for P508A/B will be lighted. G. Place HX bypass switch 2S40 in the "10 MW" position. ] H. Master control switch IS1 should be in the test position.
- 1. Place valve V509 switch to the manual /open position. l J. Turn on pool pump P50SA/B as appropriate by turning the control switches to on. Verify proper flow. g K. Start cleanup pump P513B and verify flow.
L. Adjust pool flow,if required, by throttling the HX outlet valve (600A) ] as necessary. M. With normal flow and pressure, place V509 switch to auto / closed. N. Verify that all the valve position indicating lights are operating. If not, replace the appropriate light bulb. If this does not clear the malfunction, l shutdown the pool system as per V.2 and verify proper valve operation l, by a visual examination of the actuator linkage during operation. . NOTE: Determine the cause of the failure and make repairs prior to startup. O. If not required for other evolutions, turn master control switch IS1 to the E on position. m V.2 Pool Svstem 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: I Rev. 6/12/95 App'd WeW\ SOP /V-2
V.3.1 B. The second approved method of filling the pool is via the 4 inch line from tank T300/301 to the pool pump suction and discharge line.
- 1. Check the 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 and T300 to drain by gravity feed alone.
- 3. Close valve V522C when the filling operation is completed.
V.4 Pool Lowering Procedure V.4.1 Lowering Pool Water Level to Refuel Bridge Two methods oflowering poollevel may be used: A. By use of the skimmer system (SOPNII.5.2). 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. Place master switch IS1 to test. ] . B. Place V509 to manual /open. ] C. Start P508A or 508B. ] D. Pool lowering procedure is as follows: ] 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 during the course of the draining operation. The pool level will not be lowered below the intermediate refuel level without the specific approval of the Shift Supervisor. ]
- 1. Health Physics personnel shall be present while lowering pool level to ensure that a high activity sample or component is not uncovered causing excessive personnel exposure.
Rev. 6/12/95 App'd N SOPN-4 [
V.4.2 D. 2. Check pool area to ensure all samples, spacers, and other ] radioactive materials are low enough to guarantee adequate shielding.
- 3. Turn skimmer pump P532 off.
[
- 4. Ensure that T301 is valved in service.
- 5. Open manual valve V5220 in room 114 to full open. Note the reduction of flow as the valve is opened.
- 6. With V522C full open, slowly throttle down on heat exchanger ]
inlet diaphragm valves 522 A and D until the flow indicated by ] 7. the flow recorderin the control room shows approximately 200 gpm. When the pool level is at the desired level or a T301 high level alarm l is received, secure P508 and immediately close V522C.
- 8. Reopen the inlet valves of the heat exchanger. ]
- 9. Ensure that Health Physics clears the bridge area for access.
V.5 Pool Cleanuo System V.5.1 To put the pool cleanup system into normal operation, the following procedure is used: A. Check valve V515T, V515N and V515P open. B. Check valves V515M, V515X (P513B bypass) and V515Q closed for normal operation. NOTE: Opening V515M and closing V515T bypasses flow around valve V509, HUT 504 and P508A/B to the input of P513B. Opening l V515Q and closing V515P returns processed water to the suction side of P508 Aid rather than back to the top side of the gj; pool. C. Make certain that one of three possible demineralizer units is valved into I)l the cleanup system according to the procedures described in Section VII. D. Turn on demineralizer flow recorder. Time and date the strip chart. l E. Turn on P513B from the control room by turning the P513B control switch to the ON position. l F. Verify a 50 5 gpm flow rate on the pool cicanup loop flow recorder. E; I G. Indicated flow rate should be 50 5 gpm and the indicated water purity Bl t should be 1e'ss than 2.0 pmhos/cm from the demineralizer. , Rev. 6/12/95 App'd (JMM SOPN-5
i l
, V.5.2 Discharging Excess Water from Primary or Pool System with T301 Full -
I moved to SMP-20. I V.6 Single Pool Pumo Oneratine Procedure i NOTE: This procedure will be accomplished after a need has been determined to secure one of the pool pumps and only with the reactor I shutdown and a radiation survey of the work area in room 114 completed. A. Shut down the reactor. B. Secure the pool system. l C. Open the breaker for the pump to be secured at the motor control center. D. Lock out the run/stop switch as the pump to be secured. E. Close the pump suction and discharge valves (on the pump to be secured). Perform appropriate system tagout. I F. Check fully open the suction and discharge valves on the operating pump. G. Fully open valve 600A (Pool HX discharge valve). ] l H. Place the pool system back on line. . I. Monitor pool flow, reflector D/P, pool demineralizer flow. NOTE: Trip point for reflector AP may have to be reset for single pump I operations. J. Adjust pool flow potentiometer. K. Note in the control console log that single pool pump operation has commenced. I 1 I l l l L Rev. 6/12/95 App'd M SOP /V-6
I VI.1 Stetan of the Secondarv Svstem - Cont'd ] D. The following valves in equipment room 114 should be in the position indicated: Onen Closed S-23 S 191 S 27 ) S-24 S-192 S-117 ] S-30 S 210 S-137 ] S 31 S-211 S-141 ] S-34 S-212 S-142 ] S-35 S 213 S-217 ) S-39 S-214 S 218 ] S-41 S 215 S 219 ] S-134 S-216 S-220 ] S-135 S 223 S-221 ] S-222 ] E. For operation of the chiller units with feed water from P-1, P-2, P-3, or P-4, the following valves in room 278 should be in the positions indicated - as follows: l Onen Closed S-53 S-57 S-54 S-149 S 55 S-58 S-146 i F. Verify that the Bailey Meter recorder Model E101 in the reactor control room is on to monitor secondary flow and temperature during operation. Time and date chart. Secondary outlet temperature for the heat ] exchangers can be monitored in the control room with the digital ] readout and selector switch. G. Verify that the circuit breakers for P-1, P-2, P-3 and P-4 on MCC-2 in the g cooling tower are closed and that the control switch on the panels is in auto mode. Rev. 6/12/95 App'd M SOP /VI-2 l
SECTION VII AUXILIARY SYSTEMS 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 levelis read out continuously on a digital meter which gives the reactor powerin 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. VII.1.1 Settine the Potentiometers The flow potentiometers are set at a fraction of a given reference flow. ] The reference flow for the primary is 4000 gpm and for the pool ] is 1600 gpm. ] To determine the pot setting for primary flow, add the indicated flow in ] primary 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 two duplicate indications of total pool ] flow. Because the pool cleanup flow is extracted before the pool water ] flows through the heat exchanger and flow orifice, cleanup flow ] does net have to be subtracted from pool flow. To determine the pot ] setting for pool flow, determine the average of the indicated flows and ] divide by the pool system reference flow of 1600. The resulting ] fraction should be set into the pot. NOTE: We no longer use recorder full scale indications as ] reference flow to determine the pool flow potentiometer ] setting. ] Rev. 6/12/95 App'd DNBW\ SOP /VII-1
4 4 REP 14 LOSS OF POOL FLOW DURING REACTOR OPERATION IE pool flow rate drops below 1000 gpm for an unspecified reason, the reactor ) operator shall: i BBfEDIATE ACTIONS:
- 1. MANUALLY SCRAM the reactor, ensure the reactor is shutting down, l; verify all rods are bottomed.
l
- 2. Shut down the pool system, leaving the primary and secondary systems on 1 line.
I SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor. -
- 2. Determine the cause of pool flow loss and correct it before restarting the reactor.
- 3. Make console log entry and fill out UNSCHEDULED SHUTDOWN REPORT.
Rev. 6/12/95 App'd M REP-14-1
REACTOR STARTUP CHECKSHEET Date: FULL POWER OPERATION Time (Started): BUILDING AND MECHANICAL EQUIPMENT CHECKLIST i l 1. Emergency air compressor Ooad test for 30 minutes after maintenance day).
- 2. Beamport Floor:
i a. Beamport radiation shielding tas required). I b. Beamport status checked' updated. I c. Seal trench low level alarm tested (after maintenance day). I d. Check closed beamport floor access gates, f 3. a. Check operation of fan failure buzzer and warning light. Notify Alpha Lab of momentary ventilation loss. (Reg'd if shutdown longer than 4 hours.)
- b. Test stack monitor and low flow alarm per SOP while in west tower.
- c. Test UPS alarm panel.
- 4. Emergency generator availability checked as per Sect. I.A. and III. of D.G. checklist.
(If shutdown for greater than 24 hours, run emergency generator for 30 minutes.) l l S. Emergency pool fill. (Check valves PIV 1 and PIV 2 locked open.)
- 6. Visual check of CT and secondary equipment:
- a. Oil level in CT fans normal (after maintenance day).
- b. Secondary makeup isolation valve power switch closed, valve cycled to verify operation and placed in auto mode.
- 7. Visual check of room 114 equipment:
- a. Valve Op Air compressor oillevel normal and cutout switch in auto.
- b. Main air back up valve VOP 33 open.
- c. Air valve for valve operating header (VOP 31) open.
- d. P501A and P501B coolant water valves open. ,
- e. Check valves 599A and 599B open.
- f. Pump controllers unlocked to start (as required).
- g. S1, S2 hydraulic pumps on (oil level normal). ]
I
- h. Valves S1 and S2 cycled in manual mode and positioned as required. ]
- i. Vent the pool hold up tank.
- j. Vent the pool skimmer systein pump.
l k. Check the pipe trench free of water. Check the four pipe annulus drain valves for water leakage after maintenance days.
- 1. Add DI water to beamport and pool overflow loop seals.
- m. Check cil reservcir fcr pumps 501A,501B, ar.d 533 fcr adequate supply. Add if necessary.
I n. Visually check room 114 and DI area after all systems are in operation. l 8. Reactor Pool: l a. Reflector experimentalloadings verified and secured for start up. ! b. Flux trap experimental leading verified and secured for start up, or strainer in place.
- c. Check power on and reset, as necessary, silicon integrator, totalizer setting, silicon rotator, and alarm system.
4 h J Rev. 6/12/95 App'd: SOP /A-la
DATE REACTOR SHUTDOWN CHECKSHEET i
- 1. Time of reactor shutdown:
- 2. All blades bottomed and drive mechanism full in. l
- 3. Magnet current switch off.
- 4. SRM set to required position (= 1000 counts if refueling).
- 5. Reactor primary system shutdown per SOP IV.
- 6. Pool system shutdown per SOP V. B Secondary system shutdown per SOP VI,in required lineup. ]
7.
- 8. Cooling tower fans off.
- 9. Digital readout switch off.
- 10. Annunciatorboard on off .
l l
- 11. Reverse osmosis unit to standby.
- 12. Sample inventory satisfactory including counts recorded, if necessary, ] l and data sheets updated. l
]
- 13. All bypass switches off and keys in key box.
on ]
- 14. Master switch off .
]
- 15. DCT system secured.
)
- 16. Room 114 check:
- a. Cooling flow to P501 A/B secured.
- b. Valves Si and S2 hydraulic motor off.
]
- c. Room 114 pump controllers locked out.
]
- 17. Completed and logged Reactor Shutdown Checksheet.
Shift Supervisadead Senior Operator I SOP /A-4a Rev. 6/12/95 App'd _h I
REACTOR SHUTDOWN CHECKSHEET (Cont'd) BUILDING SHUTDOWN CHECKSHEET:
- 1. Poollevel normal.
- 2. ARM trip levels set per SOP.
Annunciator board off. [ 3. 4 TV unit secured.
- 5. Off-gas recorder paper supply okay, chart timed and dated. 1
- 6. Primary / pool drain collection system secured per SOP.
- 7. Routine patrol completed.
[ l 8. SRM, IRM, WRM, PRM, ARM and process radiation monitors in operate mode.
- 9. Master key switch off and in key box.
- 10. Test of containment intrusion alarm completed. System energized.
- 11. All keys accounted for.
- 12. Building shutdown and reactor secured.
- 13. Control room doors locked.
- 14. Logbook entries complete, crews signed out. I
- 15. Completed building shutdown checksheet. I WARNING: If TRUMP-S experiments are in progress and the control room is not staffed, there 1 must be one TRUMP-S experimenter in the Alpha Lab and a licensed operator or j health physicist present in the MURR facility. j l
If no TRUMP-S experiments are in progress and the control room is not staffed, a I licensed operator or health physicist must be present in the MURR facility g any I actinide within the glove box is in a fire proof container. 1 Shift Supervisor / Lead Senior Operator e Rev. 6/12/95 . App'd M, SOP /A-4b
MODE PROCESS DATA DATE Time l In Pool Ht. Exch. l l l Pressurizer Level l ..; J Pool Refl. A P l l l PS 944A l 1 PS 944B DPS 928A DPS 92SB DPS 929 Sec.Th (1) Sec.T e (2) Sec. A T Sec. Water Flow PoolT e (3) (4) ] Pool T h Sec.Th Pool (5) 1 j Sec.Th Pri. - (6) ' Sec.T Pri. (7) ) e j i Pool Hx Sec. Flow F2 Cond In Rx Cond Out Pool Cond in Pool Cond Out Stack Gas Stack Part. Stack Iodine Operator Reader Heat Balance by Manual Calculation: Rev. 6/12/95 App'd M SOP /A Sb I I
1 PROCESS DATA Mods D:te i Time l Pri. Fl:w A i Pri. Fl:w B l Pool Flow 1 ) Pool Fl:w 2 j i Demin Flow A Demin Flow B Pri. T e Pri. T h Pri. AT j l Pool T e Pool T h 1 Pool AT ; l North Wall ARMS West Wall ARMS l j South Wall ARMS , 1 Air Penum 1 l Second:ry Water Bridge Fuel Vcult Room 114 Air Plenum 2 Fission Product TAA Yellow TAA Rod Run In TAA Green Rx Pressure Rx T e Loop A Rx T e Loop B SOP /A-5c llev. 6/12/95 App'd 1
Date POOL SYSTEM VALVE LINEUP CHECKSHEET This checksheet shall be completed when required by the SOP. The operator performing the check will l verify the position of each valve and indicate the verification by initialling the 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 normal position on this sheet, and write in the actual position of the valve. The reason for the valve being positioned abnormally 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 l position in the space provided on the checksheet. Valve # Valve Description Position
- 1. 598A Air supply to 546 Open
- 2. 555P Air supply valve to V-517 Closed
- 3. 548A P-532 pool suction Open 4 548B P-532 pool (at refuel) suction Closed
- 5. 518U Vent valve (pool Tn) Closed
- 6. 515X P-513B bypass Closed 7 515N P-513B discharge Open
- 8. 518H P-513B suction gage cutout Open
- 9. 518G P-513B discharge gage cutout Open
- 10. 522C Pool drain / fill Closed
- 11. 522B Pool fill Closed
- 12. 515Q Cleanup rerum to loop Closed
- 13. 515M Cleanup suction from pool Closed
'14. 515T Cleanup suction from loop P-508A discharge Open Open l
- 15. 522F 522E P-508B discharge Open
- 16. l
- 17. 53SC P-50SB bypass Closed ]
- 18. 5181 P-508A gage cutout Open
- 19. 518J P-508A gage cutout Open
- 20. 518AD P-508B gage cutout Open
- 21. 518 AC P 508B gage cutout Open 22, 599J PS-947 cutout Open
- 23. 539A P-508A suction Open
- 24. 539C P-508B suction Open
- 25. 518V Vent valve Closed App'd __\j@ SOP /A-14a Rev. 6/12/95 I
< POOL SYSTEM VALVE LINEUP CHECKSHEET (Cont'd)
Valve # Valve Description Position
- 26. 515P Cleanup return to pool Open
- 27. 514B HUT outlet Open g
- 28. 522A HX 521 inlet Open ]
- 29. 522D HX-521 inlet Open ]
- 30. 600A HX-521 outlet Throttled ]
- 31. 518N HUT vent cutout Open
- 32. 518K HUT vent Closed
- 33. 515R HUT drain Closed (locked)
- 34. 515Z HX-521 drain Closed )
- 35. 518AJ HX-521 vent Closed ]
- 36. 518AG Pool system "Y" strainer drain Closed 37, 518Q Drain valve (tunnel) Closed
- 38. 518R Drain valve (tunnel) Closed
- 39. 514A V-509 cutout Open
- 40. 568G PT-917 cutout valve Open
- 41. 599Z PT-917 vent Closed ,
- 42. 599Y P-532 suction vent Auto Float
- 43. 5151 P-532 suction Open 44 518D P-532 gage cutout Open
- 45. 518C P-532 gage cutout Open
- 46. 515E Skimmer filter inlet Open
- 47. 515D Skimmer filter outlet Open
- 48. 567A Drain collection pump suction Open
- 49. 567B Drain collection pump suction drain Closed
- 50. 566 Drain collection system discharge Open
- 51. 567C Drain coll system discharge to 513B suction Open
- 52. 593 Skimmer suction T 300/T 301 Open
- 53. 568C FE-921 valve manifold Inlet / outlet open; equalizer closec ]
- 54. 568D FE-921 valve manifold inlet / outlet open; equalizer closec 1
- 55. 599S FT-912D drain Closed 56, 599T FT 912D drain Closed
}
57, 599N FT-912F drain Closed 1 r Rev. 6/12/95 App'd W SOP /A-14b
P POOL SYSTEM VALVE LINEUP CHECKSHEET (Cont'd) Valve # Valve Description Position FT-912F drain Closed
- 58. 599Q 56SF FE 923B valve manifold Inlet / outlet open: equalizer closed -
59.
- 60. 5953 Pool cleanup efnuent to sample station Open g
- 61. 595G Poolinfluent to sample station Open m
- 62. 595K Pool cleanup vent Closed
- 63. 515AC Pool cleanup to blank Dange Closed
- 64. 518AL Pressure ind. 927 pool outlet Open ]
Pressure ind. 427 pool inlet Open ] !
- 65. 518AK
- 66. 599U FT 912D LP side high point vent Closed ]
- 67. 599X FT-912D HP side high point vent Closed ]
FT 912F LP side high point vent Closed ]
- 68. 599P 599R FT 912F HP side high point vent Closed ]
69. COMMENTS: E I I E; 1 E I OPERATOR Rev. 6/12/95 App'd _h SOP /A-14c I4 I
The foll: wing valyzs will be found in Room 114: Valve # Valve Description Position
- 59. S-161. dp transmitter hp isolation Open
- 60. S 183- Rosemount hp isolation Open
- 61. S-130 Bailey hp isolation Open
- 62. S-182 Rosemountlp isolation Open
- 63. S-131 Bailey lp isolation Open
- 64. S-162 dp transmitterlp isolation Open f 65. S-23 HX 503A supply isolation Open
- 66. S 24 HX 503B supply isolation Open
- 67. S-30 S-1 supply side isolation Open
- 68. S-31 S-1 return side isolation Open
- 69. S-34 S-2 supply side isolation Open
- 70. S-35 S 2 return side isolation Open
- 71. S-39 HX 503A return side isolation Open
- 72. S-41 HX 503B return side isolation Open
- 73. S-176 HX 503A sparge Open
- 74. S-178 HX 503B sparge Open 75.- S-181 Bailey hp test connection Closed
- 76. S-185 'Rosemount hp test connection Closed
- 77. S-184 Equalizing valve Closed
- 78. S-186 Rosemountlp test' connection Closed
_ . 79. S-180 Bailey lp test connection Closed
- 80. S-133 Transmitter flush valve Closed
- 81. S 27 S 1 bypass valve Closed
- 62. S-137 HX 503B drain Closed
- 83. S 142 HX 503B vent Closed
- 84. S-136 S 1 drain Closed
- 85. S 134 Hydro connection (AP gauge) Closed ]
- 86. S 135 Hydro connection (AP gauge) Closed ]
- 87. S 141 HX 503A vent Closed
- 88. S 117 HX 503A drain Closed
- 89. S-195 Return to HX503A from waste heat system Closed Rev. 6/12/95 App'd M SOP /A-21c Valves deleted; remaining renumbered only ]
P-Valve # Valve Description Position j
- 90. S 194 Supply from HX503B to waste heat system Closed
- 91. S-134 HX 503A AP gauge Open ]
- 92. S-135 HX 503A AP gauge Open ] .j
- 93. S-191 HX 503B AP gauge Open ] i
- 94. S-192 HX 503B AP gauge Open ] l;
- 95. S-210 HX 521 inlet Open ]
- 96. S-211
- 97. S 212 HX 521 inlet HX 521 bypass Open Open
]
]
l
- 98. S-213 HX 521 inlet pressure ind. Open ]
- 99. S-214 100. S-215 HX 521 outlet pressure ind.
Flow transmitter inlet Open Open
]
]
(l g 101. S-216 Flow transmitter outlet Open ] 102. S-217 Water chem. inlet side Closed ] g 103. S-218 Water chem. outlet side Closed ] 104. S-219 HX 521 inlet vent Closed ] i ( 105. S-220 HX 521 inlet drain Closed ] l 106. S-221 HX 521 outlet vent Closed ] 107. S-222 HX 521 outlet drain Closed ) , i 108. S-223 Reactor hx inletisolation Open ] 109. S 224 Flow transmitter equalizer Closed ] , 110. S-225 P-4 check valve isolation Open ] 111. S-226 Secondary flow transmitter LP side isolation Secondary flow transmitter HP side isolation Open Open
]
]
l 112. S-227 113. S-228 Secondary flow transmitter equalizer Closed ] l, 114. S-229 Secondary flow transmitter HP side vent Closed ] 115. S-230 Secondary flow transmitter LP side vent Closed ] l The following valve is found in the waste tank room: E 116. S-169 Waste tank isolation Closed I Rev. 6/12/95 App'd \1 SOP /A-21d I
STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) l Revision Number 16 Revision Date: 10/19/95 Page Number Page Number SOP /II-2 SOP /A-12a SOP /II-3 SOP /A-12b l SOP /II-4 SOP /A-12c SOP /II 8 SOP /A-12d SOP /II-11 SOP /A-14a SOP /III-1 SOP /A-14b SOP /III-2 SOP /A-14c SOPNI-1 SOP /A-21a SOPNI-2 SOP /A-21b SOP /A-4a SOP /A-21c SOP /A-6a SOP /A-21d SOP /A-lb SOP /A-21e SOP /A-3a I I 1 II-5
11.1.1 Procedure for Reactor Startun (cont'd) 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. Verify that all nuclear instrumentation is responding normally. ] M. Take a complete set of nuclear data on the Startup Nuclear Data ] l Sheet. Indicate on this sheet the critical control and reg blade positions and the primary and pool temperatures. N. 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 position between any two blades always remains l less than 1 inch. O. As the reactor power level approaches 1 MW, increase the period until ] I a stable period remains that is no less than 100 seconds for all power increases greater than 1 MW. I P. Bring the reactor critical at a steady state power level of 5.0 MW for ] mode I(10 MW) operation. At this powerlevel:
- 1. Verify that the nuclear instrumentatien is in essential agreement with the actual power level which can be read out directly from the I digital calorimetric meter. Ensure that the steady state power level is maintained long enough for the digital calorimetric meter indication to stabilize (at least five (5) minutes). Note the actual power level in the l operations console log book. In the case of the calorimetric meter g being out of commission during a startup, the power level should be B determined by manual calculation.
- 2. Note the time of arrival and departure from this power level on the l Nuclear Startup Data Sheet.
l Q. Continue the reactor powerincrease by withdrawing only one control blade at a time, maintaining the reactor period at no less than 100
]
seconds. I Rev.10/19/95 App'd h SOP /II-2
H.L1 Procedure for Reactor Startun (cont'd) ] R. As the scheduled power levelis reached, adjust the control blades until ] 1 the reactor is critical at the desired steady state power in either the l manual or automatic control mode. S. Switch IRM recorder from fast to slow speed and secure the SRM ] recorder and scaler. T. Announce to experimenters the reactor powerlevel, and note arrivalin ] the log book. l U. After the temperatures stabilize, take a complete set of nuclear and ] process data. 11.1.2 Procedure for Hot Startun I 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, i 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. B. Obtain an estimate of the critical banked control blade position from the I1 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, taking a set of startup g nuclear data at five inch increments. Ensure the stable period is no less a than 30 seconds. F. Continue the startup, ensuring that the maximum difference in position ] between any two (2) blades always remains less than one (1) inch.
~
G. Stabilize reactor power at a powerlevel of 5 MW in Mode I. At this ] powerlevel: I App'd \1wm SOP /II.3 Rev.10/19/95
ILI.2 Pmcedure for Hot Startun (cont'd) ] G. 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 and the time of arrivalin 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.
H. Continue the reactor startup by withdrawing only one control blade at ] a time, maintaining the reactor period at no less than 100 seconds. L As the scheduled power level is reached, stabilize power in either ] manual or automatic control and complete the following:
- 1. Switch the IRM recorder to slow speed and secure the SRM recorder and scaler.
- 2. Note the time of arrival in the console log book and in the Startup Nuclear Data Sheet.
- 3. Announce to experimenters the reactor power level.
- 4. Take a complete set ofnuclear and process data as soon as the temperatures stabilize enough to get a representative AT on the primary and pool.
II.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.
l
- 3. The power trace pointer (black) on the WRM recorder must be
! reading greater than the auto control prohibits set point (red). l 4. The reg blade position must be greater than 60% withdrawn, such that 60% annunciator alarm is energized. B. Procedure To place the reactor into the automatic control mode: Rev.10/19/95 App'd U$lh SOP /II-4
11.1.6 hactor Shutdown Procedure f A. The procedure for a routine reactor shutdown requires only that the g manual rod run in circuit be activated. However, prior to shutting down WI the reactor:
- 1. Turn on the source range recorder and time and date the chart.
- 2. Place the IRM recorder in fast speed and time and date the chart. ]
g- l S. Take a set of nuclear and process data. ] B. Depress the manual rod run-in button on the control console. Enter the I time of shutdown in thelog book. C. Follow the reactor power decrease by changing the range selector switch so as to keep channel WRM-4 on scale. g D. Complete the Reactor Shutdown Checksheet if the control room is to be left unattended for an extended period. E. Ensure that the primary and pool systems are shutdown as per SOP IV.2 and V.2, respectively,if the control room is left unattended for an g! l extended period of time. E, II.1.7 bductions in Power ! The procedure for reductions in power to perform short evolutions (< 45 E minutes) such as Room 114 entry, shall be as follows: 3 A. Turn on source range recorder and time and date chart. gj B. Place IRM recorder to fast speed and time and date the chart. ] I' C. Take a set of nuclear and process data. ] D. Depress the manual rod run-in button on the control console. ] E. Drive control rods in 3" or to a height of 21" withdrawn, whichever corresponds to a lower md height.
] l F. After evolution is completed, recover power following procedure for hot ]
startup (11.1.2). G. If the evolution for which the reduction in power is made exceeds or ] appears that it will extend past 45 minutes, shutdown the reactor following procedure II.1.6. Rev.10/19/95 App'd M SOP /II-8 I
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. Check both the physical latching mechanism and the proper indication for the unlatched condition of the tool. C. Place the bridge ARMS to upscale position. I D. Ensure the pool is at the normal operating level. l E. Remove the pressure vessel head. F. Turn on the Source Range Monitor Scaler and Chart Recorder. ] G. Attach a fuel element to the handling tool. I H. The operator handling the fuel element tool shall verify that the element is fully latched and verbally report this to the supervising Senior I Reactor Operator. NOTE: A positive latch is achieved only after noting a discernable drop in the fuel tool upon air cylinder actuation and when the red i plunger on the air-handling tool is fully retracted and flush with the end of the cylinder. Arg protrusion of the plunger means l the fuel element is not properly latched.
- 1. Remove and visually identify the fuel element and place itin the position I specified on the loading sheet.
