ML20010F425
| ML20010F425 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/26/1981 |
| From: | Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010F421 | List: |
| References | |
| 50-266-81-13, 50-301-81-15, NUDOCS 8109100163 | |
| Download: ML20010F425 (2) | |
Text
=--.
Appendix A s
NOTICE OF VIOLATION Wisconsin Electric Power Company Docket No. 50-266
]
Docket No. 50-301 As a result of the inspection conducted on July 1-31, 1981, and in accord-ance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
the following violations were identified:
1.
Technical Specification 15.6.8.1 requires, in part, that, "The plant shall be operated and maintained in accordance with approved procedures.
Major procedures, supported by appropriate minor procedures (such as checkoff lists, operating instructions data sheets, alarm responses, chemistry analytical procedures, etc.) shall be provided for the following operations where these operations involve nuclear safety of the plant:
Normal sequences of startup, operation and shutdown of components, systems and overall plant."
Contrary to the above, on July 5,1981 the inspect or noted that Procedure REI 19, which is referenced in major Prosedure OP-3C dated June 23, 1981, had not been issued to the control room.
This is a Severity Level V viu?ation (Supplement 1).
2.
10 CFR 50, Appendix B, Section XIV requires, in part, that, " Measures shall also be established for indicating the operating status of structures, systems, and the components of the nuclear power plant or fuel reprocessing plant, such as by tagging valves and switches to prevent inadvertent operation." Operating Point Beach Nuclear Power Plant Administrative Control Policies and Prccedures Manual 3
Section 4.13, " Equipment Isolation Procedure" is one of the measures established to satisfy the Appendix B requirement. Technical Spec-ification 15.6.8.1 requires, in part, that, "The plant shall be operated and maintained in accordance with apuroved procedures."
l 8109100163 810826 PDR ADOCK 05000266 0-PDR i
-,,-n---._..
-n
...,,..-n
,.~,.,.,,--e-
Appendix A Contrary to the above, on July 20, 1981, numerous violations of the equipment isolation procedure were noted.
These violations included failure to identify whether post work testing was required, failure to obtain proper tag clearance authorization, and failure to adequately document tag removal.
This is a Severity Level VI violation (Supplement 1).
3.
Technical Specification 15.6.8.1 requires that "The plant shall be operated and maintained in accordance with approved procedures,"
and identifies fire protection implementation as one area requiring such procedural compliance.
In accordance with 10 CFR 50.48(b), re-quirements for control of transient fire hazards are established in Section 6.3 of the Fire Protection Safety Evaluation Report, dated August 2,1979 and incorporated by license amendments DPR-24/39 and DPR 27/44. These requirements are promulgated procedurally in Section 3.31 of the Operating Point Beach Nuclear Plant Administra-tive Control Policies and Procedures Manual.
Contrary to the above requirements, on July 8, 1981, an open locker not externally identified as containing flammable agents was iden-tified out=ide primary pipeway No. 1 on the eight foot level of the primary auxiliary building. The locker contained numerous aerosol cans and two open cans of paint thinner.
This is a Severity Level V violation (Supplement 1).
With respect to Items 1 and 2, the inspection showed that action had been taken to correct the identifico items of noncompliance and to prevent recurrence. Consequently, no reply to these items of noncompliance is required and we have no further questions regarding this matter. With respect to Item 3, pursuant to the provisions of 10 CFR 2.201 you are l
required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each item of noncompliance:
(1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further noncompliance; and (3) the date when full compliance will be achieved. Under the authority i
of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted un ter oath or affirmation.
Consideration may be given to extending your re'sponse time for good cause shown.
i l
l l
Dated R. L. Spessard, Director Division of Resident and Project Inspection
_