ML20024D795
| ML20024D795 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/13/1983 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20024D793 | List: |
| References | |
| SP-12.014.07, NUDOCS 8308080220 | |
| Download: ML20024D795 (31) | |
Text
ATTAC1 MENT I 1 =
] /#-
Q Submittcd: f TdEddr/M16' Reviewed /0QA Engr.: 'k+N 1
~
- Approv,ed/ Plant Mgr.: i/
[' MC-1 SP Number 12.014.07 Revision: 1 , .
Date Eff.: 6//a/&G
' ' ~ '
TPC TPC TPC LICENSED OPERATOR REQUALIFICATION PROGRAM O
1.0 PURPOSE
Io establish a method of implementation for the licensed operator requalification program. I,
2.0 REPONSIBILITY
The Training Supervisor shall be responsible for ensuring proper implementation of the requirements set forth by this procedure.
PPF 1021.200-6.421 rgnT!GR "fT bJ ngw hfii J n G Jli
- =-
g 8308080220 830002 PDR ADOCK 05000322 V PDR I.,
~ .
4 - *
3.0 DISCUSSION
i 3.1 Periodic requalification for all operators and senior operators is
^
necessary for the personnel to maintain competence, particularly to respond
, to abnormal and emergency situations.
- 3. 2' ' This procedure describes the method to periodically relicense NRC licensed Reactor Operators (RO's) and Senior Reactor Operators (SRO's), and to meet the requirement of References 11.1, 11.2, and 11.3.
3.3 ' Licensed RO's and SRO's who have been actively and extensively engaged as RO's or SRO's shall participate in the requalification program.
Individuals who maintain RO or SRO licenses for the purpose of providing backup capability to the operating staff.shall also participate in the requalification program.
3.4 ~ -Definitions related to the SNPS Licensed Operator Requalification Program are contained in Appendix 12.1.
3.5 The following topics are contained in this procedure:
Page 8.1 Schedule 3 8.2 Lectures 3 8.3 On-the-job Training 5 8.4 Evaluations 0~, 8.5 Records 7
8 Appendix 12.1 - SNPS Requalification Program Definitions Appendix 12.2 - SNPS Requalification Control Manipulations Appendix 12.3 - Drill Scenario Form
4.0 PREREQUISITES
N/A
5.0 PRECAUTIONS
N/A 6.0 LIMITATIONS AND PRECAUTIONS:
N/A 4
SP 12.014.07 Rev.1 Page 2 e
r~
()N
- 3.0 DISCUSSION:
3.1 Periodic requalification for all operators and senior operators is necessary"for the personnel to maintain competence, particularly to respond
, to abnormal and emergency situations.
3.2 This procedure describes the method to periodically relicense NRC licensed Reactor Operators (RO's) and Senior Reactor Operators (SRO's), and to meet the requirement of keferences 11.1, 11.2, and 11.3.
3.3 Licensed RO's and SRO's who have been actively and extensively engaged as R0's or SRO's shall participate in the requalification program.
Individuals who maintain RO or SRO licenses for the purpose of providing backup capability to the operating staff shall also participate in the requalification program.
i 3.4 Definitions related to the SNPS Licensed Operator Requalification Program are contained in Appendix 12.1, 3.5 The following topics are contained in this procedure:
Page 8.1 Schedule 3 8.2 Lectures 3 8.3 On-the-job Training 5 0 8.4 Evaluations 7
8.5 Records 6 Appendix 12.1 - SNPS Requalification Program Definitions Appendix 12.2 - SNPS Requalification Control Manipulations Appendix 12.3 - Drill Scenario Form
4.0 PREREQUISITES
I N/A
5.0 PRECAUTIONS
N/A 6.0 LIMITATIONS AND PRECAUTIONS:
[
N/A i
l O
V SP 12.014.07 Rev. 1 Page 2
l . . . s,
. .- ..= .n-3 ~
\ ',
{ % <
7.0 TEST EQUIPMENT: .
':- ~*
N/A * -
. :~ u , 5 8.0 , PROCEDURE: ,
~
! c x 8.1 , Schedule
, , . =
8.' 1.1 The SNPS Licensed Operator Rcquelific'ation Program shall be Jrepetitive and completed .on a pne year basis, resulting in license (.
renewal every two years.m The program shall consir;tfof preplanned Lelassroom Icetures, on-theljob trainin'g, simulator training, plant '
drills and examinations as necessary to document operator proficiency and annual, evaluations.