A Reactor Operator or Senior Reactor Operator shall initial the loading l J. sequence sheet after each step. K. Verify the elements in the reactor are seated, using the board and reference mark. Is. Perform a post-refueling map check, verifying that the appropriate positions in the "X", "Y" and "Z" baskets contain fuel elements as l indicated on the post fuel handling sequence drawing. M. A Senior Reactor Operator will inspect the core prior to replacing the I pressure vessel head. I Rev.10/19/95 App'd M SOP /II-11
SECTION III f REACTOR CONTROL AND INSTRUMENTATION SYSTEM l l III.1 Prenaration of Reactor Instrumentation for Ooeration III.1.1 General I Power to the process instrument panel is provided by the UPS system. ~i 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 performed by a licensed Reactor Operator or l l an Electronics Technician. After any maintenance is performed on a Nuclear Instrumentation 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 l performed with either a gamma or neutron source. The SRM shall have ] g an operability check done using the Chi square statistical test. The ] 3 successful response check shall be noted in the control room log book. III.1.2 Procedure for Securing Electrical Power to Console and Instrument Panel NOTE: " STANDBY" position does not remove detectors from circuit. g Electrical transients in this mode may result in damage to detectors or high voltage power supplies. A. B. Place all N.I. drawers to zero/zero 1. Remove VR units from N.I. drawers. Il g E ll C. Turn power switch to "OFF" on 2PS1 and 2PS2. D. E. F. Turn power switches for area radiation monitor to "OFF". Disconnect ARM's bell. Prop open back-up doors. ll , G. Open breakers for sliding doors (504/505). g' H. On Emergency LightingPanel: 3
- 1. Open E15
- 2. Open E18 g' I. On UPS-2 Panel:
- 1. Open breaker #2
- 2. Open breaker #3 l
- 3. Open breaker #5
- 4. Open breaker #7 g,
- 5. Open breaker #9 5
- 6. Open breaker #10 E
App'd (IAortv\ SOP /III-1 Rev.10/19/95 I
( IILI.2 Pmc+ dure for Securina Electrical Power to Console and ] Instrument Panel (cont'd) ] J. On UPS-3 Panel:
- 1. Open breaker #1
- 2. Open breaker #2
- 3. Open breaker #3
- 4. Open breaker #4
- 5. Open breaker #5 III.2 Pre-Startuo Check of Source Range Nuclear Instrument Channel 1 A. Verify power ON" to recorder and alarms cleared.
B. Check the internal drawer test functions (any order) by depressing ] and holding the underlined button until all functions are ] verified: )
- 1. 12.2 Hz. Check the following indications: ]
- a. Drawer Inoperative indicator light. ]
- b. NuclearInstrument Anomaly. ]
- c. Channel 1 Lo Count Rate annunciation occurs. ]
- d. Local and wmote indication reads 8 to 15 cps. ]
[ e. Recorderindicates 8 to 15 cps. ]
- 2. 100 Khz. Check the following indications: ]
- a. Drawer Inoperative indicator light. ]
- b. Nuclear Instrument Anomaly. ]
- c. Local and remote level indication reads 8 x 104 to ]
1.5 x 105 cps. ]
- d. Recorder indicates 8 x 104 to 1.5 x 105 cps. ]
- e. Channel 1 Lo Count Rate annunciation is clear. ]
- f. Local and remote period indication reads infinity. ]
- 3. . CAL Check the followingindications: ]
- a. Drawer Inoperative indicator light. ]
- b. NuclearInstrument Anomaly. ]
- c. Local and remote period indication reads +3 second ]
period. ]
- 4. Trin reset. ]
- a. Verify Channel 1 Lo Count Rate annunciation is clear. ]
{ b. Verify Nuclear Instrument Anomaly annunciation is ] clear. ] [ Energize SCALER for startup, if necessary. C. Rev.10/19/95 App'd h SOP /III-2
f SECTION VI gi SECONDARY COOLING SYSTEM VI.1 Startun of the Secondarv System l A. Before attempting to start up the secondary system,it should be g determined that: E l
- 1. Water level in the cooling tower basin is between 5 and 14 inches.
- 2. All personnel are clear of cooling tower equipment and fans. gI
- 3. Oil level in the gear reducers to the fans is normal. ;
- 4. The automatic sump makeup water isolation valve electrical power switch is in auto. lil B. The following manually operated valves in the cooling tower should be in positions indicated:
g, S-17 Onen S-10 S-107 Closed S-129 l S-18 S-11 S-108 S-101 g S-19 S-12 S-109 S-126 5 S-20 S-118 S-110 S-121 S-21 S-119 S-111 S-125 g S-22 S-120 S-112 S-127 S-117 S-163 S-113 S-155 S-5 S-6 S-114 S-115 S-128 S-47A S-102 S-47B l S-7 S-116 S 123 ] g S-8 S-105 m S-9 S-106 NOTE: S-47A provides cooling to chiller units. C. The following valves in equipment room 114 passageway and waste tank room should be in the positions indicated: Onen Closed S 199 S 151 ] S-169 S-170
]
]
l I Rev.10/19/95 App'd M SOPNI-1 I
VI.1 Startun of the Secondary System - Cont'd D. The following valves in equipment room 114 should be in the position indicated: Ooen Closed Set as Indicated on Valve ] S-23 S 183 S-27 S 223 ] S-24 S-182 S-117 S 232 ] S-30 S-210 S 137 S-31 S-211 S-141 S 34 S-212 S-142 S-35 S-213 S-217 S-39 S-214 S 218 S-41 S-215 S-219 S-161 S-216 S-220 ] S 162 S-221 ] S-222 E. For operation of the chiller units with feed water from P-1, P-2, P-3 or P-4, the following valves in room 278 should be in the positions indicated as follows: Onen Closed S 55 S-54 S 53 ] S-58 S-146 S 57 ] S-149 f F. Verify that the Bailey Meter recorder Model E101 in the reactor control room is on to monitor secondary flow and temperature during operation. Time and date chart. Secondary outlet temperature for the exchangers f can be monitored in the control room with the digital readout and selector switch. G. Verify that the circuit breakers for P-1, P-2, P-3 and P-4 on MCC-2 in the cooling tower are closed and that the control switch on the panels is in auto mode. f Rev.10/19/95 App'd tws SOP /VI-2
f REACTOR STARTUP CHECKSHEET FUIl POWER OPERATION (cont'd) Page 2 REACTOR CONTROL SYSTEM CHECF1IST
- 1. All chart drives on; charts timed and dated. IRM recorder to slow. g
- 2. Fan failure warning system cleared. 3
- 3. Annunciator board energized; horn off.
- 4. Television receiver on.
- 5. Primary / pool drain collection system in service per SOP. (Manually pump DCT)
- 6. Secondary system on-liner per SOP (as needed).
- 7. Primary system on.line per SOP:
l l a. Primary cleanup system on line.
- 8. Pool system on line per SOP:
- a. Pool cleanup system on line,
- b. Pool reflector AP trips set as required.
- 9. Nuclear Instrumentation check completed per SOP:
l l a. The following trip values were obtained during the check: IRM 2 run-in seconds (11i1) Scram seconds (9 i 1) IRM-3 run-in seconds (1111) Scram seconds (9 1) WRM-4 run in % (11411) Scram % (11911) PRM 5 run in % (11411) Scram % (119 1) PRM 6 run in % (11411) Scram % (11911) g
- 10. Channel 4,5 and 6 pots returned to last heat balance position. 3
- 11. SRM 1 detector operability checked (Chi square test). ]
- 12. Check of process radiation monitors (front panel checks):
- a. Fission product monitor,
- b. Secondary coclant monitor.
NOTE: Items 13 through 34 are to be completed in sequence immediately prior to pulling rods for a reactor startup.
- 13. Annunciator tested.
I
- 14. Annunciator alarm cleared or noted.
- 15. Power selector switch IS8 in position required.
16.a. Bypass switches 2S40 and 2S41 in position required.
- b. Allkeys removed from bypass switches.
- 17. Master switch IS1 in "On" position.
- 18. Magnet current switch on, check " reactor On" lights.
- 19. Reactor isolation, facility evacuation and ARMS checks (after maintenance day). These items g are to be checked with scrams and rod run ins reset, and when appropriate items are actuated, g verify that the TAA's do trip. (Announce test to facility and notify police of security alarm.)
l l a. Reactor isolation trip from security cabinet. g (leaves valves and doors closed) (after maint. day) W
- b. ReactorIsolation switch.
- c. Facility evacuation switch (check outer containment horns) (after maint. day).
SOP /A-lb Rev.10/19/95 App'd hNnn E
Date Time REACTOR SHORT FORM PRECRITICAL CHECKSHEET
- 1. Nuclear Instrument checks completed per SOP Section III
- a. The following trip values were obtained during the checks:
IRM-2 run-in see (11 i 1) Scram see (9 i 1) IRM-3 run-in see (11 1) Scram see (9 1) I WRM-4 run in % (11411) Scram % (119 1) PRM-5 run in % (114 1) Scram % (119 il) f PRM-6 run in % (114 1) Scram % (119 1)
- 2. Channel 4,5 and 6 pots returned to last heat balance position.
- 3. SRM-1 detector operability checked (Chi-square test). ]
- 4. IRM recorder in fast speed.
- 5. Cycle WRM range switch.
- 6. Annunciator board energized; horn on.
- 7. Reset " white rat" scram monitor.
- 8. Estimated critical position (corrected): inches.
- 9. Reset scram and rod run-in circuits.
- 10. Reflector and flux trap experiment loadings secured and ready for startup.
- 11. Reactor ready for startup.
Shift Supervisor / Lead Senior Operator { Rev.10/19/95 App'd M SOP /A-3a
f Date: REACTOR SHUTDOWN CHECKSHEET
- 1. Time ofreactor shutdown
- 2. All blades bottomed and drive mechanism full in.
- 3. Magnet current switch off.
I
- 4. Reactor primary system shutdown per SOP IV. ] l
- 5. Pool system shutdown per SOP V. ]
- 6. Secondary system shutdown per SOP VI,in required lineup. ]
- 7. Cooling tower fans off. ] g
- 8. Digital readout switch off. ]
- 9. Annunciatorboard on off . ]
- 10. Reverse osmosis unit to standby. ]
- 11. Sample inventory satisfactory, including counts recorded, if necessary. ]
and data sheets updated. ]
- 12. Allbypass switches off and Ireys in key box. ]
- 13. Master switch off on . ]
- 14. DCT system secured. ] l
]
- 15. Room 114 check:
- a. Cooling dow to P501 A/B secured.
I
- b. Valves Si and S2 hydraulic motor off.
l
- c. Room 114 pump controllers locked out.
- 16. Completed and logged Reactor Shutdown Checksheet. ]
Shift Supervisor / Lead Senior Operator I I Rev.10/19/95 App'd M SOP /A-4a I
STARTUP NUCLEAR DATA CORE: Date: { APP. BANK RR TIME POS. POS. SRM 1 IRM-2 IRM 3 WRM-4 PROCEEDINGS I l CriticalRodPosidon A B C D RR ECP Power at Cridcal Position Pri. Temp. / Pool Temp. / Operator / Remarks: I CORE: Date: APP. BANK RR 1 TIME POS. POS. SRM1 IRM-2 IRM-3 WRM-4 PROCEEDINGS I I CrincalRodPosition A B C D RR ECP Power at Critical Position Pri. Temp. / Pool Temp. / Operator / Remarks-CORE: Date: APP. BANK RR TIME POS. POS. SRM-1 IRM 2 IRM 3 WRM-4 PROCEEDINGS J _ CriticalRodPosition A B C D RR ECP Power at Crincal Posidon Pri. Temp. / Pool Temp. / Operator / Remarks Rev.10/19/95 App'd M SOP /A-6a
I Date PRIMARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET This checksheet shall be completed when required by the SOP. The operator performing the check will verify the position of each valve and indicate the verification by initialing the 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 normal position on this sheet, and write in the actual position of the valve. The reason for the valve being positioned abnormally will be noted in the COMMENTS section. Valve manifold labels designated 568 will have valve ] designation 568A LP,568A HP and 568A EQ, etc. QDF= Quick Disconnect Fitting. 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. Valve # Valve Description Position
- 1. 551 Vent tank regulator valves Zero pressure g
- 2. 518AM Anti-siphon tank air supply Closed ] W
- 3. 518AV Anti. siphon tank vent Closed ]
- 4. 518AY Anti. siphon tank drain Closed ]
- 5. 598B Air supply to 543 A & B Open
- 6. 598A Air supply to 546 Open
- 7. 518S Loop drain (in tunnel) Closed )
- 8. 518T Loop drain (in tunnel) Closed ]
E
- 9. 5180 Tu vent and FPM return isolation Open ] E
- 10. 595L HP isolation valve for DPS-929 Open ]
- 11. 568H DPS-929 Test Valve Manifold HP/LP closed; ]
equalizer closed ]
- 12. 595M Isolation valve for PS-944A Open
- 13. 595N Isolation valve for DPS 929 & PS-944B Open
- 14. 595B Isolation from FPM Open ]
- 15. 518X Tu vent valve Closed ]
- 16. 510A P 501A suction Open
- 17. 510D P 501B suction Open g
- 18. 518A P-501A gauge isolation Open ] E
- 19. 518AH P 501B gauge isolation Open ]
- 20. 518B P-501A gauge isolation Open ]
- 21. 518AB P 501B gauge isolation Open ]
- 22. 538A P 501A bypass Closed ]
- 23. 538E P-501B bypass Closed ]
- 24. 5100 P-501A discharge Open
- 25. 510E P-501B discharge Open Rev.10/19/95 App'd M SOP /A-12a I
l l I PRIMARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd) l Valve # Valve Description Position
- 26. 518P P501 combined discharge vent Closed ] j
- 27. 510B HXinlet to 503A Open
- 28. 510F HXinlet to 503B Open
- 29. 515A HX drain for 503A Closed ]
30, 568I DPS 928A test valve manifold HP/LP closed; ) equalizer closed ]
- 31. 595D HX 503A DPS inlet Open
- 32. 595C HX 503A DPS outlet Open
- 33. 515Y HX drain for 503B Closed ]
- 34. 595F HX 503B DPSinlet Open
- 35. 595E HX 503B DPS outlet Open 1
- 36. 568J DPS-928B test valve manifold HP/LP closed; ]
equalizer closed ]
- 37. 540A HX outlet for 503A Throttled Cocked)
(No. turns open 1
- 38. 540B HX outlet for 503B Throttled Oocked) i (No. turns open ) )
- 39. 5991 PT 943 isolation Open ] l
> i
- 40. 518Y HX 503 combined discharge vent Closed ]
- 41. 595A Inlet to FPM Open ]
- 42. 518M HUT vent Closed
}
- 43. 518L HUT vent Closed ]
44, 515K HUT drain Closed ]
- 45. 568A FE 913A valve manifold HP/LP open; ]
equalizer closed
- 46. 568B FE 913B valve manifold HP/LP open; ]
equalizer closed
- 47. 518AE HX 503A T strainer drain Closed ]
- 48. 518AF HX 503B T strainer drain Closed ]
- 49. 518AA HX 503A vens Closed ]
- 50. 518AI HX 503B vent Closed ]
- 51. 528 P 533 recire. to T 300 Closed 4 52. 515J P-513A suction Open
- 53. 518E P 513A suction gauge isolation Open ]
, 54. 518F P 513A discharge gauge isolation Open ]
- 55. 515L P-513A discharge Open
- 56. 515W P-513A bypass Closed Rev.10/19/95 App'd b SOP /A 12b
PRIMARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd) Valve # Valve Description Position _
- 57. 568E FE 923A valve manifold HP/LP open; ]
equalizer closed 595H Primary sample valve Open 58.
- 59. 515U V 527A isolation Open ] g Pressurizer drain to drain collection system Open 1/2 turn Oocked) E
- 60. 515AA
- 61. 515B V-527C isolation Open ]
- 62. 515S V-527D isolation Open ]
- 63. 544 V-545 isolation Open ]
- 64. 518AT PZRlocallevelindicator cutout Closed ]
- 65. 518AQ PZRlocallevelindiciator cutout Closed ]
- 66. 515AB Pressurizer drain to waste system Closed
- 67. 515C P-533 suction Open ]
- 68. 599A PS 938 isolation Open ]
- 69. 599B PS-939 isolation Open ]
- 70. 599C PS 940 isolation Open ]
- 71. 599D PS-941 isolation Open ] g Open ] E
- 72. 599E PS-945 isolation
- 73. 599F PS 946 isolation Open ]
- 74. 518AR PZRlevelindication isolation Open ]
518AU PZRlevelindication cutout Open ] 75.
- 76. 518AP PZRlevelindication cutout Open ]
- 77. 518AN PZRlevelindication isolation Open ]
- 78. 5150 PZR drain Closed ]
- 79. 518AW PZRlocallevelindication vent Closed ]
- 80. 518AO PZRlocallevelindication drain Closed ]
- 81. 599M FE-913A QDFisolation Closed ]
- 82. 5990 FE-913A QDFisolation Closed ]
- 83. 599V FE-913B QDF isolation Closed ]
- 84. 599W FE 913B QDFisolation Closed ]
I I I SOP /A 12e Rev.10/19/95 App'd M I
PRIMARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd) COMMENTS: Operator l Rev.10/19/95 App'd h SOP /A-12d
Date 1 POOL SYSTEM VALVE LINEUP CHECKSHEET This checksheet shall be completed when required by the SOP. The operator performing the check will verify the position of each valve and indicate the verification by initialling the 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 normal position on this sheet, and write in the actual position of the i volve. The reason for the valve being positioned abnormally will be noted in the COMMENTS section. g ) QDF= Quick Disconnect Fitting. ] gl 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. Valve # Valve Description Position ,
- 1. 598A Air supply to 546 Open
- 2. 555P Air supply valve to V-547 Closed ;
- 3. 548A P-532 pool suction Open !
- 4. 548B P 532 pool (at refuel) suction Closed
- 5. 518U Vent valve (pool Tn) Closed
- 6. 515X P-513B bypass Closed
- 7. 515N P-513B discharge Open ,
- 8. 518H P-513B suction gauge isolation Open ]
- 9. 518G P 513B discharge gauge isolation Open ]
- 10. 522C Pool drain / fill Closed
- 11. 522B Pool fill Closed
- 12. 515Q Cleanup return to loop Closed
- 13. 515M Cleanup suction from pool Closed
- 14. 515T Cleanup suction from loop Open Open
- 15. 523F P 508A discharge g
- 16. 522E P 508B discharge Open a
- 17. 538C P-508B bypass Closed 518I P 508A gauge isolation Open )
18.
- 19. 518J P-508A gauge isolation Open ]
- 20. 518AD P-508B gauge isolation Open ]
- 21. 518AC P-508B gauge isolation Open ] .
- 22. 599J PS-947 isolation Open ]
539A P-508A suction Open 23. 539C P-508B suction Open 24. 518V Vent valve Closed 25. SOP /A-14a Rev.10/19/95 App'd M I
POOL SYSTEM VALVE LINEUP CHECKSHEET (Cont'd) Valve # Valve Description Position
- 26. 515P Cleanup return to pool Open
- 27. 514B HUT outlet Open 28, 522A HX-521 inlet Open ]
- 29. 522D HX 521 inlet Open
- 30. 600A HX-521 outlet Throttled
- 31. 518N HUT vent cutout Open
- 32. 518K HUT vent Closed
- 33. 515R HUT drain Closed Oocked)
- 34. 515Z HX-521 drain Closed
- 35. 518AJ HX-521 vent Closed
- 36. 518AG Pool system "T strainer drain Closed
- 37. 518Q Drain valve (tunnel) Closed
- 38. 518R Drain valve (tunnel) , Closed
- 39. 514A V-509 cutout Open
- 40. 568G PT-917 cutout valve Open
- 41. 599Z PT-917 vent Closed
- 42. 599Y P-532 suction vent Closed ]
- 43. 515I P-532 suction Open
- 44. 518D P 532 gauge cutout Open
- 45. 5180 P-532 gauge cutout Open
- 46. 515E Skimmer filter inlet Open
- 47. 515D Skimmer filter outlet Open
- 48. 567A Drain collection pump suction Open
- 49. 567B Drain collection pump suction drain Closed
- 50. 566 Drain collection system discharge Open
- 51. 567C Drain collection system discharge to 513B suction Open
- 52. 593 Skimmer suction T-300fr-301 Open
- 53. 5680 FE-921 valve manifold (FT 912D) HP/LP open; equalizer closed ]
- 54. 568D FE-921 valve manifold (FT 912F) HP/LPopen;equalizerclosed ]
- 55. 599S FT-912F QDF, isolation LP Closed ]
- 56. 599T FT-912F QDF, isolation HP Closed ]
- 57. 599N FT-912D QDF, isolation LP Closed ]
- 58. 599Q FT-912D QDF, isolation HP Closed ]
Rev.10/19/95 App'd M SOP /A 14b
POOL SYSTEM VALVE LINEUP CHECKSHEET (Cont'd) Valve Description Position Valve # HP/LP open; equalizer closed ]
- 59. 568F FE 923B valve manifold (PT-912C)
Pool cleanup effluent to sample station Open
- 60. 595J Pool influent to sample station Open
- 61. 595G 595K Pool cleanup vent Closed 62.
515AC Pool cleanup to blank flange Closed 63. Pressure indication 927 pool outlet (HX 521) Open ]
- 64. 518AL Pressure indication 927 pool inlet (HX 521) Open ]
- 65. 518AK FT-912F LP side high point vent Closed )
- 66. 599U FT 912F HP side high point vent Closed ]
- 67. 599X FT 912D LP side high point vent Closed ]
- 68. 599P FT 912D HP side high point vent Closed ]
- 69. 599R Closed ]
- 70. 599AA Vent valve FT 912C QDF, isolation LP Closed ) l
- 71. 599AE t FT-912C QDF, isolation HP Closed ) i
- 72. 599AD l
COMMENTS: I I 1 I I OPERATOR SOP /A-14e Rev.10/19/95 App'd (M I
Dite SECONDARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET This checksheet shall be completed when required by the SOP. The operator performing the check will
. v:rify the position of each valve and indicate the verification by initialing the 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 normal position on this sheet, and write in I the actual position of the valve. The reason for the valve being positioned abnormally 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 I p:sition in the space provided on the checksheet. The following valves will be found in the cooling tower or cooling tower tunnel. Valve # Valve Description Position
- 1. S-5 P-1 discharge Open
- 2. S-6 P-2 discharge Open
- 3. S-7 P-3 discharge Open
- 4. S-8 P-1 suction Open
- 5. S-9 P-2 suction Open 1 6. S-10 P-3 suction Open
- 7. S-11 P-4 suction Open
- 8. S-12 P-4 discharge Open
- 9. S-105 P-4 strainer AP gauge Open ]
- 10. S-106 P-4 strainer AP gauge Open ]
5 11. S-107 P-1 strainer AP gauge Open ]
- 12. S-108 P 1 strainer AP gauge Open ]
- 13. S-109 P 2 strainer AP gauge Open ]
- 14. S-110 P 2 strainer AP gauge Open ]
- 15. S-111 P-3 strainer AP gauge Open ]
- 16. S-112 P 3 strainer AP gauge Open ]
- 17. S 114 P-1 suction pressure gauge Open I 18. S-115 P-2 suction pressure gauge Open
- 19. S-116 P 3 suction pressure gauge Open
- 20. S-117 P-4 discharge pressure gauge Open
- 21. S-118 _ P-1 discharge pressure gauge Open
- 22. S-119 P-2 discharge pressure gauge Open
- 23. S-120 P-3 discharge pressure gauge Open
- 24. S-128 Chemical addition connection (ground level) Open
- 25. S-155 Condensate return to secondary Open ]
[ 26. S-157 P-2 discharge gauge isolation Open ] Rev.10/19/95 App'd I tkW\ SOP /A 21a -,uma
1 SECONDARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd) Valve # Valve Description Position S-163 Drain of relief valve on pump discharge Open J 27.
- 28. S-197 Conductivity and pH sampling (ground level) Open Open i
- 29. S-198 Conductivity and pH sampling (ground level)
- 30. S-17 Cooling tower distribution valve Open
\
- 31. S-18 Cooling tower distribution valve Open ;
- 32. S-19 Cooling tower distribution valve Open
- 33. S-20 Cooling tower distribution valve Open
- 34. S-21 Cooling tower distribution valve Open
- 35. S-22 Cooling tower distribution valve Open
- 36. S-47B P-4 return to cooling tower distribution line Open
- 37. S 113 Drain isolation (2") on secondary supply Closed j
- 38. S-121 P-4 line vent Closed
- 39. S-123 P 1,2 & 3 line vent & chemical addition isolation Open ]
- 40. S-125 To floor drain Closed
- 41. S-101 Return line to floor drain Closed g
- 42. S-126 Returnline to floor drain Closed 3 Condensers to floor drain Closed
- 43. S-102 l
- 44. S-129 P-4 supply drainline (groundlevel) Closed ] l i 45. S-127 P-4 discharge to cooling tower Closed ] I
- 46. S-47A P-4 to cell #1 south (winter & maintenance) Throttled ]
- 47. S-196 Drain valve for P-4 cell #1 south Closed
- 48. S-208 P-1,2 & 3 header vent Closed ] ,
- 49. S-164 Chemical pump No. I header isolation Open ]
- 50. S-165 Chemical pump No. 2 headerisolation Open ] ,
- 51. S-176 Test tee air isolation to check valve S-46 Closed ]
- 52. S-192 Cooling tower basin drain isolation Closed ]
- 53. S-204 P-1 casing vent Closed ] g
- 54. S-205 P 2 casing vent Clesed ] 3
- 55. S-206 P-3 casing vent Closed ]
- 56. S-207 P 4 casing vent Closed ]
l The following valves will be found in the 114 passageway: Air supply to primary heat exchangers Closed ] I
- 57. S-171 Air supply to pool heat exchanger (line capped) Closed ]
- 58. S-172 Open
- 59. S-202 Corrosion rack isolation -in Open
- 60. S-203 Corrosion rack isolation - out Rev.10/19/95 App'd M SOP /A 21b
SECONDARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd) Valve # Valve Description Position The following valves will be found in the 114 passageway:
- 61. 170 Blowdown isolation Throttled
- 62. S-103 Supply to old Calgon unit Closed )
- 63. S-151 Return from old Calgon unit Closed ]
- 64. S-199 Blowdown isolation (ball vaIve) Open ]
- 65. S-104 Return from old Calgon unit (petcock valve) Closed )
- 66. DCWR7 DCW from Alpha Lab Closed
- 67. S-195 Return from waste heat system Closed )
- 68. AX-1 Secondary supply isolation Open ]
- 69. AX-5 Secondary return isolation Open ]
The following valves will be found in Room 114:
- 70. S-161 AP transmitter HP isolation Open
- 71. S-183 Rosemount HP isolation Open
- 72. S-130 Bailey HP isolation Open
- 73. S 182 Rosemount LP isolation Open
- 74. S-131 Bailey LP isolation Open
- 75. S-162 AP transmitter LP isolation Open
- 76. S-23 HX 503A supply isolation Open
- 77. S-24 HX 503B supply isolation Open
- 78. S-30 S-1 supply side isolation Open
- 79. S-31 S-1 return side isolation Open
- 80. S-34 S-2 supply side isolation Open
- 81. S-35 S-2 return side isolation Open
- 82. S-39 HX 503A return side isolation Open
- 83. S-41 HX 503B return side isolation Open
- 84. S-132 Transmitter flush valve Closed )
- 85. S-178 HX 503B sparge (not connected) Closed ]
- 86. S-185 Rosemount HP test connection Closed
- 87. S-184 Equalizing valve Closed
- 88. S-186 Rosemount LP test connection Closed
- 89. S-180 Bailey LP vent Closed ]
- 90. S-133 Transmitter flush valve Closed
- 91. S-27 S-1 bypass valve Closed
- 92. S-137 HX 503B drain Closed Rev.10/19/95 App'd SOP /A 21e
- ~. - - __ _. - - SECO. N DARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (c:nt'd) Valve Description Position , Valve # The following valves will be found in Room 114: HX 503B vent Closed
- 93. S-142 S-136 S-1 drain Closed 94.
S 1 tee bypass drain Closed )
- 95. S 177 AP gauge isolation (no gauge installed) Closed )
- 96. S-135 HX 503A vent Closed i
- 97. S 141 1 HX 503A drain Closed
- 98. S-117
- 99. S-194 Supply from HX 503B to waste heat system Closed gi S-191 HX 503B drain Closed ] 5 100.
