ML20216F519
| ML20216F519 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 07/06/1960 |
| From: | Geisler G, Rice R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20216F225 | List:
|
| References | |
| FOIA-98-100 P-107, NUDOCS 9804170106 | |
| Download: ML20216F519 (4) | |
Text
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WTR N O. P-107 TECHNICAL OPERATIONS OPERATING PROCEDURES AND STANDARDS PAGE 4 0F 7 l SUBJECT)
ABNORMAL OPERATION PROCEDURES h
DATE: HEVISION NQ. SUPERSEDES S. P. N O.:
July 6.,1960 Original N v' '
DATED!.
UNEXPLAINED REACTIVITY IILSS In the event of any unexplained reactivity loss, as evidenced by: I
- 1. A negative period less than 100 seconds,
- 2. A power level drop of 2 r.iW or greater, ,
3 Continuous control rod motion when on AUTOMATIC control, the reactor will be removed from AUTO control, and no attempt will be made to restore reactivity or power level by pulling rods until the phenomenon can te explained.
In the event of a major reactivity loss, as evidenced by:
- 1. Period meter offs'cale (negative),
- 2. A power level drop of 10 MW or greater, the reactor will be scrantned immediately and no attempt to restore power will be made until the phenomenon can be e::plained.
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l 9804170106 980413 PDR FOIA ROLLER 98-100 PDR ,
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PREPARED BY: W.E.Freidhof andG.C.Geial er APPROVED: .Ge a .B t 'e tc h
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WTR N O. P-107 TECHNICAL OPERATIONS OPERATING PROCEDURES AND STANDARDS
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SUBJECTg PAGE 5 0F ABNORVAL OPERATION IROCEDURES i
DATE: ftEVISION NO. SUPERSEDES S. P. NO.:
R l July 15, 1960 Original D MD!
! FISSION PRODUCT RELEASE INTO PRIMARY C001AFf f Fission product release because of a defective fuel element or experiment will l be indicated by high level on the Fission Product Monitor and/or the Head Tank l Vent Monitor. In the event of an alarm from either of these channels, the follow-ing procedure will be initiated.
I 1. Cutback reactor power level manually to 20 M#.
j 2. Verify alarm.
- a. If alarm is from Fission Product Monitor, check against Head Tank Vent Monitor.
. b. If alarm is from Head Tank Vent Monitor, close valve with manual control. If level drops, alarm should be presumed to be genuine.
3 Scram reactor immediately and carry out Plant Shutdown Procedure F-105, but keep PC Ion Exchanger in' service. Return water from Surge Tank to Head Tank as necessary to balance Ion Exchanger flow.
I 4 Obtain complete radiation survey of WTR site and water samples from
, accessible points in Shutdown Coolant System. Further steps will be I determined by the results of this sampling.
ADDITIONAL STEPS FOR IJRGE SCALE RELEASE If a large scale release occurs, such as might be caused by a fuel element melt-down, the fission product concentration in the head tank will raise radiation levels throughout the plant to the point where most of the radiation monitor I channels will alarm. If it becomes apparent that this has happened, the reamor l will be scrammed and the procedure below will be initiated. ,
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- 1. The Shift Supervisor, or his delegate in the Control Room, will order evacuation of the plant with exception of Control Room staff and assume the duties of Emergency Coordinator, as specified in the WTR Emergency l
Procedure Manual.
- 2. Make certain that automatic closure of Head Tank Vent Valve and shutdown of Surge Tank Blower have taken place. l 3 Close Main Flow Control Valve.
4 Open Shutdown Stop Valve (stopping PC pumps).
- 5. Close Main Stop Valve.
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PREPARED BY: W.E.Freidhof and G.C.GeisleAPPROVED: G.C.Geisler an yv ' win- ronu ye
T WTR N O. P_107 TECHNICAL OPERATIONE OPERATING PROCEDURES AND STANDARDS ABNORMAL OPERATION PROCEDURES I
DATE: ftEVISION NQ. SUPERSEDES S. P. N O.:
July 15,1%0 Original REV. NO.:
DATED
- 6. Start Shutdown Coolant Pump.
l 7. At this point the Control Room will be evacuated if necessary, due to l high radiation level or airborne contamination. Otherwise, continue sters l below. If evacuation is necessary, they will be carried out as soon as l control room een be re-entered. ,
l 8. Initiate per.bdic radiation surveys and PC water analysis. Pump water l from surge tink to head tank as needed to balance flow through PC Ion I j Exchanger.
j 9. The next step will be to allow off-gassing of head tank. .
