ML20052D391
| ML20052D391 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/22/1982 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052D382 | List: |
| References | |
| 50-277-82-06, 50-277-82-6, 50-278-82-06, 50-278-82-6, NUDOCS 8205060476 | |
| Download: ML20052D391 (3) | |
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i APPENDIX A l
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 March 10 - April 20,1982 and in accordance with the NRC Enforcement Policy 10CFR2 Appendix C (47FR9987, March 9,1982), the following i
violations were identified.
A.1 Technical Specification 6.8 and Regulatory Guide 1.33 (November 1972)
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require implementation of procedures for control of measuring and test equi znent. Licensee Procedure M65.4, Revision 5, June 15,1981, Hydraulic l
Snub >er Testing, requires a daily velocity meter calibration check prior to. snubber testing.
t Contrary to the above, on March 17,1982, two hydraulic snubbers were tested without the specified prior check of the velocity meter calibra-i tion. Further, a substitute check used was not a valid calibration check.
This is a Severity Level IV Violation (Supplement I) applicable to DPR-44.
i A.2 Technical Specification 3.14.B requires a continuous firewatch for the Cable Spreading Room when its Carbon Diexide Fire Protection System is inoperable.
j Contrary to the above, about 12:10 p.m., March 19, 1982, with the Cable Spreading Room Carbon Dioxide Fire Protection System inoperable, a con-tinuous firewatch was not maintained: the firewatch had his head down and eyes shut for about two minutes.
This is a Severity Level IV Violation (Supplement I) applicable to DPR-44 and DPR-56.
A.3 Technical Specification 6.8 and Regulatory Guide 1.33 (November 1972)
I Appendix A Section I.5 require procedural control of maintenance and i
repair work, including actions to be taken into account to minimize radiation exposure to workers.
Contrary to the above, on April-1,1982, with the reactor shut down, pro-cedural controls did not adequately safeguard against worker radiation exposure; the blocking control for repacking the open but not backseated l
High Pressure Coolant Injection System inboard steam line isolation valve l
was to maintain reactor. water level below the main steam lines, and an i
on-duty reactor operator was not aware of the isolation valve work or that-a rising reactor water level could result in spilling or spraying of 150oF radioactive reactor coolant on or near workers in the drywell.
This is a Severity Level IV Violation-(Supplement I) applicable to DPR-56.
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7 FFICIAL RECORD COPY O
PDR U
Appendix A 2
A.4 Technical Specification 6.8 and Regulatory Guide 1.33 require implementa-tion of procedures for equipment control. Licensee Procedure A-8 Revision
- 4. January 22, 1980, Procedure for Control of Locked Valves, and Appendix A-8A require that valves on the Locked Valve Lists be locked with a padlock and chain when no related maintenance is in progress and that, if a lock is removed, an entry be made in the " Locked Valve Log."
1 Contrary to the above, on April 2,1982, the following three Emergency Service Water valves listed in Appendix A-8A were not locked and no re-I lated maintenance was in progress:
504C, Inlet to 'C' Diesel; 519C, Inlet to 'C' Diesel; and 505C, Outlet from 'C' Diesel. Further, no entries regarding these valves had been made when the 'C' Diesel was blocked for maintenance on March 14 - 17, 1982.
This is a Severity Level IV Violation (Supplement I) applicable to DPR-44 and DPR-56.
A.5 Technical Specification 6.8 and Regulatory Guide 1.33 (November 1972) require implementation of written procedures for plant operttions.
Administrative Procedure A-7, Revision 17, May 18,1981, Shift Opera-tions, requires that shift operations be conducted in accordance with approved procedures.
Reactor Core Isolation Cooling (RCIC) System Lineup Procedure C.O.L.S.3.5.A Revision 10. May 30, 1978, requires that RCIC turbine exhaust drain line isolation valves, A0-137 and A0-138, be OPEN during operations. Approved RCIC procedures permit deviation from the prescribed OPEN position for surveillance or maintenance but require these valves to be returned to the OPEN position when the reactor is above 100 psi and no system maintenance or testing is in progress.
Contrary to the above, RCIC valves A0-137 and A0-138 were found SHUT at 8:20 a.m., April 9,1982, when the reactor was above 100 psi and no system maintenance or testing was in progress.
This is a Severity Level IV Violation (Supplement I) applicable to DPR-56.
A.6 Technical Specification 6.11 requires adherence to personnel radiation protection procedures. Procedure HP0/CO-9C, Revision 3. May 12, 1980 Respiratory Protective Equipment Maintenance and Quality Assurance, pro-hibits reissue or use of an air purifying canister or filter more than one year after its seal is broken. The date the seal was broken must be marked on each device, e
Contrary to the abooe, on April 9,1982, among filters and canisters stored ready for worker use in the Turbine Building, seven canisters' seals had been broken for over one year, and three canisters and about 50 filters were not marked with the date the seal was broken.
This is a Severity Level IV Violation (Supplement IV) applicable to DPR-44 and DPR-56.
0FFICIAL RECORD COPY
i Pursuant to 10 CFR 2.201, Philadelphia Electric Company is hereby required to submit to tnis 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 results achieved, corrective steps which will be taken to avoid further violations, and the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as acunded, this response shall be submitted under oath or affirm-ation. Where good cause is shown, consideration will be given to extending your response time.
APR 22 N
(( M' Date A, K, A M 9 Richard W.
4tecki, Director Division o ect and Resident Programs i
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OFFICIAL RECORD C0FT l
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