HX 521 inlet Open 101. S-210 S-211 HX 521 outlet Open ] 102. HX 521 bypass Open 103. S-212 HX 521 inlet pressure indication Open 104. S-213 HX 521 outlet pressure indication Open 105. S-214 106. S-215 Flow transmitter outlet Open ] 107. S-216 Flow transmitter inlet Open ] Water chem. inlet side Closed
, 108. S-217 Water chem. outlet side Closed 109. S 218 HX 521 inlet vent Closed 110. S-219 111. S-220 HX 521 inlet drain Closed g 112. S-221 HX 521 outlet vent Closed W HX 521 outlet drain Closed 113. S-222 Reactor HXinletisolation Open; throttled 1 114. S-223 Flow transmitter equalizer Closed ]
115. S 228 P-4 check valve isolation Open ] 116. S-231 Secondary flow transmitter LP side isolation Open 117. S-226 Secondary flow transmitter HP side isolation Open 118. S-227 HX 521inletisolation Open; throttled ] 119. S 232 HX 521 strainerisolation Open ] 120. S-233* Strainerinlet AP gauge isolation Open ) 121. S-234* Strainer outlet AP gauge isolation Open J 122. S-235* HX 521 strainer drain Closed ] g 123. S 236* Closed ] 5 124. S-237* HX 521 strainer vent
] *Not installed.
SOP /A-21d Rev.10/19/95 App'd I
SECONDARY SYSTEM NORMAL OPERATION VALVE IJNEUP CHECKSHEET (c:nt'd) Valve # Valve Description Position The following valve is found in the waste tank room: 125. S-169 Waste tank isolation Closed For operation of the air conditioners with feed water from P-1, P 2, P-3, or P-4. The following valves will be found in Room 278: 126. S-53 Sepply to NC unit #2 Closed; open if ] running ] 127. S-57 Discharge NC unit #2 Closed; open if ] running ] 128. S 55 Supply to A/C unit #1(LiBr) Closed; open if ] running ] 129. S-58 Discharge NC unit #1 (LiBr) Closed; open if ] I 130. S-200 Flow isolation running Open
]
131. S-201 Flow isolation Open 132. S-146 Vent (by DI 300) Closed 133. S-54 Vent (by steam supply to LiBr unit) Closed i 134. S-149 Vent (by DI-300) Closed I COMMENTS: I 9 I I _ 1 1 Operator ~ Rev.10/19/95 App'd M SOP /A 21e
[ MURR SITE EMERGENCY PROCEDURES AND [ FACILITY EMERGENCY PROCEDURES Revision Number 19 [ Revision Date: 6/19/95 [ I Section Page Number Number [ SEP-1 1 of 5 SEP-1 4 of 5 [ SEP-2 1 of 5 SEP-8 1 of 3 [ Emergency Call List ( -[ [ [ [ [ [ [ [ } II-6
Paga 1 of 5 SEP-1 ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE I. FACILITY EMERGENCIES:
- 1. The Facility Emergency Organization (FEO) shall be activated as per the Facility Emergency Procedures (FEP) for each FACILITY EMERGENCY CLASSIFICATION:
a) Facility Evacuation b) Reactor Isolation c) Fire d) Medical e) Security [ SAFEGUARDS INFORMATION AS PER 10CFR50.34(c)]
- 2. In addition to the procedures for each FACILITY EMERGENCY I CLASSIFICATION, an assessment of off site consequences shall be determined.
I II. EMERGENCIES WITH POSSIBLE OFF-SITE CdNSEQUENCES:
- 1. The duty shift supervisor orindividual authorized to assume the Emergency 1 Director position shall determine the need to activate the FEO for I emergencies with possible off-site consequences. This need will be based upon the action levels specified for the minimum classification, UNUSUAL EVENT. These action levels are:
- a. Report or observation of severe natural phenomenon.
I b. Threats to or breaches of security. Concentration of airborne radioactivity at the stack monitor exceeding l c. 20,000 AEC* when averaged over 24 hours.
- d. The projected concentration of airborne radiological effluent at the I distance corresponding to the nearest site boundary exceeding 15 mrem whole body accumulation in 24 hours.
- c. Prolonged fire or explosion within the facility (e.g., a fire that may ]
l affect the reactor) that does not include a laboratory fire that ] involves nuclear materials. ] l f. Other plant conditions exist that warrant ensuring emergency personnel are available to respond to an emergency to prevent exposures of 1 rem I whole body or;5 rem thyroid to the public or staff. l
'AEC Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev. 6/19/95 App'd e ]
Page 4 of 5 SEP-1 (Cont'd) TABLE I E ACTION LEVELS FOR EMERGENCY CLASSES E Unusual Event
- 1. Report or observation of severe natural phenomenon.
- 2. Threats to or breaches of security. l
- 3. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours.
- 4. The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding 15 mrem whole body accumulated in 24 hours.
- 5. Prolonged fire or explosion within the facility (e.g., a fire that may affect the ] 3 reactor) that does not include a laboratory fire that involves nuclear - ] E materials. ]
- 6. Other plant conditions exist that warrant ensuring emergency personnel are available to respond to an emergency to prevent exposures of1 rem whole body or 5 rem thyroid to the public or staff.
=
- 1. Concentration of airborne radioactivity at the stack monitor exceeding 100,000 AEC* when averaged over 24 hours.
- 2. The projected concentration of airborne radiological efIluent at the distance corresponding to the nearest site boundary exceeding 75 mrem whole body l
accumulated in 24 hours.
- 3. Radiation levels at the distance corresponding to the nearest site boundary of 20 mrem /hr for 1 hour whole body or 100 mrem thyroid dose.
- 4. Loss of physical control of the facility.
- 5. Other plant conditions exist with a level of significance of a major failure of fuel l m
cladding, but primary and containment boundaries exist to reduce releases. I I
*AEC. Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
I Rev. 6/19/95 App'd M I
Page 1 of 5 SEP-2 UNUSUAL EVENT PROCEDURE ACTIONS LEVELS: IE there is:
- a. Report or observation of severe natural phenomenon.
l b. Threats to or breaches of security. [See REACTOR EMERGENCY PROCEDURE (REP-22).] l c. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours. [See REACTOR EMERGENCY PROCEDURE (REP-21).] NOTE: Use overlays to determine extent of activity foriodine, particulate, and gas.
- d. The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding 15 mrem whole body accumulated in 24 hohrs.
l
- e. Prolonged fire or explosion within the facility (e.g., a fire that may ]
affect the reactor) that does not inclu& a laboratory fire that ] involves nuclear materials. ]
- f. Other plant conditions exist that warrant ensuring emergency personnel are available to respond to an emergency to prevent exposures of1 rem whole body or 5 rem thyroid to the public or staff.
THEN at least an UNUSUAL EVENT condition exists. l IMMEDIATE ACTIONS:
- 1. Activate the Facility Emergency Organization (FEO), as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE. if not l already activated.
- 2. Operations shall provide information to the Emergency Director / Emergency
'l Coordinator. L
- 3. If airborne activity is involved, continue with step 4. If not, go to step 7.
- 4. Time and date stack monitor chart for reference.
*AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev. 6/16/95 App'd M __m_ . _ _ _ _
Page 1 of 3 SEP-8 EMERGENCY EQUIPMENT MAINTENANCE PROCEDURE Purnose: This procedure states how the operational readiness of emergency equipment and supplies required by the Emergency Procedures is to be maintained, calibrated, l tested, and periodically inventoried. l Health Physics' Emercency Eouinment: g Health Physics' Emergency Equipment and supplies required by the Site Emergency E Procedures shall be maintained in two designated readily accessible locations. The two locations are the MURR Emergency Equipment Cabinets in the copy machine room and the Backup Emergency Equipment Cabinet at RPDB in room 10. The g' inventory checklists for each location are attached to this procedure and shall be used to verify quarterly that the contents of the cabinet meet at leasuhe required levels. All maintenance and inventory records on emergency equipment shdl be maintained kll i in the Health Physics Office. The civil defense kits stored at each location contain a G-M survey meter, an ion chamber meter (500 R/hr range), and a set of self reading pocket dosimeters. These hits are exchanged routinely by Missouri SEMA for updated kits of l instruments which have been calibrated by SEMA. The emergency Health Physics' g equipment is supplemented by the Health Physics' instruments and equipment used 3l! for daily routine evaluations and is maintained and calibrated by the Operational Health Physics' Program. g Off-Gas Monitorinc Eauinment: The off-gas stack monitor has three channels: gas, particulate, and iodine. The three channels shall be calibrated semiannually by the Health Physics / Reactor Chemistry l group using Reactor Chemistry Standard Operating Procedures: , RC/III-2 Calibration of Stack Particulate Monitor ~ RC/III-3 Calibration of Stack Iodine Monitor l RC/III-4 Calibration of Stack Gas Monitor The operability of the off-gas monitor is checked as part of the start-up checklist for normal reactor start-ups. Fire Fichtinc Eouioment: The fire hydrant in the reactor site is checked operable routinely by the Columbia Fire Department. The fire extinguishers shall be checked in accordance with the ] l schedule determined by the University of Missouri Physical Plant. ] Rev. 6/16/95 App'd M I
L- J UVU ' EMERGENCYPROCEDURES EMERGENCY CALLUST Director's Office Facilities Operations Emergency Support Organizations Phone No. Phone.No. Phone.No. J.Rhyne 442-4967 C. Edwards 443-7529 UMC Police 882-7201 J. C. McKibben 445-7843] B. McCracken 449-7731 W. Oladiran 443-5658 Reactor Operations D. Peeler 816-848-2471 Columbia Fire Deoartment 9-911 Phone.No. K. Beamer 314-682-5499 W. Meyer 442-7675 J. Evans 816-848-2156 ] T. Schoone 443-8862 R. Kitch 875-2045 UM Hosoital & Clinics R. Huttsch 442-6653 C. Kribbs 314-682-3980 Emergency Services 882-6003 C. Anderson ~~ 696-5506 S. Rinehart 314-682-2807 Ambulance 882-6128 or 9-911 B.Bezenek 445-5680 T. Seeger 474-3891 Walk-in (Emergency Center) 882-8091 G. Gunn 875-1162 J. Baskett 474-2046 N. Tritschler 474-9388 M. Richardson 446-1014 L Foyto 446-0491 UMC Health Physics (Office) 882-7221 J. Fruits 474-0774 Staff Resource Personnel Sue Langhorst (Home) 442-3534 A. Hartweg 474-7882 Phone.No. Jamieson Shotts (Home) 474-2194 R. Hudson 445-6769 S. Morris 445-4217 David Spate (Home) 657-9450 V. Jones 445-2543 V. Spate 657-9450 P. Muren 874-0219 C. Baskett 474-2046 P.Neel 442-8693 M. Glascock 443-4172 MU News Bureau 882-6211 W. Oldham 474-0987 D. Nickolaus 443-0502 See Public Information Procedure for other 882-9143 R. Wa!ker 443-0970 G. Ehrhardt 445-3570 phone numbers (SEP-7). 882-9144 M. Wallis 314-387-4859 A. Ketring 657-9614 T. Wamer 816-882-6740 B. Yelon 445-8147 M. Kilfoil 449-2524 State Emeroency Manaaement Anency (SEMA 314-751-2748 Health Physics /Rx. Chemistry S, Gunn 443-2125 Phone No. L Krueger 442-0740 J. Ernst 445-5621 T. Storvick 445-4038 NRC Ooerations Center. Washinaton. DC 301-816-5100 ] l J.Schuh 449-0992 R. Dinger 449-0992 R. Ayem 443-6328 D. Pickett 474-0709 NRC Reaion til 708-829-9500 A. Shipp 442-4304 S. Keithley 443-1929 American Nuclear Insurers 203-561-3433 Rev. 6/16/95 App'd
l MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES I Revision Number 20 Revision Date: 10/18/95 l l Section Page Number Number l SEP-5 20f2 SEP-6 2 of 2 SEP-7 2 of 4 SEP-8 1of3 SEP-9 1of2 SEP-11 l 1 of 2 Emergency Call List Worksheet B l Worksheet E FEP-1 8 of 9 l FEP-1 9 of 9 FEP-3(a) 1 of 2 I I I I I I II-7
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Page 2 cf 4 SEP-7 (Cont'd)
- 5. The MU News Bureau staff member contacted should verify a call concerning an emergency at the University of Missouri Research Reactor by calling 882-4211 or 874-4119 and asking to speak to a member of the Facility Emergency Organization (FEO). If the person answering the phone does not know who is in the FEO, then ask for any individuallisted below. After ]
verifying the person's identity by asking for his social security number, the emergency call can be verified. VERIFICATION LIST FOR MURR EMERGENCIES Name Soc. Sec. No. Name Soc. Sec. No. Chuck Anderson Charlie McKibben Rex Ayers Walt Meyer Joe Baskett Paul Muren Kenneth Beamer PhilNeel Barry Bezenek - Willy Oldham Brian Brocker ] Harold Osborn ] Ronita Dinger Dave Peeler Chester Edwards Derek Pickett Judd Evans ] Jim Rhyne ) John Ernst Mark Richardson Les Foyto Tony Schoone I John Fruits Jim Schuh Greg Gunn Tom Seeger Robert Hudson Andrea Shipp Rolly Hultsch Nolan Tritschler Vernon Jones Robert Walker l MikeWallis Scott Keithley ] Ron Kitch Tim Warner Charlie Kribbs ]
- 6. MU News Bureau personnel contacted will determine the need for staffing and equipping an emergency information center and will call in the required staff and arrange for necessary facilities.
- 7. MU News Bureau personnel willinform news media and others of the public, as necessary, of the emergency.
- 8. If possible, a MU News Bureau staff member will be sent on-site to assist the Emergency Director with the release of information.
t Rev.10/18/95 App'd M
I SEP-8 Page 1 of 3 l EMERGENCY EQUIPMENT MAINTENANCE PROCEDURE l Purnose: This procedure states how the operational readiness of emergency equipment and i supplies required by the Emergency Procedures is to be maintained, calibrated, tested, and periodically inventoried. Health Physics' Emercency Eauioment: Health Physics' Emergency Equipment and supplies required by the Site Emergency Procedures shall be maintained in two designated readily accessible locations. The l two locations are the MURR Emergency Equipment Cabinets in the copy machine g room and the Backup Emergency Equipment Cabinet at RPDB. The inventory ) E checidists for each location are attached to this procedure and shall be used to verify quarterly that the contents of the cabinet meet at least the required levels. All maintenance and inventory records on emergency equipment shall be maintained in g, the Health Physics Office. The civil defense kits stored at each location contain a G-M survey meter, an ion I chamber meter (500 R/hr range), and a set of self-reading pocket dosimeters. E These kits are exchanged routinely by Missouri SEMA for updated kits of u instruments which have been calibrated by SEMA. The emergency Health Physics' equipment is supplemented by the Health Physics' instruments and equipment used for daily routine evaluations and is maintained and calibrated by the Operational l Health Physics' Program. Off-Gas Monitoring Eouinment: The off gas stack moniter has three channels: gas, particulate, and iodine. The three channels shall be calibrated semiannually by the Health Physics / Reactor Chemistry group using Reactor Chemistry Standard Operating Procedures: I RC/III-2 Calibration of Stack Particulate Monitor RC/III-3 Calibration of Stack Iodine Monitor g RC/III-4 Calibration of Stack Gas Monitor E The operability of the off-gas monitor is checked as part of the start-up checklist for normal reactor start-ups. Fire Fightine Ecuioment: The fire hydrant in the reactor site is checked operable routinely by the Columbia Fire Department. The fire extinguishers shall be checked in accordance with the g schedule determined by University of Missouri Campus Facilities. ] Rev.10/18/95 App'd 96& I
i Page 1 of 2 l
- SEP-9
- TRAINING PROCEDURE OF EMERGENCY PREPAREDNESS 4
I. TRAINING OF EMERGENCY ORGANIZATIONS ! A. Facility Emergency Organization (FEO) Training i This organization consists ofMURR staffin the Director's Office,
- Operations, and Health Physics / Reactor Chemistry groups. This 4 organization will respond to hath General Facility Emergencies (Facility
- Evacuation, Reactor Isolation, Fire, Medical, and Security emergencies) and Emergencies with Possible Off Site Consequences (Unusual Event, Alert,
- Site Area Emergency, Partial Site Area Evacuation).
l 1. The members of the FEO will train initially and annually thereafter, by emergency plan and procedure review of each member's role in j emergency preparedness. This training will be documented by each member signing the Emergency Plan / Procedures Review Documentation List. l l 2. An annual on-site emergency drill shall be conducted as an action drill to i test the training of FEO members to carry out their roles under simulated emergency conditions.
- B. Training of Facility SinfrOther than FEO Members i
- 1. The members of MURR staff not assigned to the FEO shall initially, and l
annually thereafter, be trained as to their respective actions for each site and facility emergency classification. This training may be by l seminar, lecture, or video tape sessions. ! . 1 ! 2. An annual on-site emergency drill will test these members' ability to properly respond to simulated emergency conditions. C. Training of Emergency Sunnort Organizations i l 1. The members of Emergency Support Organizations shall be trained i initially on their role in maintaining emergency preparedness. ] Continued training will be performed biennially by inviting ] ! members of each Support Organization to have discussions with ] i MURR staff, stressing familiarization with the facility or specific ] changes to the Emergency Plan or Procedures that may effect their response. This training will be scheduled prior to each biennial drill and l willinclude drill planning and scenario development. If members of a ] support group are unable to attend the training, a letter will be ] i sent indicating any specific changes to the Emergency Plan ] that may effect their response. ] 1 Rev.10/18S5 App'd \@ a
Page l of 2 g SEP-11 MONITORING EMERGENCY EXPOSURES ] i NOTE: The EMERGENCY DIRECTOR must approve each volunteer to exceed exposure limits of10CFR20. PURPOSE This procedure provides the guidelines for monitoring, dosimetry and records for a persons who volunteer for lifesaving and accident mitigating activities which 3 could result in planned radiation exposures in excess of10CFR20 limits. GUIDELINES A. Emergency Exoosure Guidelines ! 1. A volunteer may be authorized to receive up to 75 rem to save human I life. 1
- 2. A volunteer may be authorized to receive up to 25 rem to prevent radiation exposures to members of the general public in excess of the following Protection Action Guides (PAGs). g The Protective Actions for all classifications are based upon a PAG of 1 rem dose equivalent for whole body and 5 rem dcse equivalent thyroid to 3 members of the general public and MURR staff on site. 5 B. Personnel Selection Considerations
- 1. Individual is a volunteer (preferably 45 years or older).
- 2. Individual is familiar with the radiological consequences of emergency radiation exposures.
l
- 3. Women of childbearing age shall not take part (Reg. Guide 8.13). l C. Self-reader Dosimeters and Locations Type Bange (mr) Locatinn E
PC 0 - 200 Receptionist Desk - Lobby PC 0 - 200 Health Physics Office PC 0 - 200 Film Badge Racks PC 0 - 200 Emergency Lockers E PC 0 - 200,000 Emergency Lockers a NOTE: PC = Self-reader Pocket Chamber E Rev.10/18/95 App'd WQM g I
i > 1 o m r u- umus ummus umuur-- NN EMERGENCY C\LLUST Director's Office Facilities Operations Emergency Support Organizations Eone No. Phone.No. Phone.No. J.Rhyne 442-4967 C. Edwards 443-7529 UMC Polce 882-7201 J. C. McKibben 445-7843 9. McCracken 449-7731 W. Oladiran 443-5658 Reactor Operatans D. Peeler 816-848-2471 Corumbia Fire Decartment 9-911 Phone.No. K. Beamer 314-682-5499 W. Meyer 442-7675 J. Evans 816-848-2156 T.Schoone 443-8862 R. Kitch 875-2045 UM Hosoital & Clinics R. Huitsch 442-6653 C. Kribbs 314-682-3980 Emergency Services 882-6003 l C. Anderson 696-5506 S. Rinehart 314-682-2807 Ambulance 882-6128 or 9-911 B. Be:enek 445-5680 T. Seeger 442-6762 ] Walk-In (Emergency Center) 882-8091 B. Brocker 449-1759 ] J. Baskett 474-2046 G.Gunn 875-1162 M. Richardson 446-1014 N. Tritschler 474-9388 UMC Health Physics (Office) 882-7221 L Foyto 446-0491 Staff Resource Personnel Sue Langhorst (Home) 442-3534 J. Fruits 474-0774 Phone.No. Jamieson Shotts (Home) 474-2194 R. Hudson 445-6769 S. Morris 445-4217 David Spate (Home) 657-9450 V. Jones 445-2543 V. Spate 657-9450 P. Muren 874-0219 C. Baskett 474-2046 P. Neel 442-8693 M. Glascodc 443-4172 MU News Bureau 882-6211 W. Oldham 474-0987 D. Nickolaus 443-0502 See Public Information Procedure for other 882-9143 R. W:alker 443-0970 G. Ehrhardt 445-3570 phone numbers (SEP-7). 882-9144 j l M. Wallis 314-387-4859 A. Ketring 657-9614 i T. Wamer 816-882-6740 B. Yelon 445-8147 M. Ki! foil 449-2524 State Emeroency Manaoement Aaency (SEMA) 314-751-2748 Health Physics /Rx. Chemistry S.Gunn 443-2125 Phone No. L Krueger 442-0740 J. Ernst 445-5621 R. Dinger 449-0992 NRC Ooerations Center. Washinoton. DC 301-816-5100 ] J.Schuh 449-0992 R. Ayers 443-6328 H. Osborn 875-3906 ] NRC Regen 111 708-829-9500 D. Pkken 474-0709 A. Shipp 442-4304 S. Keithley 443-1929 American Nuclear Insurers 203-561-3433 Rev. 10/18/95 App'd (M
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WORKSHEET E RECORD AND AUTHORIZATION OF EMERGENCY EXPOSURES ] A. Emergency Exposure Authorization: Emergency Director Date B. Volunteer Signature Date C. Record of Exposur Measured by Dosimeters
- 1. Name __ _
- 2. Exposure limit assigned forjob mrem.
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Paga l cf 2 g FEP-3(a) E CONTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE E l NOTE: Thmughout this procedure continue to monitor stack exhaust monitor, Alpha E I Laboratory exhaust monitor (alpha-6) or Alpha Laboratory room monitor E I (alpha 3) for indication of airborne radioactivity, as appropriate.
- 1. If a fire is detected by fire alarm or reported in the Alpha Laboratory, the shift supervisor (or senior licensed person in control) will verify and call the Columbia Fire Department. l
- 2. The shift supervisor will activate the Facility Emergency Organization by page g system (or after hours by Emergency Call List) and provide warning to stay clear 3 of facilitybasement.
- 3. The Emergency Director will determine nature and specific location of fire (i.e., if fire is in glove box or equipment exterior to glove box).
- 4. If fire cannot be put out immediately with local fire extinguishers, the reactor will be shut down to fbcus attention on the fire. g
- 5. Ensure Alpha Laboratory doors are shut and personnel are out of the laboratory.
If no experimenter is present, call the on-call experimenter as soon as time ; 1 permits.
- 6. If there is a likelihood of the fire spreading through the ventilation system, secure EF-13 and EF-14 at breaker on the emergency distribution center (in north inner corridor).
- 7. Secure electrical power to Alpha Laboratory at following locations: g
- a. Breaker #13 on UPS #2 - in control room (this secures power to the argon glove box and deactivates the glove box exhaust valves in their current position).
- b. Breaker #17 on 120/208 V distribution center - in north inner corridor (this secures power to LP-34 which will secure lights and receptacles).
Open all breakers on ELP 2, except #4 (which powers the Alpha 6 ) I c. monitor). ] g Rev.10/18/95 App'd M I
MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 21 Revision Date: 12/27/95 i Section Page l Number Number SEP-1 1of5 SEP-1 4 of 5 SEP-1 5 of 5 SEP-2 1 of 5 SEP-3 l of 6 l SEP-3 SEP-3 2 of 6 4 of 6 l SEP-4 SEP-4 1 of 6 2 of 6 SEP-4 l SEP-5 4 of 6 1of3 Sof3 l SEP-5 SEP-6 2 of 2 Emergency Call List Worksheet B FEP-3(a) 1of2 1 1 i II-8
Prge 1 cf 5 SEP-1 ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE L FACILITY EMERGENCIES:
- 1. The Facility Emergency Organization (FEO) shall be activated as per the l Facility Emergency Procedures (FEP) for each FACILITY EMERGENCY I CLASSIFICATION:
a) Facility Evacuation b) Reactor Isolation c) Fire d) Medical e) Security (SAFEGUARDS INFORMATION AS PER 10CFR50.34(c)]
- 2. In addition to the procedures for each FACILITY EMERGENCY CLASSIFICATION, an assessment of off-site consequences shall be determined.
II. EMERGENCIES WITH POSSIBLE OFF-SITE CONSEQUENCES:
- 1. The duty shift supervisor or individual authorized to assume the Emergency Director position shall determine the need to activate the FEO for I emergencies with possible off-site consequences. This need will be based upon the action levels specified for the minimum classification, UNUSUAL EVENT. These action levels are:
I a. Report or observation of severe natural phenomenon.
- b. Threats to or breaches of security.
l
- c. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours.
l
- d. The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding I 15 mrem whole body accumulation in 24 hours.
- e. Prolonged fire or explosion within the facility that does not involve ]
I TRUMP-S materials (americium, neptunium, plutonium). ] l
- f. Other plant conditions exist that warrant ensuring emergency personnel 1 are available to respond to an emergency to prevent exposures of 1 rem whole body or 5 rem thyroid to the public or staff.
'AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd MY\ )
i l SEP-1 (C:nt'd) Pcge 4 of 5 l TABLE I ACTION LEVELS FOR EMERGENCY CLASSES g' Unusual Event
- 1. Report or observation of severe natural phenomenon.
- 2. Threats to or breaches of security.
- 3. Concentration of airborne radioactivity at the stack monitor exceeding l
20,000 AEC* when averaged over 24 hours.
- 4. The projected concentration of airborne radiological efIluent at the distance corresponding to the nearest site boundary exceeding 15 mrem whole body accumulated in 24 hours.
l 5. Prolonged fire or explosion within the facility that does not involve TRUMP-S ] l materials (americium, neptunium, plutonium). ]
- 6. Other plant conditions exist that warrant ensuring emergency personnel are available to respond to an emergency to prevent exposures of 1 rem whole body or 5 rem thyroid to the public or staff.
l,' l Alert g'
- 1. Concentration of airborne radioactivity at the stack monitor exceeding 100,000 AEC* when averaged over 24 hours.
l 2. The projected concentration of airborne radiological efIluent at the distance corresponding to the nearest site boundary exceeding 75 mrem whole body ' accumulated in 24 hours. l 3. Radiation levels at the distance corresponding to the nearest site b r.mdary of a 20 mrem /hr for 1 hour whole body or 100 mrem thyroid dose. E
- 4. Loss of physical control of the facility.
- 5. Fire in which up to 3 grams of TRUMP S materials (americium, ]
neptunium, plutonium) are involved. ]
- 6. Other plant conditions exist with alevel of significance of a major failure of fuel ]
I cladding, but primary and containment boundaries exist to reduce releases. I I l
*AEC Air Efnuent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd M I l
SEP-1 (Cont'd) Page 5 of 5 TABLE I (Cont'd) ACTION LEVELS FOR EMERGENCY CLASSES l Site Area Emergency
- 1. Concentration of airborne radioactivity at the stack monitor exceeding
( 500,000 AEC* when averaged over 24 hours.
- 2. The projected concentration of airborne radiological effluent at the distance f corresponding to the nearest site boundary exceeding 375 mrem whole body accumulated in 24 hours.
- 3. Radiation levels at the distance corresponding to the nearest site boundary of 100
[ mrem /hr for 1 hour whole body or 500 mrem thyroid dose.
- 4. Fire in which more than 3 grams of TRUMP S materials (americium, ]
neptunium, plutonium) are involved. ]
- 5. Other plant conditions exist with a level of significance of major fuel damage and ]
conditions that indicate actual or imminent failure of containment integrity and primary system interrity. l { f L
*AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd
Pag 31cf 5 l SEP-2 l UNUSUAL EVENT PROCEDURE I ACTIONS LEVELS: E there is:
- a. Report or observation of severe natural phenomenon. Il
- b. Threats to or breaches of security. [See REACTOR EMERGENCY g PROCEDURE (REP-22).] 3;
- c. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours. [See REACTOR !
EMERGENCY PROCEDURE (REP-21).] NOTE: Use overlays to determine extent of activity for iodine, particulate, and gas. l'I
- d. The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding l 4 15 mrem whole body accumulated in 24 hours. j
- e. Prolonged fire or explosion within the facility that does not involve ] Il i TRUMP S materials (americium, neptunium, plutonium). ]
I
- f. Other plant conditions exist that warrant ensuring emergency personnel are available to respond to an emergency to prevent exposures of 1 rem 3 whole body or 5 rem thyroid to the public or staff. 5 THEN at least an UNUSUAL EVENT condition exists.
