ML20214Q380

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Forwards Request for Addl Info Re Review of Licensee 861027 Reactor Operator/Senior Reactor Operator Requalification Program.Response Requested within 30 Days of Ltr Date
ML20214Q380
Person / Time
Site: Ohio State University
Issue date: 11/26/1986
From: Berkow H
Office of Nuclear Reactor Regulation
To: Redmond R
OHIO STATE UNIV., COLUMBUS, OH
References
NUDOCS 8612050135
Download: ML20214Q380 (5)


Text

4 November 26, 1986 Docket No. 50-150 Mr. Robert F. Redmond Executive Director Engineering Experiment Station Ohio State University 142 Hitchcock Hall Columbus, Ohio 43210

Dear Mr. Redmond:

SUBJECT:

OHIO STATE UNIVERSITY R0/SR0 REQUALIFICATION PROGRAM REVIEW The staff has completed its initial review of the Ohio State University R0/SR0 Requalification Program sutaitted on October 27, 1986. The program was reviewed against the requirements of Appendix A to 10 CFR 55 and the criteria set forth in ANSI /ANS 15.4-1977, "American National Standard, Selection and Training of Personnel for Research Reactors".

Our review has indicated the need for the additional information requested in the enclosure. Accordingly, we request that you revise the program to include the additional information within 30 days of the date of this letter.

Following receipt of your revisions, the staff will continue its review.

If you have any questions, please contact John Dosa, our Project Manager for your facility, at (301) 492-8529.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

DISTRIBUTION:

As stated lDocketFil.e.

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j WASHINGTON, D. C. 20555 November 26, 1986 Cocket No. 50-150 Mr. Robert F. Redmond Executive Director Engineering Experiment Station Ohio State University 142 Hitchcock Hall Columbus, Ohio 43210

Dear Mr. Redmond:

SUBJECT:

OHIO STATE UNIVERSITY R0/SR0 REQUALIFICATION PROGRAM REVIEW The staff has completed its initial review of the Ohio State University R0/SR0 Requalification Program submitted on October 27, 1986. The program was reviewed against the requirements of Appendix A to 10 CFR 55 and the criteria set forth in ANSI /ANS 15.4-1977, "American National Standard, Selection and Training of Personnel for Research Reactors".

Our review has indicated the need for the additional information requested in the enclosure. Accordingly, we request that you revise the program to include the additional information within 30 days of the date of this letter.

Following receipt of your revisions, the staff will continue its review.

If you have any questions, please contact John Dosa, our Project Manager for your facility, at (301) 492-8529.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, b

~

~ Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page J

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,s Ohio State University Docket No. 50-150 cc: Attorney General Department of Attorney General 30 East Broad Street Columbus, Ohio 43215 Ohio Department of Health ATTN: Radiological Health Program Director P. O. Box 118 Columbus, Ohio 43216 Ohio Environmental Protection Agency Division of Planning Environmental Assessment Section P. O. Box 1049 Columbus, Ohio 43216 Mr. Richard D. Myser Reactor Operations Manager Engineering Experiment Station Ohio State University 142 Hitchcock Hall Columbus, Ohio 43210 s

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ENCLOSURE THE OHIO STATE UNIVERSITY RESEARCH REACTOR DOCKET N3. 50-150 REQUALIFICATION PROGRAM FOR LICENSED OPERATORS AND SENIOR OPERATORS REQUEST FOR ADDITIONAL INFORMATION 1.

Comprehensive Annual Written Examinstion. The program does not include participation in the retraining program if the grade in a single category is less than 70% and greater than 55%.

Please modify the program to include this provision.

Reference:

Section 6.2 of ANSI /ANS 15.4 2.

Reactor Operations.

a)

The revised program includes an annual evaluation of individual performance. The previously approved program submitted on December 20, 1974, contained monthly evaluations of individual performance and also included written evaluations. Please explain why the evaluation period was reduced and the justification for a reduction in the program.

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Reference:

10 CFR 50.54 (j-1) b)

The current and revised programs do not.contain provisions for retraining or accelerated training if performance evaluations clearly indicate the need. The revised program must be modified to include these provisions.

Reference:

Section 6.3 of ANSI /ANS 15.4, Section 4e, Appendix A of 10 CFR "55.

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$ 3.

Document Review /0n-the-Job Training. The program appears to contain records that indicate if licensed personnel have reviewed changes in the facility license, design, and procedures. The program should describe how personnel are informed of the changes.

In addition, there appears to be no method to ensure that licensed personnel periodically review abnormal events and emergency procedures. Please clarify these two issues.

Reference:

Section 6.4 of ANSI /ANS 15.4, Section 3, Appendix A of 10 CFR 55.

4.

Special Conditions. The revised program includes provisions to suspend licensed duties if a licensee does not complete the annual written examination in a timely manner. The program should state what you consider a reasonable grace period, i.e., 20-30 days.

5.

Records. The revised program does not contain records of periodic evaluation of personnel performance and competency. Please revise your program accordingly.

Reference:

Section 7.1 of ANSI /ANS 15.4, Section 5, Appendix A of 10 CFR 55, OSU Revised Requalification Program of December 20, 1974.

6.

Additional Comments.

6-a)

Retraining study material should be modified to include additional applicable portions of 10 CFR, i.e., Parts 19 and 70.

b)

You should consider the addition of periodic meetings or seminars to discuss planned activities and important events germaine to research reactors. A recent example is Generic Letter 86-11. " Distribution of Products Irradiated in Research Reactors."

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