- a. Open Head Tank Vent Valve. If Head Tank Vent Monitor approaches level required for automatic closure, it will be closed immediately.
Repeat at 15 minute intervals until it is possible to leave valve open.
i b. Start surge tank blower. If Head Tank Vent Monitor approaches level required for automatic shutdown, stop blowe" immediately. Repeat at intervals of 15 minutes until blower can bc . ft in operation.
- c. Start up PC System and operate at 4,000 gp... If Head Tank Vent monitor approaches the control point, the vent valve will be closed, the PC system shutdown, and the entire process repeated in 30 minutes. During this period the Secondary Cooling System will be l
operated to keep primary coolant as close to normal operating temperature as possible, i
- 10. The PC system will be operated in this manner for at least four hours, and longer if it appears to be still effective. At the end of this period periodic overflowing of the surge tank will be allowed, to produce a gradual drop in head tank level.
- 11. When sufficient water has been drained from the PC system to make further 1 operation impossible, it will be shut down and Shutdown Coolant Flow re-established.
- 12. When the reactor core has decayed to the point at which convection cooling and reduced water level will provice adequate heat removal, the snake pit valves will be opened and the vessel and associated piping drained down to the level of the outlet line. While this is being done, the LP thimble instrumentation should be monitored to detect any undesirable temperature increase, rk , &n f V.ddC#,
PREPARED By W.E.Freidhof :md C .C.GeislerAP PROVE D. G.C .Geisler l . . . . .
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1 WTR N O. P-107 f TECHNICAL OPERATIONS f OPERATING PROCEDURES AND STANDARDS {
PAGE 7 0F 7 SUBJECTg ABNORMAL OPERATION PROCEDURES ;
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DATE REVISION NO. SUPERSEDES S. P. NO.
R EV. NO.: {
July 15, 1960 Original DATED!
l 13 At this point it may be desirable to refill the vessel and drain it j
! again. This will be determined after a review of the results of water j sampling.
f 14 Refill PC System to minimum operating level and restart, operating at l 4,000 gpm.
Steps subsequent to this will be determined by a review of the results of water sampling.
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LerAPPROVED: G.C.Geisler ce PREPARED BY* W.E.Freidhof and G.C.Geis . .
A WTR-FORM *.
r UNITED STATES OF AMERICA ATOMIC ENERGY COMMISSION y ,/
In the Matter of )
Facility License No. TR-2
)
- WESTINGHOUSE TESTING REACTOR)
AMENDMENT TO ORDER DATED JUNE 30, 1960 By an Order dated June 30, 1960 Westinghouse Electric Corporation (Westinghouse) was prohibited from loading or starting up the WIR with-out the prior written approval of the Commission; was ordered to file a report of certain corrective measures taken or to be taken to prever.t recurrence of the incident which occurred on April 3,1960; and was re-quired to submit plans relating to redesign of the containment of the facility.
By letter dated July 12, 1960, Westinghouse requested that the Order dated June 30, 1960, be amended to permit installation of nine control rods with fuel element followers and four fuel elements with instrumented experiments. Westinghouse stated that granting of their request would l
avoid a delay in returning the reactor to service af ter authorization to load and start up the f acility is received.
The AEC has found that the installation of the thirteen fuel elements would not endanger tae public health and safety. Installation of these l
i fuel elements would not permit criticality to be achieved and would not f I create any hazard of accidental criticality.
In view of the foregoing and pursuant to the Atomic Energy Act of 1954, .
as amended, and the regulations in Parts 2 and 50, Title 10, Code of Federal Regulations, the Order dated June 30, 1960, in the above entitled matter is B
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.: ' , ,,/ hereby amended by adding the following paragraph:
"Notwithstanding .the foregoing provisions of this Order, Westinghouse, in accordance with Facility License No.
TR-2, may install the nine control rods with fuel element followers and the four fuel elements with instrumented experiments described in the letter from Westinghouse dated July 12, 1960 "
FOR THE ATOMIC !!NERGY COMMISSION H. L. Price -
Director Division of Licensing and Regulation l
l j Date: July 25,1960 t
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