ML19327B931
| ML19327B931 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/02/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-89-2127, NUDOCS 8911140229 | |
| Download: ML19327B931 (8) | |
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OPU Nuclear Corporation g
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Route 441 South 9
Middletown, Pennsylvania 17057 0191 717 944 7621 i.
i TELEX 84 2386.
J Writer's Direct Dial Number:
November 2, 1989 C311-89-2127-t U.S. Nuclear Regulatory Commission
. Attn: Document Control Desk l
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~ Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 i
Reactor Operator and Senior Reactor Operator a
Licensing Examination is a' listing of Exam Reference Material' that was sent to Nels Jenson, EG&G Idaho. This material was sent October 11, 1989 in. response to a NRC letter dated October 2, 1989. This was the only set of information requested.
Sincerely, b
H. D. Huk 11 Vice President & Director, TMI-1 HDH/DVH/spb:2127 Attachment
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PDR ADOCK 05000289 V
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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation f
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o C311-89-2127 Page 1 of 7 i
EXAM REFERENCE MATERIAL SENIOR REACTOR OPERATOR GROUP $14 BOOK BOX NO.
DESCRIPTION NO.
1 ADMINISTRATIVE PROCEDURES 1001A THRU 1009 1
2 ADMINISTRATIVE PROCEDURES 1011 THRU 1036 1
3 ADMINISTRATIVE PROCEDURES 1037 THRU 1044 1
4 EMERGENCY PROCEDURES 1202-2 THRU 1202-31 1
5 EMERGENCY PROCEDURES 1202-32 THRU 1202-42 1
6 ABNORMAL PROCEDURES 1203-1 THRU 1203-45 1
7 ABNORMAL TRANSIENT PROCEDURES 1210-1 THRU 1210-10 2
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OPERATING FROCEDURES 1101-1 THRU 1101-3 2
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OPERATING PROCEDURES 1101-4 THRU 1102-10 2
10 OPERATING PROCEDURES 1102-11 THRU 1103-8 2
11 OPERATING PROCEDURES 1103-11 THRU 1104-9 2
1 12 OPERATING PROCEDURES 1104-11 THRU 1104-19 3
13 OPERATING PROCEDURES 1104-20 THRU 1104-24P 3
14 OPERATING PROCEDURES 1104-25 THRU 1104-28I 3
15 OPERATING PROCEDURES 1104-28J THRU 1104-29N 3
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16 OPERATING PROCEDURES 1104-29P THRU 1104-38 4
l 17 OPERATING PROCEDURES 1104-40 THRU 1104-45N 4
l 18 OPERATING PROCEDURES 1104-46 THRU 1104-52 4
l 19 OPERATING PROCEDURES 1104-53 THRU 1105-8 4
20 OPERATING PROCEDURES 1105-9 THRU 1105-19 5
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21 OPERATING PROCEDURES 1105-20 THRU 1106-7 5
22 OPERATING PROCEDURES 1106-8 THRU 1107-1 5
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[mn-C311-89-2127 Page 2 of 7
(_
EXAM REFERENCE MATERIAL f
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SENIOR REACTOR OPERATOR GROUP #14 BOOK BOX
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NO.
DESCRIPTION NO.
