ML20053E867
| ML20053E867 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/24/1982 |
| From: | Starostecki R, Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20053E864 | List: |
| References | |
| 50-277-82-09, 50-277-82-9, 50-278-82-09, 50-278-82-9, NUDOCS 8206100161 | |
| Download: ML20053E867 (1) | |
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i APPENDIX A NOTICE OF VIOLATION Philadelphia Electric Company Docket / License: 50-277/DPR-44 Peach Bottom Units 2 and 3 50-278/DPR-56 During inspection on April 21 - May 19,1982, and in accordance with the NRC Enforcement Policy,10CFR2 Appendix C (47FR9987, March 9,1982), the follow-ing violations were identified.
A.1 10CFR50 Appendix B Criterion V requires that instructions and procedures be appropriate to the circumstances. 10CFR50 Appendix B Criterion III requires that the design basis be translated into procedures and instruc-tions. FSAR Section 5.2.2 lists ability to withstand the maximum credible earthquake as a design basis of the Primary Containment.
Contrary to the above, procedures for inspection of seismically qualified air supplies to Primary Containment Isolation Valves in the Containment Atmosphere Control System were not appropriate: no checks of seismic sup-port of the supply bottle were required routinely, or following bottle replacement which disturbs the bottle's seismic restraint, and on April 28,1982, the air supply bottle for Torus Exhaust to Standby Gas Treatment Valve A0-3511 was not seismically restrained.
This is a Severity Level V Violation (Supplement I) applicable to DPR-44.
A.2 TechnicalSpecification6.8, Procedures,andRegulatoryGuide1.33(Novem-ber 1972) require implementation of procedures for refueling equipment operation.
Procedure FH-6C Revision 11. March 8,1962. Fuel Movement and Core Alteration Procedure During a Fuel Handling Outage, is applica-ble during refueling outages and for all core components and requires that an individual holding a Senior Reactor Operator's license direct and supervise all operators assigned to the fuel floor.
Contrary to the above, about 3:00 p.m., April 29, 1982, during a refuel-ing outage, the senior licensed operator assigned to the fuel floor was not supervising an operator manipulating the refuel bridge auxiliary hoist, an activity that resulted in unplanned lifting of a control rod and unnecessary radiation exposure to four persons:
the senior licensed operator had left the refuel bridge and was removing his protective clothing in order to leave the fuel floor.
This it a Severity Level IV Violation (Supplement I) applicable to DPR-44.
A.3 Technical Specification 6.8, Procedures, and Regulatory Guide 1.33 (Novem-ber 1972) require implementation of procedures for fire protection sys-tems and for general control of maintenance, repair and modification work. Plant housekeeping Procedure A-30, Revision 4, May 21,1981, states i
l-8206100161 820524 Q
-0FFICIAL RECORD COPY PDR ADOCK 05000277
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O Appendix A 2
I that placement of equipment and material shall not impede accessibility of i
fire-fighting equipment, and that trash and litter shall not be allowed to accumulate and create conditions which will adversely affect quality.
A.3.1 Contrary to the above, about 9 a.m., May 5,1982, in the Unit 2 Reac-tor Building 135-foot elevation, placement of two welding machines blocked access to~ fire-fighting equipment station 135-21 and a larger table blocked access to fire-fighting equipment station 135-22.
A.3.2 Contrary to the above, about 9 a.m., May 5,1982 and 2 p.m., May 10, 1982, in the Unit 2 Reactor Building, a fire hazard was created by accumulation of litter of the following: plastic boots, plastic and cloth gloves, coveralls, caps, plastic bags, papers, and dirt.
This is a Severity Level IV Violation (Supplement I) applicable to DPR-44.
4 A.4 Technical Specification 6.11, Radiation Protection Program, requires adherence to radiation protection procedures. Procedure HP0/CO-100, Revision 12. Janu-ary 25, 1982, Health Physics Guides Used in the Control of Exposure to Radio-active Material, requires posting of areas with removabic surface contamina-tion above 1000 disintegrations per minute per 100 square centimeters with
" Contaminated Area" signs or a radiation tape barrier line.
i A.4.1 Contrary to the above, about 10:30 a.m., May 5,1982, an area along the western border of the North Accumulator Aisle in the Unit 2 Reactor Building had removable surface contamination of 4000 disintegrations per minute per 100 square centimeters and was not posted with " Con-taminated Area" signs or a radiation tape barrier line.
A.4.2 Contrary to the above, about 2 p.m., May 10,1982, an area near the control rod drive access hatch in the Unit 2 Reactor Building had re-movable contamination of 15,000 disintegrations per minute per 100 square centimeters and was not posted with " Contaminated Area" signs or a radiation tape barrier line.
This is a Severity Level IV Violation (Supplement IV) applicable to DPR-44.
Pursuant to 10CFR2.201 Philadelphia Electric Company is hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply including the corrective steps which have been taken and 1
the results achieved, corrective steps which will be taken to avoid further viola-tions, and the date when full compliance will be acnieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation. Where good cause is shown, consideration will be given to extending your response time.
Or s 151gn dBy:
'l Date NAY 2 41962
. /9M Rich ~ard W.' Starost Division of Projec%t1/ Director t"ap Resident Programs l
OFFICIAL RECORD COPY
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