, e
- s. 1 8.1.2 A minimum of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.of reasonably spread, preplanted lectures .s shall be scheduled each year. '
,: ;
8.1.3 ,The lectures will be scheduled throughout the year.; Each license holder should participate in the training schedule ene week out of N
~
every six.
~\
8.1.4 Individuals who maintain licenies for the purpose of, pro'iiiding backup capability to the operating staff shdll participate'in the requalification~ program to the extent that their norm'al, duties '
preclude the need for specific (retraining in particular areas.
1 s -s, - s x' 8.1.5: Pd.rsonnel assigned to li'ccr.'se requalification training shall be
, assigned no concurrent dutias during the periods tiiat they are -
actually engaged in;t. raining activities.
q -
8.2 Lectures *
->: f, ,, s 8.2.1 Preplanned classrcom : lectures chn11. be scheduled ard should provida. as a minicuC training in the following subjects:
8.2.1.1 Reactor Operator Training
. 1 Principles of Nuclear Power Plant Operation.
.2 Fundamentals >of Thermodynamics, Heat Transfer and Fluid Flow.
.3s " Plant Design includir.,g Safety and Emergency Systems.
.4 InstrumentdandContrc ^
", (; ,s ,
s w .. , .,
}
~
u s;-
,; -
(.- ( , (.. '
- s[ c. ,
. -s
'i ,- <
'SP 12.614.07 Rev. 1 ' '
v '
. =Page 3 . ( ,
?
_ , .. \% ,
l ~_ _# _ .. ._. . s __ a ._ 1. h_ v. _ _" _ . - . - . -
fO). #
, .5 Procedures - Normal. Abnormal, Emergency and Radiological Controls, and changes to these procedures.
~
.6 Technical Specifications. .
,.7 Related Nuclear Industry Operating Experience.
.8 Changes to Facility Design and License.
.9 Applicabic portions of Title 10 Chapter I Code of Federal Regulations.
.10 Hitigation of Core Damage (1 8.2.1.2 Senior Reactor Oper,ator Training:
.1 Theory of Nuclear Power Plant Operation.
.2 Theory of Fluids and Thermodynamics.
.3 Plant Systems Design, Control and Instrumentation.
4 Procedures - Normal. Abnormal, Emergency and Radiological Controls, and changes to these procedures.
.5 Administrative Procedures, Conditions and Limitations.
.6. Technical Specifications.
.7 Appifcabic portions of Title 10 Chapter I Code of Federal Regulations.
.8 Changes to Facility Design and License.
8.2.2 Each license holder shall review the abnormal and emergency operating procedures on an annual basis.
Compliance with this requirement may be met by:
8.2.2.1 Actual performance under abnormal or emergency operating conditions.
8.2.2.2 Walkthrough of the procedural steps necessary to cope with the situation.
x)
SP 12.014.07 Rev. 1 Page 4
(\~#) 8.2.2.3 Drills utilizing a training simulator or on-site preplanned drill scenario.
8.2.2.4 Preplanned lectures. ;-
8.2.2.5 Supervised self study. All self study will be under supervision of the training section and documentation
- will include examinations to verify effectiveness of the self study.
8.2.2.6 Procedure review and/or rewrite as part of normal job function.
8.2.3 No more than 50% of the lecture series outlined in this section may be presented by videotape or film presentation. All lectures should be a balanced presentation of live instruction with related training aids.
8.2.4 A written examination shall be administered at the completion of each vrek of on-site requalification training and each individual should also participate in at least 3 plant drill scenarios each training week.
8.3 On the Job Training 8.3.1. Control Manipulations-O.. .
8.3.1.1 Ten reactivity control manipulattens are required to be performed annually by each licensed operator and senior operator. Reactivity. control manipulations performed at SNPS or at the Limerick simulator can be used to fulfill this requirement.
8.3.1.2 Until the SNP3-specific simulator becomes availabic, the SNPS requalification training program will utilize the Limerick plant simulator for retraining licensed operators. Use of the Limerick simulator will include.
the following:
a) SNPS normal, abnormal and emergency operating procedures as well as the appropriate SNPS alarm response procedures will be used by SNPS operators during simulator requalification training at the Limerick Simulator, b) Simulator requalification training will be conducted using a crew concept; the students will be required to duplicate to the extent practical the functions l
SP 12.014.07 Rev.1 Page 5 i
g g- e
__- ~- - - *>...%-,. . _ _ m _
e ,
9 *
.q -
j3 if and responsibilities of the normal SNPS control room stcff. .
c) Each SNPS licensed RO and SRO williundergo at Icast
, five days of training at the simulator every.six months. During these five days of simulator training, each student will spend at least three days operating the simulator controls as part of the training crew.
d) Individual performance on the simulator will be evaluated by use of a drill scenario form (Appendix 12.3). Drill scenario forms will be completed for each licensed operator during each week of simulator training.
