IR 05000219/1989080
| ML19325E776 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/22/1989 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19325E764 | List: |
| References | |
| 50-219-89-80, IEB-79-14, NUDOCS 8911080439 | |
| Download: ML19325E776 (56) | |
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"c U.'S, NUCLEAR REGULATORY COMMISSION
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REGION I
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Report No.
50-219/89-80 l
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Docket No.
50-219
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License No. OPR-16 Licensee:
GPU Nuclear Corporation
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EO. Box 388
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Forked River. New Jersey 08731 f
r Facility Name: Oyster Creek Nuclear Generating Station
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Inspection At:
Forked River and Parsippany, New Jersey I.
Inspection Conducted: August 14 to September 15, 1989
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I Inspection Team Members:
.W. H. Baunack, Senior Reactor Engineer i
J. E. Carrasco, Reactor Engineer
E. H. Gray, Senior Reactor Engineer, Team Leader
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H. I. Gregg, Senior Reactor Engineer
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J. T. Haller, Consultant - Electrical
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J. R. Houghton, Consultant -
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Mechanical, Design Calculations K. L. Parkinson, Consultant - Instrumentation &
Controls
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/0/27/S9 Approved By:
Durr, Chief Engineering Branch, date fF
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vision of Reactor Safety
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Inspection Summary:
Inspection conducted on August 14 - September 15, 1989
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l-(Report No. 50-219/89-80)
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Areas Inspected: An announced safety systems functional inspection (SSFI) of
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L the emergency service water (ESW) and containment spray (CS) systems was performed. The interface between corporate engineering and the site also was examined.
Results: Refer to the Executive Summary in the report.
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SUMMARY OF WEAKNESSES l
A weakness is a condition or potential problem that is presented for Itcensee i
review to establish what, if any, corrective actions are required. The following
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is a summary of weaknesses as noted by the inspection team.
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1.
The licensee has failed to demonstrate timely responses to USNRC
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inspection report unresolved and/or open items and to a self-audit per
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corporate policy, j
2.
Communication between Operations, Maintenance and Corporate Engineering.
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3.
A fault, on the cables connecting an emergency diesel generator to its bus i
will result in the temporary loss of that bus.
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The worst case fault on the 4.16 KV system that was analyzed is not i
demonstrated by calculations or studies to be the worst case.
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5.
Impact of automatic fast transfer on motors and driven equipment has not
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been analyzed.
6.
Synchro-check logic is not used in the automatic fast transfer scheme to
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reduce the potential for out-of phase transfer of motors.
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7.
The Class IE station battery "C" rack as installed has the potential to damage battery jars during a seismic event.
8.
Emergency diesel generator loading on loss of off-site power followed by
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a loss of coolant accident can result in potential overloads to the machines.
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9.
The licensee failed to adequately review the accuracy of their self-SSFI report TOR 986 prior to its issue.
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In the area of calculations, the team identified errors in I&C and Mechanical
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Engineering calculations that were not found by the calculation verifier.
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II. Corporate System Engineers do not have a procedure or formalized listing
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of their primary responsibilities.
12.
Engineering does not have a calculation review and update program.
13.
Failure to resolve repetitive heat exchanger maintenance problems including need for chlorination improvements.
14.
Corroded condition of steel support beams and electrical conduits at
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service water intake areas.
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l 25. Observations of heat exchanger relief valves with broken or missing
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adjustment lockwires and nameplates.
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l 16.. Excessive paint on valve packing, lubrication sight glasses and pump vibration marks.
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Lack of understanding on how to grease pumps with grease cups.
18. Observation of pump lubricant level is not part of the surveillance i
procedure prerequisites.
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19. Engineering requests for operators to deviate from procedures during
surveillance testing.
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20. There is a need to resolve technical specification vs. design basis conditions such that needed setpoints and values are included in procedures (
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I to adequately quantify " operability".
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k APPENDIX II
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PERSONS CONTACTED GPU Nuclear J. Abramovici, Heat Exchanger and Pressure Vessels Manager A. Agarwal, Manager, Instrumentation - Corporate K. Barnes, Licensing J. Bishop, Senior Job Coordinator
- R. Blouch, MCF Technical Support Manager M. Bradley, I&C Job Coordinator D. Brittner, Control Room Operator W. Brostow, Engineer, Plant Materiel
G. Busch, Oyster Creek Licensing Manager
i A. Cassell, Quality Assurance Engineer
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A. Cazaban, Engineer, Inspections
P. Cervenka, Engineer, Plant Engineering
.F. Cimino, Maintenance Foreman
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M.LColangelo, Work Authorization Manager, Plant Materiel
D. Croneberger, Acting Director, Tech. Functions
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D. Custodio, Engineer, Plant. Engineering.
