ML20033C821
| ML20033C821 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/16/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20033C819 | List: |
| References | |
| 50-267-81-24, NUDOCS 8112040336 | |
| Download: ML20033C821 (2) | |
Text
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APPENDIX A MSIGNA D ORIGINAIf cwtities 97 /jkwg NOTICE OF VIOLATION v
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Public Service Company Fort St. Vrain of Colorado Docket:
50-267/81-24 Based on the results of an NRC inspection conducted during the period of October 1-31, 1981, and in accordance with the Interim Erforcement Policy, 45 FR 66745 (October 7,1980), the following violations were identified:
Technical Specification 7.4.a, " Procedures, Administrative Cor.trols,"
states in part that, "... written procedures shall be established, implemented, and maintained...."
1 Administrative Procedure P-2, " Equipment Clearances and Operation Deviations," Issue 4, dated June 12, 1981, Section 4.1 Step 15, states in part that, "...The Standard Clearance Points form is checked off as tags are pulled and equipment is returned to normal operation...." Procedure OPOP I, Section B deter-mines the normal operability of certain valves via a Sealed Valve Checklist which states that V-22184 should be sealed open.
In accordance with OPOP III, V-22184 must be sealed open whenever reactor power is greater than 2%.
Contrary to the above, on October 20,1981, at 2:M o.m. MDT, with reactor power at 34%, the NRC inspector determined that V-22184, Loop I Main Steam Electromatic Relief Valve Shutoff Valve, was not returned to normal due to the valve not being sealed.
This is a Severity Level V Violation.
(Supplement 1.E.)
2.
Procedure HPP-20, " Operation and Calibration of Radiation Detection Instruments," Issue 12, dated September 9,1981, states in part under the section titled " Precautions", "...Do not leave calibration source unattended outside the source storage room...."
Contrary to the above, on October 30,1981, at 9:00 a.m. MST,
(
the NRC inspector determined that sources numbered 184 and 92 were left unattended outside of their assigned storage room.
This is a Severity Level V Violation.
(SupplementI.E.)
8112040336 811116 PDR ADOCK 05000267 G
3.
Technical Specification LC0 4.6.1.e) states in par t that:
"The two station batteries and their associated D.C. buses and battery chargers are operable.
One battery charger or battery may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided conditions 1 through 4 below are satisfied...."
"3) Both diesel generators and their associated essential 480V buses are operable...."
Contrary to the above, on September 11, 1981, at 7:00 MDT, the 1A station battery was placed on routine overcharge.
- However, 18 emergency diesel generator unit was out of service at the time due to replacement of the outboard bearing on the clutch shaft of 1D diesel engine.
This is a Severity Level III Violation.
(Supplement I.C.)
Pursuant to the provisions of 10 CFR Part 2.201, Public Service Company of Colorado is hereby required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been t hen and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Consideration may be given to extending your response time for good cause shown.
The responses directed by this Notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paper-work Reduction Act of 1980, PL 96-511.
Dated November 16, 1981 hM G. L. Madsen, Chief Reactor Projects Branch
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