8.3.2 Methods of Training 8.3.2.1 All licensed personnel shall be kept cognizant of SNPS design, procedural and facility changes using one of the following methods:
.1 Brief lectures conducted by section supervision or other appropriate personnel.
.2 Staff meetings (also includes Review of Operations L O'" - Committee meetings).
.3 Written communications to each licensed individual.
.4 Pre-planned lecture series.
.5 Required reading list.
8.3.2.2 Other o:n-the-job training such as cross job training and on-shift discussion may be used to increase the individuals proficiency.
8.3.2.3 On an annual basis, each license holder shall participate in plant drills and control manipulations covering the
, evolutions listed in Appendix 12.2.
~
Participation in a plant drill involves responding to drill conditions or being an evaluator who observes a'nd evaluates drill response.
Plant drills will be conducted on a crew basis and will involve reviewing plant procedures steps, action identification, equipment control location, expected SP 12.014.07 Rev. 1 Page 6
.j D
instrumentation response, plant communications and Technical. Specification action identification.
Each drill will be planned in a drill scenario as
+
indicated'in Appendix 12.3 and will include'the following:
.1 Plant Condition
.2 Initiating Indication
.3 Expected Response
.4 Individual Evaluation
.5 References The Training Supervisor will review drill critiques and initiate corrective remedial actions if necessary.
8.3.2.4~ Backup licensed reactor operators and senior reactor operators not permanently assigned to an operating shift shall stand one 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> watch per quarter.
8.3.2.5 Persons holding c currently valid NRC license, but not in h an active status for a period of four months or more, shall be refamiliarized and examined prior to resuming licensed activities. This reft.miliarization shall consist of changes or incidents that occurred during the inactive' period and shall include:
.1 Procedural changes
.2 License changes
.3 Plant system modifications Y .4 Plant incidents i The completion of the refamiliarization program shall include written and/or oral examinations, as directed by the Chief Operating Engineer, to document that the license holder is currently familiar with the plant. The Training Supervisor shall document the satisfactory completion of the refamiliarization program, and the NRC shall be notified in accordance with Reference 11.2.
O SP 12.014.07 Rev. 1 Page 7
4 (IT A result of 80% on the written exam and/or a failure on N an oral exam shall require the individual to receive additional training in those designated areas and to observe station operations for a minimu,m of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> prior to re-examination.
6 8.4 Evaluation 8.4.1 An annual written examination comparable in scope.and degree of difficulty to an NRC examination, consistant with the level of license held, will be given to each license holder. Exam topics will be selected from material covered as part of the requalifiction program. Oral one-on-one walkthrough examinations will also be used to supplement this examination.
8.4.2 A licensed individual who receives an overall grade of less than (1 80% or receives a grade of less than 70% in any one category of the annual written exam administered by the SNFS Training Section shall be relieved of his license duties and placed in an accelerated Requalification Program prior to retesting.
8.4.2.1 Training provided to personnel participating in an accelerated requalification program may include preplanned lectures, self study, on the job instruction, or other training as required and will be evaluated via written and/or oral examination.
8.4.3 A grade of less than 70% on any 1ccture series examination shall require that individual to be rescheduled for re-examination and upgrading in that area.
8.4.4 A licensed individual who receives a-failing grade on the annual oral exam shall be placed in an accelerated requalification program.
8.4.5 Licensed individuals who are directly involved with the preparation and grading of examinations are exempt from taking the examinations.
8.5 Records 8.5.1 Rec 0rds for each individual shall be maintained for a minimum of two years by the Training Supervisor and shall include the following:
8.5.1.1 Copies of written examinations administered and answer keys t hat contain point values for each correct answer.
.h SP 12.014.07 Rev. 1 Page 8 L - _ _ _
) 8.5.1.2 Answers given by the licensee to written exaninations.
8.5.1.3 Results of performance evaluations (drill scenarios).
, 8.5.1.4 Documentation of additional training administered to licensed individuals in areas where deficiencies have been demonstrated.
8.5.1.5 Records of attendance at preplanned Icctures.
8.5.1.6 Documentation of licensed personnel cognizance of changes made to station design, appropriate procedures, and the
-station license.
