ML19312C064
| ML19312C064 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/21/1975 |
| From: | Thies A DUKE POWER CO. |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19312C062 | List: |
| References | |
| NUDOCS 7911280597 | |
| Download: ML19312C064 (2) | |
Text
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DUKE POWER COMPANY Powra Butt.orwo 42a SouTu CH uacar SrazrT, CuARI.OTTE, N. C. asaot R 8 * * '8 si..Iv$$$.,e ~,
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May 21, 1975 Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission Suite 813 230 Peachtree Street, Northwest Atlanta, Georgia 30303 Re:
IE:II:TNE 50-269/75-4 50-270/75-4' 50-287/75-4
Dear Mr. Moseley:
In reference to your letter which transmitted IE Inspection Report 50-269, -270, and -287/75-1, Duke Power Company does not consider information contained in this report to be proprietary.
Please find attached our responses to Items I.A.1 and I.B.l.
With regard to tne t.tlibration of Reactor Coolant System pressure transmitters, procurenent of new narrow range transmitters is in It is estimated that these transmitters will be available progress.
for installation in the first quarter of 1976.
In the interin, the transmitters are being calibrated r.onthly and at operating terperatures so as to minimize transmitter drift.
Very truly yours, my f2kf-MCs A. C. Thics l
ACT:vr Attachment 7911280
'7 d
J RESPONSE TO ITEMS *.~.A.1 AND I.B.1 I.A.1
..h,
s Contrary to Criterion II of 10 CFR 50, Appendix B, as implemented by Section 2.5.4.7 of Duke's Administrative Policy Manual for Nuclear Stations, the licensee has not conducted periodic training on a regular basis to provide instruction in radiation protection.
RESPONSE
A comprehensive radiation-protection training program has been provided for all new employees.
In addition, special training has been provided in preparation for specific tasks such as refueling and maintenance activities.
In order to provide for periodic health physics training, a course has been prepared to be administered on an annual basis.
The first session was held on April 23, 1975, and future sessions will be held once a conth until all i
employees have attended.
i I.B.1 Contrary to Technical Specification 6.1.2.1.d.3, no SRC review of some t
i Technical Specification violations has been performed.
RESPONSE
Technical Specification violations identified by the statien are documented _
in Incident Investigation Reports and are reviewed by the SRC.
In cases where a Technical Specification violation is identified by the NRC inspections, an applicable group head reviews the violation and prepares a response to the
.I item.
In addition, the group head reco== ends, and where appropriate, 1
institutes corrective action to prevent recurrence.
In order to prevent recurrence of this incident, the Technical Services Engineer, Chair =an of the SRC, will screen inspection and enforcement reports to determine if Technical Specification violations have been identified.
These items will be scheduled for review by the SRC along with the response by the applicable j
group-head, The SRC has reviewed the itcas in'IE Inspection Report 50-269/74-10, 50-270/74-8, and 50-287/74-11 and has determined that.the corrective action taken has been adequate to prevent recurrence.
i J
Duke Power Company Oconee 1 50-269/75-4 Oconee 2 50-270/75-4 oconee 3 50-287/75-4 Ltr to Duke Power Company fa N. C. Moseley dtd: APR 2 01975 IE Inspection Report Mos. 50-269/75-4, 50-270/75-4 and 50-287/75-4 DISTRIBUTION H. D. Thornburg, IE IE:HQ (5)
Office of Standards Development Division of Reactor Licensing (13) 0entral Files 2
PDR Local PDR NSIC TIC State - South Carolina
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