ML20033D196
| ML20033D196 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 10/23/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20033D190 | List: |
| References | |
| 50-369-81-23, NUDOCS 8112070357 | |
| Download: ML20033D196 (2) | |
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APPENDIX A NOTICE OF VIOLATION Duke Power Company Docket No. 50-369 McGuire 1 License No. NPF-9 As a result of the inspection conducted on July 15 - September 15, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980),
the following violations were identified.
A.
Technical Specification 6.8.1.a reguires that the applicable procedures recommended in Appendix A of Regulatory Guide 1.33 (Rev. 2, February,1978) shall be established, implemented and maintained.
Station Directive 3.1.1, Reactor Operator's Logbook, was established to cover item 1.h in Appendix A of RG 1.33 and section 3.1.7 of the Administrative Policy llanual for Nuclear Sta tions.
3tation Directive 3.1.1 requires that all annunciator alarms pertaining to reactor core conditions and other important alarms (whether recorded by the computer or not) on Reactor Coolant System, Engineered Safeguards Systems, Reactor Protective System, etc., will be listed in the log with explanation.
Contrary to the above Technical Specification requirement, Station Directive 3.1.1 was not properly implemented or followed on June 2,1981, when the Unit 1 control room annunciator alarm A-6 (Diesel Generator A panel trouble) occurred on panel 1 AD 11, and was not listed in the R0 log with explana-tion. On August 25, 1981, the alann still had not been corrected and was not listed or explained in the logbook.
This is a Severity Level V Violation B.
10 CFR 50 Appendix B and the accepted QA program Section 17.2.5 requires that activities affecting quality shall be prescribed by documented proce-dures and that these activities shall be accomplished in accordance with these procedures. Station Directive 3.11.0, Housekeeping and Cleanliness, requires that in Level IV areas, smoking or use of tobacco products is not permitted and that trash shall be collected and removed.
1 Contrary to the above, on tours conducted on-September 11-14, the inspector noted cigarette butts and paper in the pipe chase at column 45 BB of elec-trical penetration room 702, which is the lower personnel entrance to the containment;. food wrappers and rags were in the cable trays of battery room 701; and cable spreading room 801 had a wooden bench, cleaning materials, and rags in the cable trays.
This is a Severity Level V Violation. A similar violation was brought to your attention in Inspection Report 81-17.
8112070357 s112 1 PDR ADOCK 0500 y G
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l-I Duke Power Company 2
Docket No. 50-369 I
Notice of Violation License No. NPF-9 C.
Technical Specification 6.3 requires that each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. Section 4.1 of ANSI N18.-1971 requires the plant personnel to have a combination of education, experience and skills commen-surate with their level of responsibility to provide reasonable assurance that decisions and actions during all normal and abnonnal conditions will be such that the plant is operated in a safe and efficient manner.
Contrary to the above, on August 10, 1981, the electrical technicians, were unable to carry out their responsibility, in that they were unfamiliar with the system and thus unable to trip channel 1 of the Refueling Water Storage Tank level within specified time of the ' action statement.
As a result, the operators had to commence unit shutdown in accordance with Technical Specifi-ca tions.
This is a Severity Level V Violation D.
Technical Specification 3.10.1 states that "... the shutdown margin requirement... may be suspended for measurement of control rod worth..
Technical Specificction 4.10.1.2 requires as associated surveillance, "each full length control rod not fully inserted shall be demonstrated capable of full insertion when tripped... within 24. hours prior to l
reducing the shutdown margin to less than the limits."
l Contrary to the above, on August 17, 1981, while the shutdown margin requirement was suspended, control rod F-10 was not fully inserted and had not been demonstrated capable of full insertion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This is a Severity Level V Violation Pursuant to the provisions of 10 CFR 2.201, you ara hereby required to submit' to-i l
this office within thirty days of the date of this Notice, a written.' statement or explanation in reply, including:
(1)~ admission or denial of the alleged viola-I tions; (2) the reasons for the violations if admitted; (3) the corrective steps ~
which have been taken and the results achieved; (4) corrective stepsLwhich will l
be taken to avoid further violations; and (5) the date when full compliance will be achieved. Consideration may be given to extending your response time for good -
cause shown. Under the authority of Section 182 of _the Atomic Energy Act of ~
1954, as amended,-this response shall be submitted under. oath or affirmation.
L The responses directed by this' Notice are not subject to the clearance procedures of the Office of Hanegament and Budget as required by the Paperwork Reduction Act of 1980 L 96-511 Da te:
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