IMMEDIATE ACTIONS:
- 1. Activate the Facility Emergency Organization (FEO), as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE. if not 2.
already activated. Operations shall provide information to the Emergency Director / Emergency I 3. Coordinator. If airborne activity is involved, continue with step 4. If not, go to step 7. I
- 4. Time and date stack monitor chart for reference. l
'AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev. 12/27/95 App'd Sh
)
Page 1 cf 6 SEP-3 ALERT PROCEDURE ACTIONS LEVELS: E there is:
- a. Concentration of airborne radioactivity at the stack monitor exceeding 100,000 AEC* when averaged over 24 hours. [See REACTOR EMERGENCY PROCEDURE (REP 21).]
NOTE: Use overlays to determine extent of activity for iodine, particulate, and gas.
- b. The projected concentration of airborne radiological efIluent at the distance corresponding to the nearest site boundary exceeding 75 mrem whole body accumulated in 24 hours.
- c. Radiation levels at the distance corresponding to the nearest site boundary of 20 mrem /hr for 1 hour whole body or 100 mrem thyroid dose.
- d. Loss of physical control of the facility.
- e. Fire in which up to 3 grams of TRUMP S materials (americium, ]
neptunium, plutonium) are involved. ]
- f. Other plant conditions exist with a level of significance of a major failure of fuel cladding, but primary and containment boundaries exist to reduce releases.
THEN atleast an ALERT condition exists. IMMEDIATE ACTIONS:
- 1. Activate the Facility Emergency Organization, as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE,ifnot already activated.
- 2. Operations shall provide information to the Emergency Director / Emergency Coordinator.
- 3. Time and date stack monitor charts for reference.
- 4. Shut down the reactor.
- AEC Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd 100ws
P:ge 2 cf 6 I SEP-3 (Cont'd) IMMEDIATE ACTIONS: (Cont'd)
- 5. Send operator to west tower with radiation monitor to:
NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF. g
- a. Verify radiation background at stack monitor.
- b. Verify control room readings.
- c. Write down the readings on the analog display, with the time, for future analysis if control room display becomes inaccessible.
l l
- d. Verify flow rate through monitor to 5 i 1 SCFM. If not, use Worksheet A to determine stack monitor values.
- 6. Pull stack monitor filters and analyze.
- 7. After determining radionuclide responsible and verifying concentrations greater than 100,000 AEC* (a) secure EF-13 and EF-14;(b) secure RF2, SF2, RF1, SF1; (
l (c) secure allindividual vent fans. ,
- 8. The Emergency Coordinator shallinitiate a protective evacuation of all public ]
and non-emergency personnel to outside the EPZ (this includes the USDA, ) Science Instrument Shop, and Greenhouses). ] NOTE: For facility evacuations or northeast quadrant evacuation, have sample countinginstrumentation removed to RPDB. (Ge-Li detector and dewer; l High Resolution Gamma Ray Spectrometer)
- 9. The Emergency Coordinator shall appoint and have a surveillance team check areas evacuated clear of personnel within 30 minutes. l NOTE: Emergency Director approval required for any voluntary radiation exposure E in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, up to 25 rem to E prevent exposure to members of general public in excess of 1 rem whole body and 5 rem thyroid.)
- 10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE III, g i
EMERGENCY SUPPORT ORGANIZATIONS.
'AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
App'd W Rev.12/27/95 I
SEP-3 (Cont'd) Page 4 of 6 CORRECTIVE ACTIONS:
- 1. If the facility was evacuated in Step 8 of IMMEDIATE ACTIONS, continue. IF NOT, go to step 2.
- a. Commence external surveys of the reactor laboratory building to detectleakage of airborne radioactivity and locate the source radioactivity.
- b. Commence air sampling at 400 meters downwind of facility as per EMERGENCY AIR SAMPLING PROCEDURE (SEP-6).
- c. Evaluate results of surveys to determine possible reentry to parts of facility for further investigation, if necessary.
- d. IEleakage concentrations exceed 100,000 AEC* averaged over,24 hours the Emergency Director should consider evacuation of Dalton Research Center ]
and Blood Bank, as per SITE AREA EVACUATION PROCEDURE (SEP-5). IF NOT. Emergency Director should evaluate de-escalating to UNUSUAL EVENT classification. f
- 2. Determine source of airborne radioactivity and try to reduce or eliminate the source.
- a. REACTOR (1) Check fission product monitor.
f (2) Check room 114 ARMS. (3) Check pool for gas releases. (4) Check dose rate on room 114 filter bank. Actions to Consider: (1) Sample primary (2) Procedure REP-20, Hich Activity Levels in Primarv (3) Reactor Isolation (FEP-2) (4) Area Evacuations (5) Portable air monitor in room 114 {
'AEC Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd kUPM
SEP-4 Page i ef 6 l SITE AREA EMERGENCY PROCEDURE ACTIONS LEVELS: I E thereis:
- a. Concentration of airborne radioactivity at the stack monitor exceeding 500,000 AEC* when averaged over 24 hours. [See REACTOR El\ERGENCY PROCEDURE (REP-21).]
NOTE: Use overlays to determine extent of activity for iodine, particulate, and I gas.
- b. The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding 375 mrem whole body accumulated in 24 hours.
- c. Radiation levels at the distance corresponding to the nearest site boundary of g 100 mrem /hr for 1 hour whole body or 500 mrem thyroid dose.
- d. Fire in which more than 3 grams of TRUMP S materials (americium, ]
neptunium, plutonium) are involved. ]
- e. Other plant conditions exist with a level of significance of major fuel damage ]
and conditions that indicate actual or imminent failure of containment integrity and primary system integrity. THEN a SITE AREA EMERGENCY condition exists. , i IMMEDIATE ACTIONS:
- 1. Activate the Facility Emergency Organization, as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE. if not already activated.
- 2. Operations shall provide information to the Emergency Director / Emergency Coordinator.
- 3. Time and date stack monitor charts for reference. g
- 4. Shut down the reactor.
'AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd Ih I
SEP-4 (Cont'd) Page 2 of 6 IMMEDIATE ACTIONS: (Cont'd) ! l
- 5. Send operator to west tower with radiation monitor to: j NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF.
. a. Verify radiation background at stack monitor. , I i
- b. Verify control room readings. l
- c. Write down the readings on the analog display, with the time, for future analysis if control room display becomes inaccessible.
l
- d. Verify flow rate through monitor to 5 1 SCFM. If not, use Worksheet A to determine stack monitor values. l
- 6. Pull stack monitor filters and analyze.
- 7. After determining radionuclide responsible and verifying concentrations greater than 500,000 AEC* (a) secure EF-13 and EF-14; (b) secure RF2, SF2, SF1; (c) secure all individual vent fans.
- 8. The Emergency Coordinator shallinitiate a protective evacuation of ]
public and non emergency personnel to bevond the nearest site ] boundary (400 m) as per SEP 5, SITE AREA EVACUATION ] PROCEDURE. ] NOTE: For facility evacuations or northeast quadrant evacuation, have sample counting instrumentation removed to RPDB. (Ge-Li detector and dewer; High Resolution Gamma Ray Spectrometer)
- 9. The Emergency Coordinator shall appoint and have a surveillance team check areas evacuated clear of personnel within 30 minutes.
NOTE: Emergency Director approval required for any voluntary radiation exposure in excess of10CFR20 limits. (Up to 75 rem for lifesaving, up to 25 rem to prevent exposure to members of general public in excess of 1 rem whole body and 5 rem thyroid.)
- 10. Determine the need for Emergency Support Organizations and, if needed, activate them or place them on standby. See Table IV, Emergency Support Organizations.
'AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd W
SEP-4 (Cont'd) Paga 4 cf 6 I CORRECTIVE ACTIONS:
- 1. If the facility was evacuated in Step 8 ofIMMEDIATE ACTIONS, continue.
IF NOT, go to step 2.
- a. Commence external surveys of the reactor laboratory building to detect leakage of airborne radioactivity and locate the source radioactivity.
- b. Commence air sampling at 400 meters downwind of facility as per EMERGENCY AIR SAMPLING PROCEDURE (SEP-6). ] l
- c. Evaluate results of surveys to determine possible reentry to parts of g facility for further investigation, if necessary. E
- d. IEleakage concentrations are less than 500,000 AEC* average over ]
24 hours the Emergency Director should evaluate de-escalating to ] l ALERT classification.
- 2. Determine source of airborne radioactivity and try to reduce or eliminate the source.
- a. REACTOR (1) Check fission product monitor.
(2) Check room 114 ARMS. (3) Check pool for gas releases. Actions to Consider: E (1) Sample primary 3 (2) Procedure REP-20, High Activity Levels in Primary (3) Reactor Isolation (FEP-2) (4) Area Evacuations l (5) Portable air monitorin room 114 I I
*AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
Rev.12/27/95 App'd M 1 i
Page 1of3 ] SEP-5 PARTIAL OR FULL SITE AREA EVACUATION PROCEDURE ), (SEE ATTACHED SITE MAP) When a PARTIAL OR FULL SITE AREA EVACUATION is deemed necessary, ] the EMERGENCY DIRECTOR shall contact the UMC Police Department to have thdr personnel notify the affected laboratory and office spaces of the need to evacuate to the Research Park Development Building (RPDB). A. For a FULL SITE AREA EVACUATION (an evacuation beyond the ] nearest site boundary): ) a) All personnel within the Golf Course Greenskeeper building, the Civil Engineering Freight Pipeline Research Laboratory building, the Laboratory Animal Center, and the Animal Psychology Laboratory in the Melvin H. Marx Research Laboratory building will proceed to the RPDB. b) All personnel within the Dalton Cardiovascular Research Center and USDA Biological Control ofInsects Research Laboratory will proceed north to the RPDB. c) All personnel within the Blood Center will proceed north on Providence Road to the RPDB. d) All personnel who have evacuated the reactor building will proceed to the RPDB. e) All personnel in the Greenhouse and Science Instrument Shop will proceed to the RPDB, B. For a PARTIAL SITE AREA EVACUATION (e.g., a protective evacuation] beyond the EPZ): ] a) All personnel within USDA Research Laboratory will proceed north ] to the RPDB. ] [ b) All personnel within the Greenhouse and Science Instrument Shop ] ( will proceed to the RPDB. ] Rev.12/27/95 App'd M\
SEP-5 (Cont'd) Page 3 of 3 ] ;
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NN EMERGENCY CALLUST Facilities Operations Emergency Support Organizations Director's Gffice Phone. No. Phone.No. Phone No. 443-7529 UMC Police 882-7201 , J. Rhyne 442-4967 C. Edwards J. C. McKibben 445-7843 B. McCracken 449-7731 W. Oladiran 443-5658 816-848-2471 Columbia Fire Deoartment 9-911 Reactor Operations D. Peeler Phone.No. K. Beamer 314-682-5499 W. Meyer 442-7675 J. Evans 816-848-2156 443-8862 R. Kitch 875-2045 UM Hosoital & Clin'es T. Schoone 882-6003 442-6653 C. Kribbs 314-682-3980 Emergency Services R Hultsch 882-6128 or 9-911 C. Anderson 696-5506 S. Rinehart 314-682-2807 Ambulance 442-6762 Walk-in (Emergency Center) 882-8091 B.Bezenek 445-5680 T. Seeger B. Brocker 499-1759 ] J. Baskett 474-2046 G.Gunn 875-1162 M. Richardson 446-1014 UMC Health Physics (Office) 882-7221 N. Tritschler 474-9388 442-3534 446-0491 Staff Resource Personnel Sue Langhorst (Home) L Foyto 474-2194 J. Fruits 474-0774 Phone.No. Jamieson Shctts (Home) 445-4217 David Spate (Home) 657-9450 R Hudson 445-6769 S. Morris V. Jones 445-2543 V. Spate 657-9450 P. Muren 874-0219 C. Baskett 474-2046 443-4172 MU News Bureau 882-6211 P.Neel 442-8693 M. Glascock 443-0502 See Public Information Procedure for other 882-9143 W. Oldham 474-0987 D. Nickolaus 445-3570 phone numbers (SEP-7). 882-9144 R Watker 443-0970 G. Ehrhardt
. M. Wailis 314-387-4859 A. Ketring 657-9614 T. Wamer 816-882-6740 B. Yelon 445-8147 449-2524 State Emeroency Manaoement Aoency (SEMA) 314-751-2748 M. Kilfoil Health Physics /Rx. Chemistry S.Gunn 443-2125 Phone No. L Krueger 442-0740 449-0992 NRC Ooerations Center. Washinoton. DC 301-816-5100 J. Ernst 445-5621 R Dinger J.Schuh 449-0992 R. Ayers 443-6328 NRC Reoion 111 708-829-9500 H. Osbom 875-3906 D. Pickett 474-0709 A. Shipp 442-4304 American Nuclear Insurers 203-561-3433 S. Keithley 443-1929 Rev. 12/27/95 App'd NW i M M M M
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DRAWN BY: D.G.N. WORKSHEET"B" DATE: 12/21/95 App'd g 22.5. SECTOR SURVEY MAP Rev. 12/27/95
l Paga l cf 2 FEP-3(a) CONTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE l, NOTE: Thmughout this procedure continue to monitor stack exhaust monitor, Alpha Laboratory exhaust monitor (alpha-6) or Alpha Laboratory room monitor (alpha-3) for indication of airborne radioactivity, as appropriate. ll
- 1. If a fire is detected by fire alarm or reported in the Alpha Laboratory, the shift supervisor (or senior licensed person in control) will verify and call the Columbia l l Fire Department.
- 2. The shift supervisor will activate the Facility Emergency Organization by page system (or after hours by Emergency Call List) and provide warning to stay clear gl of facility basement.
- 3. The Emergency Director will determine nature and specificlocation of fire.
If fire involves TRUMP S materials implement SEP 3, ALERT
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l PROCEDURE, in conjunction with this procedure. ] i
- 4. If fire cannot be put out immediately with local fire extinguishers, the reactor will be shut down to focus attention on the fire.
- 5. Ensure Alpha Laboratory doors are shut and personnel are out of the laboratory.
l;l If no experimenter is present, call the on-call experimenter as soon as time permits.
- 6. If there is a likelihood of the fire spreading through the ventilation system, secure EF-13 and EF-14 at breaker on the emergency distribution center (in north inner ,
corridor). l Secure electrical power to Alpha Laboratory at followinglocations: 7. E,
- a. Breaker #13 on UPS #2 - in control room (this secures power to the argon glove box and deactivates the glove box exhaust valves in their current g E
position).
- b. Breaker #17 on 120/208 V distribution center - in north inner corridor (this g secures power to LP-34 which will secure lights and receptacles).
- c. Breaker #2 on emergency power panel - in north inner corridor (this secures power to ELP #2 outside Alpha Laboratory, which will secure Alpha l
Laboratory supply and exhaust fans). Rev.12/27/95 App'd h I
HEALTH PHYSICS STANDARD OPERATING PROCEDURES (New manualissu :. ~0/29/90) Section Page Nos. Revision No. Revision Date HP-2 1-3 2 9/27/95 HP-8 1-5 1 9/27/95 HP-9 1-2 1 9/26/95 HP-12 1 1 9/26/95 HP-22 1-2 1 9/26/95 I HP-25 1-2 2 9/27/95 l HP-28 1-6 4 12/18/95 HP-29 1-2 3 9/27/95 HP-31 1-7 3 12/18/95 HP-34 1-3 2 12/18/95 HP-36 1-3 1 9/25/95 HP-40 1-4 0 4/25/95 HP-41 1-4 0 12/18/95 I I I I I II-9 w
Q SOP MP-2 Rev. 2 Page 1 of 3 App r' d - b-Sate S ect embe r 27, 1995 Foc, 134 Unscheduled Entry 1.0 Policy ) Entries into Room 114 are made following an evaluation of potential radiation harards and the establishment of adequate controls. 2.0 Purpose ] The purpose of this procedure is to allow entry to Room 114 after shutdown prior to Health Physics performing a full Radiation and Contamination Survey. 3.0 Scope ) This procedure is valid only for unscheduled entries to Room I 114 deemed necessary by the Reactor Shift Supervisor. Entry into this area is allowed to perform evolutions which are
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necessary for safe continued plant operation when health ] I physics personnel are unavailable or a full survey is not warranted.
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4.0 Pesponsibility ) The Shift Supervisor is responsible for the control and use of the Room 114 Unscheduled Entry Standard Operating Procedure. I At MURR, a Senior Reactor Operator may be the supervisor on duty. 5.0 Oualifications ) Entries to Room 114 under this procedure will be limited to health physics staff, licensed reactor operators, and other ) I nece s s a:.y p. a... ._ .. s :. . : c _ . .; . . operator. The reactor must be in a shutdown condition.
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6.0 Performance ) 6.1 When entry to Room 114 is required, the person entering ) shall have the following: A. Radiation Survey Meter ) B. Self-Reading Pocket Dosimeter ) w
MP-2 I SOP Rev. 2 Page 2 of 3 Appr'u e-/Q'n5/> Date settember 27. 1995 C. Shoe Covers ) I D. Unscheduled Entry Survey Map. ] NOTE: Work under this entry shall not exceed 30 minutes. ) 6.2 Fill in entry data on the survey map including initial ) pocket chamber reading. ] l 6.3 As the persen enters the room, they shall monitor the ) 3 radiation levels to and at the specific location where 5 plant evolutions must be performed. 6.4 Upon completion of the evolution, the person shall exit ) I, the area using appropriate contamination control techniques at the boundary and record the following on the map at the boundary: A. Record the radiation level in the area where work ) was performed (if there was more than one location of work, record all work location radiation levels.)
- 3. Record the total exposure dose received as indicated )
by self-reading pocket dosimeter. Record the ) , radiation instrument model number and serial number. ] C. Record name, time in/out and the date. ] 7.0 Limitations ) 7.1 If the general area radiation level exceeds 500 mrem /hr, ) the person shall exit the area immediately and the Shift Supervisor shall contact the Manager, Reactor Health Physics (Exception: If the safe operation of the reactor g is in jeopardy, the radiation dose shall not exceed 25 5 rem.). 7.2 Work under this procedure shall not exceed 100 mR )
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individual dose or 30 minutes duration without Reactor Health Physics coverage. Check pocket chamber reading at ) 10 minute intervals. ] 7.3 Entry to Room 114 made under this SOP shall be recorded ) in the Reactor Console Log. I
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4 SOP MP-2 i Rev. 2 Page 3 of 3 l Appr' d n5 l !~ Date Sectember 27, 1995 i ~ 7.4, Reactor Health Physics shall be notified of each entry ) 7 under'this SOP. This notification is the responsibility 1 of the Operations Engineer. Notification shall be made during the next normal work day. 1
- 8 ~. 0 Pestrictions }
! The following types of activities are HQI to be performed ] l under the Room 114 Unscheduled Entry Standard Operating Procedure: 8.1 Breach of Primary System Containment. ] )
'8.2 Movement of radioactive materials or components. )
j 8.3 ' Scheduled work which could be performed during regular ) ' scheduled hours. 8.4 Evolutions which could produce an airborne. contamination -) problem. 4 1 l l 4 I 4 4 1
l I 1 SOP "?-9 ii Rev. 1 Pag,e 1 ef 5
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Date 9 err e+e r 27. 1995
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centre 11ed Seacini Emesures- At:.:A censidara-icrs
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1.0 Felicy Centrolled Special Exposures shall be reviewed and authorized by persons with appropriate responsibility fer the individual's work. No one below the level of Associate Director shall approve their own Controlled Special Exposure.
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2.0 Purrese The purpose of this procedure is to define specific authoriration requirements for individuals to receive Centrolled Special Exposures which would exceed 10% of any J limit stated in Federal Regulations. As the amount of the ) planned exposure increases the organization level of the person required to authorize it is increased.
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3.0 refinition of a contre 11ed seecial Excesure 3.1 A controlled Special Exposure is a planned exposure ] anticipated to exceed 10% of any limit stated in Federal ) Regulations. Authorizatien is for a single work project
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which may extend over several work shifts. This procedure applies to all operaticas under any NRC license 3 used at the Reactor Center. It does not apply to procedures
) g performed while operating under the MURR Emergency Plan.
Nothing in this procedure is intended to authorize exceeding a ) limit for personnel exposure as stated in the Federal ] Regulations. resienatien of Persens m ;,._ c_= _ ;:. u - _ _ ' . _ ' '. '. E 5.0 Excesures a
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Persons designated to authorize Controlled Special Exposures } are listed in Table I. Authorization of special exposures can be by the person temporarily filling the position designated in Table I. I I
1 I SOP MP-9 ( Rev. 1 Page 2 of 5
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App r' d w:T'ah'f J Date Sectember 27, 1995 Table I Desienation of Persons to Authorize cont re11ed Scecial Excesures
, Maximum mrem Designated Health Physics Authorization Authorizer Approval Fecuired 5000 Director Manager )
5000 Associate Director Manager ) 1000 Reactor Manager Manager 1000 Facility Operations Manager Manager ) 1000 Reactor Operations Engineer Manager 500 Shift Supervisor Technician ) 6.0 Responsibilities ) 6.1 Authorization to receive a special exposure is made by a ) member of management as designated in Table I. Thai person is responsible to ensure supervisory control of the work is provided to maintain control of radiation exposure as planned. 6.2 A member of Health Physics designated in Table I is ) responsible to ensure that an overexposure will not occur by providing: A. A review of the radiation history of the worker for ) the current calendar year. ) B. In cooperation with the work group involved, help ) plan procedures to maintain personnel exposures as low as reasonable (ALARA) for the work in progress. ) C. Adequate radiation monitoring for the worker and ) communicate monitoring data to the job supervisor as the work progresses. 6.3 The worker is responsible to fully understand the ] procedures before starting work on the project and to perform the work in a prudent manner which will minimize radiation hezards. 7.0 Procedure ) 7.1 When a special exposure is anticipated Health Physics ) will prepare a Controlled Special Exposure Authorization ) Form as per this procedure. ]
i SCP MF-8 I l Rev. 1 Pace 3 of 5
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l App r' d I4s",i'T l Date Ser*erber 27 1995 = 7.2 An Radiation Work Permit (RWP) shall be prepared and ) l
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signed by the necessary individuals to establish adequate ) control cf radiation hazards. , 7.3 The Controlled Special~ Exposure Authorization Form shall ) be signed, in advance, by appropriate persons authorized ) as per Table I. 7.4 Once work has commenced, the doses of the individual (s) ) shall be tracked at intervals which will allow close 3 control of exposure. ) 7.5 After work completion, a summary will be conducted by the ) Health Physics Group and then reviewed by the Health 3 Physics Manager. } I Il I I! I I I I I I
i SOP MP-8 Rev. 1 Page 4 of 5 Appr'o ,
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Oate Septeser 2 '1 1995 CONTROLLED SPECTAL EXPOSURE AUTHORTZATION FORM ] NAME: DATE: SSN: 3 RWP NUMBER: ACCUMULATED EXPOSURE TO DATE
!! PERIOD mrem mrem mAem Measurement TEDE Skin Extremities Method )
1 Lifetime YCar to Date Expected Dose 3 Margin to Limit Limit-Expected = 3 i Limit Approved (mrem) Approved By: / _ _ _ ) Signature / Title Health Physics R0cd and Approved by employee: Date: Signature
o I a SOP HP-B Rev. 1 Page 5 of 5 Appr' d ~JLh [/76'/- 7 Date Senterher 27, 1995 i S:1mmarv of Exoosure Received and Comments ] I Health Physics Dese Received: mrem TEDE: ) I mrem skin: I~ mrem extremity: Other-Exclain in Detail and elaborate . internal / external: ) I I Comments and Further Exclantion/ Evaluation: ) I I I Health Physics Date I Date 3 Health Physics Manager I I
SOP MP-9 Rev. 1 Pace 1 of 2 Appr' d - 'M Date Sectember 26, 1095 Standard Contamination Wire Proced2re
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1.0 Peliev A centamination survey should be performed by radiatien workers whenever a potential exists for radioactive contamination of surfaces in the work area. Reactor Health Physics performs surf ace contamination surveys as-a monitoring function. Health Physics will also provide surveys on call when appropriate. 1 2.0 Purcese The purpose of surface contamination surveys is to prevent the spread of contamination by detecting, defining, and causing the clean up of contaminated surfaces. This procedure is for ) determining levels of removable (loose) contamination, not fixed contamination.
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3.0 Precedure
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3.1 Equipment required A. Suitable wipe paper. Health Physics normally uses 4.25 cm Whatman ) qualitative filter paper or cloth smears.
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B. Wipe counting instrumentation suitable for measuring ) the types of contamination that might possibly be ) encountered.
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C' . Latex or rubber gloves; use if high levels of ) contamination are suspected.
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3.2 Protocol 1 A. Don gloves.if high levels of contamination are } suspected.
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B. Wipe 100 cm2 area with a dry wipe paper or cloth ) smear using moderate pressure.