8.5.1.7 Documentation of the annual review of abnormal and emergency procedures.
8.5.1.8 Documentation of participation in reactivity control manipulations (including use of simulator training if applicable). ,
5 9.0 ACCEPTANCE CRITERIA:
N/A 10.0 FINAL CONDITIONS:
N/A
11.0 REFERENCES
11.1 SP 12.014.01, Personnel Training Requirements 11.2 Code of Federal Regulations, Title 10,'Part 55 11.3 FSAR, Section 13.2.2 11.4 FSAR, Table 13.5.1-1, Sections B.1, B.2 L.3 and B.4 11.5 INP0 Guidelines for Requalification Training and Evaluation, GPG 02-10-80 11.6 ANSI /ANS 3.1 - 1978 11.7 NUREG - 0660, Vol. I, 1980 11.8 NUREG 0737, 1980 i
SP 12.014.07 Rev. 1 Page 9
() ,12.0 APPENDICES:
12.1 SNPS Requalification Program Definitions
~
,12.2 SNPS Requalification Control Manipulations 12.3 Drill Scenario Form SPF 12.014.07-1 O
i I
l SP 12.014.07 Rev. 1 Page 10
,4 . .
. c
~
J APPENDIX 12.1 Page 1 of 2 SNPS REQUALIFICATION PROGRAM DEFINITIONS E
~1. JOB CROSS-TRAINING Job cross-training for shift personnel shall consist of assuming the duties and
. performing the functions of other shift classifications.
- 2. ON-SHIFT DISCUSSIONS On-shift discussions may include review of procedures, discussions of plant operations 'and/or other specific material assigned by the Training Supervisor or Ops. ' Supe rvision. These discussions should include review of Reactor Operating Experiences.
- 3. ACTIVE STATUS Licensed individuals whose normal duties are at the station on a day-to-day basis and who are involved in the daily activities at the station shall be considered on " active status".
- 4. BACK-UP PERSONNEL O These are personnel holding an NRC Reactor Operator or Senior Reactor Operator licence but not permanently assigned to an operating shif t. The Operations Engineer and Assistant Operations Engineer are not considered bcckup personnel.
- 5. LICENSED OPERATOR (RO)
Any individual who possesses an operator's license pursuant to Title 10, CFR, Part 55, " Operators' Licenses".
- 6. LICENSED SENIOR OPERATOR (SRO)
Any individual who possesses a senior operator's license pursuant to Title 10, CFR, Part 55, " Operators' Licenses".
- 7. NORMAL OPERATING PROCEDURES Normal Operating Procedures are those procedures which cover those operating activities defined in Appendix 12.1.1, O
SP 12.014.07 Rev. 1
/ / Page 11
('^)/
x-APPENDIX 12.1 Page 2 of 2 S. ABNORMAL OPERATING PROCEDURES 6
Abnormal Operating Procedures are those procedural actions included in the appropriate system operating procedures for the activities listed in Appendix 12.1.1.
- 9. EMERGENCY OPERATING PROCEDURES Eccrgency Operating Procedures are those procedural actions provided for
' combating the potential ecergency conditions listed in Appendix 12.1.2.
O N,-]
SP 12.014.07 Rev. 1
/ / Page 12
. .e . .*
o .
it.
- "
- APPENDIX 12.1.1 Page 1 of 2-SYSTEM OPERATING' PROCEDURES ..
6-
- 2. . Control Rod Drive System
- 3. . Core' Spray System
-4. Diesel Generator 5.- 4,160'V. System 6 '. 480 V System '
.. '7. '120 V AC Instrument Bus
- 8. 120 V AC Reactor Protection System Bux
- 9. 120 V AC Uninterruptible Power Supply
- 10. 125 V DC System O ;> 1. Feel Pee 1 Cee11eS
- 12. HPCI
- 14. _ Of fgas (Incl. SJAE, HOGGER)
.15. Primary ~ Containment Inerting cl6. HVAC-Drywell Cooling-
~17. Reactor Bldg Closed Loop Cool. System
- 18. Reactor Bldg Normal Ventilation Systea (RBNYS)
.19. RCIC 120.- EHR System 1 .
SP 12.014.07 Rev. 1
'/ / Page 13 o
- -
)7. .
(I APPENDIX 12.1.1 4 \s-}/ .- Page 2 of 2
- . 21. Reactor Recirculation' System *
'22.- + Service Water 4
- 23. Reactor Bldg Standby Ventilation System (RBSVS)
.24. Standby Liquid Control System 25.. Condensate System
- 26. Feedwater System
- 27. HVAC - Control Room
. 28. .HVAC - Turbi~ne Building
, 29. Generator Scal.0il System r *
- 30. Main Steam System
- 31. ' Reactor Water Cleanup System
- 32. Station Air System-
- 33. Turbine'Bld'g, closed Loop Cooling System
~
- 34. Turbine Generator
- 35. Turbine EllC
- 36. Turbine Lube 011 System i
- 37. Containment Area Leakage Detection System j 38.- RBSVS & CRAC Chilled Water l~
i SP 12.014.07 Rev. 1
/ / Page 14
- _ _ _ . _ _ _ . . .
i.