P. Czaya, licensing J. DeBlasio, Manager, Mechanical Engineering
T, Dempsey, Tech. Functions Plant Systems Manager
A. Dickenson, Supervisor, Electrical Engineerirg A. Duffield, Mechanical Maintenance Planner R. Evers, Engineer, Projects M. Filippone, Work Authorization Coordinator, Plant Materiel E. Fitzpatrick, Vice President and Director J. Flynn, Manager Engineering Data Conformance Control
T. Gaffney, I&C Supervisor, Plant Materiel J. Galanto, Engineer, Plant Engineering
J. Hagan, Instrumentation Engineer C. Hager, Engineer, Plant Engineering G. Harttraft, Engineer, Plant Materiel A. Hawley, Plant IST Coordinator (Pump IST)
G. Hicks, Quality Assurance Engineer R. Huddy, Program Development & Audits M. Husain, Plant Engineer, Spare Parts
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J. Isch, Plant Maintenance l
D. Jerko, Licensing
D. Jones, Plant Engineering C. Lefler, Project Engineer, Technical Functions J. Logatto, Engineering & Design
S. Narayan, Engineer, Plant Engineering R. Markowski, Program Development & Audits
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D. McFarlane, OC Site Audits R. McGarriagle, Design and Drafting D. Most, I&C lechnician L. Munzing, Plant Operations
L. Newton, Plant Operations
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E. O'Hara, Engineer, Mechanical Compenents M. Orlowski, Human Factors Specialist
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R. Owstrowski, Staff Consultant (ISI)
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D. Pino, Plant Material
P. Procacci, Project Engineer D. Ranft, Plant Engineering Manager
Ll G. Rhedrick, Engineer, QA-ISI
H. Robinson, Engineering & Design E. Roessler, Manager Nuclear Safety
u J. Rogers, Licensing A. H. Rone, Plant Engineering Director G.-Sadauskas, Engineering & Design C. Schilling, Supervisor Mechanical Engineering
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D. Slear, Engineering & Design
J. Smith, Engineering & Design P. Smith, Systems Engineer
J. Solakiewicz, Operations QA Manager
N. Trikouras, Tech. Functions SAPC Manager
.D. Whitley, I&C Technician R. Zak, Engineer, Engineering Mechanics Indicates presence at the exit meeting on 9/1/89
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t APPENDIX III DOCUMENTS REVIEWED Portions of the items listed in this Appendix were reviewed as part of the SSFI inspection. The list is not complete but is provided as a background for reference in report follow-up.
MECHANICAL
2.
GPU Nuclear Corporation "0yster Creek Nuclear Generating Station Docket
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No. 50-219 IE Inspection Report 85-14".
Dated November 7, 1985 i
2.
GPU Nuclear TDR No. 369, Rev. O, dated December 14, 1982 " Evaluation of I
Containment Spray / Emergency Service Water System Condition -- August 1982" 3.
Casagrande Report - April 21, 1972, Forked River Nuclear Station, Investigation of stability characteristics of soil in the canal banks
'4.
GPU Nuclear Specification for Oyster Creek Nuclear Generating Station
"1985 IE Bulletin 79-02/14 Inspection Program Design Input for Piping Support Analysis".
Specification No. SP-1302-12-212, Rev. 1, dated June 9, 1988 5.
GPU Nuclear Specification for Oyster Creek Nuclear Generating Station
"1985 IE Bulletin 79-02/14 Inspection Program Design Input for Piping Stress Analysis." Specification No. SP-1302-12-208, Rev. 2, dated June 5, 1989 l
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GPU Nuclear TDR No. 829, Rev. O, dated Januar,y 20, 1987 "UT and Visual l
Inspections of OCNGS Emergency Service Water Piping"
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GPU Nuclear TDR No. 723, Rev. 1, dated October 15, 1985 " Evaluation of l
ESW System Pipe Coating Failure" 7.
GPU Nuclear Short Form Specification SP 1302-26-010, Rev. 1, dated
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January 28, 1986 "UT Inspection of the Intake Structure Non-Immersed
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L Piping" l
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GPU Nuclear Specification SP 1302-26-012, Rev. 2, dated October 12, 1988
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"12R Inspection of Intake Structure Non-Immerse ESW Piping" h
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9.
Oyster Creek SOER 86-03 Check Valve Program.
