ML19246A890
| ML19246A890 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/18/1979 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 7907090183 | |
| Download: ML19246A890 (3) | |
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Portland General E!ectricCon pany
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a P: M -rc May 18, 1979 Chf ; Gn u n,.
Docket tio. 50-344
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t-Mr. R. II. Engelken, Director f'
US Nuclear Regulatory Commission, Region V 1990 North California Blvd.
Walnut Creek, California 94596
Dear Sir:
Attached is statistical data concerning the requalification training program at the Trojan Nuclear Plant.
This inforna-tion una requested in IE Bulletin No. 79-10 which was transmitted to us on May 16, 1979.
Sincerely,
.tCt,_ < tQ
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a C. Goodwin, Jr.
Assistant Vice President Thermal Operations 6 Maintenance CG/DFK:cb Attachment c:
J. L. Williams D.
- 1. Broehl R. L. Sullivan S. L. Loy S. R. Christensen Nuclear Operations Board Trojan Operating Committee Plant Review Board L. W. Erickson L. Frank, Director, DOE /EFSC Office of Management Information and Program Control NRC Resident Inspector File s gg
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. 8 17C P. age 1 of 2 TABLE 1 Utility:
Portlanci ceneral ricetric Dato:
s/10/79 Facility: Trojan Nuclear Plant Operators Senior Operators Exam Exam Exam Exam Exam Exam Exam Exam 1
2 3
4 1
2 3
4 1.
Action 1: Responses A.
Total nutrber failed o
o o
o o
o annual examination B.
Percent that failed o
o o
o o
o annual examination 2.
Action 2: Responses
- A.
Percent required.to 57.1 50 36.4 o
27.3 16.7 attend additional lectures
- B.
Ilumber of operators attending specified number of lectures (no.
2/1 3/1 2/1 3/1 2/1 of operators /no. of 1/2 1/2 lectures) 1/4 1/3 3.
Action 3:
Responses A.
Total number attending 0
0 0
0 0
0 accelerated training because 70 percent on annual written examination B.
Percent attending
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accelerated training 0
0 lesson because 70 percent on annual written examination L. -
C.
Total number attending accelerated training
.g g
g g
g g
because unsatisfactory oral examination
- Because<Bo percent on any one category on annual written examination.
161
2-Operators Senior Operators Exan Exam Exan Exan Exam Exam Exan Exam 1
2 3
4 1
2 3
4 D.
Percent attending accelerated training
.o o
o o
o o
because unsatisfactory oral examination Date of Exam 1 1/1s/77 1715f77 2
1/15/78 1/15/78 3
1/15/79 1/15/79 4
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UNITED STATES 4
W, NUCLEAR P.EGULATOnY COMMISslON f,@[j$jg7g 7,,
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SUITE 202. W ALNUT C RE EK PL AZ A TROJAN NUCLEAR PWII s ' 2,/,.
1990 N. C ALIFOHNt A DOULEVARo O
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d 9*****p W ALNUT C RE EK. C ALIFOR NI A 94596 May 11,1979 Docket !!o. 50-344 Portland General Liectric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention: Mr. Charles Goodwin Assistant Vice President Gentlemen:
A The enclosed IE Bulletin flo. 79-10 is forwarded to you for action.
written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
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,. H, ~Engelken irector
Enclosure:
IE Bulletin tio. 79-10 TROIAN NUCL[AR l'LANT
[i'e c w/ enclosures:
ACT'ON DIst B. Withers, PGE 4? '/
F. C. Gaidos, PGE C
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UtilTED STATES fiUCLEAR REGULATORY COMMISSIOil 0FFICE OF lilSPECTIOil AND EllFORCEl:EllT WASHIflGT0tl, D. C.
20555 May 11, 1979 IE Bulletin tio. 79-10 REQUALIFICAT10ll TRAlllIi!G PROGRAM STATISTICS Description of Circumstances:
Because of the apparent failure of the operators at Three Mile Island to recognize certain plant conditions and take appropriate action to effec-tively cool the core and contain fission products af ter release from the core, the ilRC Commissioners are evaluating licensee's requalification training programs.
As one element in this evaluation, the tiRC is interested in obtaining statistics about the failure rate on the annual requalification examinations.
The information requested below along with other information will then be used to evaluate the effectiveness of the operator requalification training program.
Action to be Taken by Licensees:
For all power reactor facilities with an operating license.
1.
Provide both the total number and percentage of operators who have failed the annual requalification examination.
2.
Provide the percentage of those operators who takn the annual requalification examination and are required to attend lectures on categories of material for which they received a grade of less than 80 percent. Also provide the total number of supple-mental lectures attended (e.g., 3 operators had to attend 2 lectures,1 operator had to attend 3 lectures, etc.).
3.
Provide both the total number and percentage of operators under the requalification program that participated in accelerated training because they either scored less than 70 percent overall on the annual written examination or had an unsatisfactory performance on the oral examination.