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C. Count the wipe to determine the level of removable l l
( - I SCP MP-9 - , Rev. 1 Page 2 ef 2
> - 1 App r' d /b"iMI Date sectember 26. 1995 contamination. I1 l
D. If the count indicates removable contamination 3 i greater than 220 dpm/100 cm2 beta-gamma or ) g l significantly above background for alpha ) contaminants, the area is to be considered . ! contaminated. If the area is an unrestricted area it must be ] decontaminated immediately or Health Physics must set up appropriate signs and barriers to establish EI 3 l it as a restricted area to satisfy requirements of
] m Federal Regulations.
g, If the area is an established restricted area Health ) Physics shall determine the appropriate action to be 3 taken. Ii , I I; I Ii I'
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1 SOP HP-12 , l Rev. 1 Page 1 of 1 Appr' d [.irn A / . l Date Sectember 26. 1995 Transfer of Radioactive Material Within Reactor Building l 1.0. Policy ) ) Materials transferred within the reactor building must be packaged to prevent radiation hazards to personnel due to ! radiation fields and/or contamination caused by loss of radioactive material. 2.0. Scope ) ] This procedure applies to radioactive samples and irradiated ; materials. Excluded, because they are covered in other i procedures, are radioactive waste, tools, and equipment. l l Transfer within laboratory rooms is also excluded from this ; procedure. 3.0. Purpose ] l The purpose is to ensure that exposure to personnel is ] minimized when transferring radioactive materials within the ] center. ] 3.1 To accomplish the stated purpose a transfer container ] design should include the following: A. A lid closure that can be installed and removed ] quickly to minimize exposure time. B. Features which assure that the material being ] transported cannot spill out if the transfer container is dropped and/or tipped on its side or upside down. Y 3.2 If a transfer container is to be 1e't unattended, it must ] be posted as required by Federal Regulations. ] 1 4.0. Specific Rules ] 4.1 When transporting material via elevator, personnel shall ] not ride with material if the exposure rate at 1 meter ] exceeds 5 mrem per hour. ] l l l 8 l 1
1 I I i 50? MF-22 1 Rev. 1 Page 3 of 2 l i / .--- , i c.,.
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Cate cer t e-l a r 2c. c5 Feview cf *? elar.ed Fadia-irr xrr ures
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l I MURR Center policy is to prevent all perscrnel radiatien frcm exceeding regulatory limits and to maintain radiation 1 exposures ALAF.A. 2.0 Purpere 2 The purpose of this procedure is to provide for review of unplanned radiation exposures as a means cf improving centrol ; of future exposures. 3.0 Secce ; This procedure should be used for personnel exposure events that were unplanned and resulted in radiatien expcsure exceeding 5% of any limit stated in Federal Regulations. ) 4.0 Precedure , 4.1 Within one work day after any member of Reactor Health ) Physics realires that a personnel expcsure has occurred which is within the scope of this procedure, the Manager of Reactor Health Physics shall appoint a three-member investigation team to review the cause of the exposure g and recomnend preventive measures to prevent a B reoccurrence. A. The members of the committee shculd include ene i person from the work unit which experienced the exposure, one member of the Isetepe Use Subcommittee and the Manager of Reactor Health Physics. B. The committee may choose to enlist other persons as ) seems appropriate to perform an efficient, effective review. 4.2 'Ihe Manager of Reactor Health Physics shall call a ) committee meeting as soon as is appropriate for the circumstances. I I
SCP MF-12 Rev. 1 Page 2 ef 2
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Appr'd ~~7CT' l'2'
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a:e Ser +-l e r 26, ~_? F 4.3 Committee crder :f business shall be:
- A. Manager, Reactor Health Physics informs members the )
purpose of the committee is to determine the cause of the expcsure (s) and to recommend measures to preven; a recccurrence. ,
- 3. Manager, Reactor Health Physics calls for a vote to )
select committee chairman, all three merbers voting. C. The selected chairman will then conduct business ) with a general cbservance of Robert's Rules of Order. 4.4 A report of the findings and reccmmendations of the ) ccmmittee shall be prepared. Ccpies will be distributed t to the Reactor Health Physics Manager, to exposed ) radiation workers and worker's supervisor. ) l
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Cate ser e-Fer 2' 1995 cera -fr Facili- Fafe-, che 9 s 1.0 Felicy ) To ensure safe use and minimum radiatica expcsure during ) operaticn cf the Ccbal: Facility, Reac:cr Health Physics will ] perform weekly safety checks as necessary. 2.0 Ec':ir e-- ) 2.1 E-y survey meter. ) 2.2 Facility door key. ) 2.0 : ece92re 3 3.1 Source check the survey instrument to ensure it is } l working prcperly. ) 5 3.2 Nctify Centrol Room if performing alene. ) 3.3 .asure pcwer is on to power box and sou.;cc L . t u.. A - s .. . . and door unlocked lights lit. Note: If any step fails, secure procedure, lock doors and 3 immediately notify appropriate personnel. 3.4 With survey meter in hand checking exposure rates, enter 3 the facility and ensure normal, secured status. A. If any exposure rates are above 5 mrem / hour, exit 3 the facility and notify the Health Physics Manager. ) 3.5 Verify scurce bottomed and on the elevator. ) 3.6 Verify clutch disengaged. This is due to the change of ) having one in-air source and one in-water source to } g having two in-water sources. The "old" in-air source has ) the elevator drive motor red tagged, with fuses removed, } I and will only be used as an in-water source. J 3.7 Verify the water level is above the blue line in the pool 3 area. ] I Ii, I
SC? MF-25 hev. 2 ?are 2 of 2 o l , - Appr ' d MF fW O /
- ste Sep-4-tar 2', 2005 3.5 Carefully raise the radiaticn detecter, which is hi..ged, -
to the upright vertical position to expose the detector. ) Expose this detector to a radiatica source that will. ) cause the alarm to sound which should cccur above 10 ) mrem / hour. ) 3.9 verify that the visual red flashing alarm unit is en and ) the audible alarm is sounding with the source in 3 pcsition. ) 3.10 Remove the scurce and verify that the. alarms are no ) lenger indicated. ] 3.11 Carefully 1cwer the detector housing back to its original ) positien. ) 3.12 Exit facility and secure teth d:crs. ) 3.13 Make appropriate entries in the logbook. ) 3.14 Return keys to Health Physics Office lock box. )
l I SOP HP-28 Rev. 4 Page 1 of 6 App r ' d ' b,1 i Date December 18, 1995 Exclusive Use 3 hip".67.0 Of FEdica0tive Materia'., LEA <5E;e 1.C EurDose and SCCDe E 1.1 This procedure establishes the requirements for making exclusive use shipments of Low Specific Activity radioactive waste. 1.2 Individual responsible for making the waste shipment must have dccumented training meeting the requirements 3 of 49 CFR 172 Subpart H. g 1.3 Persen respensible for this waste shipment E 1.4 Date of this . taste shi. ment r E 2.0 Procedure
2.1 Prerecuisites
A. Notify FJ Environmental Health and Safety of the Radioactive Waste Shipment. B. Material must not exceed the limits for a DOT Type A Quantity. C. Material must meet the definition of Radioactive Material - Low Specific Activity. D. Obtain a current ecpy of the recipients license and ensure that they are authorized to receive the quantity and form cf -'d' ---dva mmrar4=1 inc'udad in the shipment. E. Determine if any Lic to transport waste through or into any states en route. If state specific permits / licenses are necessary ensure that they are obtained and valid for the intended shipment.
50? MP-29 Rev 4 Page 2 of 6 Appr' d N(n5 ras / I J Cate Derarber 10, 2999 2.0 PrScedure 2.1 Prerecuisires t een-inu ed) - F. If a Broker or Brokerage Service is utilized ensure l that all necessary permits and licenses are i 1 possessed by the Broker. Ensure that the permits / licenses are valid and that the broker is , authorized to utilize them. l l 2.2 Packace celecrier and Leading: 1 A. Radicactive - LSA materials may be shipped exclusive , use in strong tight containers (STC's) . These l containers must not leak radicactive material under i ccnditiens normally incident to transportatien. I Initialling en this space indicates that the package l has been evaluated by MURR and that MURR has determined that it meets the definition of a strong tight centainer. , i B. Load the radioactive material into the strong tight container. Survey the material as it is leaded to ensure that package radiation levels will remain below the limits specified in 49 CFR 173.441. Tnese limits specify that a package loaded in an exclusive use closed transport vehicle may exhibit a surface radiation level of 1000 mrem /hr provided the following conditions are met. The dose rate on the external surfaces of the vehicle may not exceed 200 mrem /hr. The dose rate at 2 m from the outer lateral surfaces of the vehicle may not exceed 10 mrem /hr. The dose rate in any normally occupied region of the vehicle may not exceed 2 mrem /hr unless you have a private carrier with the exposed personnel wearing radiation dosimetry devices and the carrier operates under provisions of a State or Federally regulated radiation protection program. If the package is loaded onto an exclusive use open top vehicle then the package may exhibit a surface radiatien level of cnly 200 mrem /hr. The other dose rate li: Lits in the previcus paragraph continue to ) annly
SCP MP-29 Rev. 4 Page 3 of 6 Appr,d MLuf Date Decetber 18. 1995 2.0 Precedure l
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2.2 Packace Selection and Leadinr (centinued) l C. Ensure that the material is blocked and braced er otherwish secured within the package to ensure that CA the ladfmg will not shift under conditions normally l incident to transportation. l 1 D. Close the package using an appropriate closure , device. ! QA E. Visually inspect package to ensure that no damage j has occurred during loading evolutions. Ensure the package still meets the recuirements of a Strong Tight Centainer. Package survey: I 2.3 l A. Perform a contamination survey on the package. Contamination levels on the external surfaces of the package should be less than 6600 dp:/300 cm2 Beta / a, Gamma and less than 660 dpm/300 cm2 Alpha. g B. Perform a radiation level survey on all sides, including the top and bottom of the package. QA External radiation levels must comply with 49 CFR 173.441. These limits specify that a package loaded in an exclusive use closed transport vehicle may exhibit a surface radiation level of 1000 mrem /hr provided the following conditions are met. The dose rate on the external surfaces of the vehicle may not exceed 200 mrem /hr. The dose rate at 2 m from the outer lateral surf aces of the vehicle may not exceed 10 mrem /hr. The dose rate in any normally occupied region nf + ~^ icle ?v not = " c e n d ? -r a - * - g unless you have a private carrier with the exposed 3 personnel wearing radiation dosimetry devices and the carrier operates under provisions of a State or g Federally regulated radiation protection program. g I
[ SOP MP-29 Rev. 4 Page 4 of 6 Y J-Appr'o y f-M n 5 / ( Cate tece-ter 19, 1995 2.0 procedure [ 2.3 Packace 9urvev fcentinuedi- [ If the package is loaded onto an exclusive use open top vehicle then the package may exhibit a surface radiation level of only 200 T. rem /hr. The other dose rate limits in the previous paragraph continue to [ apply. Document this survey en a MURR survey form. Measure { the Transport Index (T:) cf the package. 2.4 Packace Markino and Labelino: A. Package shall be marked as "Radicactive - LSA". The packages are excepted from all specification labelling. B. Packages should have gross weight marked on the container. 2.5 Leadine the Packace on to the Cenveyance A. Package shall be loaded onto the vehicle by the consignor. B. Package shall be braced on the vehicle to prevent shifting during normal transportation conditions. C. There shall be no loose radioactive material in the conveyance. D. Perform a vehicle Radiation Survey. The dose rate on the external surfaces of the vehicle raf not QA exceed 200 mrem /hr. The dose rate at 2 m from the outer lateral surfaces of the vehicle may not exceed 10 mrem /hr. The dose rate in any normally occupied region of the vehicle may not exceed 2 mrem /hr unless you have a private carrier with the exposed personnel wearing radiation dosimetry devices and the carrier cperating under priv;sicna cf a State cr - Federally regulated radiation protection program. ~
l l SOP MP-29 Rev. 4 Page 5 of 6 Appr'd -- b'1 Date December 18. 1995 El l 2.0 Procedure j 2.5 Leadine the Packace on to the ccnvevance (centinued) - E. Perform a vehicle contamination survey. ! Contamination levels on the vehicle shuld be less l than 660 dpm/300 cm2 Beta / Gamma and less than 66 dpm/300 cm2 Alpha. 2.6 Placard the vehicle A. Transport vehicle must bear the Radicactive Placards on all four sides. g ; g! 2.7 Shippine Papers- ! A. Prepare a bill of lading and have it reviewed by a Certified Shipper. Certified Shippers Initials. B. The following reports shall acccmpany all shipments: Radioactive Shipment Manifest (RSM), Vehicle Radiation Survey, Bill of Lading, Emergency Response Guide and Exclusive Use Instructions. 2.8 Shipment Release I A. Notify the consignee that the radioactive material shipment is taking place. This notification may be made by telephone call or by FAX. Shipment approved for release by: Signature / Date B. Package released to carrier. I
SOP MP-28 Rev. 4 Page 6 of 6
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I Appr' d _ b'r/ > #/ Date Dece-Par 19. 1995 2.0 Frchedure (centinued) 2,9 E~ercenev Peseense Infor atien A. Deliver a copy of the Bill of Lading, RSM and Emergency Response Guide to the Control Room Emergency Response Book. [ (
I l I SO? MF-29 Rev. 3 Page 3 of 2
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- d ~ 'h% ! o . - i Cate serrerber 27, 1995 Mea?rh Frysics Meniscrir.: cf Fear Fer s fer Feactor 9 a r 'f r 1.0 Pelity )
It is'MURR policy to monitor the area around a beam port ) during the initial reactor start-up after work has been performed en a beam port which could increase the radiation levels in the area. 2.0 Purrere ) The purpose of this procedure is to assure that excessive ) radiation levels which might result from work at a beam port are detected and corrected immediately to avoid unwarranted l m radiatien exposure to persennel. 3.0 Procedure ) m 3.1 When the manager of Reactor Health Physics, the Reactor ) E ;' Manager, or their designee, determine it necessary, a . cualified persen shall be assigned to moniter the radiation levels at a beam port during reactor start-up j and rise to power. l 3.2 The Reactor Health Physics Group will assure that Reactor ) ll Operations is informed of the monitor assignment. 3.3 The monitor will be instructed as follows: ) l l A. Know and understand 10MW SOP, Volume 1, Section ) I . 4. 3 (I) and (J).
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B. Know and understand this SOP. ) C. Examine past surveys to be familiar with expected ) radiation levels. 3.4 While reactor power is increasing past critical the } monitor should: A. Be alert for radiation levels in excess of those ) anticipated. B. Be alert to warn persennel who approach the area of ] changing radiological conditions and, if considered
SOP MP-29 Rev. 3 Page 2 of 2 Appr'd M(~ N#5 Cate Setterher 27 1995 advisable to avoid unwarranted personnel exposure, request such persons to leave the area. C. If a radiation area is developing that would exceed- ) 100 mrem /hr or seems imminent, alert Control Room personnel and, jointly with the centrol room, decide ) on immediate action to be taken. D. When reactor is at full power, survey area to assure ) that a safe condition exists. E. Post the area consistent with Reactor Health Physics ) practice and Federal Regulations. ] F. Report results of survey to Control Rocm persennel ] before leaving Centainment Building. This report will normally be a verbal report followed on the next normal work day by a formal detailed survey report on the appropriate beam port survey map. l
SOP WP-31 Rev. 3 Page 1 of 7 Appr' d eN Date December 18. 1995 Personnel Indoctrination at MURR _.0 Policy All personnel with unescorted access to MURR shall have completed the indoctrination program to provide them with . basic information concerning their responsibility with regard 4 to the security, health physics.. and emergency programs at MURR commensurate to their level of access. 2.0 2.nr2m The purpose of this procedure is to define the indoctrination E' E ' prc4 gram and the associated recordkeeping. 3.0 Definitions 3.1 Sponsor Guidelines: A. Students - MURR supervisor
- 3. MURR personnel - Immediate supervisor C. Campus Facilities /Other contractors - Manager or Engineer, Facilities Operations D. Collaborators - MURR liaison 3.2 Levels of Security Access and Approval Signatures:
Level of Indoctrination Final Security Completed Approval Accessi Sicnature Lab / Limited HP HP Manager Lab HP HP Manager Containment w/o combination HP Reactor Manager Containment Reactor Manager 2 w/ combination HP 3 Reindoctrination Receptionist for any access or HP 1 Health Physics training levals include Non-Containment l E Limited, Non-Containment, Containment, and Beamport Area Access (see HP-35) 2 Normally upgraded following a period of time at Access Level " Containment w/o ecmbination" 3 Same as final approval for access level being renewed
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SOP MP-M Rev. 3 Page 2 of 7 Appr' d b 15 Date December 19, 1995 3.3 Temporary worker - individual not issued ID Badge with picture (see HP-24) due to werk assignments being temporary at !EIRR. Permanent worker - individual issued ID Badge with picture (see HP-34). 4.0 Procedure for T-dectrira-ion 4.1 Sponsors can consult the Health Physics' bulletin board to sign up individuals for scheduled indoctrination-times. Request for indoctrination must include individual's name, sponsor and level of access requested. 4.2 A member of the Health Physics staff will present the current indoctrination program. 4.3 The following pictures will be obtained: A. Temporary workers: Containment - two pictures (one picture required for control room photo file and one picture to be attached to original indoctrination form at reception desk). Laboratory - one picture.to be attached to original indoct rination form at reception desk. i l B. Permanent workers: l Containment - two pictures (one required for ! control room photo file and one required for I.D. Badge) and picture photo copy to be attached to original indoctrination form at reception desk. Laboratory - two. pictures (one required for I.D. . I Badge and one picture to be attached to 3riginal indoctrination form at receptic, desk) l 4.4 After indoctrination is complete, appropriate signatures will be secured on the indoctrination form and the person's access will be added to the appropriate access
. list .
4.5 The Reactor .Nanager will add the names of the new
SOP MP-31 l l Rev. 3 Page 3 of 7 I App r' d h bn h Date December 18, 1995 ! containment indoctrinees to the containtment list i maintained by the control room. 4.6 The Director's Office will add names of all new indoctrinees to the appropriate access list maintained by th'e receptionist. These access lists will be updated monthly or more often as necessary and copies distributed to: A. Health Physics, Manager (1 copy). B. Reactor Control Room (1 copy). C. Emergency Responsce clipboard in Lobby (1 copy). 4.7 The Director's Office will keep the file of the active indoctrination forms. 5.0 Precadure for Re-Indoctrination The Director's Office will generate a list of all persons on current access lists for whom it has been one year since their indoctrination or reindoctrination. 5.1 The Director's Office will contact sponsors to determine need for reindoctrination of personnel during the last week of the month prior to the month in which access ends. (See Item 6.0 for procedure for termination of access). 5.2 All persons needing reindoctrination will complete an annual reindoctrination with the EPs or be sent (on the last day of the month prior to the month which access ends): A. Cover letter from Reactor Manager. B. Indoctrination form. C. Indoctrination questionnaire. D. MURR indoctrination packet. 5.3 When the completed reindoctrination packet is returned to the Director's Of fice, the required signatures 'till be secured. The Director's Of fice will track signature
SOP MS-31 Rev. 3 Page 4 of 7 Appr'd b'1 Date December 19. 1995 process. 5.4 If the reindoctrination packet is not returned by the fourth week of the month in which reindoctrinaticn is due the Director's Office will contact the sponsors informing them of late paperwork. Memo #3 may be ured to make this contact. 5.5 The Director's Office will file the new indoctrination form and update the appropriate access list. The old indoctrination form and approved questionnaire will be marked with the reindoctrination date and returned to Health Physics. 5.6 Reindoctrinatien must be ccmpleted and approved by an HP if: A. Access is changed from Lab / Limited to Lab or to l Containment. B. Access is changed from Lab to Containment. C. Reindoctrination is net completed before 14 months following individual's last indoctrination or reindoctrination. D. Campus Facilities Custodial Services, Energy Management, or University Police personnel. 5.7 Health Physics staff will enter the reindoctrination information on the appropriate training forms. The g updated indoctrination forms and questionnaire will be l filed in the active personnel files. 6.0 . Termination of Access 6.1 Persons not requiring continued access to MURR will not be reindoctrinated after one year. I 6.2 Access .ay be terminated :r limite d 't ar-; time at the request of the Sponsor, Health Physics Manager or Reactor Manager. 6.3 Access shall-be terminated after 14 months following the date of the individual's last indoctrination or i reindoctrinaticn. Memo #2 may he distributed to sponsors advising them of their recourse if needed, and
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l SOP MP-31 Rev. 3 Page 5 of 7 App r' d I b5 Date December 18, 1995 j l 1 asking them to collect keys and ID badge. 1 6.4 The individual's sponsor is responsible for retrieving cutstanding ID badges. The Director's Of fice T.ay assist sponsors if needed by: A. First day of month in which access ends -- send i memo #1 to sponsors asking for them to retrieve i keys and/or ID badges. 1 B. First day of month in which access ends -- send I memo #4 to personnel who need to return keys and/or ID badges. 6.5 Those badges not retrieved will, be added to the list, maintained by the Director's Office, of badges
" Lost / Stolen /Not Returned". This list will be distributed on a monthly basis to:
A. Reactor Manager B. Health Physics Manager C. Reactor Physicist 6.6 The Director's Office will mark the terminated indoctrination or reindoctrination form " inactive", date, and return it to Health Physics along with individual's permanent ID badge. Health Physics will retrieve individual's photo from the Control Room photo file and place the form and photos in the individual's inactive personnel file.
SCP FP-31 Rev. 3 Page 6 of 7 Appr'd b *Y Date December 18. 1995 7.0 semela Memos MEMO #1 DATE: TO: FROM: Reactor Manager ] Below you will find a list of the persons that you sponsor who have been deleted from the MURR facility access list, per your request. ( A J This is for your informaticn cnly. No further action is necessary. ( B )You will need to contact the individuals to retrieve their identification badge. [C )You will need to contact the individuals to retrieve their keys. 1.{ ) 2.[ ] 1 3.[ ] l MEMO #2 l DATE: TO: FROM: Reactor Manager ) Below you will find a list of the persons that you sponsor who have been deleted from our facility access list. You were previously given notice that their re-indoctrination l packets were overdue, and we still have not received them. 1 All of them are severely past due for re-indoctrination. Note the "Date to Reindoc" at the bottom of the page. If you wish
- for any person on these forms to have access to the building, l please contact the Health Physics office to schedule a time for indoctrination. You will need to centact the individuals to retrieve their identification badge and/or keys.
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l . I: SOP MP-31 Rev. 3 Page 7 of 7 l Appr' d Date December 18, 1995 MEMO #3 DATE: g TO: g FROM: Reactor Manager ] I Below are the names of the people that you sponsor who have not completed or returned their reindoctrination questionnaire and MURR Indoctrination Form. Please notify l I these persons that their re-indoctrination packet is overdue and that unless it is returned immediately their access may be terminated. Thank you for your prompt attention to this 3l B i matter. g Past due Re-indoctrination packets: g 1 1.
- 2. El l
- 3. El MEMO #4 ;
DATE: 1 TO: ) FROM: Reactor Manager ] Our records indicate that your unescorted access to the E University of Missouri Research Reactor is no longer valid. 3 Please return the following items immediately to the address given below in the return envelope provided, postage paid. Please return the above item /s to Il i I 204 Research Reactor Columbia, MO 65211. If you have any questions, please contact the Senior Receptionist at 314-882-4211. I Il 1
SOP HP-34 Rev. 2 Page 1 of 3 Appr'd Date December 18, 1995 MURR' Identification Badge Program and Implementation 1.0 Policy All personnel with unescorted access to the f acility shall wear I.D. badges to aid in maintaining 'the security of the MURR facility by preventing unauthorized access. 2.0 Purpose To provide guidelines and policies for the use and issue of identification badges at the MURR facility. 3.0 general Personnel at the facility will be issued I.D. badges based en level of access, purple for centainment access and green for lab access. Personnel having containment combination access will be identified by a special hole punch in the white side of the badge. This will assist in maintaining positive control of the combination. Along the bottc= of the badge the individual's name and group affiliation will be printed. Temporary badges will also be available for use as spares and for personnel who have unescorted status but visit the site infrequently. These badges will appear much like the permanently assigned badges with the following exceptions: in place of a photo the word " TEMP" will be visible; and instead of a name a serialized number will be used for identification at the bottom of the badge These will be maintained at the Front Desk and in the Control Room and will be logged out as needed. Personnel requiring an escort will be recognizable by their lack of-an I.D. badge. All personnel at the facility without an I.D. badge shall be escorted by badged personnel. 4.0 Responsibility Inside the facility, I.D. badges are to be worn at all times and shall be worn visibly on the front of the body. Supervisors will be responsible to ensure that people in their group wear their badges.
I I SOP MP-34 Rev. 2 Page 2 of 3 Appr' d
- b Date December 18. 1995 Lost, misplaced, or defaced badges will be replaced at a cost of 52.00 (cost of materials) for the first replacement and S5.00 each subsecuent replacement. Chronic loss or forgetting a !
of badges.will be reviewed and could result in loss of access to the facility. E' During nonworking hours each person will be responsible for ' the safe, secure keeping of the issued I.D. badge. Badges shall be kept in a manner which will preclude theft or misuse of this identifica icn material. They should not be hung from 3 rear view mirrors or left on car seats or in any unsecured 3 area where theft could occur. At the time of termination of access to the MURR facility, the l individual and sponsor will ensure that the I.D. badge is j turned in to the receptionist for proper disposition. l Any unescorted personnel inside the facility without an I.D. E f badge shall be challenged and the Control Room notified of the j unauthorized entry. The individual shall then be escorted to g; the lobby for interrogation by the receptionist or reactor gI cperator. This applies as well to a person with lab access i I.D. badge found unescorted inside containment. 5.0 Precedure = Persons desiring unescorted access will be photographed g following indoctrination and the photo will be used to produce 3 an identification badge. New personnel with complete indoctrination paperwork may be given a temporary I.D. badge g while awaiting permanent I.D. badging. The new personnel g should normally receive their permanent I.D. badge within a week. The designation of combination access will be made by the Reactor Manager. As such, the tool used to delineate this will be maintained in the Control Room. Once an individual g is on the list of persons authorized to have containment g entry, the operators will be able to give the combination and make the designation symbol on the I.D. badge. During normal working hours, issuance of temporary I.D. badges will be done at the Front Desk in the lobby. The receptionist will verify the individuals access level and then log cut by g serial number a temporary badge to the person based on access 3 I
SOP HP-34 i I 3 of 3
- Rev. 2 Page Appr' d M 6N Date December 18, 1995 J
level. After normal working hours temporary badges shall be , obtained by contacting the Control Room (882-5213). The ] j
- operations personnel on shift will verify access level and ,
, issue the appropriate I.D. badge and log the badge out to the l individual. Temporary badges shall be returned at the end of the use to the respective issuing place. i 1
-- sop "P-36 Rev. 1 Pace 1 cf 3 ,
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f / 4-d'rM l Date sertember 25, 1995 1 Remete Sampling of Centairment Air 1 1.0 Pelicy ) )! l When containment isolation has occurred and there is ' indicatien that airborne centaminatien exists, an estimatien of radioactive airborne concentration shall be made before ) i reentry of personnel into containment, except for cases of life-saving and accident ritigating activities (SEF-11). 2.0 Purrese ) This procedure will be used to obtain air sample (s) using the remote containment sampling station. The sample (s) will then ' be analyzed to estimate radioactive airborne concentratica ) levels pric: to reentry cf perscnnel into containment. ,
) l 3.O S.c.c;;a This precedure will apply in cases where airborne E centamination is suspected following containment isolation. g, Airborne contamination will be suspected by increased stack monitor readings (s) , sustained increases in several of the ARMS readings, or by the circumstances leading to the isolation. This procedure will not be required in the cases of life-saving and accident mitigating activities (SEP-11).
4.0 Procedure ) 4.1 The remote sampling station is located in the basement ) area next to the pneumatic tube blower system. A schematic for the remote sampling station is shown in Figure 1. 4.2 Request DANGER tags on BLR 1,4 he removed by the Control ) l Room. (These DANGER tags are normally hung for ) l Containment integrity) ] 4.3 Check shut BLR valves 5, 6, and 7. Open BLR valves ) 1,2,3, and 4. Start the pump, and allow the pump to ) recirc for 5 minutes to flush the system. Monitor dose ) rates at the pump during recirculation. ] I l I l
I i SOP MP-?6 l l Rev. 1 Pa a 2 ~ of ? j kppr'd & i Date Sectemb=r 25, 1995 i i 4.4 With the pump still running, connect evacuated air sample ) { can to connection located at 51R-7. Open ELR-7 to obtain ) l containment air sample, then prcmptly shut 3LR-7 If ) ! required then secure system by securing. pump, and ) l shutting 3LR 1,2,3, and 4. ) l 4.5 Analyze. sample can via gamma spectrosecpy to identify ) l 1sotopic contamination and estimate radioactive airborne ) ! concentration levels in containment air. This ) { information will be included in the review of precautions ) required for reentry into containment or recovery from ' containment isolation. 4.6 This remote sampling station may also be utilized with in ) l other types of air sampling devices, such as particulate
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and charcoal filters. } j l 1 i l l
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I I SOP HP-36 Rev. 1 Pa e 3 of 3 ! Appr' d 5 h//3 $ Date Sectember 25, 1995 I I CONTAINMENT MANOMETERS SENSING LINE l REFERENCE CANS f INSIDE CONTAINMENT ll c X : :>< y BLR-4 BLR-6 BLR-3 X X
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8LR-1 BLR-5 L_j
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X BLR-2 g
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BLR-7 l I H.C.- HOSE CONNECTION g BLR - BUILDING LEAK RATE PUMP E Figure 1. Remote Sampling Station for Containment Air I I I
i i SCP "P-40 .i 1 Rev. O Page 1 of 4 n App:'d a, Cate 4/25/95 Survey of_:: ems fcr Unrestri::ed Felease 1.3 Policy
'To ensure that radicactive materials are n:: inadvertently removed from the MURR Center, cer: sin materials must be surveyed prior to their release. The level of survey depends upon where the materials have been located in the Center.
2.0 Purro=e and scese 2.1 The purpcse of this precedure is to p cvide guidance en the level of survey to be performed en materials destined for unrestricted release frem MURR. It also provides guidance on the proper techniques to be utilized when perfcrming these surveys for unrestricted release. 2.2 The scope of this procedure enecmpasses all items. removed from the MURR Center. A. Equipment and supplies which have been' located in posted Radioactive Materials Areas shall be surveyed by the Health Physics Group prior to release from the Center. Items in a posted area which were under the control of the user the entire time they were in 1 the posted area and which were never used in the vicinity of loose radicactive material may be removed from the Center without Health Physics Survey provided they are carried through the Center Portal Monitor as described in section 3.3. B. Refuse from the Center shall be surveyed by the l Health Physics Group or other appropriately trained l members of the Center .Staf f prior to disposal. C. Items which have never been 1ccated in a posted area may be removed f ron the Center without a survey provided the individual reroving the iten has full knowledge of the histcry of use cf the item and that q , history does not include any use in posted areas.