10. EPRI Monograph Titled " Application Guidelines for Check Valves in Nuclear l
Power Plants", Section 3, Information on Performance Characteristics of l
Check Valves 11. GPU Nuclear Memo of July 5,1989, No. 2310-M89-061, " Completion of
" Checkmate" Check Valve Monitoring - Phase I"
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Appendix III
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12. Oyster Creek Nuclear Generating Station Operation Plant Manual - Module 09 Containment Spray and Emergency Service Water Systems, Rev. 1, dated March 7, 1988 13. GPU Nuclear Calculation No. C 1302-241-5320-024, Rev. 02, "0yster Creek NSR Piping Analysis Containment Spray" (outside drywell), dated November 10, 1988 14. GPU Nuclear Calculation No. C-1320-241-5320-023, Rev. 2, dated i
May 20, 1988, HGR No. 241-NQ-2-H30-74 15. GPU Nuclear Calculation No. C-1302-532-5320-008, Rev. 02, "0yster Creek NSR Piping Analysis Emergency Service Water (ESW)", dated October 10, 1988 16. GPU Nuclear Calculation No. C-1302-532-5320-009, Rev. 02, "0yster Creek Emergency Service Water", dated November 17, 1988, HGR No. 532-SW-SN-5-17 17.
GPU Nuclear meeting notes (Memorandum No. C320-89-24), dated August 15, 1989)
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USNRC Generic Letter 89-13, (dated July 18,1989)
19.. USNRC Inspection report No. 50-219/85-23, dated October 7, 1985 20. USNRC Inspection report No. 50-219/89-04, dated April 28, 1989
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21. CS System General Physics Corporation.
Drawing Piping Isometric i
Containment Spray System No. ICP-19436 Sheet I to 11, Revision 2, dated i
September 25,1979 (Field verification for NRC I&E BLTN 79-14)
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Burns and Roe Incorporated Emergency Water Service (Reactor ana Turbine
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building) Isometric Piping No. H0102 and H0103, Revision 0 23. Jersey Central Power and Light Company Generation Department; Composite Yard Piping Key Plan No. BR 2192, Revision 12, dated May 1983 24.
Burns and Roe, Incorporated Engineers and Contractors " Composite Yard Piping" No. 2193, Revision 8, dated September 1967 25.
Burns and Roe, Incorporated Engineers and Contractors " Piping Isometric Chlorination System Upgrade," Revision 0, drawing No. M0225 l
26. GPU Nuclear Calculation No. C-1302-532-5310-006, Revision 0, "ESW Pipe Support No. ISH-10," dated September 20, 1984.
27. GPU Nuclear Calculation No. C-1302-104-5320-016 ESW Support SW-1-HIA, O.C. dated October 16, 1984
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' Appendix III
4 MECHANICAL DESIGN-1.
FSAR Sections a.
Section 3.'.
"Conformance With NRC Gencral Design Criteria",
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Section 6.2.2, " Containment Heat Removal Systems",
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Section 9.2.1.1, " Service Water Systems".
d.
Figure S.2-4, Rev. 2, dated 6/87, " Containment Spray System Inservice Diagram".
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Figure 3.2-11, Rev. 2, dated 6/87, " Service and Emergency Service Water Inservice Diagram" f.
Figure 6.2-14 Rev. 3, dated 2/88, "P&ID-Containment Spray System" g.
Figure 9.2-1, Rev.- 3, dated 2/88, " Flow Diagram-Circulating, HP Screenwash, Service & Emergency Service Water Systems" 2,
Technical Specifications a.
1.1, " Definitions" (Operable-Operability)
b.
Table 3.1.1, " Protective Instrumentation Requirements" c.
3.4/4.4, " Emergency Cooling" 3.
Plant Procedures and Data a.
607.4.004, Rev. O, dated 6/11/89, " Containment Spray and Emergency Service Water System 1 Pump Operability and Service Test" b.
607.4.005, Rev. O, dated 6/11/89, " Containment Spray and Emergency Service Water System 2 Pump Operability and Service Test" c.
TP 200/0.1, Rev. O, dated 30/15/85, " Emergency Service Water (ESW)
i Pump Operability Test" i
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1000-POL-7220.01, Rev. 1, dated 1/10/89, "GPUN Welding Program Policy"
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6150-ADM-3272.01, Rev. 2, dated 11/15/88, "Special Processes and Programs-Inservice Inspection Program Development and Documentation"
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1504-ADM-3272.02, Rev. 0-00, dated 7/1/85, " Repair and Replacement" i
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310, Rev. 33, dated 4/29/89, " Containment Spray System Operation".
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125.1, Rev. O, dated 1/31/84, "In-Service Test Program Administration" (Pump Test Fecord sections, 1986-1989)
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Standing Order 36, Rev. 4, " Allowable IST Ranges for Pumps" j.
"ASME XI Oyster Creek Nuclear Generating Station Pump and Valve
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Inservice Testing Program", dated 3/12/87.
