ML20035C731
| ML20035C731 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 03/22/1993 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20035C725 | List: |
| References | |
| NUDOCS 9304090044 | |
| Download: ML20035C731 (7) | |
Text
'
CCN 93 14034 h
6 PIIILADELPIIIA ELECTRIC COMPANY PEACil BUTIOM AlOMIC POWrR STATION R. D.1, Ik1x 208 Delta, IYnnsyhania 17314 ruce mornwrm romu or 5 xcam u a GIT) 456-7014 D. B. Miller, h.
Vice herident i
March 22, 1993 I
i Mr. Lee H. Bettenhausen, Chief f
Operations Branch 5
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
Final Requalification Program Evaluation Report
Dear Mr. Bette ihausen:
i lhis report provides the facility evaluation of the Licensed Operator Requalification Examinations administered by the NEC to eight (8) licensees at Peach Bottom Atomic. Power Station (PBAPS) from March 9 - 12, 1993.
The number of Licensed Operators examined by the NRC this year, combined with the licensees examined in 1992, was sufficient to perform a program evaluation using the 'riteria set forth in the Operator Licensing Examiner Standards (NUREG-1021) Section ES-601.
Post examination review indicators and results from Philadelphia Electric Company examinations administered during the periods of March 9 - 12, 1992 and March 9 - 12, 1993 have shown the-Licensed Operator Requalification Program to be SATISFACTORY with no 9eneric weaknesses.
The following attachments detail various aspects of the examinations administered between March 9 - 12, 1993.
1)
PBAPS Requalification Exam Results Summary 2)
PBAPS Identified Strengths and Areas for Improvement Included with this report are completed Requalification Examination -
Feedback forms requested in accordance with NUREG 1021, ES-601.
t 9304090044 930402 PDR ADOCK 05000277 y
4 To: Mr. Lee H. Bettenhausen, Chief Page 2 If you should have any questions, please contact Mr. Dennis McClellan, Manager, Operations Training at (717) 456-3204.
Sincerely, B,-
N Y
/)
',]lk.-
DBM/
/DWM/KPP:clg Attachments (2) cc:
R. A. Burricelli, Public Service Electric & Gas W. P. Dornsife, Commonwealth of Pennsylvania J. J. Lyash, Senior Resident inspector, US NRC
- 1. T. Martin, Administrator, Region 1, US NRC R. 1. McLean, State of Maryland H. C. Schwemm, Atlantic Electric C. D. Schaefer, Delmarva Power l
r t
t, l
t 1
l J
I
______ _ __ ____________ _ m
Page1orI t
PEACli IlOTTOM ATOMIC POWER STATION REQUALIF1 CATION EXAM RESUIII'S
SUMMARY
l REQUALIFICATION CYCLE:
92-06 (NRC)
PASSED FAILED OVERALL RESULTS TOTAL NO.
NO: /%
NO: /%
REACTOR OPERATOR 4
4/100 0/0 SENIOR REACTOR OPERATOR 4
4/100 0/0 TOTAL OPERATOR RESULTS 8
8/200 0/0 i
OPERATING CREWS 2
2/100 0/0 I
1-WRITTEN SCORE %
SAT JPM SAT J PM OVERALL RESULTS (P/F)
PERFORMANCE QUESTIONS JPM
@ @ ID-A B
TOTAL OF OF GRADE %
WRITTEN JPM SIM
{,Q. ( 1 N/A %
N/A %
N/A %
N/A 0F N/A N/A 0F N/A N/A I N/A N/A P
I I GO9tf 83.33%
86.95%
85.71%
5 OF 5
NA/ OF N/A 100 %
P P
P
!6036!
100 %
91.30%
94.28%
5 0F 5
N/A 0F N/A 100 I P
P P
952.f 75.00%
82.60%
80.00%
4 0F 5
N/A 0F N/A 80 %
P P
P GiOM N/A I N/A %
N/A %
N/A 0F N/A N/A 0F N/A N/A %
N/A N/A P
6t3ty 91.66%
82.60%
85.71%
5 0F 5
N/A 0F N/A 100 %
P P.
P c.632.(
100 %
100 %
100 %
5 0F 5
N/A 0F N/A 100 %
P P
P
(,tibO 91.66%
91.30%
91.42%
5 0F 5
N/A 0F N/A 100 %
P P
P OF OF OF OF i
I OF OF OF OF OF OF i
f I
OF OF
{ 2 egext es. fire t
Attochment 2 Page 1 of 4 -
PBAPS IDENTIFIED STRENGTHS AND AREAS FOR IMPROVEMENT -
The following strengths and areas for improvement were determined from a systematic analysis l
of the examination results. Actions to address the areas for improvement will be taken in accordance with established facilit3 processes..
I.
DYNAMIC SIMUIATOR EVALUATIONS A.
Procedure use and compliance in general was noted as a strength with the following
[
items specifically addressed:
I.
Strengths Emergency ResIxmse procedures were promptly and accurately carried out.
a.
b.
Technical Specification limiting conditions for Operations were promptly i
and accurately determined.
2.
Areas for Imorovement Alarm Response card use, though very good, must include a review of all key a.
alarms.
b.
Operational Transient and Ofr Normal procedures should be implemented during Transient Resp (mse procedure use.
Securing of ECCS stayfull systems during the performance of T-240 should.
c.
not delay plant emergency depressurization.
f d.
Alternate means of negative reactivity insertion should be pursued while establishing minimum alternate flooding pressure, e.g., driving individual rods using T-220.
B.