I S;P MF-4' I Rev. O Page 2 ef 4 Appr'd v
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E Date 4 /25 /C5 3.0 Procedure 3.1 The type cf survey to be perfermed en a specific item depends upcn the physical attributes of the item tsize, I weight, etc.) as well as the physical attributes cf g potential centaminants (i.e. pure beta emitters, Icw energy gar.a emitters, alpha emitters, etc.). Determinatien of the prcper survey technique shall be made by a me:r.ber of the Health Physics Staf f. 3.2 A direct f risk with a thin window GM instrument is the most ccmmen survey technique chosen for unrestricted release of material frca the MURR Center. Direct frisk surveys shall be performed in an area of low ambient 3 background. The instrument should be set en the Icwest g scale that does not alarm at ambient backgrcund count rates. An audio cutput is highly desirable for , performing surveys at background or near background Count rates. A. It is the respensibility of the surveyor to ensure j that the instrument chosen is both calibrated and ! operational. B. The survey shall be performed in the following manner. The thin window probe should be located approximately one inch from the surface being surveyed. The probe should be moved very sicwly l (approximately 1 inch per second) over the area being checked. Internal surfaces of items shall be checked as well as external surfaces. 3.3 An acceptable alternative to a direct frisk survey is to use the portal monitor as a surveying instrument. This is particularly useful for tools. A. A portal monitor survey may be conducted by holding the item in ene's hand near a single portal meni:cr g detector or placing the item (s) en the b:: tem grill 5 of the instrument .hile it performs it' s ccunt . If relatively dense items are being surveyed by this E technique then it may be appropriate to rotate the g item and repeat the survey to ensure all sides are I adequately surveyed. I
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? ppr' d h/h Date 4/25/95
- 3. If the portal moniter alarms during this survey then the items shall be brcugh: :o the Health Physics Office for a survey as cu: lined in secticn 3.2.
3.4 Suspected ncn-radicactive refuse may be surveyed by the folicwing technique pric: to placing it in the facility dumpster. A. This survey may be performed by personnel trained and approved by Health Physics.
- 3. These materials shall be placed on the base of the portal menitcr, if their si:e allows, and a portal count initiated by blocking the range finder with one's hand.
C. If the portal .cni cr alarms during this survey then the item shall be brough: to the Health Physics Office for a survey as outlined in section 3.2. D. If the materials to be disposed are too large to fit in the portal monitor they should be brought to the Health Physics Office for a survey as outlined in sectica 3.2. 3.5 Materials which have been located in the alpha laboratory or which may reasonably be expected to be contaminated by alpha emitting isotopes shall be surveyed by the following technicue. A. A direct f risk of the material with a Zns scintillation instrument is the survey technique of choice for items which fit into this category. The surveyor should ensure that the instrument chosen is bcth calibrated and cperational.
- 3. The ZnS scintillation probe should be located no f greater than one-half inch from the surface being surveyed. The prebe shculd be moved very slowly over the area being checked. The sweep should be slow enough to cover only the width of the monitor I every 2-3 seconds.
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- ste e/29/09 C. Due to the extrenely short range of alpha particles i the items should be dry and no attenuators should be l present between the surface being frisked and the j monitor. l 3.6 Items noted to produce a positive indication of radioactivity above background levels will not be E unconditionally released. They will be placed in 5 storage for further evaluatien, transferred to another licensee er transferred to radicactive waste.
3.7 All radioactive material labels shall be removed er obliterated prior to unrestricted release from the Center. 3.8 In the event that competing survey technicues provide different results then the most conservative result will E' be accepted. (i.e. If the portal indicates centaminated 3 but a direct frisk indicates uncontaminated then assume the material is contaminated.) l Il I I I I I I
l I I SOP MP-41 ; e 1 ! Rev. O Page_ 1 of 4 l Appr'd bneM ' l Date December 18. 1995 i Non-Exclusive Use Shipment of Radioactive Material, LSA, Kaste L 1.0 Purpose and Scepe
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l 1.1 This procedure establishes the requirements for making l nonexclusive use shipments of Low Specific Activity , radioactive waste. 1.2 Individual responsible for making the waste shipment 1 must have documented training meeting the requirements ; of 49'CFR 172 Subpart H. l 1.3 Person responsible for this waste shipment l I 1.4 Date of this waste shipment . ; I c 2.0 Precedure l 2.1 Prerecuisites-I l A. "ctify MU Environmental Health and Safety of the I Radioactive Waste Shipment. i
- 3. Material must n:t axceed ths lirit frr s DCT Type A l Quantity. l C. Material must meet the definition of Radioactive Material - Lcw Specific Activity.
D. Obtain a current copy of the recipients license and ensure that they are authorized to receive the L quantity and form of radioactive material included in the shipment. E. Determine if any Licenses or Permits are necessary l to transport waste through or into any states en route. If state specific permits / licenses are necessary ensure that they are obtained and valid for the intended shipment. 4 O
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I I SCP "P-41 Rev. O Page 2 of 4 I Appr'd -- ">N rate Dacerber 19. 1995 F. If a 3rcker er 3rckerage Service is utilized ensure that all necessary permits and licenses are pcssessed hy the 3rcker. Ensure that the 3 permits / licenses are valid and that the broker is E authorized to utilize them. 2.2 Packace Selection and Leadinc: A. Radioactive - LSA materials which are not shipped exclusive use must be shipped in a DOT Specification E 7A package. Initialling en this space indicates that 3 the package has been evaluated by MURR and that MURR has determined that it meets the definition of a DOT g Specification 7A container. Initialing this space E also indicates that MURR has a ccpy of the package certification on file. B. Load the radioactive material into the DOT Spec 7A container. Survey the material as it is loaded to ensure that package radiation levels will remain 3 below the limits specified in 49 CFR 173.441. These g limits specify that each package of radioactive material offered for transportation shall he prepared for shipment so that under conditions normally incident to transportation the radiation level does not exceed 200 mrem /hr at any point on the external surface of the package a.nd the E transport index does not exceed 10. 5 C. Ensure that the material is blocked and braced or g otherwise secured within the package to ensure that g QA the lading will not shift under conditions normally incident to transporf.ation. D. Close the package uning an appropriate closure device. QA E. Visually inspect the package to ensure that no damage has occurred during leading evolutions. I
SOP MP-41 Rev. O Page 3 of 4 Appr' d n Date December 18, 1995 2.3 Packace survey: A. Perform a contamination survey on the package. Contamination levels on the external surfaces of the package should be less than 6600 dpm/300 cm2 Beta / Gamma and.less.than 660 dpm/300 cm2 Alpha. B. Perform a radiation level survey on all sides, including the top and bottom of the package. QA External radiation levels must comply with 49 CFR 173.441. These limits specify that the radiation level shall not exceed 200 mrem /hr at any point en the external surface of the package and the transport index shall not exceed 10. Attach a copy of the package survey to this check sneet. 2.4 Packace Markirc and labeline: A. The package shall be labeled with the appropriate category radioactive material labels. Two labels should be applied, cne each on opposite sides of the package. Appropriate entries should be made on the chosen category labels. If subsidiary risk labels are necessary then they should be applied in the immediate vicinity of the appropriate radioactive labels. l B. The package shall be marked with the proper shipping name and UN number: Radioactive Material, LSA, n.o.s. UN 2912. RQ should be displayed on this marking if the activity in the package represents a reportable quantity. C. The package shall be marked with an address label with the address of the consignee and the return address of MURR. D. The package shall be marked with the gross weight. E. The package shall be marked with " USA DOT 7A Type A" ) )
I SOP MP-41 I Rev. O Page 4 of 4 Il ' Appr' d EM Date _ December _9, 1995 1 l 2.5 Shipoine Papers- ) A. Prepare a bill of lading and have it reviewed by a Certified Shipper. Certified Shippers Initials. B. The following reports shall accompany all shipments: Radioactive Shipment Manifest (RSM), Bill of Lading and the appropriate Emergency Response Guide, g i 2.6 Shioment Release ll A. Notify the consignee that the radioactive material shipment is taking place. This notification may be made by telephone call or by FAX. Shipment approved for releasa by:
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Signature / Date B. If the package is category Yellow III then the transport vehicle requires placards. If this E shipment is classified as requiring a Yellow III E label then placards shall be offered to the courier and the following statement must be signed by the courier. I accept this shipment and certify that I have been offered radioactive placards at the time this package was offered for transport. Couriers Signature /Date C. Package released to carrier. 2.7 Emercency Resconse Information
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A. Deliver a copy of the Bill of Lading, RSM and Emergency Response Guide to the Control Rccm Emergency Response Book. I I
MURR SHIPPING PROCEDURES MURR-SAS-00000 Revision Number 2 Revision Date: 7/12/95 Pace Number 6 of16 7 of16 8 of16 9 of16 13 of16 14 of16 l 15 of16 I I MURR-SAS-00002, Revision No.1, dated 8/9/95: Deleted Precautions / Limitations l and Definitions which were inserted into MURR-SAS-00000. I MURR-SAS-00003, Revision No.1, dated 8/17/95: Deleted Precautions / Limitations l and Definitions which were inserted into MURR-SAS-00000. I 11-10
Mt'R R-SAS-00000 Service Applications Departmental Administrative: Shipping 2.20 Ensure that all beta-gamma dose rate survey equipment and . meter stick calibration stickers have not passed the calibration due date prior to use. 2.21 The requirements for each package containing fissile material shall comply in accordance with 49CFR. 2.22 Shipping activity: The Irradiation Project Specialist or his designee is responsible for the activity listed on all shipments and should report all radionuclides to the 90th percentile of activity at the time of shipment. 2.22.1 In the absence of the Irradiation Project Specialist, the following individuals are qualified to approve shipment I activities;
- Processing Project Specialist I
- Service Applications Engineer Manager Health Physics
- Project Specialist of Radio pharmaceuticals 2.22.2 The Irradiation Project Specialist may designate a list of samples by company and target, whose activity may be derived by means of Capintec or equivalent measurement.
2.22.3 The Irradiation Project Specialist may designate a list of individuals who are authorized to approve shipment activity for secondary samples. I 2.23 Guidance Limits for various Health Physics operations: I Reactor Pool Operations l I Topaz Cans - 300 mR/hr to remove from reactor pool. 150 mR/hr to open can. III I Silicon - 300 mR/hr for a bin. 500 mR/hr for a bin on Thursdays. I1I I 100 mR/hr for a single can. 400 mR/hr for silicon spacer. Air loads - 10 R/hr. III I MUGGS /QUEGS - 300 mR/hr. I I Hot Cell cask - 5 R/hr Rev.02 SA N llP r/E Date: 12. July 1995 MURR-SAS-OOOOO page 6 of 16 REFERRAL USE PROCEDURE
MURR-SAS nn000 Service Applications Departmental Administrative: Shippina I 1 2.24 QA files shall be maintained for cath piece of test and calibration i i equipment used as part of the QA/QC Program showing the Justification for: I 4 1
- Frequency of calibration, I
- Traceability to nationally recognized standards I
- Copies of all past calibrations.
I 2.25 QA instrumentation used in connection with the QA/QC Program shall j i contain a calibration sticker affixed to the instrument containing: 1 i
- Instrument model number, I e Instrument serial number, I
- Calibration date, i e Calibration due date. ;
I 2.26 QA instrumentation used by the QA/QC Program shall not be used unless the I calibration sticker is current. I 2.27 QA Performer / Inspector: Must be approved by the QA Supervisor. I 2.28 QA Procedures that call for the use of QA calibrated equipment must l l contain the statement: "QA Calibration Required" to the procedure step I calling for the use of the instrument. I 2.29 QA Procedure Control Check Sheet must be written for the calibration of I each instrument used in association with QA Procedures. I 2.30 Quality Assurance (QA) 10CFR71.101(a): Requirements applying to design, I fabrication, handling, shipping, storing, cleaning, assembly, inspection, I testing, operation, maintenance, repair, and modification of components I of packaging which are important to safety. I 2.30.1 Comprises all those planned and systematic actions necessary to I provide adequate confidence that a system or component will perform I satisfactory in service. I 2.31 Training: 10CFR71.105(d): The licensee shall provide for I indoctrination and training of personnel performing activities affecting I quality as necessary that suitable proficiency is achieved and maintained. I I The licensee shall review the status and adequacy of the quality g i assurance program at established intervals. 3 I 2.31.1 Training Requirements for the Inspectors: Shall demonstrate thorough g I expertness in the practice of each specific item the Procedure and g I Control Check Sheet to the Quality Assurance Supervisor. I I IIP M Date: 12 July 199S MURR-SAS-00000 page 7 of 16 Re. 02 SA REFERRAL. US!! PROCEDURE I
MURR-S \S Oo000 Service Applications liepartmental Administrative: Shipping i 2.32 Inspector's qualification shall be recorded on that individual's QA I Qualification Card, and the name submitted to the Reactor Manager for I inclusion on the authorized inspector's list. I 2.33 Procedure Control Check Sheet: hiust be written and used for all the I Quality Assurance Program (s). 1 2.34 Procedure Control Check Sheets must be initialed by a QA Approved I Performer / Inspector as the specific steps of a procedure are performed. I 2.35 RTS Technology, Inc.: Must certify in writing that the cask was ready in all I respects for loading when it was shipped to MURR. I 2.35.1 RTS Technology procedure does not cover Quality Control (QC) in I respects to repair or maintenance of the shipping container as all I repairs must be performed by RTS Technology, Inc. I 2.36 All routine maintenance shall only be accomplished in accordance to I Quality Controlled Procedures relating to the physical characteristics I and quality of the material or components to be used to predetermined I requirements. 1 2.37 Amersham Procedure Control Check Sheet: Must be written and I used for the Quality Assurance Program for the Amersham i GB/0924BP/B(U). I 2.37.1 Amersham must certify in writing that the cask was ready in all I respects for loading when it was shipped to MURR. I 2.37.2 This procedure does not cover Quality Control (QC) in respect I to repair or maintenance of the shipping container as all I repairs must be performed by Amersham International. I 2.37.3 Routine maintenance shall only be accomplished in accordance I to Quality Controlled Procedures relating to the physical I characteristics and quality of the material or components to be used I to predetermined requirements. I 2.38 Procedure Control Check Sheet: Must be written and used for I the Quality Assurance / Quality Control Program for the i USA DOT 20WC 1 Container. ( [ [ Rev.02 SA d llP d Date: 12 July 1995 MURR-SAS-00000 page 8 of 16 REFERRAL USE PROCEDURE
MURR-SAS 00000 Service Applications Departmental Administrative: Shippinn 3.0 SERVICE APPLICATIONS-SHIPPING: DEFINITIONS 3.1 A1: The maximum activity of " SPECIAL FORM" Radioactive material permitted in a Type A package. 3.1.1 Values of Al for most Radionuclides are given in 49CFR and IATA Regulations. 3.2 A2: The maximum activity of Radioactive material, other than "Special Form" Radioactive material, permitted in type A package. 3.2.1 Values of A2 for most Radionuclides are given in Tables of 49CFR and IATA Regulations.
3.3 Activity
Is a measure of the quantity of radioactivity emitted by a radioisotope and is used to determine the amount of radioactive material which may be transported in various types of packaging. 3.4 Becquerel (Bq): Is the standard unit of measure for the Radioactivity of a Radionuclide used in IATA, Dangerous Goods Regulations. One E Bq equals one decay per second. E 3.4.1 Gigabecquerel (GBq): One GBq = 1,000,000,000 Bq or 1E9 Bq. 3.4.2 Terabecquerel (Tbq): One TBq - 1,000,000,000,000 Bq or 1E12 Bq. 3.4.3 The Bq replaces the older unit for activity, the Curie (Ci). ! 3.4.4 One Ci is equal to 37 Gbg. 3.5 Conversion Factors: Table shows conversion facters to four significant figures. 3.5.1 To convert To Multiply by: Ci GBq 37.00 TBq Ci 27.03 1 3.6 Excepted Packages: Limited quantities of radioactive materials, instruments and articles, articles containing natural uranium or I I thorium and empty radioactive materials packaging as specified in 49CFR.
3.7 Experiment
Is any device or material which is exposed to significant radiation from the reactor and is not a normal part of the reactor or any operation designed to measure or monitor reactor characteristics or parameters. 3.8 External Contamination: Is the non-fixed Radioactive contamination on any external surface of any package. it must be kept as low as practical and, under normal condition 3 of transport, shall not exceed the levels specified in 49CFR and 3 Date: 12 July 1995 MURR-SAS-00000 page 9 of 16 Rev.02 SA.3d. IIP REFERRAL USE PROCEDURE I
Ml!RR-SAS-00000 Service Applications Departmental Administrative: Shipping 3.24 Primary Processed Samples: Samples that have been under continuous Service Applications-Shipping Control after removal from reactor. I 3.2 S QA Control of measuring and test equipment 10CFR71.125: The licensee shall I establish measures to assure that tools, gauges, instruments, and other i measuring and testing devices used in the activities affecting quality are I necessary limits. I 3.26 Quality Assurance (QA) 10CFR71.101(a): Requirements applying to design, I fabrication, handling, shipping, storing, cleaning, assembly, inspection, I testing, operation, maintenance, repair, and modification I of components of packaging which are important to safety. I 3.26.1 Comprises all those planned and systematic actions necessary to i provide adequate confidence that a system or component will perform I satisfactory in service. I 3.27 Quality Control (QC) 10CFR71.101 (a): Quality assurance includes quality I control, which comprises those quality assurance actions related to control I of the physical characteristics and quality of the material or component to I predetermined requirements. 3.28 Radioactive Contents: The radioactive material together with any contaminated solids, liquids and gases within the package. 3.29 Radioactive material: 3.29.1 DOT: Any material having a specific activity greater than 0.002 micro curies per gram (uCi/g). 3.29.2 NRC: " Specific activity" of a radionuclide, means the activity of the radionuclide per unit mass of that nuclide. The specific activity of a material in which the radionuclide is essentially uniformly distributed is the activity per unit n' ass of the material. 3.30 Sample: Is a chemical or physical makeup of the target material or combination of target and encapsulation. 3.31 Sample Log Books: These log books (two) are located in the Control Room and designated as the:
- Flux Trap, III, and BPLS (Bulk Pool Lead Shield) Book and,
- Silicon Book.
The log books are broken down into sections designated to correspond with the reactor irradiation and in-pool storage area. 3.31.1 " Sample Run Sheets" are placed in the appropriate Section of the log books during irradiation of the sample, after which, they are moved to the Storage Section. Rev.02 SA 2 ilP d Date: 12 July 1995 MURR-SAS-00000 page 13 of 16 REFliRRAl. USE PROCEDURE
l MURR-SAS.( o000 Service Applications Departmental Administrative: Shipping 3.31.1.1 The stored position is recorded on the Sample Run Sheet. 3.31.1.2 The Flux Trap, lil, and BPLS Book consists of the following sections: i Flux Tray Loading Sheet, Tube A, Tube B, Tube C, Ill, BPLS (Bulk Pool B l Lead Shield), Bisco, Storage, Reuter Stokes, and Samples in use. m 3.31.1.3 The Silicon Book consists of: J-1, K-2, R (Red, also known as "J") LL3, L 3 positions, N positions, B (Blue, also known as 1). Y (Yellow, also known g as II), G (Green also know as G), Bin Storage, and Sample Storage. ! 3.32 Secondary Processed Samples: Samples that are directly submitted for shipping by RPG, NAP or HP. 3.33 Shall. Must. Should: 3.33.1 Shall: Regulatory Commitment to Code of Regulations,10CFR,49CFR and IATA Dangerous Goods Regulations. 3.33.2 Must: MURR Internal Commitment to 10CFR,49CFR and IATA Regulations. l 3.33.3 Should: Should be accomplished; not required. 3.34 Shipping container: To contain the sample (s) during transport: Can'be a lead a pig (2 LB. to 30 LB), or a depleted uranium shield. E; 1 3.35 Spacer: Used to take up space in the host can to minimize capsule movement. 3.36 Special Form Radioactive Material: Radioactive Material is either an in-dispersible solid Radioactive Material or a sealed capsule containing Radioactive Material. 3.36.1 Special Form Radioactive Material shall meet the requirements of 49CFR l and IATA Regulations. 3.361.1 If it is in a sealed capsule, that capsule shall be so constructed that it can only be opened by destroying. 3.36.1.2 The Special Form Radioactive Material shall have at least one dimension not less than S mm. 3.36.1.3 The Special Form design shall have received unilateral approval. I 3.37 Training: 10CFR71.105(d): The licensee shall provide for indoctrination I and training of personnel performing activities affecting quality as I necessary that suitable proficiency is achieved and maintained. I l I Rev.02 SA IIP b Date: 12 July 1995 MURR-SAS-OOOOO page 14 of 16 REFERRAL USE PROCEDURE I
MURR-SAS-00000 Service Applications Departmental Administrative: Shipping I 3.38 Training requirements for the Performer and Inspector: Shall demonstrate thorough expertness in the practice of each specific item in i the Procedure and Control Check Sheet. 3.39 Specific Activity: The activity of the radionuclide per unit weight of that nuclide. 3.40 Transfer Cask: Used to transport samples within the facility. 3.40.1 Orange Roll Up cask is included as a transfer cask. 3.41 Transport Index Meter Stick: A ruler; one Meter (39.370 inches) in length. used to determine the Transport index Number. 3.42 Transport index Number (TI), Radioactive Material Only: The dimensionless number (rounded up to the first decimal place) placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. 3.42.1 The Tl number is determined by 49CFR and IATA Regulations. 3.42.2 The transport index is determined as follows: 3.42.2.1 The number expressing the maximum radiation levelin 1 millirem per hour at one meter (3.3 feet) from the external surface of the packaging; or, 3.42.2.2 For fissile class Il packages or packages in a fissile 111 shipment, the number expressing the maximum radiation level at one meter (3.3 feet) from the external surface of the package, or the number obtained by dividing 50 by the I allowable number of packages, which may be transported together, whichever is larger. 3.43 Type A Packaging: A type "A" package must not contain activities greater than the following: 3.43.1 For "Special Form" Radioactive Material the value of Al is listed in Tables of 49CFR and IATA Regulations. 3.43.2 For other Radioactive Material the value of A2 is listed in I Tables of 49CFR and IATA Regulations. 3.44 Type B Packaging: The only limits on the activities contained I in type B packages are those prescribed on their approval certificates in accordance with the Code of Federal Regulations,10CFR and 49CFR. i Rev.02 SA M HP M Date: 12 July 1995 MURR-SAS-00000 page 15 of 16 RiiFl.RRAL USE PROCL DURii
SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT 1 January 1996 through 31 December 1996 During the past year, Reactor Operations staff has made a concerted effort to update and make corrections to the Hazards Summary Report. These changes were reviewed by licensed staff and by members of the Safety Subcommittee and have been determined not to involve a change in Technical Specifications or an unreviewed safety question as defined in 10CFR50.59. HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1,1965) Original HSR, page 84, Section 3.2.8, paragraph 1, sentence 1: Dalgia' 'The pneumatic tube system components entering the reactor containment consist of nine lines, . . . ." Replace with: 'The pneumatic tube system components entering the reactor containment consist of eight lines, . . . ." Original HSR, page 84, Section 3.2.7, paragraph one, sentence 3: Delsta: "'Ihis 16 inch pipe has a 12 inch collar . . . ." Replace with: "This 16 inch pipe has a 12 inch long collar . . . ." Original HSR, noge 8 7, Section 8.2.8, paragraph one, sentences 3 through end of section: (This revision also replaces 1988 mvision.) Delata: Sentence 3 through end of section. Reolace with:
" Located within the containment building on the fifth level in the mechanical equipment space (Figure 3.3) is an emergency air compressor. This emergency air compressor normally
" rides" on the main air supply line until there is a drop of pressure in the main air line to less than 85 psi. At that time the small emergency air compressor comes on and a check valve closes off all of the compressed air system external to the containment building. This emergency air compressor, under these circumstances, carries the air requirements within the containment building. The compressed air supplied by one or the other of these two separate systems is maintained in accumulator tanks located on the compressor and goes from these tanks by meane of a piping system to a pressure reducing and regulation system to provide the motive force for the inflated gaskets.
This system is equipped with check valves and automatic starters such that if there is a failure or loss of compressed air fkom the main unit, the emergency air system will come on and carry the inflat able gaskets and any other air controlled devices associated with the reactor.
'Ihe emergency sir compressor is also connected to the emergency diesel generator in the event c(electrical pont failure."
III-1 l
l Original HSR, page 3 9, Section 3J, paragraph 2, sentence 1: Delete "The containment system integrity is compromised only during reactor shutdown and only then . . . ." l Renlace with: "The containment system integrity is compromised only when the reactor is secured and only then . . . ." Original HSR, page 311, Figure 3.1; 1990-1991 Annual Report Revision: . 1 Renlace with: Updated Figure 3.1--Basement Level (MURR Dwg # 2269, Sheet 1 of 3, dated 10/25/93) Original HSR, page 312, Figure 3.2; 19901991 Annual Report Revision: Renlace with: Updated Figure 3.2--Grade Level Plan (MURR Dwg #2269, Sheet 2 of 3, dated 10/25/93) Original HSR, page 313, Figum 3.3: Renlace with: Updated Figure 3.3-Third, Fourth and Fifth Level Plan (MURR Dwg #2269, l Sheet 3 of 3, dated 10/25/93) Original HSR, page 314, Figure 3.4: Renlace with: Updated Figure 3.4--North and East Elevations (dated 1/3/95) l Original HSR, page 3-15, Figure 3.5: Renlace with: Updated Figure 3.5--South and West Elevations (dated 1/3/95) Original HSR, page 318, Figure 3.8; 1971-72 Annual Report Revision: Renlace with: Updated Figure 3.8-Cooling Tower Building at Grade Plan (1/3/95) Original HSR, page 41, Section 4.1, paragraph 2, sentence 1: Delete- "The fueled region is an annulus of a right circular cylinder with a nominal inner radius of 2.77 inches and an outer radius of 5.81 inches." Reninee with: "The fueled region is an annulus of a right circular cylinder with a nominalinner radius of 2.67 inches and an outer radius of 5.88 inches." Original HSR, page 4-2, Section 4.2, paragraph 2, sentence 2: Delete: "The overall radial dimension of an assembly is 3.28 inches." Renlace with: " The overall radial dimension of an assembly is 3.21 inches (as determined from radial length from inside ofinner roller to outside of outer roller)." Original HSR, page 4-2, Section 4.2, paragraph 3,last sentence: Delete: "The radius to the innermost plate is 2.77 inches and to the outermost plate is 5.76 inches." Renlace with: "The nominal radius to the innermost plate is 2.77 inches and to the outermost plate is 5.76 inches." III-2
Original HSR, page 4 9, Table 4.1: Delete- Average Specific Power 0.962 MW/Kg (25) at 5 MW 1.613 MW/Kg (25) at 10 MW Ranlmee with- Average Specific Power. 0.962 MW/kg (235) at 5 MW 1.613 MW/kg (235) at 10 MW Delete: Initial Fuelleadings 5.2 Kg (25) for 5 MW cores 6.2 Kg (25) for 10 MW cores Ranime wia- Initial Fuel Ioadings 5.2 kg (235) for 5 MW cores 6.2 kg (235) for 10 MW cores Delete- Uniform Critical Mass App. 2.6 Kg (25) Renlace with: Uniform Critical Mass App. 2.6 kg (235) Original HSR, pages 4-9, Table 4.1; 1981-82 Annual Report Revision: Delete: Max. k.g With One Stuck Rod, 6.2 Kg (25) Core 0.938 Ak Renlace with: Max k.gWith One Stuck Rod, 6.2 kg (235) Core 0.938 ok Original HSR, page 410, Table 4.1: Deleia: Xenon Worth,5.2 Kg (25) Core Replace with- Xenon Worth,5.2 kg (235) Core Original HSR, page 410, Table 4.1: Delete: Xenon Worth,6.2 Kg (25) Core Renlace with: Xenon Worth,6.2 kg (235) Core Original HSR, page 4-10, Table 4.1: Dalata. Mass Coemeient of Reactivity: (Ak/k)/ Am/m) 5.2 Kg (25) 0.1014 6.2 Kg (25) 0.0736 Ranlace with: Mass Coemeient of Reactivity: (Ak/k)/ Am/m) 5.2 kg (235) 0.1014 6.2 kg (235) 0.0736 Original HSR, page 5-5, Section 5.3, first sentencei Deltla: ". . . main circulating pump, heat exchangers, a pool return diffuser . . . ." Renlace with: ". . . main circulating pumps, a plate type heat exchanger, a pool return diffuser . . . ." III-3
Original HSR, page 5-6, Section 5.3, paragraphs 2 & 3: Delete: "The basic design conditions for the pool loop cooling system are that it will i transfer 2 x 108 BTU /hr from a flow rate of 600 gpm when the secondary water is delivered to the heat exchanger at a temperature of 87'F and at a flow rate of E' 400 gpm. These conditions provide for a reactor thermal power of 5 MW. E When the complete system is installed the heat transfer rate will be approximately 3.7 x 108 BTU /hr and the flow rate will be 1200 gpm. This provides for a maximum thermal power of 10 MW, Two heat exchangers are installed for design power i operation." l Rentnee with "The basic design conditions for the poolloop cooling system are that it will transfer 3.6 x 108 BTU /hr and the flow rate is 1200 gpm. This allows for a maximum reactor thermal power of 10 MW. One heat exchanger has been installed for design power operation." l Original HSR, page 5 7, Section 5.3.4, paragraph 2; 1973 74 Annual Report Revision: 1 Delete paragraph from 1973-74 revision which reads:
*The pumps are sized to overcome system pressure drops at variable flow rates from 550 to 750 gpm when one pump is used and from 1100 to 1500 gpm when two pumps art, used ."