2 APPENDIX 12.1.2
) Page 1 of 1 EMERGENCY PROCEDURES ,,
'1. ' Acts of Nature
~2 -Abnormal Releases of-Radioactivity
-3. ~ Control Rod Drop
- 4. Emergency Use of S.L.C.
- 5. Fuel Cladding Failure
- 6. . Fuel Handling Accident-
- 7. Emergency Shutdown
- 9. Loss of containment Integrity .
- 10. Loss of Electrical Power
' I 1. Loss of~ Instrument Air
- 12. Loss of Reactor Building Closed Loop Cooling Water
- 13. Loss of Service Water
- 14. Loss of Shutdown Cooling
- 15. Loss ofLTurbine Building Closed Loop Cooling Water 116. ' Shutdown from Outside Control Rocm
- 17. . Level Control
- 18. Cooldown
~19. Containment Contro).'
- 20. : Level Restoration
- 21. ; Rapid RPV Depressurization
- 22. RPV Flooding
- 23. Transient with Failure to Scram O
SP 12.014.07 Rev. 1
/ / Page 15 L m_ ___ _ _m.m__ __a- - -- --_--%_-+
n- . .
t'
\ '
APPENDIX 12.2 Page 1 of 2 SNPS REQUALIFICATION CONTROL MANIPULATIONS a
The following control manipulatinos and plant evolutions are acceptabic for meeting the reactivity control manipulations required by Appendix A, paragraph 3.a of 10 CFR Part
- 55. The starred items shall be performed on an annual basis; all other items shall be performed on a two-year cycle. However, each' individual should participate in as many reactivity changes as plant conditions permit. Ihose control manipulations which are not performed at the plant may be perforned on a simulator or as part of the plant
-drill program. Personnel wi~ t h SRO licenses are credited with the activities if they direct or evaluate control manipulations as they are performed.
- A. Approach to critical from suberitical on the source range instrumentation to the point of adding nuclear heat verified by establishing a predetermined heatup rate.
B. Plant shutdown.
- C. Manual control of feedwater during plant startup and' shutdown.
- D. Any power change of 10% or greater using control rods or manual recirculation flow control.
- E. Loss of coolant including, Icak rate determination.
- 1. Inside and outside primary containment.
'2 . Large and small F. Loss of instrument air _(must be performed via drill at SNPS).
G. Loss of electrical power (and/or degraded power sources).
- H. . Loss of recirculation flow.
- 1. Loss of condens'er vacuum.
J. Loss of Reactor Building service water.
K. Loss of ROCLCW to individual components.
- L. Loss of feedwater/feedwater system failure.
M. Loss of a protective system channel.
I O
SP 12.014.07 Rev.1
/ / Page 16
APPENDIX 12.2 Page 2 of 2 N. Hispositioned or dropped control rod or rods.
- 0. Inability to move control rods.
P.- Conditions requiring use of the standby liquid control system.
Q. Fuel cladding-failure or high activity in reactor coolant or offgas.
R. Turbine or generator-trip.
S. Malfunction of automatic control system (s) which affect reactivity.
T. Malfunction of reactor pressure control system.
U. Reactor Trip.
V. Main steam line break (inside or outside containment).
W. Nuclear instrumentation failure (s).
.X. Operation of the fuel handling bridges during refueling or core loading or unloading (licensed fuel handling personnel only).
'Y. Moving' control rods in response to a xenon transient.
Z. Manual rod control prior to and during generator synchronization.
/M. Turbine - Generator startup.
BB. Recirculation Flow control malfunction.
CC. Abnormal reactor water level.
DD. Loss of shutdown cooling.
..h SP 12.014.07 Rev. 1
/ / Page 17
APPENDIX 12.3 Page 1.of 1-DRILL SCENARIO ,
PLANT. CONDITION:
INITIAL INDICATIONS:
EXPECTED RESPONSE:
ACTUAL PROBLEM:
'()
{ EVALUATION: SAT.
UNSAT.
Pa Panel ECCS ,
BOP Normal Rx Systems & Electrical _,-
SRO Integrated Plant / Supervisory / / i COMMENTS:
REFERENCES:
SP:
ARP T.S. .