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ESW Pump and Containment Spray Pump Curves (IST Furnished).
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Engineering Procedures (Technical Functions Division)
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ES-001, Rev.1, dated 3/15/89, "GPUN Engineering Classifications"
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b.
5000-ADM-7311.01 (EP-006), Rev. 3-00, dated 2/13/89, " Calculations" (
c.
5000-ADM-1291.01 (EP-016), Rev. 3-07, dated 6/1/89, " Nuclear Safety /
l Environmental Impact Determinations and Evaluations" l
d.
5000-ADH-7313.01 (EP-005), Rev. 3-03, dated 6/1/89, " Modification and i
System Descriptions"
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5000-ADM-7311.02 (EP-009), Rev. 3-00, dated 4/18/88, " Design Verifiestions" l
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Appendix III:
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Engineering Specifications
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S-2299-40, " Containment Spray Pumps", dated 1/19/66 (Burns & Roe)
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21A5410, Rev. O, dated 4/30/65, " Containment Spray System Pumps" (G.E.)
c.
Purchase Specification #141-75-2, Rev 4, dated 5/1/78, " Containment i
Spray Heat Exchangers" d.
S-2299-43 and Addendum 1, dated 10/22/65, " Emergency Service ~ Water Pumps" (Burns & Roe)
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22A1018, Rev. 2, dated 1/19/66, " Design Specification for Primary Containment Spray System" (G.E.)
f.
Design Criteria No. 466-79-4, Rev. O, dated 2/5/80, " Replacement of Containment. Spray Heat Exchanger Emergency Service Water Connections" g.
Installation Specification No. 0C-15-315302-001, Rev. 1, dated 8/27/82,
" Modification To The Containment Spray Heat Exchangers" h.
Installation Specification No. OC-MM-402871-001, Rev. 1, dated 9/1/87,
" Containment Spray Heat Exchanger Delta Pressure Gages - Oyster Creek"'
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Installation Specification No. OC-MM-402742-005, Rev. O, dated 1/13/88,
" Addition of Tell-Tale Drain to Service Water System - Oyster Creek" 6.
Safety Evaluations
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SE No. 00-000241-001, Rev. 2, dated 2/16/87, " Containment Spray Heat Exchanger Tube /Shell Differential Pressure"
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SE No. 402672-001, Rev. O, dated 1/9/84, " Containment Spray. Pumps Suction Pressure Gauges"
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SE No. 000532-007, Rev. O, dated 12/9/88, "ESW Weephole Modification, MNCR 880394" d.
SE No. 00532-003, Rev. O, dated 2/2/88, "Tell-Tale Drain Service Water System"
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SE No. 000532-002, Rev. 1, dated 8/2/85, "ESW System Return to Service-ESW Pipe Cleaning-Oyster Creek" 7.
Technical Data Reports (TDRs)
a.
TDR 165, Rev. O, dated 6/19/80, " Performance Evaluation of the Oyster Creek Containment Spray Heat Exchangers" b.
TDR 369, Rev. O, dated 12/14/82, " Evaluation of Containment Spray /
Emergency Service Water System -- August, 1982" c.
TDR 532, Rev. O, dated 5/3/84, " Torus Water Chloride Mixing Time and Containment Spray Heat Exchanger Leakage Analysis" d.
TDR 701, Rev. O, clated 12/12/85, " Evaluation of Emergency Service Water System" e.
TDR 716, Rev. 3, dated 5/1/86, "Best Estimate Analysis of Oyster Creek DBA LOCA Containment Analysis" f.
TDR 723, Rev. 1, dated 8/23/85, " Evaluation of ESW Pipe Coating Failure"
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TDR 777, Rev. 1, dated 9/4/86, " Evaluation to Increase High Drywell l
Pressure Setpoint Limit" l
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TDR 808, Rev. O, dated 1/7/87, " Evaluation to Eliminate Containment
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Spray Automatic Start Logic" 1.
TDR 829, Rev. O, "UT and Visual Inspections of OCNGS Emergency Service
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Water Piping"
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Appendix III
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8.
Audits t
a.
Audit Report S-0C-86-05, dated 9/17/86, " System Functional Audit-Containment Heat Removal" 9.
Calculations a.
13432.15-01, Rev. O, dated 11/18/81, " Adequacy of Containment Spray
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System to Preclude Operation of Pumps at Runout' Flow" (Stone & Webster)
b.
13432.15-07 Rev. O, dated 12/25/81, "Available NPSH For Containment Spray Pumps" (Stone & Webster)
c.
C-1302-241-5360-004, dated 10/7/83, " Containment Spray / Emergency Service Water System Performance" d.
