ML16294A361
| ML16294A361 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/11/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7906110060 | |
| Download: ML16294A361 (9) | |
Text
UNITED STATES A o NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA STREETN.W.
ATLANTA, GEORGIA 30303 S1 979 In Reply Refer To:
RII:JPO 50-269, 50-270 50-287 Duke Power Company Attn:
Mr. W. 0. Parker, Jr.
Vice President, Steam Production P. 0. Box 33189 422 South Church Street Charlotte, North Carolina 28242 Gentlemen:
The enclosed Bulletin 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 P. O'Reilly
&A-Director
Enclosures:
- 1.
- 2.
List of IE Bulletins Issued in Last Twelve Months 7906o o OO
MAY 1 1 979
-2 Duke Power Company cc e S h, Station Manager Post office Box 1175 297
- Senec, eSouth Carolina 29678 1e
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 May 11, 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 Coissioflers are evaluating licensee's requalification training programs. As one element in this evaluation, the NRC is Pnterested 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 equalification training program.
Action to be Taken by Licensees:
F
'~or 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 take the annual requalification examination and are rquired to attend lectures on categories of material for which they received a grade of les than 80 percent. Also provide the total number of supple mental lectures attended (e.g., 3 operators had to attend 2 lectures, I 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.
May 11, 1979 IE Bulletin No. 79-10 Page 2 of 2
- 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:
Date:
Facility:
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 2
-2 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 1 2
3 4
IE Bulletin No. 79-10 Enclosure May 11, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
79-09 Failures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systems OL or CP 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile 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 Enginei Errors and System Mis-ing Designed Pressurix alignments Identified Water Power Reactor During the Three M4ile Facilities with an Island Incident Operating Licensee 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and System Mis-Power Reactor Facilit alignments Identified
.of Westinghouse Desig During the Three Mile with an OL Island Incident ew of Operational 4/11/79 All Pressurized Water 79-06 Review of Ope i
Power Reactors with a alignments Identified OL except B&W facilit During the Three Mile Island Incident 4/5/79 All B&W Power Reactol 79-05A Nuclear Incident at 4/i/79 Three Mile Island Facilities with an 01 79-05 Nuclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP
IE Bulletin No. 79-10 enclof 3 May 11, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 79-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.
79-02 Pipe Support Base Plate 3/2/70 All Power Reactor Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or CF 79-01 Environmental Qualification 2/8/79 All Power Reactor of Class IE Equipment Facilities with an OL or CP 78-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Component In ASCO with an OL or C Solenoids 78-13 Failures in Source Heads 10127/78 All general and of Kay-Ray, Inc., Gauges specific licensees Models 7050, 705FB, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061lB gauges78-12B Atypical Weld Material 3/19/78 All Power Reactor
- 78-12A Atypical Weld Material 11/24/78AlPoeRacr of CassIE EuipentFacilities with an in Reactor Pressure Fclte iha Vessel Welds OL or CP 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds L or CF
IE Bulletin No. 79-10 Enclosure May 11, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Welds Facilities for action Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello as Vermont Yankee 78-10 Bergen-Paterson Hydraulic 6/27/78 All BWR Power Reactor Shock Suppressor Accumulator Facilities with an Spring Coils OL or CP 78-09 BWR Drywell Leakage Paths 6/14/79 All BWR Power Reactor Associated with Inadequate Facilities with an Drywell Closures OL or CP 78-08 Radiation Levels from Fuel 6/12/78 All Power and Researc Element Transfer Tubes Reactor Facilities a Fuel Element transf tube and an OL 78-07 Protection afforded by 6/12/78 All Power Reactor Air-Line Respirators and Facilities with an 0)
Supplied-Air Hoods all class E and F Research Reactors vi' an OL, all Fuel Cycl Facilities with an 0 and all Priority 1 Material Licensees 78-06 Defective Cutler-Hammer 5/31/78 All Power Reactor Type K Relays with DC Coils Facilities with an OL or CP 3-