ML20107C586
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ATOMIC ENERGY COMMISSION
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WASHINGTON, D.C. 20S45, i
ket No. 50-219 Jersey Central Power & Light Company ATTN: Mr. Ivan R. Finfrock, Jr.,
Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Gentlemen:
By letter dated December 27, 1973, in accordance with the requirements of 10 CFR Part 50, you submitted a proposal for our approval for the requalification of-the licensed operators and senior operators at the-1 Oyster Creek Nuclear G2nerating Station'. We have reviewed your proposed program and we conclude that the revisions identified in Attachment A are necessary to bring your program into conformance with previously approved requalification programs. The iten:s in Attachment A are referenced to the appropriate sections of your submittal. Attachment B contains a list of acce table control manipulations for meeting the 10 reactivity control mani ulations required in paragraph 3a of Appendix A to 10 CFR Part 55.
In order that we may complete our review, please submit a revised program within 30 days from the date of this letter.
Sincerely, i
Paul F. Collins, Chief Operator-Licensing Branch Directorate of Licensing 4
Enclosures:
1.
Attachment A 2.
Attachment B-cc: See next page e
e4 960'4170414 960213 PDR FOIA
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DEKOK95-258.
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3m Jersey Central Power & Light Co. i cc:
G. F. Trowbridge, Esquire i
Shaw, Pittman, Potts, Trowbridge and Madden 910 - 17th Street, N.W.
Washington, D. C. 2006 GPU Service Corporation ATTN:
Mr.' Thomas M. Crimins Safety & Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Anthony Z. Roisman, Esquire Berlin, Roisman and Kessler 1712 N Street, N.W.
Washington, D. C.
20036 Paul Rosenberg, Esquire Daniel Rappoport. Esquire 2323 S. Broad Street Trenton, New Jersey 08610 Ocean County Library 15 Hooper Avenue Toms River, New Jersey 08753
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0 ATTACHMENT A OYSTER CREEK NUCLEAR GENERATING STATION DOCKET N0. 50-219 I.
We believe it is inappropriate to commit the Atomic Energy
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Connission to supply specifics of our examination results to facility management. Therefore, the applicable sentences in the middle of Page 3 should be deleted.
Following the requalification training administered to a licensed individual who has not carried out the functions of his license for a period in excess of four months, a certification of a satisfactory rating must be made to the AEC prior to the individual's return to licensed duties, i
II.B The FSR program is described as consisting of self-study assignments, possible tutorial sessions with designated technical instructors and evaluation quizzes.. Appendix A of 10 CFR Part 55 specifically requires the indicated subjects 'to be part of a preplanned lecture series.
In order to comply with the requirements of Appendix A a statement should be included that no more than 50% of the FSR program maybe accomplished through the means of films, videotapes and/or individual study.
III. The list of reactivity manipulations must be more definitive.
Item 1 must be more' accurately described.
Item 2 is acceptable only if it includes a startup to the point of adding heat and states this.
Items 4 & 5 are not considered acceptable reactivity manipulations.
An acceptable list of manipulations for BWR's appears in Attachment 3.
It should be specifically stated that the additional operations listed are not considered to be reactivity manipulations for credit.
The program, as described, is designed to be administered on site.
However, the program states that a simulator may be used in meeting the on-the-job training section'of the program.
We would consider the use of a simulator to be significant change pursuant to Section 10CFR Part50.54(1-1).
Consequently, we would have to review the plan prior to implementatien.
V.
The program indicates that records of all on-the-job activities shall be maintained. These records must include documentation that each licensed operator and each licensed senior operator reviews the contents of all abnonnal and emergency procedures on a regular *,y senedu'ed basit.
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VI.
Item 3 under Lecture Attendance should be revised to a grade-criterion of 80% instead of 70%.
Item 4 under Lecture Attendance should be revised to show a range of 80% to 85% rather than a range of 70% to 85%.
Item 6 under Lecture Attendance must be revised to show a passing grade of 80% on the evaluation quizzes covering either the OR lecture series or FSR program.
Item 1 under Evaluations must include a specific commitment that if an individual receives a grade of less than 70% overall on the annual written examination it will be mandatory that he be placed in an accelerated ~requalification program. His participation in the accelerated program should be such that it would preclude per-forming licensed duties. The duration and course content, of course, must be determined in each case.
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ATTACHMENT B ACCEPTABLE REACTIVITY MANIPULATIONS FOR A BWR i
1 OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 1.
Plant or reactor startups to include a range such that reactivity '
feedback from heat addition is noticeable.
2.
Plant shutdowns 3.
Control rod sequence changes 4.
Shutdown margin checks 5.
Control rod scram insertion time tests.
6.
Any reactor power. change of 10% or greater including testing of equipment where load changes are performed with control rods,
" load selector" of EHC system or where the recirculation system is in manual speed control.
7.
Plant and reactor operation that involves emergency or transient procedures where reactivity is changing.
8.
Refueling operations where fuel is moved over the
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