Renlace with: "The pumps are sized to overcome system pressure drops at variable flow rates to a maximum flow of 1075 gpm when one pump is used and 1325 gpm when two pumps are used." Original HSR, page 5-7, Section 5.3.5; 1972 73 Annual Report Revision: Delata entire section (including 1972-73 revision) which reads: l "Hant Wehanpers One heat exchanger is required to service the pool coolant system when the reactor is operated at a maximum thermal power of 5 megawatts. Two heat exchangers are required for 10 megawatt operation. Each heat exchanger is a water-to-water shell and tube unit with a removable tube bundle. The tubes and all surfaces in contact with pool water are stainless steel. The demineralized pool water flows on the tube side of the exchanger and secondary coolant water flows on the shell side. The exchanger is capable of removing 2 x 108 BTU /hr of heat at a maximum flow of 600 gpm of pool water, returning at a temperature of approximately 99'F when secondary water is entering at 87'F and 400 gpm." Renlace with:
" Heat Exchanger One heat exchanger is provided to service the pool coolant system when the reactor is operated at a maximum thermal power level of 10 megawatts operation.
The heat exchanger is a water to water plate type with all surfaces in contact with pool water being constructed of stainless steel. The heat exchanger is capable of removing 3.6 x 108 BTU /hr of heat at a flow rate of 1200 gpm of pool water, returning at a temperature of approximately 99'F when secondary water is entering at 87'F and 500 gpm." Original HSR, page 7 4, Section 7.1.5, paragraph 2, last three sentences: Delete: "The higher of these vents the tank through a relief valve whenever the liquid level in the tank recedes to a preset elevation. If the vent tank liquid level continues to recede, the lower controller operates a second relief valve in parallel E with the first. Operation of the lower controller also initiates alarm and rod run. E back." III-4
1 i ! l I t I I l- Renlace with "The higher of these vents the tank through a solenoid valve to a pressure i regulator whenever the liquid level in the tank recedes to a preset elevation. ) If the vent tank liquid level continues to recede, the lower controller operates , i a second relief solenoid in parallel with the first. Operation of the lower i
- controller also initiates alarm and rod run-in." '
f i ! Original HSR, page 7-4, Section 7.1.8, first sentence: : i l l Delete: "In addition to the normal laboratory air compressor, the inflated gasket seals for 1 i the equipment entry, personnel entry, and supply-exhaust air doors are connected 4 to a standby compressor located in the mechanical equipment room on the reactor j fifth level." i Renlace with: "In addition to the normal laboratory air compressor, the inflated gasket seals l for the equipment entry, personnel entry, and the fifth level isolation doors are
- connected to a standby compressor located in the mechanical equipment room on I the reactor fifth level."
\
- Original HSR, page 7 5, Section 7.1.8, paragraph 3
} l Delete paraFranh: "Both of the reactor exhaust isolation valves are of the air operated, quick-closing type. The air for their operation is supplied by a small compressor- ! accumulator unit located at each valve." Replace with "One of the reactor exhaust isolation valves is of the air open-closed type. The ( air for its operation is backed-up by a smaller compressor and accumulator J located on the fifth level." i 1 Original HSR, page 74, Section 7.1.7, paragraph 1, sentence 1;198142 AnnualReport l Revision: i Dalcia: "4 inch" from Original HSR and "6 inch" from 198182 Annual Report Revision. f ! Replace with: "8 inch" 2
- Original HSR, page 74, Section 7.1.7, paragraph 1, sentence thme
f, Dalata: ". . . water trap."; Raplace with:". . . seal trench." 4 1974 75 Annual Report Revision to the Original HSR, page 74, Section 7.1.8, j paragraph 1, sentence 2: Dalata: "All fuel handling will be done in accordance with SNM Control and Accounting i Procedures as outlined in Volume 4 of the 10 MW Standard Operating Procedures." 1 I j Replace with: "All fuel handling will be done in accordance with SNM Control and Accounting Procedures and as outlined in the 10 MW Standard Operating Procedures." j Original HSR, page 74, Section 7.1.8, paragraph 2, sentences 1 & 2; 1988-89 Annual i Report: l 5- Dalcia: "New fuel, when first received, will be placed in a storage vault provided with criticality j detection instrumentation and security against unauthorized entry. Fuel will be stored j in the vault in specially constructed critically safe arrays." l Real== with: "New fuel, when first received, will be placed in a storage vault provided with 2 security against unauthorized entry. Fuel will be stored in the vault in critically , safe geometry such that the calculated k.gis less than 0.9." l i j III-5
l Original HSR, page 7-6, Section 7.1.8, paragraph 2, last sentence: Delete: ". . . storage in a suberitical manner." Renlace with: ". . . storage in a suberitical geometry." Original HSR, pages 7 7 and 7 8, Section 7.1.8, paragraphs 7,8, and 9; Paragraph added to Section 7.1.8,1982 Annual Report: Delete:
"The highest dose rate during the spent fuel transfer operation will be approximately 100 mr/hr during the short interval of time required to lift the element over the lip of the pressure ,
vessel. This will not require over one minute to accomplish per element. To remove fuel the reactor will be shut down and a decay period allowed. The pool level will ll ' be lowered to the lower bridge (approximately six feet) and, by using special tools, the reactor 3 l pressure vessel head will be removed. Reactor operators working from the lower bridge will remove each fuel element one at a time from the reactor core to the storage racks provided at the bottom of the pool. A special tool will be used which provides a positive grip on the fuel element. I Either all new elements will be loaded or all elements will be turned upside down and reloaded. With the water at the refueling level a minimum of eight feet of water will be between the I operator and any single fuel element during the transfer. g A longer air operated fuel handling tool is presently being used. The poollevel remains at its normal level when using the longer tool. Fuel can be transferred to the X, Y or Z baskets g using this longer tool. [This paragraph was added in 1982 Annual Report.] Following fuel loading the pressure vessel head will be replaced and the water level in the pool raised to normal operating height. Any spent fuel in the pool storage racks will then be transferred to the long-term fuel storage racks a$acent to the reactor gamma irradiation facility (i.e. in the spent fuel storage pool)." Renlace with:
"The highest dose rate during spent fuel transfer is approximately 25 mr/hr during the short interval of time when an element is passed into the weir area for storage and when en element is raised to clear the top of the pressure vessel.
The reactor must be shut down and the pressure vessel head removed using special tools prior to removing fuel from the reactor. Reactor operators working from the upper bridge will move fuel in and out of the core to designated spent fuel areas one element at a time. The normal fuel handling tool is air operated, has buoyancy assist tanks and provides position indication oflatching prior to movement of an element. Following each refueling sequsnee a test to assure fuel elements are fully seated is performed and inventory management checks are completed prior to bolting the pressure vessel head in place." Original HSR, page 7 8, Section 7.1.9, paragraph 2, sentence 2: Delata: 'The holdup tank is provided with an off-gas vent which is manually operated at intervals to assure limited gas accumulation." Original HSR, page 7 9, Section 7.1.9, paragraph 2,last sentence: Delete: the word " bypass" Original HSR, page 7 9, Section 7.1.9, paragraph 4, sentence 2: Delete end of second sentence after 140*F, which reads:
". . . with 40 days between regenerations."
I III-6
'l Original HSR, page 7 9, Section 7.1.9, paragraph 4, sentence 4:
Dalata: "These units are capable of maintaining the bulk reactor and pool water at conductivities ofless than one micro mho." Replace with: "These units are capable of maintaining the bulk reactor and pool water at conductivities ofless than two micro-mho." Original RSR, page 710, Section 7.1.9, paragraph 8, sentence 8 and 4: Dalata "After the resin has been sluiced into the regenerant shell the bed is separated remotely by means of a water backwash. Following bed separation it is regenerated remotely using a caustic and acid solution piped to the regenerant station through a plastic (PVC) piping system." Replace with: "After the resin has been sluiced into the regenerator column, R 200, the bed is dumped to a resin drying apparatus and a new, pre-regenerated, bed is loaded for service." 1972 78 Annual Report avision, new paragraph added after second full paragraph of Original IISR, page 710, Section 7.1.9: Dalata the word " regeneration"in sentence two and three; Replace with the word " replacement" Dalata the word " hot"in sentence three; Replace with the words " radioactive liquid" Original HSR, pages 710 and 711, Section 7.1.9, paragraphs 7 and 8: Dalcia "The regeneration station has been designed to provide central regeneration for any one of the three demineralizers. Piping and valves are provided to permit the transfer of spent resins from the regeneration station into a disposal container. The caustic and acid mixing tanks for the regeneration station are located in the cooling tower building approximately 150 feet south of the reactor building. The regenerant solutions are provided to the regeneration station by means of pumps located at the mixing tanks through a PVC piping arrangement. All effluent (wastes) from the regeneration station, including the sluicing water are directed into the hot waste storage system." Reolace with:
"The regeneration station (R-200) has been designed to be a central transfer access point and piping and valves are provided to permit the resin transfer to and from any of the DI tanks, including the storage tank.
All effluent (wastes) from the R-200, including sluicing water, are directed into the radioactive liquid waste storage system." Original HSR, page 711, Section 7.1.9, last paragraph of section, sentence 3: Dalcia "When a particular unit is depleted and in need of regeneration it is valved off and the standby demineraliser is valved into that loop." [ Replace with: "When a particular unit is depleted and in need of replacement it is valved off and the standby demineraliser is valved into that loop." and unove before the mentence "All of these operations are performed . . . ." III-7
1972-73 Annual Report revision, sentence changed and sentence added to Original HSR, I page 711, Section 7.1.9: Delete "The depleted resin bed in the rasin storage tank is then sluiced, by means of a water carrier, from the resin storage tank to the regenerator where it is separated and recharged. The depleted resin bed in the demineralizer is then sluiced to the resin storage tank and the regenerated bed . . . ." Renlace with: "The depleted resin bed in the resin storage tank is then sluiced, by means of a water carrier, from the resin storage tank to the regenerator where it is dumped. E The depleted resin bed in the demineralizer is then sluiced to the resin storage 5 tank and the pre-regenerated bed . . . ." Original HSR, page 711, Section 7.1.9, last paragraph of section, last line: Delete: "It will be noted that access to the demineralizer cells is restricted by a number of wire gates each of which is locked with the keys in the possession of the reactor supervisor." Renlace with: "It will be noted that access to the demineralizer cells is restricted by a number of wire gates each of which is locked and remotely alarmed in the control room." Original HSR, page 712, Section 7.1.10,1st paragraph, last line: Delete: "The pool coolant clean-up line does not have a holdup tank." Original HSR, page 712, Section 7.1.10, paragraph 2, sentence 1: Delete 'The pool coolant clean-up stream is taken off prior to its being passed through the heat exchanger." Renlace with- "The pool coolant cleanup line does not have or require its own holdup tank, but rather has its suction at a point in the pool system before the heat exchanger and after the bulk pool water has passed through the pool water hold up tank." Original HSR, page 712, Section 7.1.11, paragraph 1, sentence 1: Delete: "The pool skimmer system consists of an adjustable skimmer tank . . . Renlace with: "The pool skimmer system consists of an acUustable skimmer surface box . . . ." Original HSR, page 713, Section 7.1.11, paragraph 4, last sentence: Delete "The skimmer filterhas removable 50 micron filter cartridges." Renlace with: "The skimmer filter has removable one micron filter cartridges." Original HSR, pages 715 716, Section 7.2.1: Delete entire section after 1st paragraph which reads:
"This system for demineralized water supply includes a pre and post filter, a mixed bed demineralizer unit, common piping and regenerant tanks as well as the necessary connecting piping and isolation valves. Demineralized water from this system is pumped to two 7,000 gallon demineralized water storage tanks located in the south tower external to the reactor containment building. The position of these tanks with respect to the containment structure is evident on the fourth and fifth level plan, Figure 3.3. On this plan these tanks are denoted as storage tanks.
The make-up demineralizer provides water for the initial filling of the pool, for the reactor loop fill and make-up, for pool make-up additions, for filling the storage tanks, and for general III8 l
j i ! laboratory use. The water to this mixed bed demineralizer is sonened water from the i University water supply. The domineralizer is manufactured by Chempure Company and j consists of a permanently installed package unit of the regenerative type. The unit is capable of . producing effluent water ofless than 0.1 ppm total hardness. l The demineralizer is a mixed bed unit with a manual regeneration station attached to the 4 shell. It is a standard unit with the exception that the mixing tanks for acid and alkali are not located at the regeneration station. These tanks are located in the cooling tower building south 1 i of the reactor facility. The alkali and acid for regeneration are piped via a PVC piping system ! l from the pumps at the mixing tanks to the regeneration station. l l The pre and post filters on this demineralizer are of the replaceable cartridge type capable of j removing 25 micron or larger particles from a continuous flow of 30 gallons per minute. This i demineralizer is capable of operation at pressures up to 125 psi." i
- Replace with
1 i %is system consists of a water sonening unit, a reverse osmosis (RO) unit, and a mixed ! bed demineralizer system. Domineralized water from the system is pumped either to a pair of f 7,000 gallon storage tanks located in the south tower (denoted as storage tank in Figure 3.3), i or the facility demineralized water storage tanks located in the north tower. The 7,000 gallon , tanks are used for reactor and pool make-up and storage, and the facility tanks are used for j clean water laboratory use. . The unit is capable of producing effluent water ofless than 0.1 ppm total hardness. In addition, the DI-300 mixed bed demineralizer is maintained as a backup. This system i includes a pre- and post-filter and a mixed bed demineralizer unit as well as the necessary
- connecting piping and isolation valves."
! Original H8R, page 716, Section 7.2.2, paragraph 1, sentence 2 through end of , paragraph: ! Delata %ese tanks perform two services. They provide a 7,000 gallon source of supply for make-up water to the reactor and pool coolant loops as well as the supply of . demineralized water to the various laboratories. The second tank, can be used in l either of two manners first, it is available as a 7,000 gallon storage reservoir for pool filling purposes and secondly it can be isolated and used to contain that water which is removed from the pool when the pool level is reduced to the lower fuel handling bridge." j Radace with: %ey provide 14,000 gallon capacity to contain that water which is removed l from the pool when the pool level is reduced to the lower fuel handling bridge or below. About 2,500 gallons inventory is kept for normal operations." , l Original HSR, page 717, Section 7.2.2,last paragraph of section: ? ! Dalata entire paragraph which reads:
%e two tanks are isolated from each other by means of valves such that pool water placed
- in storage in the second tank cannot enter the demineralized water supply system for the
- laboratories, i
l Renlace with: 1 ' "The three facility DI water storage tanks are located in the north tower and are made of 304 stainless steel and have a capacity of 420 gallons each. The tanks are all cross connected resulting in a total capacity of 1260 gallons. This system is used only for supplying non-
- contaminated water to the facility labcratories. A high level alarm and make-up system trip is incorporated to prevent over filling and a low level alarm alerts the Operations staff of the need to refill."
i 3 III-9
a I: Original HSR, page 717, Section 7.2.4, sentence 1: Delete: "The Research Reactor Facility has ten fire hose cabinets . . . ." Renlace with: "The Research Reactor Facility has eleven fire hose cabinets . . . ." Original HSR, page 7-18, Section 7.2.5, sentence 1: , Delete: 'The reactor and laboratory has fifteen emergency battery lights . . . ." RenInce with: "The reactor and laboratory has sixteen emergency battery lights . . . ." Original HSR, page 718, Section 7.2.7, paragraph 1: Delete the word " complex" from sentence 1. Add the following to the end of sentence 2:
"with additional makeup coming from three laboratory building roof top air handlers (RTAH)."
Original HSR, pages 7 20 and 7 21, Section 7.2.9, first and last paragraphs of section: Delete-
"The intercommunication and paging system has two master stations and several staff stations as shown in Table 7.1. One master station is in the reactor control room and one is in the reception desk at the main entrance to the building. Speakers for the paging system are located as shown in Table 7.2.
Any staff or the other master control station may be called from either master control l station. Any staff station may call either master control station. Voice paging may be accomplished from either master control station." Renlace with:
"The intercommunication and paging system has one master station and several staff E stations as shown in Table 7.1. The master station is in the reactor control room. Speakers for E the paging system are located as shown in Table 7.2.
Any staff station may be called from the master control station. Any staff station may call the master control station. Voice paging may be accomplished from the master contro station." Original HSR, page 7 20, Section 7.2.9, Table 7.1, first entry under Master Stations: Delete- " Room 205 Reception Desk" Original HSR, page 7 20, Section 7.2.9, Table 7.1, under Staff Stations: Ihltja- " Room 275 Reactor Laboratory" Reolace with: " Room 286 Airlock" , Add: " Rooms 282/271 ET/ Machine Shops Room 242 Health Physics Office" 4 f I III-10 l
Original HSR, ptge 7 21, Section 7.2.9, Table 7.2: After " Room IW add "(3)" Add to lint-
Containment Building Third Level"
" Room 231A"
' Room 231B"
" Room 231C"
" Room 251" Original HSR, page 7 22, Section 7.3.2, sentence 2:
Delete: ". . . sealed paper containers."; Renlace with: ." . . sealed containers." Original HSR, page 7 22, Section 7.3.2, sentence 3: Delete. 'The containers will then be picked up . . . ." Renlace with: "The containers will then be processed . . . ." Original HSR, page 7 22, Section 7.3.3, sentences 3 and 4: Delgia' ". . . or that the waste must be concentrated by a distillation unit. Since the concentrated liquid waste will represent a significantly high level of activity, these wastes will be prepared at the site for subsequent direct land burial." Original HSR, page 9-2, Section 9.1, paragraph 5, sentence 1: Delete: "Since the purpose of the UMRR is to provide neutrons for experimental users it is intended that the reactor be started up each work day and operated continuously at some fixed power level with a minimum of unscheduled shutdowns throughout the work day." Renlace with: "Since the purpose of the MURR is to provide neutrons for experimental users it is intended that the reactor be operated continuously, with a regular schedule of shutdowns for maintenance and refueling." Original HSR, page 9-4, Section 9.2, paragraph 1, sentence 5: Dr.leta. "A second door in the south wall of the control room leads into a storeroom." Original HSR, page 9-4, Section 9.2, paragraph 2: Add the following sentence to the end of peragraph 2:
"One inch steel plating is attact,ed te the lower half of the windows, shielding the operating staff from pool background radiation."
Original HSR, page 9-5, Table 9.1, (a) Displays: Delets (a) Dianinva: I " Fission Counter " Full In" 18 19 Fission Counter "Mid" 20 Fission Counter " Full Out" I III-11
Original HSR, page 9-8 through 9 7, Table 9.1, (b) Contmis; and 1982 revisions to I (b) Controls: Delete (b) Controls and renlace with: (b) Controla Numhar Fimetinn h 12 Control Mode " Manual" P.B. Switch 13 Control Mode " Auto" 16 Reg. Blade " Jog In" E 17 Reg. Blade " Jog Out" 3 21 Mode Selection "Off Test-On" 3 Pos. Master Switch 22 Max. Power Level Selector "50kW-5MW-10MW" Selector Switch 23 Control Blade Selection "A-B-C-D-Gang" 5 Pos. Selector Switch 24 Select Wide Range Channel Range 18 Pos. Range Switch 25 Control Blade "In-Off-Out" 3 Pos. Switch-Spr. Return to Center 26 Control Blade " Rod Run-In" P.B. Switch 3 27 29 Reg. Blade "In-Off-Out" Power Sched. %wer-Off. Raise" 3 Pos. Switch-Spr. Return to Center g 30 Annunciator " Acknowledge" P.B. Switch 31 Annunciator " Test" " g 32 Annunciator " Reset" g 33 " Scram" 34 Scram " Reset" 51 Magnet Current "Off-On" Selector Switch 52 Isolation / Evacuation Switches "Off-On" 2 Pos. Switches 53 Rod Run-In " Reset" P.B. Switch 54 Bypass-Off(6)"Off-Bypass" Key Lock Sel. Switch 58 Select IRM for Recording "Ch2-Ch3" Selector Switch 59 Intrusion Alarm Switch "Off-On" 2 Pos. Switch 78 Intercom Box 79 T.C. Door Shutter "Off-On" 2 Pos. Switch 3 80 Airlock Door Security Switch " Closed-Open" 2 Pos. Switch B 82 P-Tube Blower Exhaust"Off-On" 2 Pos. Switch 83 Airlock Door Open Switch P.B. Switch 84 Digital Selector Switch 24 Pos. Switch 1981-82 Annual Report revision to Original HSR, pages 9-7 through 910, Table 9.2: Delete- 5 Area Radiation and Process Recorder 14 Reactor Water Inlet-Outlet Differential Temperature 15 Pool Water Inlet-Outlet Differential Temperature B 29 Master Power (2CBINB) g 35 Area Radiation Monitoring 36 Area Radiation Monitoring 37 Area Radiation Monitoring 3 g 43 Fuel Rupture Monitoring 45 Secondary Coolant Monitoring 46 Door 101 Open Lite and Tag 48 South Wall Area Radiation Monitor E 49 West Wall Area Radiation Monitor E 50 North Wall Area Radiation Monitor 51 Fuel Storage Area Radiation Monitor 53 Cooling Room Area Radiation Monitor 54 Building Air Plenum Area Radiation Monitor 55 Bridge Area Radiation Monitor (4) 56 Bridge Area Radiation Monitor (2) 61 (Not Used) III-12 l
62 Pump and Fan Operation "Off-On" (Note 2) (13) 63 (Not Used) 67 Pump and Fan Control (See Note 2)(13) Fan Switch,3 Pos "On-Off-On" Pump and Fan Control (See Note 2)(13) Pump Switch,2 Pos "Off-On" 136 Emergency Generator On 167 Back Up Door Alarm 168 3 Off-Gas Recorders 169 Stack Monitor Motor On Light, Hi/14 Flow Alarm 170 Auxiliary Radiation Monitor and Nuclepore Alarm Panel 231 Rod Drop On/Off Power Switch 232 Rod Drop Reset Push Button 233 Control Blade Drop Time 234 Rod A Drop Timer 235 Rod B Drop Timer 236 Rod C Drop Timer 237 Rod D Drop Timer RenInce with: 5 Area Radiation Monitor 14 Pool Water Inlet-Outlet Differential Temperature 15 Reactor Water Inlet-Outlet Differential Temperature 29 (Not Used) 35 Panalarm - Alpha Lab 36 (Not Used) 37 (Not Used) 43 Rod Drop Timer Circuit 45 (Not Used) 46 Bridge Upscale Switch and Light 48 North Wall Area Radiation Monitor 50 South Wall Area Radiation Monitor 51 Air Plenum 1 Area Radiation Monitor 53 Bridge ALARA Area Radiation Monitor 54 Bridge Area Radiation Monitor 55 Nuclepore Radiation Monitor 56 Fuel Vault Radiation Monitor 61 Exhaust Plenum 2 Area Radiation Monitor 62 Pump and Fan Operation "Off-On" Lights (Note 2)(13) 63 Fission Product Radiation Monitor 67 Pump and Fan Control (See Note 2) (13) Switch,3 Pos "On-Off-On" 136 (Not Used) 167 (Not Used) 168 Off-Gas Recorder,3 Pen 169 Stack Monitor Motor On Light, Hi/Lo Flow Alarm, Alarm Cutout Switch 170 Nuclepore Alarm Panel, Alpha Lab Fire Alarm 231 (Not Used) 232 (Not Used) 233 (Not Used) 234 (Not Used) 235 (Not Used) 236 (Not Used) 237 (Not Used) Add: 52 Secondary Coolant Radiation Monitor 57 Eoom 114 Area Radiation Monitor 263 Pneumatic Tube Irradiations Counters III-13
Original HSR, page 9-10, Section 9.3.1, paragraph 1, sentence 5: I Delete- "The intermediate range channels provide trip outputs on both short period and high period power." bninee with: %e intermediate range channels provide trip outputs on short period." Original HSR, page 9-11, Section 9.3.2: Delete Section 9.3.2. bninee with:
"The startup channel detector is a fixed position fission chamber with 45 inches of sensitive length. The fission chamber is mounted in a water tight drywell enclosure and located in the pool outside the reflecter region approximately centered at the elevation of core centerline.
Pulses from the fission chamber are first received by a remote amplifier mounted on the biological shield at the mezzanine level. The amplifier assembly contains the signal conditioning circuitry, de power supplies and the high voltage detector excitation supply. From the amplifier the conditioned signal is fed into the signal processor assembly in the g rack mounted instrument drawer in the control room. The signal processor provides further 3 processing of the detector signal into signals which are a measure of the logarithm o?cosnt rate and rate-of-change of count rate. The log count rate signal drives a local panel indicadon, a remote meter mounted on the control console, and a log count rate recorder. The period indication is displayed on a local indication and a remote period meter mounted on the control console. The discriminated output of the source range channel is also delivered to a panel mounted scaler. The scaler provides count rate information that is used to measure suberitical multiplication during a startup." Original HSR, page 9-13, Section 9.3.4, paragraph 2: Delete- "The third power level channel Wide Range Monitor monitors reactor power from shutdown to full power in twenty linear ranges. The detector for this power level channel is a compensated ion chamber which is located near the uncompensated ion chambers." Renlace with: "The third power level channelis the Wide Range Monitor. It monitors reactor power from shutdown to full power in eighteen linear ranges. The detector for this power level channel is a compensated ion chamber." Original HSR, page 914, Section 9.4.1, paragraph 1, last sentence: Delete- "The trip actuator amplifiers reset when the " Scram Reset" button is depressed." bolace with "The trip actuator amplifiers can be reset when the scram input signal is cleared and the " Scram Reset" button is depressed." Original HSR, page 9-14, Section 9.4.1, paragraph 2, sentences 2 and 3: Delete- "The logic units initiate a " scram" whenever any one of nine inputs is interrupted. Both units have the same nine inputs connected in parallel." bnlace with: "The logie units initiate a " scram" whenever any one ofits inputs is interrupted." I III-14 l
I I Original HSR, page 915, Section 9.4.2, paragraph 2, sentence 1: l Deleta: "Once tripped, the trip actuator amplifier must be reset by depressing the " Rod Run-In" reset button." Replace with: "Once tripped, the trip actuator amplifier must be reset by depressing the " Rod Run In" reset button after the rod run-in input signal is cleared." Original HSR, page 915, Table 9.8, line 4: Delete: " Return to Normal On Dim Off' Baplace with: " Return to Normal Flashing Dim On" 198182 Annual Report revision to Original HSR, page 9-16, Section 9.4J: Dalata: (17); previously deleted by 198182 Annual Report revision. Eenlace with: "(17) Reactor loop high temperature." l Original HSR, page 9-17, Section 9.4.8: I Dalata- "(26) Pool at refuellevel." 4 Ran1=e= with: "(26) Anti-siphon tank high orlow pressure." ! M d: "(36) Reflector valve 547 off open." l l Original HSR, page 917, Section 9.5: Dalaia: "(2) " Rod Run-In" switch is reset." Renlace with: "(2) " Rod Run In" and " Scram" switches are reset." , Dalata: "(5) Startup channel more than 1 count per second." Replace with- "(5) Startup channel more than 1 count per second or IRM recorder , indication greater than red pointer." l 1990-91 Annual Report avision to Original HSR, page 9 30, Table 9.4: Dalaia last two lines of table from the 1990-91 Annual Report revision:
" Reactor Bridge ALARA 0.1 - 100K mR/hr l Cooling Equipment Room 0.1 - 100K mR/hr" '
Replace with-
" Reactor Bridge ALARA 1 - 100K mR/hr Cooling Equipment Room 1 - 100K mR/hr" 1990-91 Annual Report revision to Original HSR, pages 9-20 & 9 21, Section 9.7.1:
Dalaia the following paragraphs from the 1990-91 Annual Report revision to Section 9.7.1:
"The information from each of the remotely located detectors is displayed on panel meters on the control room instrument panel. Each of the panel meters is equipped with an adjustable alarm contact which illuminates a lamp at that meter and annunciates an alarm whenever the detected radiation level exceeds the set point.
