ML19262A538
| ML19262A538 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/14/1972 |
| From: | Collins P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Wise METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7911130554 | |
| Download: ML19262A538 (8) | |
Text
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SEP 14 1972 M,elropolitan Edison Ccapany e
ATIN: Mr. John L. Wise Superintendent Three Mile Island Nuclear Tenerating Station Post Offica Box 480 Middletown, Pennsylvania 17057 Gentlemen:
This letter supplies the information regarding the scheduling of operator and senior operator examinations for Three Mile Isund Nuclear Power Plant.
Prior to the administration of cold examinations at a facility, we must be assurel chat the facility control mechanism and instru-mentation s-e in such condition to permit the effective administration of a simulated operating test, that the facility license review is essentially completed, inr1= ding determination of the technical specifications, and that we have received the facility's normal and emergency operating proesdures.
Enclosed is a listing of procedures that are normally submitted to this office in order for us e.a properly prepare the examinations.
We realize that some of the proceduus may not be applicable to your facility and that your procedure titles may not be the same as listed. Also, you probably will have procedures that are not contained in the enclosed listing, such as administrative procedures that define the authorities and responsibilities of licensed operators and senior operators during normal, abnormal and emergency conditions.
Any such procedures that pertain to the duties and respousibilities of licensed personnel should also be submitted, a n ei A A[o o P lo
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Hr. John L. Wise 39 ; 4 g Based on the Three Mile Island fuel loading date, we suggest the following time sequence for the administration of the cold exami-nations. This schedule is predicated on the items listed above being resolved in a timely manner.
If they are not, or if your fuel loading data changes appreciably, the schedule would be revised.
DATE ACTIVITY Eight weeks prior to the Receipt by the Operator Licensir.g administration of written Branch of all applications and examinations.
all operating. emergency and appli-cable administrative procedures.
Six to eight weeks prior Administration of the operator and to fuel loading.
senior operator written ar==inations.
Two to four veska prior Administration of the " cold" to fuel loading.
operating tests.
One week prior to fuel Notification of final examination loading.
results and issuance of licenses.
The above schedule vill provide time for preparing the examinations, grading the written examinations and evaluating results of the " cold" operating tests so that successful applicants vill receive licenses prior to the beginning of the core loading operation.
Normally, we administer the " hot" written '>==4n=tions and operating test to applicants after the plant has operated at 20 to 30: power.
We find that the applicants are well-prepared for the====4nationn after they have had an opportunity to participate in the control room activities during the startup testing prograu. However, we have administered the written portion of the examination prior to fuel loading to well-motivated and highly-trained applicants. We can administer these written examinations with the " cold" applicants or at the time the " cold" applicants are administered their operating test.
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Mr. John L. Wise SEP 141972 I hope this information is of use to you.
Sincerely yours, ORIGitmL blunED BY P. F. COLLINS Paul F. Collins, Chief Operator Licensing Branch Directorate of Licensing Enclosurst FW1 Procedures bec:
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Form AEC-31s tRev. 9 51) AECM 0240
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e P'/R PROCEDURES INTEGRATED OPERATING PROCELURES 1.
Plant startup from cold condition to hot standby.
2.
Plant startup frc hot standby to power.
3.
Plant shutdown i'rct pcwer to hot shutdoun.
4.
Plant shutdcun fres hot shutdown to cold shutdown.
5.
Operation hot pcwcr.
6.
Operation with less than full fica.
SYSTf21 PROCEDURES 1.
Reactor control and protection system.
2.
Reactor coolant pump operation.
3.
Prassuricer level and pressure control.
4.
Pressurizer relief tank operation.
5.
Boric acid concentration.
6.
Ecric acid dilution.
7.
Charging letdown and reactor ccolcat pump sccis.
8.
Coolant chemistry addition and control.
9.
Beton recycle systan.
10.
Dtnineralizer resin regenera tion.
11.-
Liquid waste disposal system.
12.
Gasecus waste disposal system.
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Solid cs ta dic;cac1 s> sten, l'.
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Nuclear instrumentation.
7.
Refueling uater purificacion pump operation.
17.
Component cooling water system operation.
18.
Spent fuel pit cooling loop.
19.
Rod control systen.
20.
Residual heat removal systen.
21.
Radiation monitoring systen.
22.
Safety injection system.
23.
Containment spray systen.
24.
Service and instrument air systcas.
25.
Steaa generator and secan generator level control systcas.
26.
Condensate systen.
27.
Primary water treatn2nt plant..
28.
Condenser and condenser circulating.*ater systems.
29.
Feedwater hcater and drain system.
30.
Moisture separator and reheater.
31.
Turbine generator cperatica.
32.
Electrical distribution systems.
33.
Diesel generator opcration.
34.
Main generator auxiliaries.
35.
Fire water sys tcas.
3 6.' Containment cooling and ventilation.
37.
Service unter systers.
38.
Seca dum, evstcas.
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Auxiliary feedwater system.
40.
Penetration seal systens.
41.
Reactor coolant system, venting, draining and filling.
42.
Hydrogen recerbiners.
43.
In-core instrumentation.
EMERGENCY PROCEDURES El.
Loss of reactor coolant.
E2.
Main steam line break, E3.
Stean generator tube rupture.
E4.
Station blackout operation.
E5.
Control room inaccessibility.
E6.
Loss of ecmponent ecoling.
E7.
Dropped rod.
E8.
Loss of reactor ccolant flow.
E9.
Continuous rod withdrawal.
E10.
High activity arca radiatica tenitoring system.
Ell.
E=crgency shutde.?n resulting fren a reactor trip.
E12.
Emc~rgency boration.
E13.
Scrvice water systen failure.
E14.
Fire.
E15.
Fuel handling accident.
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AE:'ORMAL FEfCEDi!RES A1.
Nuclear instrunentatica malfunction.
A2.
Highreactorcoolbnt activity.
o A3.
Malfunction of pressurizer relief for safety valves.
A4 Malfunction of residual heat removal.
AS.
Failure of spent fuel pit cooling.
A6.
Malfunction of rod drive system.
A7.
Malfunction of reactor makeup control.
AS.
Malfunction -: reactor coolant pump seal.
l.9.
Reactor coolant systea leakage.
A10.
Turbine vibration.
All.
Loss of heater drain pump, feedwater pump or condensate pump.
A12.
Partial loss of condenser vacuum.
A13.
Secondary load rejection.
A14 Accidental release of liquid or gaseous radioactive vaste.
FUEL HANDLING PROCEDURES FHl. Initial fuel loading.
FH2. Handling of ne" fuel assemblics.
FH3. Refueling.
FH4 Fuel handling and RCC elenent replacement.
FH5. Limitatiens and precautiens for handling new and partial spent fuel asse='alies.
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Handling burnable poison rod asse=blics.
FH7.
Refueling equipment operating instructions.
- " FH8.
Recovery from refueling.
RADIATION PROTECTIO: PROCEDURES RPl.
Radiation Control Guidelines RP2 Radiat' ion k'ork Permits RP3.
Centrol Area Access RP4 Personnel Mcnitoring RP5.
Decontamination RP6. Area Surveys RP7. Use of Prctective Clothing and Equiptent RP8.
Survey Instrument Calibration and Use RP9.
Handling of Radioactive Materials P.P10 Radicactive Liquid Spills RPil.
Personnel Injury in Controlled Area 0
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