C-1302-532-5360-002, dated 11/8/83, "CS/ESW System Pressure Profile" e.
C-1302-241-5360-006, dated 12/28/83, " Containment Spray System Pressure Profile" f.
C-1302-532-53220-004, dated 2/22/84, "0C ESW Flos Analysis" g.
C-1302-532-5360-007, Rev. O, dated 9/24/85, " Loss of Flow From ESW System Through Chlorination Branch Connections & Hx Relief Lines" h.
C-1302-212-5450-010, Rev. 1, dated 8/8/86, "O.C. E0Ps: Core and Containment Pump NPSH Limit Curves" 1.
C-1302-241-5450-012, Rev. 1, dated 6/10/86, "0C E0Ps: Torus Spray Initiation Pressure" j.
C-1302-241-5360-031, Rev. O, dated 6/22/88, OCNGS-Cont. Spray Hx Area Reduction" k.
C-1302-243-5450-044, Rev. O, dated 6/23/88, "0C DBA LOCA Containment Response With Reduced Containment Spray Heat Exchanger Area"
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C1302-241-5450-035, Rev. O, dated 8/7/89, " Torus Temperature Response To ESW Temperature of 95F and 75% Reactor Power" ELECTRICAL FSAR OCNGS FSAR Update, Rev. 3, dated 2/88, Chapter 8, Electric Power
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Amendment 32 to Construction Permit, Response to Question 3, datec' 1/9/68.
l-Diagrams BR3001, Rev. 14, dated 7/19/89 - Main One Line Diagram BR3002, Rev. 26, dated 7/19/89 - Auxiliary One Line Diagram l
BR3031, Rev. 5, dated 3/27/87 - Synchronizing Diagram l-GE-15786350, Sheet 20, Rev. 7 - Motor Control Center 1821B SK-861-W-1002, Rev. 1, dated 5/19/86 - 16GH-4STG, VTP (Byron Jackson - ESW Pump outlin f
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- Appendix III
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L Specifications 21A0100, Rev 0, dated 8/20/62 - Electric Motors 21A5410, Rev. O, dated 4/30/65 - Containment Spray Pumps
.21A1018 Rev. 2, dated 1/19/66 - Primary Containment Spray System
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S-2299-40, Rev 0, dated 1/66 - Containment Spray Pumps h
S-2299-43, Rev 0, (not dated) - Emergency Service Water Pumps
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S-2299-61 Rev. O, (not dated) - Standard Valves SP-9000-41-005, Rev 5, dated 11/2/88 - Installation Specification for Cables
& Raceways at Oyster Creek Nuclear Generating Station
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.0CIS-328180-001, Rev. 1, dated 10/23/87 - Installation Specification for 480 V Unit Substation 1A2 & 182 Transformer Cooling Fans 00-MM-328184-003, Rev. 2, dated 10/20/87 - Installation Specification for Changout of 49/50 Relays on Emergency Service Water (ESW) and Core Spray Maine (CSM) Pumps 0C-MM-328206-001, Rev. O, dated 8/12/88 - Installation Specification for
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Diking Required for Removal of PCB Fluids from Transformers v
Calculations and Studies C-1302-700-5350-003, Rev. 2, dated 11/3/88 - Oyster Creek Protective Relays C-1302-700-5350-005, Rev. 1, dated 9/8/87 - OCNGS - Class 1E Solid State Trip Device Settings for 480 V USS Circuit Breakers
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C-1302-741-5350-001, Rev. 1, dated 6/27/88 - OC, Loading of Diesel Generators and Associated Buses EAGB-80-383, dated 8/11/88 - (Letter to USNRC) Docket No. 50-219, Grid Undervoltage Protection TOR-630, Rev. O, dated 5/30/85 - Electrical Load Interrupting Device Coordination Study
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Audits
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S-0C-86-05, dated 9/17,'86 - System Functional Report - Containment Heat Removal S-0C-87-19, dated 8/4/88 - Onsite AC Emergency Power System
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L Appendix III
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Procedures and Guidelines 337, Rev. 22, dated 5/11/89 - Oyster Creek Nuclear Generating Station Procedure - 4160 V Electrical System
- 341. Rev. 29, dated 3/30/89 - Oyster Creek Nuclear Generating Station r