III-15
Additionally, when the radiation level sensed by either of two building exhaust air plenum I detectors or either of two reactor bridge monitors exceeds the trip level a " building isolation"is a initiated. In a building isolation: (1) The reactoris scrammed; (2) The building is sealed (all ventilation opening are closed); and (3) the exhaust and supply fans are de-energized." Egglace with:
"The signal from each of the remotely located detectors is displayed on panel meters on the control room instrument panel. Each of the panel meters is equipped with an adjustable alarm contact which illuminates a lamp at that meter and initiates an audible alarm whenever the detected radiation level exceeds the setpoint.
Additionally, when the radiation level sensed by either of two containment building exhaust air plenum detectors or either of two reactor bridge monitors exceeds the trip level a
" reactor isolation" is initiated. In a reactor isolation:
(1) The reactor is scrammed; (2) The containment building is sealed (all ventilation openings are closed); and 3 g (3) The containment building exhaust and supply fans are de-energized." 1990-91 Annual Report avision to Original HSR, page 9-21, Section 9.7.2: Deleta the last sentence of Section 9.7.2 from the 1990-91 Annual Report revision:
'This information is indicated on a panel meter that is equipped with a high level alarm."
Reolace with: 'This information is indicated on a control room panel meter that is equipped with an adjustable high level alarm, which also initiates an annunciator alarm." 1990-91 Annual Report revision to Original HSR, page 9-22, Section 9.7.4: Delete the last sentence of Section 9.7.4 from the 1990-91 Annual Report revision:
"This information is indicated on a panel meter that is equipped with a high level alarm."
Renlace with: "This information is indicated on a control room panel meter that is equipped with an acUustable high level alarm, which also initiates an annunciator alarm." Original HSR, page 9-23, Section 9.8.1.1, paragraph 4, last sentence: Delete: "Whenever the control valve reaches either limit, indicating that no more control is available, the reactor operator is alerted by annunciator action." Reolace with: "Whenever the control valve approaches either limit, indicating that little control is available, the reactor operator is alerted by annunciator action." Original HSR, pages 9 24 and 9-25, Section 9.8.2.1; 1981-82 Annual Report revision: Deleia entire section (including 1981-82 Annual Report revision) which reads:
"The reactor loop flow measurement system includes one orifice plate and three flow switches.
Flow, as measured by the orifice plate, is recorded in the control room on the instrument panel. The recorder has two pens. The second pen will record flow in a parallel reactor heat exchanger loop when installation of the 10 megawatt cooling capacity is completed. The orifice plate flow measuring channel will alarm at 90% of normal flow. At 85% of normal flow the core isolation valves, reactor convective loop valve and the siphon break valves operate and the reactor scrams. III-16 l
%e three flow switches operate when the coolant flow drops to 50% of normal. Operation of any of these switches causes the core isolation valves to close, the convective loop and siphon break valves to open and the reactor to scram."
Replace with:
"The reactor loop flow measurement system includes two orifice plates, one in each of two heat exchangerlegs.
Flow, as measured by the transmitters connected to these orifice plates, is recorded on a control room instrument panel mounted two pen recorder. he orifice plate flow measuring channels will alarm at 90% of normal flow. At 85% of normal flow the core isolation valves, reactor convective loop valves, and the siphon break valves operate as the reactor scrams." l Original HSR, page 9 25, Section 9.8.2.2: Dalela paragraph 2, which reads:
" Flow, as measured by the orifice plate, is recorded on the control room instrument panel mounted two pen recorder. The second pen will record flow through a duplicate heat exchanger which will be installed when the cooling plant is exposed for 10 megawatt peak power operation."
Replace with: " Flow, as measured by two transmitters connected to this orifice plate, is recorded on a control room instrument panel mounted two pen recorder." Delgia sentence 2, paragraph 3, which reads: i "If the flow reaches 85% of normal the reactor is scrammed." Ranlace with: "If the flow reaches 70.8% of normal, the reactor scrams." Dalgia paragraph 4, which reads:
"When the pressure drop across the reflector region becomes excessive an annunciator alarm occurs."
Renlace with: "When the pressure drop across the reflector region becomes high or low a reflector high/ low differential pressure scram occurs." Delgia paragraph 5, which reads:
"In addition to the flow monitoring devices the pool coolant loop has a pressure switch on the discharge side of the coolant circulation pump. When the pump discharge dynamic head decreases to the switching level the pump is stopped, the pool isolation valve closes and the pool natural convection valve opens, and the reactor is scrammed."
Replace with:
"In addition to the flow monitoring devices the pool coolant loop has a pressure switch on the discharge side of the coolant circulation pumps. When the pumps discharge dynamic head decreases to the switching level, the pumps shut off, the pool isolation valve closes, and the reactor scrams."
{ III-17
Original HSR, page 9 26, Section 9.8J.1, paragraph 1; Revised 1968-69 Annual Report: ' Delete paragraph 1 of Section 9.8.3.1, Original HSR (including 1968-69 Annual Report revision) which reads:
"Two pressure switches, electrically connected in series, are installed in the outlet leg, outside of the pool, of the reactor coolant loop. When the loop pressure at these switches decreases to 25 psig the following action takes place."
Renlace with:
"I'wo pressure switches are installed in the outlet leg of the reactor coolant ' .eop.
t When l the loop pressure at these switches decreases to approximately 25 psig the following action a takes place." Original HSR, page 9-26, Section 9.8.3.1, number (4): Delete- "(4) Reactor coolant circulation pump stops." Renlace with: "(4) Reactor coolant circulation pumps stop." Original HSR, page 9-26, Section 9.8.3.2, last paragraph, sentence 1: Delete: " Pressurizer water level is maintained by adding water with a positive displacement pump if the level is low and dumping water to the hot waste system if the level is too high." Renlace with: " Pressurizer water level is maintained by adding water with a positive displacement pump if the level is low, and dumping water to the drain collection system if the levelis too high." Original HSR, page 9-27, Figure 9.1: Reninee with: Updated Figure 9.1--Reactor Control Room Layout (dated 1/3/95) Original HSR, page 9-28, Figum 9.2: Renlace with: Updated Figure 9.2-Control Console Layout (dated 1/3/95) Original HSR, page 9 29, Figum 9.3: Renlace with: Updated Figure 9.3--Instrument Cabinet (MURR Drawing #74, Sheet 12 of 12, dated 1/19/94) Original HSR, page 9-30, Figure 9.4-Reactor Scram System: Renlace with: Figure 9.4-Safety System,10 MW (MURR Dwg #139 dated 11/10/75) Original HSR, page 9-31, Figum 9.5: Renlace with: Updated Figure 9.5-Rod Run-In System (MURR Dwg #140 dated 2/13/79) Original HSR, page 9-33, Figum 9.7: Renlace with: Updated Figure 9.7-Nuclear Instrument Detector Drywell Locations (dated 1/3/95) III-18 I
Original HSR, page 9-34, Figure 9.8--Ion Chamber Location Elevation View: Delete Figure 9.8 and Add the following note:
"The relative plan view location of the Nuclear Instrument Drywells is depicted by Figure 9.7. Each detector elevation is typically centered on core centerline (t 6") and are adjusted as necessary to minimize rod shadowing effects and occasional flooding of beamtubes for maintenance."
{ Original HSR, page 10-4, Section 10.3, paragraph 2, last sentence: Delgie: ( . . . a tag out procedure will be followed." Renir.ce with: ". . . a tag out procedure will be followed for affected systems and equipment." ( Original HSR, pages 11 9 & 11 10, Section 11.7: Delcig: . . . reactor supervisor . . ." throughout the section. Renlace with: ". . . Reactor Manager . . ." throughout the section. Original HSR, page 11 11, Section 11.9, paragraph 2, last sentence: [ Delete- "
. . . reactor supervisor . . . ."; Rentnee with: ". . . Reactor Manager . . . ."
Original HSR, page 1112, Section 11.10; Records: Under list of parameters recorded, add: " Pool coolant flow rate' Original HSR, pages 11 13 and 11 14, Section 11.10: Under list of nuclear data recorded: [ a) Add: " Nuclear channel 1" t b) Delete individual rod positions; Replace with " Average Shim Rod Position" c) Delete: " Mode of operation (Auto-Manual)" d) Delete: " Operator initials"; the nuclear data sheet is combined with the Process Data ( Sheet which includes operator initials. Under list of process data recorded, add:
" Pressurizer level" "Off-gas stack activity" III-19
I I: ADDENDUM 1 HAZARDS
SUMMARY
REPORT (FEBRUARY 1966) , HSR, Addendum 1, page 6, Item 3.1, paragraph 10, sentence 2: Dalgte- "If these tests show any evidence of rod or sticking, immediate corrective action will be l taken." Reninee with: "If these tests show any evidence of the rod sticking, immediate corrective action will be taken." HSR, Addendum 1, page 13, Item 3.4: After first paragraph Add a note which reads:
" NOTE This topic was reevaluated at 10 MW upgrade (see Hazards Summary Report, Addendum 4, Appendix A)."
HSR, Addendum 1, page 17, Item 3.6: l Delete response which reads:
"I'wo independent detectors are used to initiate building isolation. One detector is located in the building exhaust air plenum on the fifth level of the reactor containment building, and one is located in the exhaust air stream from the reactor pool surface. These detectors are isolated from each other in that the operation of one does not affect the operation of the other. l The power supply to these two detectors is common. However, the power supplies are a monitored by an alarm circuit which alerts the reactor operator in the event that power to any detector is lost so that corrective action may be taken. Both high voltage and low voltage power is monitored independently by the alarm circuit.
In addition, a lamp on the front panel indicates that power is available to the common power supply system. In case power is lost, an isolation is initiated as the result ofloss of power to a normally energized relay. Power to the area radiation monitoring system is from E the emergency bus so that in the event ofloss of commercial power the area radiation E monitoring system is energized by the motor-generator set. The system that initiates the building isolation on high radiation levels is either redundant or is provided with alarm-monitoring circuits such that no single failure can result in the loss of isolation protection." Reolace with:
"Four independent detectors are used to initiate containment building isolation. Two detectors are located in the exhaust plenum on the fifth level of the reactor containment building, and two are located near the reactor pool surface. If any one of these detectors senses 3 a radiation level above the trip setpoint, a reactor scram and isolation is automatically g initiated.
The air plenum detectors are isolated from each other in that the operation of one does not affect the operation of the other. The pool surface detectors are clso isolated from each other, but have different trip setpoints. The detector with the lower trip setpoint can be temporarily cutout to avoid an inadvertent scram and isolation during controlled experimental transfers or minor maintenance in the reactor pool area. The pool surface detector with the higher setpoint always remains in continuous operation. l These detectors are powered by independent low voltage power supplies and are, a therefore, not subject to a single failure event. The power supplies are monitored by an alarm circuit which alerts the reactor operator in the event power to a detector is lost. The resulting loss of signal from the detector will initiate a reactor isolation and scram. Power to the area radiation monitoring system is routed from the uninterruptible power supply (UPS) and the emergency power distribution system, which will provide continuous power in the event of a loss of normal site power." 111-2 0 l
HSR, Addendum 1, page 29, Section 3.10, paragraph 6, sentence 1: Delete 'The actuation of the isolation or evacuation switches located on the control console, or the evacuation switches located in Rooms #205 and 269, . . . ." Renlace with: "The actuation of the isolation or evacuation switches located on the control console, or the evacuation switch located in Room #202 (MURR Lobby), . . . ." HSR, Addendum 1, pages 31, Item 3.11, paragraph 6, sentence 3: Delete- "A portable source will be used on the detector." Reninee with: 'The built in source will be used on the detector." HSR, Addendum 1, page 97, Item 3.20: Delete the paragraph numbered "4.":
"4. The 16" and 4" air operated exhaust valves have their own motor driven air supply and are also supplied with compressed air both from the main air compressor and the emergency air compressor. Therefore, these valves have three possible air supplies."
Renlace with:
"(4) The containment building exhaust line contains two 16" butterfly valves. The 16" A valve is air /open--spring /close (assumed fail safe) while the 16" B valve is air /open air /close. Air to the valve operators is supplied from the main facility compressor and the emergency compressor. The 16" B valve has an additional dedicated emergency air compressor.
Adequate redundancy is attained by the fact that there are two separate isolation valves, and the 16" B valve has redundant air sources." HSR, Addendum 1, page 97, Item 3.20: Add the following sentence to the end of the paragraph numbered "5":
" Additionally, there are air-piston operated backup doors in the air supply and return plenums which are air /open--gravity /close. These backup doors close automatically with any automa-tically initiated containment building isolation. They will fail closed upon loss of air or electrical power."
1989 90 Revision to HSR, Addendum 1, page 102, Item 3.22, paragraph 8, last sentence: D.elete: " Exhaust air from the mechanical equipment room is delivered to EF-13 or 14 through > activated charcoal and absolute filters." 1989 90 Revision to HSR, Addendum 1, page 102, Item 3.22, last paragraph, sentence 1: Delete- ". . . enters EF 13 or 14 through two . . . ." Renlace with: " enters EF-13 or 14 through a 16 inch line with two . . . ." HSR, Addendum 1, page 103, Section 3.22, Figure 3.22.1: Renlace with: Updated Figure 3.22.1 (MURR Dwg #2420, dated 4/25/95) HSR, Addendum 1, page 104, Section 3.22, Figure 3.22.2: Reolnee with: Updated Figure 3.22.2 (MURR Dwg #1125, Sheet 2 of 2, dated 4/25/95) l III-21
l ADDENDUM 2 - HAZARDS
SUMMARY
REPORT (MAY 1966) I1 HSR, Addendum 2, page 17, Item 7: l l After first paragraph Add a note which reads:
"HD.TE This topic was reevaluated at 10 MW upgrade (see Hazards Summary Report, l Addendum 4, Appendix A)."
1 , l HSR, Addendum 2, page 19, Item 8, paragraph 3,last sentence: Delete: "If the solenoid or supply power fails, the door is driven closed by air pressure." Reolace with: "If the solenoid or supply power fails, the door is driven closed by gravity." l HSR, Addendum 2, page 29, Item 11: After question insert the following note:
" Hole: This question is no longer relevant due to Facility Modification Package 88-7. See 1989-1990 Annual Report for updated information." l l
l l I l l l I l I. l I I III-22 l
. ~ . . .__ _ _ _ ~ . _ _ ____ ___ . . _ _____ __ _ ._ - _ _ __. ___ _ _ _ _ . _
1 l ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972) HSR, Addendum 3, page 12, Section 2.2.1, sentence 2 through end of paragraph: Dalein: "To facilitate 10 MW operation of the reactor, it is also necessary to double the heat removal capability of the pool water cooling system. This will require the installation of an additional pump and heat exchanger in parallel with the existing units. ' Modifications will also be made to the existing pool system to improve its reliability and to facilitate parallel operation of the pumps and heat exchangers. All components described in this section are shown in Figure 2.1. l hnlaea with: 'To facilitate 10 MW operation of the reactor, it was necessary to double the
- heat removal capability of the 5 MW pool water cooling system. At 10 MW 2 upgrade an additional pump was installed in parallel with the existing unit.
- Subsequent analysis revealed the pool system will have adequate cooling with a single pump. Modi' cations have been made to the existing pool system to improve its reliabili' / and to facilitate parallel operation of the pumps. All
- components described in this section are shown in Figure 2.1(see Addendum 4 of HSR for revised Figure A.2--Piping & Instrument Diagram).
HSR, Addendum 3, page 12, Section 2.2.2, sentences 1 & 2: Dalata:
"The major change in the pool system for 10 MW operation is the installation of an additional pump and heat exchanger plus the valves, fittings and instrumentation associated with these components. The new pump and heat exchanger will be installed in a piping leg which parallels the respective pump and heat exchanger of the existing system."
hn1.e. with:
"The major change in the pool system for 10 MW operation was the installation of an additional pump, doubling heat exchange capability, plus valve fittings and instrumentation associated with these components. The new pump has been installed in piping leg which parallels the existing pump of the existing system."
HSR, Addendum 3, page 12, Section 2.2.2.2: Delete "The heat exchanger designated 521B is a carbon steel shell, stainless steel U tube exchanger which is identical to the existing unit (521A)." hnlaea with: "The heat exchanger designated 521 is a plate type heat exchanger constructed of stainless steel plates with EPDM gaskets. The heat exchanger will have spray shields installed on it." HSR, Addendum 3, page 12, Section 2.2.2.5: Changed tense from past to present tense. HSE, Addendum 3, page 14, Section 2.2.2.9: Dalata: "The flow orifice FE-921B is a stainless steel orifice identical to the existing orifice FE-921A." hnlaca with: "A single flow orifice designated FE-921 is made of stainless steel and has four sets of flange taps, two sets attached to flow transmitters." III-23
HSR, Addendum 3, page 14, Sections 2.2.2.10 and 2.2.2.11: Changed tense from past to present tense. HSR, Addendum 3, page 15, Section 2.2.3: Delete: " Changes will be made to the existing pool system to facilitate parallel operation of the heat exchanger and to improve the capabilities of calibrating the RTDs and venting the system. The following modifications will be made to the existing system." Renlace with: " Changes have been made to the existing pool system to facilitate operation of I a single heat exchanger and to improve the capabilities of calibrating the RTD's and venting the system." HSR, Addendum 3, page 15, Section 2.2.3.1: Delete: " Change the outlet isolation valve on heat exchanger 521A from a 4" gate valve to a 4" diaphragm valve of the 522 series type. This valve will be used to control the flow through heat exchanger 521A and thus balance the flow and heat removal load of the two heat exchangers when they are operated in parallel." Renlace with: "The outlet isolation valve on heat exchanger 521 has been changed from a 4" diaphragm valve of 522 series type to a 6" diaphragm type. This valve is used to control the flow through heat exchanger 521." .HSR, Addendum 3, page 15, Sections 2.2.3.2, 2.2.3.3, 2.2.3.4: Changed tense from past to present tense.- HSR, Addendum 3, page 15, Section 2.2.3.5: Delete- "The RTD designated TE-9800 will be added to the outlet side of heat exchanger 521A. This RTD along with TE-9900 on the seco:wbry water side will enable the operator to calculate the heat being removed by the heat exchanger and will also permit determination of the heat transfer coefficient for the heat exchanger which will E provide early warning of possible fouling of the heat exchanger." 3 Renlace with: 'The RTD designated TE-980C has been installed to the inlet side of heat exchanger 521. This RTD along with TE-990C on the secondary water side will enable the operator to calculate the heat being removed by the heat exchanger and permits determination of the heat transfer coefficient for the heat exchanger which provides early warning of possible fouling of the heat exchanger." HSR, Addendum 3, page 20, Figure 2.2; 1994 Annual Report Revision: Renlace with updated Figure 2.2 (MURR Dwg #502, dated 11/2/95) HSR, Addendum 3, pages 23,24 and 25: Delete Figures 2.3,2.4 and 2.5 Renlace with updated figures: 2.3.a (MURR Dwg #522, Sheet 1 of 2, dated 11/20/95) 2.3.b (MURR Dwg #522, Sheet 2 of 2, dated 12/5/95) 2.4 (MURR Dwg #2, Sheet 2 of 6, dated 11/28/95) 2.5 (MURR Dwg #1, Sheet 1 of 2, dated 11/28/95) III-24
4 HSR, Addendum 8, page 26, paragraph 4, sentence 2:
- Dalata " Process transducers provide a signal to the temperature flow instrumentation v hich ,
supplies direct readout and recorded data of water temperatures, pressure and tiow l ! processes." Renlace with: " Process transducers provide a si al to the temperature and flow l instrumentation which supplies et readout and recorded data of wates temperatures, pressure, and flow." HSR, Addendum 8, page 81, Section 2.5.8.3: l l Dalata: "3. Valve 543 A&B operation
- 4. Valve 507 A&B operation
- 5. Valve 546 operation
! 6. Pump 501 A and D operation." Renlace with: "3. Valve 546 A and 8 operation (Open)." i , HSR, Addendum 8, page 32, Section 2.5J.4, Sentence 1: Delete: "The additional heat exchanger 521B will be monitored for flow by flow element 921B, flow transmitter 912F, square root converter 919F, pool alarm unit 920D, and recorder 915D." j Renlace with: " Pool system flow is monitored by a single flow element supporting two flow l 1 transmitters,912F and 912D. Flow transmitter 912F, square root converter l 919F, pool alarm unit 920D, and recorder 915D form one flow instrument leg. Flow transmitter 912D, square root converter 919B, dual alarm 920C, and recorder 915C form a second flow instrument leg." HSR, Addendum 8, page SS, Section 2.5.8.5, Paragraphs 1 and 2: ! Delete: 'The additional heat exchanger 503B will be monitored for flow by flow element 913B, flow transmitter 912E, square root converter 919E, electronic alarm 920B, and recorder 915B. l Flow of heat exchanger 503A will be monitored by flow element 913A, flow transmitter 912A, square root converter 919A, electronic alarm 920A, and recorder 915A." Replace with: "The additional heat exchanger 503B is monitored for flow by flow element 913B, flow transmitter 912E, square root converter 919E, electronic alarm 920B, and recorder 915B. Flow of heat exchanger 503A is monitored by flow element 913A, flow
- transmitter 912A, square root converter 919A, electronic alarm 920A, and
! recorder 915A." HSR, Addendum 8, page 35, Section 2.5.4.1: Dalalai "2.5.4.1 Power level selection indicators in conjunction with power level switch (IS8) will allow a visual indication of power level selected. Visual indicators are to be Panalarm light units, SCAM Corp. Part No. BCS-M." hnba with: "2.5.4.1 Power level selectica Ndicators in conjunction with power level switch (188) allows a visual indication of power level selected." HSR, Addendum 8, page 86, Figure 2.6- Amplifier: Replace with: Updated Figure 2.6--Amplifier 2.6 (MURR Dwg #965, dated 5/11n9) III-25 ew .< ,- - , , , - , , - - - -
l l l HSR, Addendum 3, Figum 2.9--Test & Feedback Unit: Renlace with: Updated Figure 2.9--Test and Feedback Unit (MURR Dwg #608, dated 10/23/73) , ESR, Addendum 3, page 44, Section 2.5.5: 1 After section' title add the following note: l " NOTE: This section (2.5.5) changed by response in Addendum 4, Appendix A." HSR, Addendum 3, page A 13, Section A.S.S.11, paragraph 3: Delete- "At present, all potentially radioactive gases from the pool, pneumatic tube system, beamports, . . . ." Reninee with: "At present, all potentially radioactive gases from the pool, beamports, . . . ." HSR, Addendum 3, page A 14, paragraph 3, sentence 7: Delete- " Control and operation are identical to the present valve, except the r.ew valve is air to-open, spring loaded to close. Renlace with: " Control and operation are identical to the first valve, except the second valve is air-to-open, spring-loaded to close." HSR, Addendum 3, page A 14, paragraph 3, sentence 9: l Delete: " Air is supplied from the same source as the present valve." Reninee with: " Air is supplied to both valves from a common source." HSR, Addendum 3, page A-14, paragraph 4: Ilcleta "As indicated in Figure A.11, the exhaust from the pneumatic tube blowers presently passes from the hot cell area through particulate filters into the containment building and connects with the 16" reactor building exhaust. In the event of a building isolation this penetration is sealed by a 4" butterfly valve which operates identically to the original 16" valve described above. The pneumatic tube exhaust will be rerouted through particulate filters directly to the MURR off-gas stack and the present E 4" containment building penetration will be sealed. This will eliminate a potential 3 breach of containment in the event of a single failure of the 4" isolation valve." Renlace with: "The pneumatic tube exhaust is routed through particulate filters directly to the MURR off-gas stack in the west tower. The old 4 inch line in the containment building has been sealed." l l III-26
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973) HSR, Addendum 4, page A.11, Section A.S.3.8, paragraph 1, sentences 1 and 2: Delete- " Protection against low pool flow operation is attained by use of flow elements 921A and 921B (Figure A.2). Each flow element measures the differential pressure generated across a flow orifice by the flow in one of two heat exchangers." Renlace with: " Protection against low flow operation is attained by the use of flow element 921, with multiple taps (Figure A.2). The flow element measures the differential pressure generated across the flow orifice by the total flow in the outlet to the heat exchanger." 1990-1991 Annual Report Revision to HSR Addendum 4, Section A.3.3.11, paragraph 2, sentence 1: Delete "A backup plenum exhaust detector and trip unit is incorporated in a separate rack unit from the primary plenum exhaust to provide a redundant plenum scram and isolation." holace with: "A backup plenum exhaust detector and trip unit is incorporated in a separate rack unit from the primary plenum exhaust detector to provide a redundant plenum scram and isolation." HSR, Addendum 4, page A-15, Section A.3.3.13, sentence 2 through end of section: Delete entire section which randa:
"An isolation valve,546A, presently prevents flow through the in-pool heat exchanger during forced convection cooling (Figure A.2).
It is proposed that an additional valve 546B, be installed in parallel with the existing valve and that the control circuits be as shown in Figure A.5. As proposed, the natural circulation cooling loop isolation valve system meets the single failure criteria." Renlace with:
" Parallel isolation valves 546A and 546B presently prevent flow through the in-pool heat exchanger during forced convection cooling (Figure A.2). Control circuits for these valves are shown in Figure A.5. As described, the natural circulation cooling loop isolation valve system meets the single failure criteria."
HSR, Addendum 4, page.A 15, Section A.3.3.14, sentences 1 and 2: Delete- ". . . valve 547 opens to allow natural convection flow of pool water into the lower plenum and up through the reflector elements, control blade gaps, and flux trap. To comply with the single failure criterion, this valve will be left open." Renlace with: ". . . valve 547 allows natural convection flow of pool water into the lower plenum and up through the reflector elements, control blade gaps, and flux trap. To comply with the single failure criterion, this valve is left open." HSR, Addendum 4, page A 21, Section A.S.10, last paragraph, sentence 3: Delete: " Actuation of pressure switches 944A,944B and 938 are verified weekly . . . ." Reninee with: " Actuation of pressure switches 944A,944B and 943 are verified weekly . . . ." HSR, Addendum 4, Figure A.1: Renlace with: Updated Figure A.1--Safety System,10 MW (MURR Dwg #139, dated 11/10/95) f III-27
1 I l l HSR, Addendum 4, Figure A.2: ) Renlace with: Updated Figure A.2--Piping & Instrument Diagram (MURR Dwg #156, dated 10/5/95) HSR, Addendum 4, Figure A.3: Renlace with: Updated Figure A.3--Process Instrumentation Control & Interlock (MURR Dwg
#41, Sheet 3 of 3, dated 7/13/83)
HSR, Addendum 4, Figure A.4: Renlace with-Updated Figure A.4.a-Reactor Control System. (MURR Dwg #42, Sheet 1 of 2, dated 9/30/92) Updated Figure A.4.b-Reactor Control System (MURR Dwg #42, Sheet 2 of 2, dated l 7/19/90) l HSR, Addendum 4, Figure A.5: l RenInce with: Updated Figure A.5--Process Instrumentation Control & Interlock (MURR Dwg
#41, Sheet 1 of 3, dated 7/7/89)
HSR, Addendum 4, Figure A.6: Renlace with: Updated Figure A.6-Process Instrumentation Control & Interlock (MURR Dwg ,
#41, Sheet 2 of 3, dated 10/21/83) i HSR, Addendum 4, Figure A.7:
Renlace with: Updated Figure A.7-Annunciator Control (MURR Dwg #138, Sheet 1 of 2, dated 9/7/83) HSR, Addendum 4, Figum A.9- Model Rm 12A Back Up Door Control Circult: Delete Figure A.9 HSR, Addendum 4, Figure A.10--Evacuation / Isolation System: Delete Figure A.10 (Safeguards Information) HSR, Addendum 4, Figure A.11: Renlace with: Updated Figure A.11-Schematic Diagram of Laboratory and Containment Buildings Ventilation System (MURR Dwg #1125, Sheet 1 of 2, dated 4/22/95) HSR, Addendum 4, Figure A.12: Renlace with: Updated Figure A.12-Ventilation Automatic Valve Air Supply (MURR Dwg
#119, dated 8/26/88)
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