ML17053B215
| ML17053B215 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/10/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053B209 | List: |
| References | |
| 50-220-79-21, NUDOCS 7911230024 | |
| Download: ML17053B215 (8) | |
Text
'APPENDIX A
- NOTICE'OF'VIOLATION Niagara Mohawk Power Corporation Docket No. 50-220 Based on the results of an NRC inspection conducted on June 11-15 and July 16-20, 1979, it appears that certain of your activities were not conducted in full compliance with the conditions of your license DPR-63 as indicated below.
These are infractions.
A.
Technical Specification 6.8.1 states, in part, that:
"Written procedures and administrative policies shall be established, implemented, and maintained that meet or exceed the requirements and recommendations of... Appendix "A" of USNRC Regulatory Guide l.33,;.."
USNRC Regulatory Guide.1.33, Appendix A, requires procedures to cover the following activities:
"A.3, Equipment Control (e.g., locking and tagging);
D.7, Emergency Core Cooling System; and D.2, Control Rod Drive System."
Contrary to the above, the following valves were found to be not locked as required by system operating procedures and/or P8ID's when checked between June ll and July 20, 1979:
Emergency Cooling Drain Valves
- EC701, 703,
- 705, and 707.
Containment Spray System Containment Isolation Valves Drain Valves.
Control Rod Drive Filter Blocking Valve CRD 8 or 9 (out of service locked closed).
B.
10 CFR 50, Appendix B, Criterion XIV, Inspection, Test and Operating
- Status, states, in part:
"Measures shall be established to indicate, by the use of markings such as.stamps, tags, labels, routing cards, or other suitable
- means, the status of inspections and tests performed upon individual items of the nuclear power plant...
Measures shall also be established for indicating the operating status of structures,
- systems, and components of the nuclear power plant...
such as by tagging valves and switches, to prevent inadvertent operation."
The licensee's approved guality Assurance
- Program, FSAR Amendment XIV,
- states, in part:
"For Nine Nile Point - Unit 1, the licensee maintains a system which ensures that the operational status of systems and components is known at all times...
Equipment is governed by procedures which require the use of suitable unambiguous labeling showing existing
- status, tests
- passed, and tests still required as appropriate."
APPENDIX A Contrary to the above, the following examples of failure to adequately label valves were identified during the conduct of the inspection.
These valves are required to be position verified prior to restart from refueling outages.
Valve FS-45 (Emergency Condensor t1akeup Tank Supply from the Fire Protection System) was labeled FS-44.
Two Liquid Poison system valves were assigned the same
- number, LP-711.
The Demineralized. Water supplies to the Liquid Poison pump and test tank were assigned two different numbers.
The Diesel. Generator Air Start valves were not labeled.
Sixty-five vent and drain valves in the Containment Spray System were not labeled.
The Reactor Building Ventilation Dampers and valves were not labeled.
C.
10 CFR 50, Appendix B, Criterion XVII, guality Assurance
- Records, states, in part:
"Sufficient records shall be maintained to furnish evidence of activities affecting quality.
The records shall include at least the... results of reviews, inspections, tests,...
Inspection and test records shall, as a minimum, identify the inspector or data
- recorder, the type of observation, the results, the acceptability, and the a,ction taken in connection with any deficiencies noted..."
The licensee's approved equality Assurance
- Program, FSAR Amendment 12, sta,tes, in'part:
"17. 6
'ns ection'and Test'Records
'ecords of inspection and test include, as.applicable, the date, identity, or signature of the inspection
'or data recorder; the type of observation, the identification of equipment or part inspected, the identification of test equipment utilized, the observer's results,'the acceptability of the results, and the action taken to resolve the deficiencies."
Contrary to the above, the Shutdown Cooling Pumps Numbers 11, 12, and 13, Casing Vent Valves SC-303,
- 304, 305,
- 306, 307, and 309, were documented checked as closed on June 17, 1979 as per procedure NI-OP-4, Shutdown Cooling and Head Spray, Revision 6, when the valves were
APPENDIX A 3
D.
not installed in the system.
No deficiencies were noted on the valve 1 ineup.
10 CFR 50, Appendix B, Criterion VI, Document Control, states, in part:
"Measures shall be established to control the issuance of documents, such as instructions, procedures, and drawings, including changes
- thereto, which prescribe all activities affecting quality.
These measures shall assure that documents, including changes, are reviewed for adequacy..."
The licensee's approved guality Assurance Program,'SAR Amendment No.
12, states, in part:
"6.2'Document'Contiol The measures which control the issuance and revision of these documents require:
(a)
The review of controlled documents for accuracy..."
Contrary to the above, examination of drawings and systems between June 11 and July 20, 1979, demonstrated that measures were'ot effective in issuing the following drawings affecting quality in that the as built condition was not depicted on the respective drawing as indicated:
Drawing C-18017-C, Emergency Cooling System, Revision 7:
Two check valves shown installed on the loop ll and 12 vent lines to Ha,in Steam were not installed.
Two manual block valves were installed on this line, not shown.
The drain valve configuration on the reactor side of IV's 39-09 and 10 was missing one of two installed valves in the drawing.
Drawing C-18019-C, Reactor Liquid Poison
- System, Revision 6:
The drawing did not incorporate an installed flow switch upstream of valve LP-12.
Drawing C-18007-C, Reactor Core Spray, Revision 9:
A vent valve and open ended pipe were installed outside the containment on the reactor side of Isolation Valve (IV) 40-05, but not shown on the drawing.
Check valves CRS 15 and 16 were not installed in the system as configured.
Three drain valves installed on CRS-11, Bypass Isolation Valve, were not shown on the drawing.
Drawing C-18012-C, Reactor Containment
- Spray, Revision 7:
Eight vent valves were shown installed on IV operator shafts.
APPENDIX A Drawing C-18013-C, Reactor Building Heatup Cooling and Ventilation
- Systems, Revision 5:
The drawing showed one valve in the suction line to the Reactor Building Exhaust airborne-mon'itor Four valves were installed in two different suction paths.
Drawing C-18016-C, Control Rod Dr ive, Revision 3:
Two valves in the process flow path (between block valves CRD 8 and 9 and the respective Drive Mater Filters) were not shown on, the drawing.