l 23 OPERATING PROCEDURES 1107-2 THRU 1107-4 5
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24 OPERATING PROCEDURES 1107-4.1 THRU 1107-8 6
25 SURVEILLANCE PROCEDURES 1300-3A/B THRU 1303-4.11 6
26 SURVEILLANCE PROCEDURES 1303-4.13 THRU 1303-5.2 6
27 SURVEILLANCE PROCEDURES 1303-7.1 THRU 1303-11.25 6
28 REFUELING PROCEDURES 1502-1 THRU 1505-1 6
29 REFUELING PROCEDURES 1505-3 THRU 1507-7 7
30 EMERGENCY PLAN IMPLEMENTING PROCEDURES 9471-IMP-1300.01 THRU 9471-IMP-1300.36 7
31 RADIOLOGICAL CONTROLS PROCEDURES (SEE BOOK FOR INDEX) 7 32 ALARM RESPONSE PROCEDURES ABA THRU IWT 7
33 ALARM RESPONSE PROCEDURES IWTS THRU MAP J 7
34 ALARM RESPONSE PROCEDURES MAP K THRU PLA 7
35 ALARM RESPONSE PROCEDURES PLB THRU RCH 7
36 ALARM RESPONSE PROCEDURES RWA THRU UPS 7
37 TMI UNIT 1 PRINT BOOK 8
38 REPLICA SIMULATOR FLOW DIAGRAMS 8
39 SIGNIFICANT DIFFERENCES BETWEEN THE PLANT AND THE SIMULATOR 8
40 SIMULATOR: REMOTE FUNCTIONS; INITIAL CONDITIONS; SPECIFICATIONS & INSTRUCTOR STATION FEATURES; OPERATIONAL LIMITS 8
41 SIMULATOR: MALFUNCTION CAUSE AND EFFECT 8
42 PUMP HEAD CURVE BOOK; TANK DATA BOOK; CYCLE 7 RELOAD REPORT 8
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Page 3 r,f 7 EXAM REFERENCE MATERIAL SENIOR REACTOR OPERATOR GROUP #14 BOOK BOX NO.
DESCRIPTION NO.
43 OPERATOR TRAINING STANDARD 8
44 OPERATIONS DEPARTMENT MEMOS 9
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45 TMI-1 TECHNICAL SPECIFICATIONS-AMENDMENT #151 9
46 TMI-1 PROCEDURE INDEX 9
47 CLASSROOM LESSON PLANS (SEE BOOK FOR INDEX) 9 48-CIASSROOM LESSON PLANS (SEE BOOK FOR INDEX) 9 49 TMI-1 PROBABILISTIC RISK ASSESSMENT-HUMAN ACTIONS ANALYSIS REPORT 9
50 TECHNICAL
SUMMARY
REPORT 9
51 REPLICA SIMULATOR EXERCISE GUIDES (SEE BOOK FOR INDEX) 9
'VOL.1 OPERATIONS PLANT MANUAL: ELECTRICAL SYSTEMS AND PRIMARY SYSTEMS 10 f
VO L. 2 OPERATIONS PLANT MANUAL: PRIMARY SUPPORT SYSTEM; RIVER WATER SYSTEMS; RADWASTE SYSTEM 10 VOL.3 OPERATIONS PLANT MANUAL: REACTOR PROTECTION INSTRUMENTA-TION AND CONTROL; i
SECONDARY INSTRUMENTATION AND E
CONTROL 10 VCL.4 OPERATIONS PLANT MANUAL: SECONDARY SYSTEMS; TURBINE AND i
1 TURBINE SUPPORT; SECONDARY i
SUPPORT 10 VOL.5 OPERATIONS PLANT MANUAL: CHEMISTRY CONTROL; FIRE I
PROTECTION SYSTEMS; HEATING AND VENTILATION SYSTEMS 10 l
VOL.6 OPERATIONS PLANT MANUAL: MISCELLANEOUS SYSTEMS 11 l
VOL.7 OPERATIONS PLANT MANUAL: BASIC POWER PLANT FUNDAMENTALS 11 VOL.8 OPERATIONS PLANT MANUAL: BASIC POWER PLANT FUNDAMENTALS 11
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VOL.9 OPERATIONS PLANT MANUAL: PRACTICAL POWER PLANT FUNDAMENTALS; GENERAL PLANT 11
D C311-89-2127