Procedure - Emergency Diesel Generator Operation 1000-A0M-7330.01, Rev 3., dated 4/10/89 - Management of Potential Safety Concerns
.E & D Guideline 4, Rey, 0, dated 8/21/89 - Engineering Guidelines, Electrical Load Control PP-057345-1, Rev 0, dated 9/24/87 - AK-2A25 Circuit Breaker Micro-Versa Trip Conversion and Overhaul PP-057345-2, Rev. O, dated 9/24/87 - AK-50 and AK-75 Circuit Breaker Trip Conversion and Overhaul Safety Evaluations 328180-001, Rev. O, dated 6/19/87 - GE AK-2, 480 V Unit Substation Circuit Breaker Trip Unit Replacement 328184-002, Rev. O, dated 8/3/87 < Changeout of 49/50 Relays on ESW & CSM Pumps I
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328206-001, Rev 1, dated 8/12/88 - Removal of PCB Fluids from Transformers 402786-001, Rev. 1, dated 4/7/86 - 480 V USS 1A & 1B Transformer Cooling Fans
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Work Requests 056731, dated 8/29/89 - Main Station Battery "C" 056732, dated 8/29/89 - Main Station Battery "C" E
Miscellaneous LAI No. 87139.01 and No. 87139.02, dated 8/9/88, Licensing Action Item, PSC j
87-006 Evaluation
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Memo 5350-89-053, dated 1/31/89, Fast Startr Seak-In Break PSC 87-006, dated 5/14/87 - Preliminary Safey Concern and Potential Licensee Event Evaluation - Diesel Generator Response to LOOP with Subsequent LOCA l
SDD OC-732A, Rev. 1, dated 11/14/86 - Division I, System Design Description
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for 480 V Unit Substation 1A2 & IB2 Xformer Cooling Fans
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LAppendixIII-
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Reports
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TDR-986, Rev. 0, dated 8/28/89 - Oyster Creek Emergency. Electrical Power Distribution Safety. System Functional Inspection (SSFI) Report
INSTRUMENTATION AND CONTROLS Procedures, Letters, Reports'and Calculations TR 038, dated 1/19/87, Evaluation to Eliminate Containment Spray System Automatic Start Logic
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TDR 777, Rev.1, dated.5/13/86, Evaluation To Increase High Drywell Pressure Setpoint Limit TDR 808, Rev. O, dated 1/7/87, Evaluation to Eliminate Containment Spray
. Automatic Start Logic i
Amend No. 3, dated 1/18/67, FDSAR Volume 1 Sections Provided By Licensee
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Amend No. 3, Rev. O, dated 12/84, OCNGS, FSAR Update Pertaining To Containment Spray Amend No. 32, undated, Response to AEC Letter of January 9,1968 l
Amend No. 32, dated 12/84 OCNGS FSAR Update Systematic Evaluation Program Summary l
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Amend No. 32, dated 12/84, OCNGS FDSAR Update Chapter 7 Instrumentation and Control s 2000-ADM-7330.01, Rev. 3, dated 4/10/89, Management of Potential Safety r
l Concerns l
r PSC 89-003, dated 3/23/89, Containment Spray Valve Logic
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PSC 87-003, dated 5/28/87, Containment Spray System (CSS) Auto-Start Logic
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PSC 86-021, dated 1/12/87, Containment Spray Auto-Start Logic f
PSC 86-020, dated 10/27/86, Automatic Initiation Of Containment Spray PSC 86-019, dated 3/2/87, Containment Spray System PSC 86-016, dated 12/11/86, Normal Containment Spray Flow
PSC 85-023, dated 12/5/85, Emergency Service Water Piping PSC 05-007, dated 2/7/85, ESW Overtoard Radiation Monitors PSC 84-014, dated 5/8/85, Containment Spray Relief Line
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i e
Appendix III
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PSC 84-002, dated.11/18/85, Emergency Service Water Line Break l
PSC 83-002, dated 9/28/83, Delta Pressure On The Emergency Service Water Heat Exchanger PSC83-005,dsted5/3/83,EmergencyServiceWaterSystemDamageFromNatural Phenomena, Inadequate Fire Protection, etc.