SPF 12.014.07-1 Rev. O SP 12.014.07 Rev. 1
/ / Page 18
ATTACIDfENT II J
4 I
i i
i
-j i
1 4
i i SNPS j LICENSED OPERATOR P.EQUALIFICATION TRAINING 1983 PROGRA'I i
f o J~. .
Cycle-1 February 7, 1983
. Topics Hours
. Program Introduction ,- 1 Station Modifications . 1
- Admin. Procedurca 4 Emergency Procedure Guidelines 8 Tech.~ Spec. Review & Problems 8 Control Room Drills 2 Study
- 6 Exam- 2.
Cycle 2 March 14, 1983 (Limerick Simulator)
. Classrooym 10 Hour,s Systems & Procedures Review Feedwater & Fcedwater Control
-RCIC.
ADS HPCI Core Spray LPCI Reactor. Pressure Control
'Recire Flow Control Simulator 30 Hours Evolutions & Drills Cycle 3 March 28, 1983.
-Systems Review Hours RWCU 1 Recirculation 1.5' RBCLCW. 1 Service Water 2 Loose Parts Monitoring 1 Special Topics
- Manual-Initiation of Scram & Turbine Trip 1 Tech. Spec. Problems- 3 LER's & Station Mods. 2
. Emergency Procedures Review 2 Emergency Pla,n, Emergency Organization Responsibilities 2 Emergency Classification 1.5 Emergency Action Levels 1.5
'l
- .>. . ;
J l
Cont.rol Room Drills. 2 Study ,
-8.5 Exam . 2
_ Cycle 4
' June 6, 1983 Syste s Review- llours
' Containment 2.3
- Steam Sealing. l '. 0 Special Topics Reactor Theory 4.0 Review Station Procedure 12.006.01 1.0 LER's & Station Mods. 2.0 Tech. ' Spec. Problem Solving 2.5
+ H.P. Self Monitoring. 2.0 Respirator Training 4.0 Emergency Plan Evacuation and Accountability 1.5 Notification and Communications 3.0 Re-entry / Emergency Repair & 1.5 Corrective Action' 1.5 Study- 8.5 Control. Room-Drills 3.0 Exam 2.0
- Cycle 5 . July 18, 1983 Systems Review Ilours
~ Extraction Steam 1 Feedwater IIcating 1 Remote Shutdown. 1 Special Topics
- Process. Computer, Operator Interface 3 i LER's & Station Mods. 2 Tech. Specs. Problem Solving 3 Emergency. Procedures Review 2
- .. Pre' Fire. Plan 1 i Thermal Limits 3.5
Emergency Plan Implementing Actions 2.0 Search for Missing Reasons 1.0 i- ;
, = . , . - . . , . ._
I
- s. < . . [
i Control Room Drills 3.0 Study 14.5 Exam 2.0 Cycle 6 August 29, 1983 Systems (Tentative) Hours Radiation Monitoring 3 H2 Seal Oil 1 Stator Cooling System 1.5 Requal Systems Review 9.0 Special Topics LER & Sta. Mods. 2 Tech. Specs. Problem Solving 3 Mitigating Core Damage 2
- Instrument Response Under Accident Conditions Emergency Plan Protective Action Guides & Recovery 2 Control Room Drills 3 Study 9.5 Exam 2 Cycle 7 Limerick Simulator Specific topics not yet scheduled.
i xrracner m a
, FEEP m .
PARCH 7 11 14 18 21 25 23 4' 7 11 14 18 21 2'S I f CB A - -
, 95-/ h i
u l .
l
[-
CB B . BS-l -
i q
l ,
l i
- g3-1 LE C -
R$-1 l ':' LIMERICK I
] l l Il ' .
g3 9 <
83-2 1. ,
LIMERICK
~
1 l
CB E i 1 c ez ->
E
~ '
l
'l I CB. F ,
.: 83-l .
l-
.[I .i , . .
'l ,
~
, > \
~'
- a. ,,,, y- r l 1i , j h ~l . ,
I ' ' / ' ' '
i L
__..___.O6 .. -y-. ....@,-----, - --. -w ww= - - - - -s hw a. e- .m % ; -_
. 1 ,
M 1
m
- 2 . _ .
- __
'O 3%
Q~
\
Y,. ._.
t
' >A N F/.C lacID JWHD' e'/.Lp '
tr) m % _.
3-
-Ci N ..
V ~
%O
' D ~
i y _.
I tq W.
e Q .% - ,
cs e,
t' M
- Dk b _
>m (G yd
= co
- .
.J I a # ( -
-~ 2 -
cc I k !
d-
__. ie t
mf W W
1
( - _
. 1 l
m ~.
e' Q)
N
-- M __
M i I c3
, i.