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Page 4 of 7 BOOK #47 - INDEX OF CLASSROOM LESSON PLANS 11.2.01.017 VITAL AC/DC DISTRIBUTION SYSTEM 11.2.01.027 CLASS 1E ELECTRICAL SYSTEM 11.2.01.028 EMERGENCY FEEDWATER SYSTEM 11.2.01.029 ENGINEERED SAFEGUARDS ACTUATION SYSTEM 11.2.01.055 ICS 11.2.01.080 NON-NUCLEAR INSTRUMENTATION 11.2.01.132 REACTOR PROTECTION SYSTEM 11.2.01.168 FUEL BEHAVIOR AND MECHANICAL MANEUVERING RECOMMENDATIONS 11.2.01.176 PRESSURIZED THERMAL SHOCK
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C311-89-2127 p
Page 5 of 7 L
i-BOOK #48 - INDEX OF CLASSROOM LESSON PLANS 11.2.01.210 ATP 1210-1, REACTOR TRIP 11.2.01.211
.ATP 1210-2, LOSS OF SUBCOOLED MARGIN i
11.2.01.212 ATP 1210-3, EXCESSIVE COOLING 11.2.01.213 ATP 1210-5, OTSG TUBE LEAK / RUPTURE 11.2.01.214 ATP 1210-6, SMALL BREAK LOCA 11.2.01.215 ATP 1210-7, LARGE BREAK LOCA 11.2.01.216 ATP 1210-8, RCS SUPERHEAT 11.2.01.217 ATP 1210-9, HPI COOLING / RECOVERY FROM SOLID OPERATIONS 11.2.01.216 ATP 1210-10, ABNORMAL TRANSIENT RULES, GUIDES, AND GRAPHS 11.2.01.219 ATP 1210-4, LACK OF HEAT TRANSFER 11.2.01.309 CYCLE PHYSICS DATA 11.2.01.311 HEAT SINK PROTECTION SYSTEM) 11.2.01.326 ATOG THEORY AND PRACTICE l-l l
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l-C311-89-2127 Page 6 of 7 L
r, RADIOLOGICAL CONTROLS PROCEDURES 4
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j 9100-ADM-4000.01 ADMINISTRATIVE DOSE LIMITS t
9100-ADM-4110.01 RADIATION WORK PERMIT 9100-ADM-4110.06 CONTROL OF LOCKED HIGH RADIATION AREAS 9100-ADM-4110.09 REACTOR BUILDING ENTRY 9100-ADM-4250.01 RELEASING RADIOACTIVE LIQUID WASTE 9100-ADM-4250.02 RELEASING RADIOACTIVE GASEOUS WASTE F
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C C311-89-2127 Page 7 of 7 -
m REPLICA' SIMULATOR EXERCISE GUIDES' P
'11.7,05.001 PLANT STARTUP TO 15% POWER 31.7.05.011 DEGRADED GRID VOLTAGE / LOSS OF FW 11.7.05.019 MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT j
11.7.05.021 STEAM LEAK IN CONTAINMENT 11,7.05.024 LARGE BREAK LOCA WITH COMPLICATIONS 11.7.05.025 TOTAL LOSS OF FEEDWATER s
11.7,05.028 OTSG TUBE LEAK AT POWER 11.7,05.031 OTSG TUBE RUPTURE 11.7.05.033 LOSS OF VACUUM, OTSG TUBE LEAK l
11.7105.036 MSSV FAILURE & TUBE RUPTURE ON SAME OTSG j
' 11.7.05.037 SMALL' BREAK LOCA 11.7,05.042' TOTAL LOSS OF NUCLEAR SERVICES CLOSED COOLING WATER 11.7.05.043 LOSS OF OFFSITE POWER AND EDG FAILURE 11.7.05.045 LOSS OF RC PUMPS DURING PLANT STARTUP 11.7,05.046 STEAM LINE BREAK INSIDE CONTAINMENT 11 7.05.047 STEAM LEAK NEAR MAIN STOP VALVES 11.7,05.048 LOSS OF R & T 480V BUSES 11.7.05.049 MAIN FEEDWATER LINE BREAKS 1
11.7.05.050 REACTOR / TURBINE TRIP 11.7.05.051 HPI/LPI PIGGY-BACK OPERATION DURING LOCA l
11.7.05.052 RCS LOCA AT RC PUMP SEAL PACKAGE 11.7.05.053 LOSS / RETURN OF "B" DC DISTRIBUTION i
11.7.05.054 SMALL BREAK LOCA AND LOSS OF PRIMARY TO SECONDARY HEAT TRANSFER 11.7,05.055 SUPERHEAT DEMONSTRATION
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