Command and Control in general was noted as a strength with the following items specifically addressed:
I.
Strencths Supervisory directives were conservative and allowed safe and integrated crew a.
performance.
b b.
Most actions were taken to pmvide early remediation of plant problems.
2.
Areas for improvement Supervisory directives must provide clear goals and objectives. e.g., post a.
ATWS establishment of adequate core cooling.
J
Attechment 2 Page 2 of 4 t
b.
Personnel task assignments should allow for full attention to important tasks i
c.g., terminating and preventing injection and establishing minimum -
alternate flooding pressure.
t Shill Manager's maintenance of an mersight role was very good w hile c.
providing a proper mix of ERP duties and TRIP procedure review.
C.
Teamwork and Communications in general were noted as strencths with the following items specifically addressed:
I.
Strencths Crew briefs were effective in establishing early action plans, goals and a.
objectis es.
t b.
Shift Manager and Shift Technical Advisor oversight and SSV assistance roles were valuable assets used for team success.
Outside support was promptly obtained as well as outside personnel c.
promptly informed of plant conditions.
2.
Areas for Improvement Individual communication should include consistent acknowledgement of receipt.
D.
Control Board Operations were noted as satisfactory with the following anas specifically addressed:
Areas for Improvement 1.
Chief Operator initial scram actions must ensure prompt verification of PCIS isolations to prevent any delay in recognition of failures.
1 2.
Electrical loss diagnosis must be complete to prevent attempting to close in on a bus which has a fault, t
3.
When directed to perform a normal depressurization assertive action is required to ensure it is initiated promptly.
l 4.
Reactor automatic scram should not be relied on during a loss of feedwater, rather a manual scram should be initiated.
5.
Ensure RIIR injection lineups are secured prior to initiation of Containment Spray lineups.
Attr.chment 2 Page 3 of 4.
II. WRITTEN EXAM 1 NATION An analysis of written exam results showed the following areas for improvement based on -
repetitis e incorrect resp <mses to the following questions.-
A.
Question #281 - Ability to predict and/or monitor changes in Secondary Containment difTerential pressure associated with operating the Standby Gas Treatment System.
(K/A: 261000A1.04)
B.
Question #390 - Further analysis has shown that difficulty was experience in determining pmper Y-axis values on T-102 Curve T/T-1 fmm reduced sized reference.
Knowledge of the operational implications ofIIcat Capacity as it applies to Imw Suppression Pool Irvel was adequately displayed during post exam review session.
(K/A: 295030EKl.03)
't C.
Question #457 - Ability to determine if adequate scram margin exists during the performance of Turbine Control Valve Fast Closure Scram Functional Testing.
ST.O-60F-420. (K/A: 241000KI.11)
D.
Question #1048 - Knowledge of Technical Specification Limiting Conditions for i
Operations application as they apply to Control Room RPV level instrumentation inoperabilities. (K/A:-216000G.05)
E.
Question #1577 - Further analysis has shown that dilliculty was experienced in determining an appmpriate frame of time in uhich to answer this question.
i Knowledge of the efTect that Reactor Water level will have on the Ifigh Pressure Coolant Injection System was adequately displayed during post exam review session.
(K/A: 206000K6.12)
I F.
Question #1586 - Knowledge of AC Electrical Distribution System design features and/or interlocks which allow or prevent 13 KV Auxiliary Bus breaker closure.
(K/A: 262000K4.01)
G.
Question #1656 - Knowledge of when to start the application of Technical Specification Limiting Conditions for Operations as they apply to Control Room Alarm conditions associated with the C(mtainment Atmosphere Dilution Liquid Nitrogen System. (K/A: 223001G.05) i i
I l
L
.o
?
Page 4 of 4 i
Ill.
JOB PERFORMANCE MEASURES GPMs)
Overall, the performance ofJPMs was very good. Ilowever, minor areas for f
improvement were noted during the performance of the following tasks:
i A.
JPM-053C - Containment Venting via the 18" Torus Vent (T-200D) 1.
One licensee opened an additional D/W Rx Bldg Equipment Exhaust damper not required by the procedure.
r 2.
Three licensees did not verify CTMT Vent Pressure on Table PC/P-3 of T-102, Primary Containment Control procedure.
1 B.
J PM-055P - Maximize CRD System Flow to the Reactor Vessel (T-246).
i 1.
One licensee did not verify oil level in the motor bearing sightglass.
i 2.
One licensee allowed the CRD drive water filter vent valve to remain cracked open.
C.
J PM-079C - Initiate Containment Sprays Using IIPSW (T-205) l One licensee did not verify positions of MO-154B, MO-174, MO-176 and MO-186 after manipulations of these valves were performed.
j i
D.
JPM-081C - Utilize IIPSW to Inject into the Torus (T-231) l One licensee started an RHR pump vice a IIPSW pump afteraccomplishing the proper valve lineup.
i E.
J PM-099C - Containment Venting via the 2" Torus Vent (T-200A) j One licensee did not verify positions of AO-2513 and AO-2514 after manipulations of these valves were performed.
i 1
F.
J PM-308CA - Startup IIPCI in the CST to CST Mode (SO 23.1.B)
(Alternate Path - Iligh Oil Temperature) i i
1.
One licensee did not verify power on to the IIPCI vibnition recorder.
2.
One licensee did not adjust HPCI pump discharge pressure between 1100 psig and 1300 psig.
3.
Four licensees did not announce the IlPCI turbine / pump start prior to admitting steam to the turbine.
(o \\wp51\\nreexam.rpt) 1
>