4.
Provide the same information required by 1 thru 3 on Senior J
Operators.
V.-
') II.
IE Bulletin No. 79-10 May 11, 1979 Page 2 cf 2 5.
Provide the ab vc nformation from four annual exaninations (written and oral, If the requalification progran has not been implemented for that period of time or records are not available, provide the maximum infornation that is available.
6.
Record information in format shown in Table 1.
7.
Within 14 calendar days of the date of issue of this Bulletin, report in writing to the Director of the appropriate Regional Office the results of your review.
A copy of your report should be sent to the United States Muclear Regulatory Ccmmission, Office of Nuclear Reactor Regulation, Division of Project flanagement, Operator Lit;nsing Branch, Washington, D.C.
20555.
Approved by GAO, B180225 (R0072), clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problens.
Enclosures:
1.
Table 1 2.
List of IE Bulletins Issued in Last Twelve flonths e
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IE Bulletin t'o. 79-10 May 11. 1979 Page 1 of 3 LISTIfiG OF IE BULLETIf;S ISSUE 0 Ill LAST TWELVE I OilTHS Bulletin Subject Date Issued Issued To flo.
79-09 Failures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systens OL or CP 79-08 Events Relevarit to CWR 4/14/79 All BWR Power Reactor Reactors Ideatified During Facilities with an OL Three !!ile Island Incident 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and Systen flis-ing Desianed Pressurized alignments identified ifater Power Reactor During the Three itile Facilities with an Island Incident Operating Licensee 79-06A Review of Operational 4/14/79 All Pressurized !!ater Errors and Systen flis-Power Reactor Facilities alignments Identified of ifestinghouse Design During the Three itile
_ ith an OL w
Island Incident 79-06 Review of Operational 4/11/79 All Pressurized t!ater Errors and Systen ilis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident 79-05A Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 fluclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP
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'IE Bulletin tio. 79-10 ltay 11, 1979 Page 2 of 3 LISTil;G OF IE BULLETItiS ISSUED Ill LAST TWELVE Il0:lIHS Bulletin Subject Date Issued Issued To fio.
79-04 Incorrect Ueights for 3/30/79 All Powar Reactor Swing Check Valves Facilities with an Ilanufactured by Velan OL or CP Engineering Corporation 79-03 Longitudinal Ueld Defects 3/12/79 All Power Reactor Facilities with an In AStiE SA-312 Type 304 Stainless Steel Pipe Spools OL or CP Manufactured By Youngstown Helding and Engineering Company 79-02 Pipe Support Base Plate 3/02/79 All Power Reactor Designs Using Concrete
. Facilities with an Expansion Anchor Bolts
.0L or CP 79-01 Environmental Qualifica-2/03/79 All Power Reactor tion of Class IE Equipment
. Facilities with an OL or CP 78-14
~~ Deterioration of Buna-t!
12/19/78
$11 GE BUR Facilities Components In ASCO
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78-13
[FailuresInSourcelleads 10/27/78
,[All General and
.of-Kay-Ray, Inc., Gauges
,. Specific Licensees
.!todels 7050, 7050B, 7051 with the subject b6
- n 78-12B IAtypical Ueld itaterial 3/19/79
All Power ' Reactor
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- in Reactor Pressure
-facilities with an
..All. Power Reactor ~~
Tin-Reactor Pressure
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^ Facilities with an D
Vessel Uelds 0L or CP 75-12 4tyhical We d tlaterial "b/29/78
[ldll' Power'Rsactor
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in Reactor Pressure Facilities with an Vessel Uelds OL or CP t-
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!!ay 11, 1979 Page 3 of 3 LISTING Of IE BULLETIfiS ISSUED IN LAST TWELVE !!0.1THS Bulletin Subject Date Issued Issued To No.
78-11 Examination of Mark I 7/21/78 CWR Power Reactor Containment Torus Helds Facilities for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, !!onticello and Vermont Yankee 78-10 Bergen-Paterson Hydraulic 6/27/78 All 8WR Power Reactor Shock Suppressor Accumulator Facilities with an Spring coils OL or CP 78-09 JWR Drywell Leakage Paths 6/14/79 All BWR Power Reactor
/>ssociated with Inadequate Facilities with an Drywe?1 Llorures OL or CP 78-08 hadiation Lcvels from Fuel 6/12/78 All Power an? Research E' mer c Transfer Tubes Reactor Facilities with a Fuel Element transfer tche and an OL 78-07 Protectic i afforded by 6/12/78 All Power Reactor Air-Line i,espirators and Facilities with an OL, Supplied-fir Hoods all class E and F U
elesearch Reactors with an OL, all Fuel Cycle
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Facilities with an OL, and all Priority 1
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Material Licensees 78-05.
Defective Cutler-Hammer 5/31/78 All Power Reactor
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TzpeftRelayswithDCCoils Facilities with an
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