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PSC 83-008, Rev. 2, dated 4/26/84, Emergency Service Water System Pipe Hangers LER 85-018, dated 8/23/85, Emergency Service Water Pipe Coating Failure LER 86-002, dated 2/21/86, Inoperative Containment Spray Snubber Caused By Personnel Error LER 86-014, dated 7/25/86, Containment Spray System Seismic Concerns
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LER 86-023, dated 12/1/86, Single Failure Of Containment Spray Automatic Initiation Logic
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LER 89-009, dated 4/20/89, Potential Loss Of Adequate Containment Cooling During a LOCA Due to a Design Deficiency in the Containment Spray System LER 88-001, dated 7/21/88, Containment Spray Inappropriately Returned to Service Due to Improperly Performed Surveillance Test I
LER 84-026, Rev. 1, dated 11/20/84, Emergency Service Water - Containment Spray Negative Delta Pressure l
LER 84-026, dated 10/29/68, Oyster Creek Safeguards Separation Summary 22A1018. Rev. 2, dated 1/18/66, Primary Containment Spray System Design
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Specification 21A5489, Rev. O, dated 9/9/65, Drywell & Suppression Instrumentation
L Specification 21A5608, Rev. O, dated 4/14/66, Pressure Switch (Containment Spray)
i l-Specification 310, Rev. 33, dated 4/29/89, Containment Spray Operatior Procedure 607.3.002, Rev. 32, dated 4/14/89, Containment Spray System Automatic
l Actuation Test Procedure 608.4.001, Rev. 5, dated 3/7/88, Emergency Service Water Valve Operability L,
Test Procedure 665.4.010, Rev. 4, dated 11/30/87, Containment Spray Leak Reduction Procedure l
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' Appendix III
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SP-9000-41-005, Rev. 2, dated 11/2/88, Cables & Raceways at Oyster Creek Nuclear Generating Station Standing Order 1, Rev 52, dated 4/14/89, Instrumentation Setpoints ES-Oll, Rev. 12, dated 3/7/88, Quality Classification List ES-027, Rev. O, dated 12/19/88, Environmental Parameters - Oyster Creek NGS
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A100-ADM-3660.01, Rev. 1, dated 6/26/89, Conduct of Installed Instrument
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Surveillance, Calibration and Maintenance A100-ADM-3053.01, Rev. 1, dated 2/22/88, Calibration of Maintenance Test and Inspection Tools, Gauges, and Instrument k-112.1, Rev. 30, dated 7/6/89, Technical Specification Supporting Installed Instrumentation Procedure 116, Rev. 26, dated 6/22/89, Surveillance Test Program Procedure 105.3, Rav. 4, dated 8/27/88, Maintenance of Oyster Creek Environmenth1 Qualified (EQ) Equipment Procedure
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104, Rev. 12, dated 6/5/89, Control of Nonconformances and Corrective Action Procedure 108, Rev. 45, dated 7/16/89, Equipment Control Procedure L
990-1464, Rev 4, dated 2/28/89, Oyster Creek EQ Master List TAR-0C-003, dated 6/13/83, Transient Assessment Report Containment Spray Event of December 21, 1982 SP-9000-44-001, Rev.1, dated 5/31/83, Instrument and Control Equipment Installation Specification PLG-0253, dated 12/82, Oyster Creek Probabilistic Safety Analysis Plant Analysis Update Report IS #333-79-2, Rev. O, dated 1/5/79, Containment Spray Undervoltage Modification Installation Specification MP #333-79-1, Rev. O, dated 1/5/79, Containment Spray Underynitage
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Modification Proposal l
SDD-II-0C-622E, Rev. 2, dated 2/3/86, RPS/ECCS/ESF Instrumentation Upgrade Phase II SOD-I-0C-622D, Rev. 1, dated 7/18/85, RPS/ECCS/ESF Instrumentation Upgrade Phase I l
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Appendix III
SDD-II-00-6220, Rev. 2, dated 7/18/85, RPS/ECCS/ESF Instrumentation Upgrade Phase I c
'PLG-0100, dated 8/79, Oyster Creek Probabilistic Safety Analysis Draft Report August 1979 IEEE Std 383-1974, dated 1974, IEEE Standard for Type Test of Class IE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations Rosemount 08300002, Rev. A, dated 3/P8/83, Conversion of 10-50 MA Instrumentation Systems for Use with 4-20 MA Transmitter MP 119-75-10, Rev.1, dated 7/13/76, Containment Spray Actuation Modific.ation
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Proposal 00-1S-328101-003, Rev. 2, dated 7/1/85, Environmental Qualification j
Replacements for Containment Spray System, Core Spray System, Local Keylock l
Switches and Indicating Lights Installatton Specification OC-IS-328101-004, Rev. 1, dated C/11/85, Environmental qualification Replacements'for Containment Spray & Torus Thermocouples Installation Specification OC-IS-402672-001, Rev. O, dated 12/23/83, Containment Spray Suction Pressure Gauges Installation Specification
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i IS 386-79-3, Rev. 1, dated 5/13/81, Oyster Creek Containment Spray Annunciator Modification Installation Specification SE 315-403-013, Rev. 1, dated 6/27/89, E0Ps Modification for Containment Spray System Valve Logic Safety Evaluation 500-510A, Rev. 1, dated 5/11/83, Emergency Service Water System Instrumentation
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C 1302-622-5350-029, Rev. O, dated 3/18/89, IP-15 Setpoint - Reset Calc.
