ML19350B679
| ML19350B679 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/10/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19350B671 | List: |
| References | |
| 50-333-80-15, NUDOCS 8103230284 | |
| Download: ML19350B679 (3) | |
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h APPENDIX A NOTICE OF VIOLATION Power Authority of the State of New York Docket No. 50-333 Based on the results of an NRC inspection during the period August 30, 1980 through October 24, 1980, it appears that certain of your activities were not conducted in compliance with your NRC Facility License No. DPR-59 as indicated below.
Items A and B are deficiencies and item C is an infraction.
A.
Technical Specification 6.9.A.4 states.in part "The reportable occurrences of Section 4.1 through 4.2B including corrective actions and measures to prevent recurrence, shall be reported to the NRC."
Technical Specification 6.9.A.4.1 states in part:
"The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the fifth working day following the event, with a written followup report within two weeks...".
Operation of the unit or affected system when any parameter or operation to a limiting condition for operation less conservative than the least conservative aspect of the limiting condition for operations established in the Technical Specifications."
Tontrary to the above, LER 80-036-03L-0 indicates that APRM Channels "B" or "D" and "F" were inoperable for a total of approximately seventy-one minutes between April 9, 1980 and April 11, 1980 without inserting a trip in the RPS Channel as required by Technical Specifications Table 3.1-1, Note 1.
This event was initially reported on May 16, 1980, a period of 37 days after the event.
Technical Specification 6.9.A.4.2 states in part:
"The types of f
events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event."
Contrary to the above, LER 80-046-03X-1 was submitted as a supplement to report out of specification test results on June 7,1980, when the original event occurred on April 30, 1980. A separate LER should have been sub-mitted since the June 7,1980 event happened 38 days after the initial event.
B.
Technical Specification 6.8(A), states in part, " Written procedures and administrative policies shall be established, implemented and maintai w',
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Appendix A 2
Operating Procedure F-0P-22. Diesel Generator Emergency Power, Revision 4, June 11, 1980, Step C, Item 2, Cautions, states, " Ensure doors between DG rooms are closed when the DG's are required to be operable."
In addition, the door between the diesel generator switch gear rooms is labeled " Fire Door to be Kept Closed".
(Note this door would auto close in the event of a fire.)
Contrary to the atove, the fire door between the diesel generator switch gear rooms was observed as being open and unattended on October 11, 1980.
C.
Technical Specification 6.11, Radiation Protection Program, states, " Pro-cedures for personnel radiation protection shall be prepared and adhered to for all plant operations. These procedures shall be formulated to maintain radiation exposures received during operation and maintenance as far below the limits specified in 10 CFR 20 as practicable. The procedures shall include planning, preparation, and training for operation and maintenance activities.
They shall also include exposure allocation, radiation and contamination control techniques and final debriefing.
Radiation Protection Operating Procedures,Section III.C, Personnel Monitoring for Contamination, Step 1, Count Rate Meter (also called "Frisker"), states in part, "A Count Rate Meter (an instrument which is sensitive to low levels of contamination) is used by personnel when they exit from contaminated areas to ensure that they are not carrying contamination with them.
The. Count Rate Meters are installed in locations in the plant where monitoring for personnel contamination is deemed necessary. The monitors are set up, calibrated and the alarm point set by Rad Pro-tection."
Contrary to the above, the "Frisker" on the 300 foot level reactor building exit was found to be inoperable on October 12, 1980. and the
" Friskers" at the Standby Gas Building exit, and the 272 foot level Turbine Building exit to the electric bays were found to be inoperable on October 19, 1980.
Radiation Protection Operating Procedures,Section III.A.2, Step Off Pad (S0P). states in part, "The main deterent for controlling the spread of contamination is the step off pad.
SOP's in conjunction with ropes and stantions are used to clearly define areas that are contaminated. 50P's provide access points to such areas and are normally placed as entrance / exit areas to contaminated areas."
Contrary to the above, Step Off Pads were observed to be improperly maintained at the recirculation pump M-G set room, and the Reactor Building track bay door on October 11, 1980; and at the northeast 300 foot level of the Reactor Building on October 14, 1980.
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Appendix A 3
Radiation Protection Operating Procedures,Section III.A.6.2, Removal of Protective Clothing, Step (e) states, " Removed clothing must be placed in the appropriate clothing hamper to simplify laundry opera-tions."
Contrary to the above, contaminated protective clothing was observed to be stacked on the floor on October 11, 1980 at the Step Off Pad in the Standby Gas Treatment Room.