~ ~
y ccC":
A --
I g -
. \ ;
- l i
t, i ,
' . . 1
- k. . _
- 2 \
1
~
1
~'
( l ,'_ .[D.' .
l i
- 4.2 / 1
~- '.- ,_ -9
.- L.. =..w .a
< m _ u '
a w u -
M W:
.e r
e
"" % % .. i 7*
(u Q"e~C a
a o f
. v -
c
i
' ' 1 e i e i l ! f
-h
- .i l -- __. ~
(
I 5 \ '
i
-3 fl [
r-m
%n
=7 ,l m , .
g i
-4 --
l - -
e .0 i C
r
- a. . -
l
'4- ! ! -
1 ,- W9 J &//9 ^9 d D '4, 200-3y it.i.g
" i I e %)
ampaper e.used- - ====>
c b' -! S e,5 I- i 7.,
m . . . . __
, i ._./ -
_ . _ l i - - . . - - - -
1 __ - _ _._
M ,
U _-
ll r.
P4 hg
.. ( u .-
- - - S2/.s'bQ'c 2g/$?,A'Q7 ?A^CDiv dud h { -
.a
- 4
..cc -
i C .y 1
>- c, u -
~
h
~
v 1 _ --
N tjj J_ , . .r. r
~~
4 __
d [
l 1*
e..- ,_ . -_
l l i __ _
L -
1 ___ _1, . --
~ _
N l
. - .[ ,
r-'L' --
-_- T
--'_.1.-
i j;
i '
I . - -
};~-}__
_ ~ __, __ , ,
4 ,
i_ - { --.-.
(***
i
.-_I.-- I i
\_ _ J, gj-
-l
! 3 -
- Ts +=.-
1
_ _ -. ._. u k~~d C Q D '***
( p i
l x'.
r-.
i
- --6 m.4 .
j . -) i,r ,J
,u u -
~e '1 l (4)
Q '-r --- ---
C 1 ( l~
Q i
L j w ~
1 l
j O
, ! i O
?
~'
" ~- -
. _ . . _ - j , , , , ,
j ~ ,
--e ,
_ il ll l 'i g- 'l p ,- ,5 ,
}
l, , i I .i p P
"~~
, . 4 l l
~~
1 i i g 4 g i
I l ..
l
, _-. _ [gg
,[ ,
i l_
i l ,
f Yc)Y b R YOY -
eq m
i v >
f ) .
. '* l.
i g i , , ,
.,,, p
>""" *=3
- . t I l N l I jj e D
k \
l 1
y --
go .
~ __ __ \
_l __-
m I l a ,, a i tp l
~.-
Q - ;%% / cf2 5,vJVNeir;f gt$ - ._
1- 1 1 -i :i t .r g et l
- l.-
- - - - - U
.l m '
I in _a L.
r I_ _
i il
$ i.
bJ a n .
D v==8 b
f;n
~
~
- i ,
i L 'OQ _-
I e I t
1 l l I l l l j l l l l h ._ i l
' b,est h,vo tevsvv3 i 1 i_i 1 g
c'9 y. ; -1
, 1 E
~,.
, i > _
)*
e,
.h
);
g.a 4 -
i i
)
g (
- t .Fb - t /
~
-.v --
l~ _ _ _ -
~
g- uu ! ! l 4 h :i ll l ( ~~l l , 1
' ~'*
._: .'.- g. 3 l . t
(
l l j ,_[ }_I, '. { _ _ _
_a r._t r,
! j~! I '
i '~~~ }
(*~ j h*" 9&,
. y q _;
i I, w
- ._
- --
..-{_ pa L
(_"' ,_. I. -- - [ ?
i
U-- I ---
~
4 g --
Q p . LLJ %. _f 1_- \
- i
- g_ '
1 i i-owe = -
V l l i
) l I j '
i g .4' -t i l '
l+ v
. - - -- - , j*
j_
1 I l I i
} } j '
1 0 '
_i I O Y . -- -
. . - - . - - - - - ~ . - - - - - . . - . _ _ - . - - . . - - _ . - , . - , . _ - - - - -
, , ., ,, ... ,,m
grm! SEPIBGE -
l - 0CTOBE. -
22 76 29 7 5 9 17 16 19_ 7 'l 76 'l0 3 7 CfBfA l 1 I __ Bs-7 _ _ !
LIP.ERICK ~
. I ..
1
_. _ _ _ - , _l_4 i ,
TW CBIB .: ~
~~~
85=C -
\
_j' l l l c :i , <
_ r .
=_ -
J__L_.. "
- -
t l_
- i 4
jgg g l CFSi C = -- -
a i -- z -
I-
,[- l_ 'i . __Ll )_ - - -
l ll l
i, l l -- - I j g ,
i ]_ - - _
l _i 4 _ _-- - -
(gjg .-
",l. __ .__ _!._ -
gy, -
-I --
l' L_LL _LL i
1
-\
4 -
'1 agues..ep., m..guurem eas. -
I i
! CWIE N 83-5' --
{y]g',[g
- -
i-
~
J
~~
=). '
l l 9 ; .
e
L_3j l l _
__ 11-- -
.CBI F -
= = = - = -
' ~ SS~'
4 --
LIFERICK .
f .l-
= -
- l j .. ,
'I
. j ,[. -4 l l l
i -
s = -
1 P.J . -
I i
[cj,1 - O
-l lIi n.C' l ll 4 l l H_ 1 i i
i I
'U{
l' -
t
f
/ oc r M = .c gggggg_ ;_
t W
ri P/ ' k -
y 19' 9)
CREW A
~~ -- ---~ ~ ~
8S-4 l i t e' = '7 CREW B ; j i as,,y l
^-
l lll l\ '
. ! l Tl I B97 i CREW C l : bygge j i l l I l i I I t
,!. SG-7 i L=;t AA l CRE%, D , ,,,,g 3.4 y l
_LI !
-l I ,
i I l l I
~ CREW E j 83-6 lI I l l i -
CREW F
j i i SS-6 i
-I!ACKues - -
l B3 '7^ !- m 83-73 s l' 'l ,f ,._ g i' % /
L'"isf/ck '
7.-;q, ri i , M rend
jY - -- -
hO-H -
p., p _ y ,w g ,; y 3 g g g g 3 ;-- - - . _
4 13 9 & 15 Jo F) gg Jg.7 _ . ._ ,_._ _..._ _. _ _
-.a. _
l l 1 l
- I Efs N3 l 8'/-/
CREW B 1 J g e[c j -[
-,.m_.
l , l l -
i l l CREW C 8</2/ TI I
i ,
i CREW D BV-/ --l -
i j g l
I ~
i- 1 I l - - -
- i ,
CREW E .< 89-/
I
_2 l
l l I
BV-/ - - -
CREW F L
'I mv O i
ielil Ft ,! '
r
. ._. L. , , v _li. iA _
I i .
- (3; -[g.
. s_. j i
II 1 I ilI i, Il l ll ,
~~
lI ,i i Fj j j jg
~Vu=cenBer:
4no cr v
}Joueu BW! ;-jd - /- -
d >-f d -V T W
'2s > (1
__l l !_
-~
~'
CREW A ~~~ 83-0 l 1
(- }-
- - -
j l __
i CREW B i
,l i 83-8 --h '
i
(
l u ;
I C 83IF i
' 83-8 CREW ;
t
,I I '
1 i
I iI CREW D 83-9 l _
l l
E ;-
~
- 83-8 i i
l' CREW '
sI l
I
! ' I
_] i l l l l-lggp LEX AM #2 1 l CREW F i<
4 j -
,i TTi~~gT*
\ ;f saecreo sr=am. resycs h [l
, i. 1 '
f f l /'w g
Ui l ;i l
litt,,riliti I;< (' -r li i U
i i
i
~ . _
VEP-NOS-5 7 s.
a.- 4 4mm
. Aik
. ,4% .
,. 'y s ,
s
- 9. g -
.,w' e
\s
- g. , . ,
% ;-
m
, h;.T '
^ , ,' _
- ,
~*
- < ,.l ~-
fjl )
Mtc::#
V.enCO
- m. f.
x
.a.
./
'\
.l K.-
4 \ N,
~ ,x i s, k. .> 4
- -
_ y.
~
. , ~ ., v e ..f;
.y ,
'.' \ w p; ._ -
SURRYLUNIT . m 1, CYCLE,7 b a"*'
STARTUP PHYSICS TEST 1 REPORT
w .
's \ \
--s .... t. _ ,
. s.
m -
\
s \ \
n
-[' %
\' ,.. .
J e .
s K ,,
~
a .
< r.
% ,.- c ,
- k. , t .
'. T '
s' s w
\. 4 - ..
\
-y
. w- I ' l-
. 3 :-
M NUCLEAR' OP$ RATIONS 'DEPAPJMENT
\. *, s
~
Virginia Electric and;Poysr Company '
q s- . .. . , ,e s.-. \ ,
s
-