Containment Spray System ES-002, Rev. 2, dated 6/24/89, Instrument Error Calculation and Setpoint Determination SDD 241 A, Rev. O, dated 1/20/84, Containment Spray Pump Suction Pressure Gauges 0C-IS-402826-001, Rev. O, dated 3/25/87, Installation of an Annubar Flowmeter in the Emergency Service Water System Installation Specification 0C-15-315302-023, Rev. O, dated 5/22/84, Installation of a Flowmeter in the Emergency Service Water System Installation Specification
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-Appendix III'
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00-1S-402140-001, Rev. O, dated 2/6/84, Emergency Service Water System
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Instrumentation Modification Installation Specification
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.C-1302-241-5450-012, Rev. 1, dated 7/15/86, OC E0Ps:
Torus Spray Initiation
L Pressure C-1302-241-5450-001, dated 5/8/84, 0.C. DW Spray Maximum Flow Rate and Initiation Pressure Limit Analysis L
C-1302-622-5350-019, Rev. O, dated 10/2/87, OC Containment Spray Flow Pump Interlock Loop Error IP 03 A/B C-1302-241-5350-009, dated 3/20/84, Oyster Creen Containment Spray Heat
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Exchenger Differential Pressure Gauges C-1302-622-5350-022, Rev, 0, dated 11/9/87, OC - Containment Spray Water Temperature Loop Accuracy - TE - 40B/C C-1302-241-5450-034, Rev. O, dated 5/5/89,.. Torus Temperature Response to
. Containment Spray Shutoff Pressure SE 328101-001, Rev. O, dated 7/1/85, Removal of TS-IP-18A, 18B, From the Containment Spray System Logic SE 315403.-007, Rev. O, dated 5/20/87, Technical Specification Change to Delete Containment Spray Automatic Start Logic SE-402136-003, Rev. O, dated 5/1/86, RPS/ECCS/ESF Instrumentation Upgrade f
50-289/88200, dated 11/29/88 Emergency Operating Procedure-(EOP) Inspection Report 21A5489, Rev. O, dated 9/9/65, Specification for Drywell & Suppression Instrumentation
'21AS436, Rev. 1, dated 9/2/65, Specification for Miscellaneous Temperature Recorders 21A5608, Rev. O, dated 4/14/66, Specification for Containment Spray System pressure Switch IP15 21A5527, Rev. O, dated 10/21/65, Specification for Containment Spray System Transmitters 21A5528, Rev. O, dated 10/21/65, Specification for Containment Spray System
. Indicators 21A529, Rev. O, dated 10/21/65, Specification for Containment Spray System Alarm Switches
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Appendix'III~
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J VM-0C-0017, Rev. 4, dated 6/13/88, Technical Manual - ITT Barton Model
288A/289A Indicating Switches
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VM-0C-0244 Rev. O, dated 9/18/87, Technical Manual - GE/MAC Transmitters Type 551, 552, 553 and 554
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VM-0C-0254, Rev. O, dated 9/18/87, Technical Manual - GE Indicators VM-0C-0021, Rev. 3, dated 8/7/89, Technical Manual - Rosemount Transmitter Model 1153, Series B VM-0C-0248, Rev. O, dated 9/18/87, Technical Manual - Type 560 Alarm Unit (4532K20-0010)
VM-0C-0265,'Rev. O, dated 11/15/88, Technical Manual - Rosemount Model 3051 g
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Pressure ~ Transmitter User's Manual
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k VM-0C-0246, Rev. O, dated 9/21/87, Technical Manual.- Type 570 Power Supply (Isolated & Non-Isolated)
FMEA-0C-241-001', Rev. O, dated 8/21/89, Failure Modes & Effects Analysis for Oyster Creek Nuclear Generating Station - Containment Spray System
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PSC 89-013, dated 8/22/89, Potential Safety Concern Initiation Pertaining to Failure of the 16K2 Relay PSC 89-012, dated 8/22/89, Potential Safety Concern Initiation Pertaining to Failure of Relays NK1, NK2, EK1 and EK2 V-1302-622-019, Rev. O, dated 12/11/87, Containment Spray Flow Pump Interlock Loop' Error IP03A/8 Calculation Verification
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C-1302-622-5350-023, Rev. 2, dated 6/16/89, OC - Barton Model 288A Pressure l
Switch Loop Accuracies V-1302-622-024, Rev. O, dated 11/20/87, OC - Barton Model 288A Pressure Switch L
Loop Accuracies i
607.3.002, Rev. 31, dated 5/25/89, Containment Spray System Automatic L
Actuation Test Data Sheet
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607.3.002, Rev. 31, dated 6/22/89, Containment Spray System Automatic Actuation Test Data Sheet 607.3.002, