ML20101K314
| ML20101K314 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/13/1984 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20101K309 | List: |
| References | |
| GL-84-10, NUDOCS 8412310297 | |
| Download: ML20101K314 (21) | |
Text
TH E C L EV E L A U D E L E CTil!C i L LU MIN ATl!!G C O M P A N Y P.o. DOX 5000 - CLEVELAND, OHIO 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLOG. - 55 PUBLIC SQUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCLEAR November 13, 1984 PY-CEI/01E-0018 L 9
M.
Mr. R6-D.-Walker, Chief Operations Branch United States Nuclear Regulatory Commission, Region 111 799 Roosevelt Road Glen Ellyn, Illinois 60137 Perry Nuclear Power Plant Dockets Nos. 50-440; 50-441 Operator Licensing
Dear Sir:
This letter is in response to your request dated October 5, 1984 to provide information concerning additional training received by the first Perry Nuclear Power Plant (PNPP) Cold License Class. As you are aware, this class completed the written and simulator exams as of October 1983, but had the oral exam
- delayed, in order to update the license candidate applications with respect to additional training and experience received, a new NRC form 398 (Personal Qualifications Statement - Licensee) will be submitted in December for each candidate. Each application will reflect the training described in the attachments to this letter. This training is designed to ensure the applicant I
remains current and proficient in the operation of the Perry Nuclear Power Plant, and includes the refresher training conducted in 1984, the observation training ressiting from NRC Generic Letter 84-10, and the additional refresher and on-shift training which the candidates are receiving prior to the oral exams. Therefore, for those candidates who have successfully passed their previous exams, written or simulator re-examination should not be necessary in order to complete the license examination process.
NOV 2113M 8412310297 841224 PDR ADOCK 05000440
's V
PDR M
a
Mr. R. D.'Walktr Novciber 13, 1984 PY-CEI/01E-0018 L If you have any questions please do not hesitate to contact us so that we can resolve this matter as expeditiously as possible. We would greatly appreciate a commitment on your part to complete the licensing process as scheduled, and we solicit your intentions relative to this matter.
Very truly yours, Murray R. Edelman Vice President Nuclear Group.
MRE:nje Attachment ec: Jay Silberg, Esq.
John Stefano J. Grobe Mr. J. McMillen, Operator Licensing Section U.S. Nuclear Regulatory Commission, Region III Mr. T. Lang, Operator Licensing Section U.S. Nuclear Regulatory Commission, Region III
r
(
e ATTACHMENT 1 The initial Cold License Class totalled twenty-seven (27) candidates. The class was composed of two (2) License Training Instructors, one (1) Operations Section General Supervisor, three (3) Shift Supervisors, seven (7) Unit Supervisors, ten (10) Supervising Operators (RO), and four (4) Operations Engineers.
After the delay of the final oral exam, the training section organized and implemented continuing refresher training similar to a requalification program.
The intent of this instruction was two-fold. The first was to review plant changes in systems, procedures, and construction, and secondly, to review material from the license training program to maintain the licensee's knowledge level as high as possible. The course also contained industry experiences (SER's, SOER's, NUREG's, and A0ED's) as well as plant tours.
This instruction was delivered to accommodate a six shift rotating schedule (i.e., one week of training every six weeks). Actual implementation began on January 9, 1984, and continued through May 11, 1984. There was a total of three weeks of training taught for each individual. For a detailed listing of material covered during this time period, refer to Attachment 2.
All the material was taught utilizing formal instruction.
This refresher training was suspended in May, 1984, with the implementation of NRC Generic Letter 84-10, which imposed strict operator experience requirements. The license candidates were sent to operating BWR stations where they participated as an extra man on shift for four or six weeks (R0 or SRO candidate respectively). Each individual was given a checklist to use as a guide (Attachment 3) and was directed to complete as much of the checklist as possible during the time of plant observation conditional upon plant operating conditions. This checklist has been retained as part of each candidates training documentation.
Since license candidates were intensively involved with the Perry Plant Start-up and Test Program, it was not considered prudent to send all operators as one group. However, by pursuing an aggressive schedule the experience /
~
observation was completed by September, 1984. Consideration was given at this point to re-initiating formal classroom refresher training. However, as invaluable experience was being gained in plant testing operations, the cold license candidates continued on shift, in the control room full time until October 1984 when the six shift (one training shift) rotating schedule described previously was reimplemented. Thus, an additional two weeks of refresher training was gained in late 1984. The operators from the first cold license class have gained experience both from the System Start-up and Test Program, and from the day-to-day operation of the systems which have been turned over to the Operating Department.
See Attachment 4 for a list of systems turned over as of October 1, 1984. Note that this list does not include those systems currently under test or in the turnover process.
pags 2 of 2 Completion has been mandatory for all operators in all the preceeding programs.
The two License Training Instructors completed six weeks of observation training, were used to teach systems and procedures to various groups, attended portions of the refresher training and are being assigned to the control room as a (SRO) Unit Supervisor as available. Operations Engineers also completed the observation training requirements and were assigned to engineering or supervisory duties in the plant organization. Attendance at the shift refresher training was optional as a later intensive refresher is scheduled.
Two of the engineers did complete an eleven month assignment at the Susquehanna Nuclear Station for sta.rt-up and test experience where they were integrated into the operations organization as Shift Test Directors (December 1983 -
October 1984).
Additionally of interest concerning the first cold license group, of the twenty-seven (27) licensee's examined in October, 1983, only eighteen (18) will be taking the oral exam as scheduled in February and May of 1985. This is due to three (3) upgrades from RO to SRO, one (1) withdrawal, and five (5) candidates that will be given re-exams with the cold license candidates scheduled for the week of March 25, 1985.
Finally, each license applicant will be required to complete an additional eight to nine weeks of training prior to the scheduled NRC oral examinations.
This training will consist of approximately five weeks of structured training covering critical plant systems, procedures, technical specifications and include additional control room simulator training. The remaining four weeks will include self-study and an audit exam.
In summary, we feel that the first group of Cold License Candidates have maintained their proficiency with the refresher training during 1984, Observation Training per NRC Letter 84-10, and the additional continuing refresher and on-shift training that these candidates will receive in 1985 prior to the actual exam.
l
p ATTACHMENT 2 t
Week 1 of Licensee Refresher Training 1.
Cooling Tower Chlorination System Review (1 Hour) b 2.
Safety Diesel Generator Revisions and Review (3 Hours) 3.
RHR Water Hammer-(A0ED, SER-55-83)
(1 Hour) 4.
SER 37-83 RPV Draining at LaSalle
(.5 Hour) 5.
Automatic Depressurization System Review and Revision (1.5 Hours) 6.
Feedwater Control Review (3 Hours) 7.
Reactor Core Isolation Cooling (RCIC) Start-Up Test (3 Hours) 8.
Reactor Feed Pump Turbine Start-Up Procedure (1.5 Hours) 9.
Plant Tour of; (4 Hours) a.
Low Pressure Core Spray b.
RCIC c.
Reactor Feed Pump Turbine
- 10. CPR Requalification (8 Hours)
- 11. Operator Tour of the System (El'ectrical Grid) Operations Center
(
- 12. Perry Administrative Procedures; (5 Hours) a.
Shift Conduct and Staffing (PAP-0110) b.
Preparation, Review, Approval, Revision, and Cancellation of Instructions (PAP-0507) c.
Conduct of Operations (PAP-0201)
- 13. Safety Meeting (.5 Hour) 14.
Seminar Conducted by PNPP Chemistry Department on Problems and Mistakes with the Water Treatment System at Perry (4 Hours) 15.
Self Study (4 Hours) b
,?
.?
Page 2 of 3 f~~
~
Week 2 of Licensee Refresher Training 1.
Rod Control and Information System Review (2 Hours) 2.
Annulus Exhaust Gas Treatment System Review (1 Hour)
-3.
Plant Tour of Annulus Exhaust Gas Treatment System (1.5 Hours)
- 4.. Plant Tour of the High Pressure Core Spray System (1.5 Hours) o 5.
Reactor Recirculation Flow Control System Review (3.5 Hours) 6.
Aberrant Behavior. (Vendor Taught)
(8 Hours) 7.
Radiation Detection and Measurement (1.5 Hours)
~
8.
Basic Instrumentation and Control (4 Hours) 9.
Instrumentation and Control Simulator (4 Hours)
'~
10.
Reactor Protection System Review (1.5 Hours)
- 11. Control Rod Hydraulics Re view (1.5 Hours) 12.
Plant Tour of the Control Rod Drive Hydraulics (1.5 Hours)
(-
13.
Plant Tour of the Reactor Protection System (1 Hour) 14.
SER's 9-84,10-84,11-84, 84-83, 85-83, 86-83,12-84,13-84,14-84 (1.5 Hours)
' 15.
Recent Industry Experience Regarding Turbine Cenerator Hydrogen Explosions (1 Hour) 16.
Perry Administrative Procedures (4 Hours) a.
Operating Rules and Practices (PAP-0508) b.
Work Request System (PAP-0902) c.
Loose Parts Monitoring Program (PAP-0213) d.
Plant ALARA Review Committee (PAP-0119) 17.
Safety Meeting
(.5 Hour) 18.
IE 84-02 (.5 Hour) e
l}.
n-
,,' c Page 3 cf 3
'i Week 3 of Licensee Refresher Training le it t
1.
SER 15-84 (.5 Hour) j, 2.
SOER's 82-10, 82-15, 81-2 (1.5 Hours) 3.
NUREG BR-0051 Volume 5, Number 5-1.6, 5-1.7 (1 Hour) l' 4.
General Employee Training (4 Hours)
- 5. -Emergency Plan Training (10 Hours)
Main Steam Isolation Valve Leakage Control System Review (1.5 Hours)
-6.
i)
- 7. ' Reactor Water Cleanup (1.5 Hours).
8.
Control Rod Drive Mechanism Temperature Monitoring Panel Operation (1 Hour) h
- 9.. Reactor Recirculation System Review (2 Hours)
- 10. Thermal Limits (4 Hours) b
- 11. Plant Tour of the Reactor Water Cleanup System (1 Hour) h
- 12. Plant Tour of the Reactor Recirculation Flow Control Hydraulic Unit k
(1 Hour) j
- 13. Main Steam Isolation Valve Leakage Control System (2 Hours)
- 14. Systems Self-Study with Quiz in Support on Non-Licensed Operator j
Qualification Guides (9 Hours) i
(
0 8
4
u Page,1 cf 7 s,
ATTACHMENT 3 Rav. 0:
31 May 84
. [
Experience Training Checklist Forword The following areas of activities will allow an individual to cover vast areas of plant operation as conditions allow. While it is not the intent of having an individual cover all of the activities listed, it would be in his best interest to cover as many as possible.
Instructions When an activity has been completed the individual will DATE and INITIAL the appropriate box and enter the LEVEL of involvement. The involvement LEVEL has been divided into three categories utilizing the following criteria:
1.
PERFORMANCE (D for Do) - Those activities in which the individual had an actual " Hands On" role, in whole or in part, under the direction of qualified personnel.
2.
PARTICIPATION (P) - Those activities in which three was direct inv'olve-ment in review and discussing associated with decisions relative to operation of the plant, or direct involvement in the conduct of an evolution.
('
3.
OBSERVATION (0) - Those activities which were witnessed without any per-formance or participation.
At the end of the assignment a representative from the host utility should sign the last page; this signature may be obtained from any individual who can s
attest to your presence at the plant for the time period indicated.
Key:
3.1 = ANSI /ANS 3.1-1981
- = Annual. requirement from 3.1 document - typically these are done on a simulator.
- = Two year requirement from 3.1 document - typically these are done on a simulator.
.I = INFO 82-008 Guideline - Control Room Operator, Senior Control Room Operator and Shif t Supervisor qualification.
(
m = The source indicated is a bit less specific; made more specific by CEI.
~
i P!gs 2 pf 7 R2v. 0:
31 May 84
( { 1.
PLANT EVOLUTIONS
-+
DATE/INIT LEVEL SOURCE k.
~
Plant ?5 ear 6p':~ ' C T
. ~E F:~. ~r e.L.
._c u -
A e a.
Startup to Rx Critical e b.
Rx Critical to Hot Standby 3.1 Im
. c.
Hot Standby to 20% Power 2.
Startup preparations following refuel 3.1 outage e 3.
Plant Shutdown:
N W
.a.
20% Power to Hot Standby e b.
Hot Standby to Hot Shutdown 3.1 Im
.c.
Hot Shutdown to Cold Shutdown i
O 4.
Observe operating activities for 6 weeks wks 3.1m (SRO's or 4 weeks (RO's) as ap; copriate; indicate number of weeks.
f (NOTE Shutdown periods greater than 1 d
week do not qualif y N
(
5.
Any 10% power change due to manual 3.1 changes in control rod position or recir-I s
culation flow N
7 N
6.
Manual feedwater contro during startup 3.1 or shutdown I
7.
Xenon transient with or without compen-sation CEI 8.
Control rod sequence change 9.
Refueling operations where fuel is moved in the core Im e Required for Shif t Supervisors a Required for all SRO's and RO's as indicated 11.
SYSTDt/ EQUIPMENT MANIPULATIONS
]
DATE/INIT LEVEL SOURCE 1.
Operation of turbine controls in manual Im 2.
Placing generator on and of f line 3.
S'hutdown margin checks 4.
Control rod tests O
-~,-----ew
-=7f
-~r
Piga 3 cf 7 j,' '
Riv. 0:
31 May 84
(~II.
SYSTEM / EQUIPMENT MANI-PULATIONS (Cont.)
DATE/INIT - LEVEL ~ - SOURCE 5.
Reactor recirculation pump shif ts 6.
TIP traces 7.
RHR system mode
}
8.
RCIC system mode changes 9.
CRD system startup/ shutdown Im 10.
Charging CRD accumulators 11.
Steam bypass operation 12.
Diesel generator operation 13.
Electrical system lineup changes
[
14.
Reactor water cleanup system startup/
shutdown Im 15.
Suppression pool cleanup system startup/
shutdown Im 16.
Of f-Gas system startup/ shutdown 17.
Condensate pump startup/ shutdown /shif t 18.
Feedwater pump startup/ shutdown /shif t 19.
Cir ulating water pump startup/ shutdown /
20.
Generator support systems startup/
shutdown Im 21.
Condenser support systems startup/
shutdown Im 22.
Chilled water systems startup/ shutdown 23.
Air compressor startup/ shutdown 24.
Demineralizer/f11ter regeneration /
precoat/ operation 1
25.
Ventilation systems startup/ shutdown 26.
Itent exchanger shif ts 27.
CR calculations including heat balance, goolant inventory and reactivity balance 1
2 8*.
Sou rc e/in t e rme d ia t e/ APRM man i pu la t ion s t
i 4
Pago,4 of 7 Rev. 0:
3L May 84
' III. SURVEILIANCE TEST (Weekly / Monthly)
.cn _ m u _.. Minimum requirement: ' Ob se rve a t-leas t five - =-= --.c..
Surveillance Tests.
DATE/INIT LEVEL SOURCE 1.
Reactor protection system instrumentation 2.
Isolation actuation instrumentation 3.
ECCS actuation instrumentation 4.
Recirculation pump trip actuation instrumentation la 5.
RCIC actuation instrumentation 6.
Control rod block instrumentation 7.
Monitoring instrumentation 8.
Turbine overspeed protection system 9.
Recirculation system 10.
Safety / relief valves 11.
Reactor coolant system leakage
(
12.
MSIV's 13.
Rasidual heat removal system 14.
ECCS systems 15.
Suppression pool system 16.
Control Room emergency filtration system 17.
RCIC system 18.
Hein turbine bypass system 19.
A.C. Sources 20.
D.C. Sources 21.
Other (list):'
A--
N P:go 5 cf 7
- 3.
- R v.*.0 :
31 May 84 A
i j ' f' IV.
PLANT OPERATION
- INVOLVING EMERGENCY /0FF NORMAL PROCEDURES u,
i,;.. _,......
DATE/INIT LEVEti' SOURCE 1.
Loss of coolant 2.
Loss of instrument air
'{
3.
Loss of electrical powe r 4.
Loss of core coolant power 5.
6.
Loss of shutdown cooling 7.
Loss of service water required for 8.
Loss of component cooling system or 3.laa cooling to ind,1vidual component 9.
Loss of feedwater/foedwater system 3.1*
failure 10.
Loss of reactor protection system 3H a
- channel 11.
Hisposition or dropped control rod
-3
(
12.
Inability to drive rods 7
13.
Conditions requiring use of standby
'174 liquid control system y71_**_z"'
14.
Fuel claddinA failure /high mestvity in J
reactor coolant or of f-gas 15.
Turbine or generator trip
"}
16.
Kilfunction of automtie control system
"}71s~av which af fects reactivity 17.
haetor scram
")
18.
Ilocisar inattur4ntation railure
~~
' p7 e
19.
niin ste, itne treak
- v. weumuu l
mate. eeu tewnu an.iv et in t ihree Cupervleing Astiviilene e '
misti rettet trieringeliarneu r neitito. N 1 Ell % Ali O = EQYhEE u 1,
3.
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Pago 6 of 7 Rev.' 0:
In May 86 l
i
(V.
SUPERVISORY ACTtVtttr# (Cont.)
JAt!LIMLLEvf.L_MWC1
?
4.
Scheduling surveillanee/edintenante activities
[g ~
5.
OLocussion of prograin retaire+ nte at
. % [*%[- -
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' ~~ '
a.
Outage planning "f
a b.
Radiation safety e.
ALARA fregram
~ ~~
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$ality Aawresse
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