ML17317B250
| ML17317B250 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dolan J AMERICAN ELECTRIC POWER CO., INC. |
| References | |
| NUDOCS 7906110094 | |
| Download: ML17317B250 (10) | |
Text
MAY 11 t979 Docket Ho. 50-315 Docket Ho. 50-316 American Electric Power Service Corporation Indiana and Michigan Power Company ATTN:
Mr. John E. Dolan Vice Chairman Engineering and Construction 2 Broadway Hew York, HY 10004 Gentlemen:
The enclosed IE Bulletin Ho. 79-10 is forwarded to you for action.
A written response is required. If you desire additional information regarding this matter, please contact this office.
Sincerely, James G. Keppler Director
Enclosures:
1.
IE Bulletin Ho. 79-10 2.
List of IE Bulletins Issued in Last Twelve Months cc w/encl:
Mr. D. V. Shaller, Plant Manager Central Piles
- Director, HRR/DPM
- Director, HRR/DOR PDR Local PDR HSIC TIC Ronald Callen, Michigan Public VS05110 048 m~(~CIP OFFICE Q Servi itixens for a Better Envir nt RIII Heishm n/gc JRR Keppler SURNAME&
DATE~
NRC Form 318A (RZE) (5-76) NRCM 02040 5/1 /79
/'(
~U S. GOVERNMENT PRINTING OFFICE:
978-253 818" 7906110QQ
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U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III May ll, 1979 IE Bulletin No. 79-10 REQUALIFICATION TRAINING 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 after release from the
- core, the NRC Commissioners are evaluating licensee's requalification training programs.
As one element in this evaluation, the NRC 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.
Provide both the total number and percentage of operators who have failed the annual requalification examination.
2.
Provide the percentage of those operators who take 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 Operators.
IE Bulletin No. 79-10 May ll, 1979 5.
Provide the above information from four annual examinations (written and oral). If the requalification program has not been implemented for that period of time or records are not available, provide the maximum information 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 Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Project Management, Operator Licensing 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 problems.
TABLE 1 Utility:
Facility:
Date:
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 number failed annual examination B.
Percent that failed annual examination 2.
Action 2:
Responses A.
Percent required to attend additional lectures B.
Number of operators attending specified number of lectures (no.
of operators/no.
of lectures) 3.
Action 3:
Responses A.
Total number attending accelerated training because 70 percent on annual written examination B.
Percent attending accelerated training lesson because 70 percent on annual written examination C.
Total number attending accelerated training because unsatisfactory oral examination
Operators Senior Operators Exam Exam Exam Exam Exam Exam Exam Exam 1
2 3
4 1
2 3
4 D.
Percent attending accelerated training because unsatisfactory oral examination Date of Exam I
IE Bulletin No. 79-10 May 11, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Sub)ect No.
Date Issued Issued To 79-09 Failures of GE Type AK-2 4/17/79 Circuit Breaker in Safety Related Systems All Power Reactor Facilities with an OL or CP 79-08 Events Relevant to BWR Reactors Identified During Three Mile Island Incident 4/14/79 All BWR Power Reactor Facilities with an OL 79-07 79-06B Seismic Stress Analysis of Safety-Related Piping Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident 4/14/79 4/14/79 All Power Reactor Facilities with an OL or CP All Combustion Engineer-ing Designed Pressurized Water Power Reactor Facilities with an Operating Licensee 79-06A Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident 4/14/79 All Pressurized Water Power Reactor Facilities of Westinghouse Design with an OL 79-06 79-05A Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Nuclear Incident at Three Mile Island 4/11/79 4/5/79 All Pressurized Water
'ower Reactors with an OL except BHl facilities All BGW Power Reactor Facilities with an OL 79-05 Nuclear Incident at Three Mile Island 4/2/79 All Power Reactor Facilities with an OL and CP Enclosure Page l of 3
IE Bulletin No. 79-10 May ll, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin No.
79-04 79-03 79-02 Subject Incorrect Weights for Swing Check Valves Manufactured by Velan Engineering Corporation Longitudinal Welds Defects In ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Co.
Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts Date Issued 3/30/79 3/12/79 3/2/70 Issued To All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP 79-01 Environmental Qualification 2/8/79 of Class IE Equipment All Power Reactor Facilities with an OL or CP 78-14 78-13 78-12B 78-12A Deterioration of Buna-N Component In ASCO Solenoids Failures in Source Heads of Kay-Ray, Inc.,
Gauges Models 7050,
- 7050B, 7051,
- 7051B, 7060,
- 7060B, 7061 and 7061B Atypical Weld Material in Reactor Pressure Vessel Welds Atypical Weld Material in Reactor Pressure Vessel Welds 12/19/78 10/27/78 3/19/78 11/24/78 All GE BWR facilities with an OL or CP All general and specific licensees with the sub)ect Kay-Ray, Inc.
gauges All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP 78-12 Atypical Weld Material in Reactor Pressure Vessel Welds in Reactor Pressure 9/29/78 All Power Reactor Facilities with an OL or CP Facilities with an Enc losur e Page 2 of 3
IE Bulletin No. 79-10 May 11, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Sub)ect No.
Date Issued Issued To 78-11 Examination of Mark I Containment Torus Welds 7/21/78 BWR Power Reactor Facilities for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee 78-10 Bergen-Paterson Hydraulic 6/27/78 Shock Suppressor Accumulator Spring Coils All BWR Power Reactor Facilities with an OL or CP 78-09 78-08 BWR Drywell Leakage Paths 6/14/79 Associated with Inadequate Drywell Closures Radiation Levels from Fuel 6/12/78 Element Transfer Tubes All BWR Power Reactor Facilities with an OL or CP All Power and Research Reactor Facilities with a Fuel Element transfer tube and an OL 78-07 78-06 Protection afforded by Air-Line Respirators and Supplied-Air Hoods Defective Cutler-Hammer Type M Relays with DC Coils 6/12/78 5/31/78 All Power Reactor Facilities with an OL, all class E and F
Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1
Material Licensees All Power Reactor Facilities with an OL or CP Enclosure Page 3 of 3
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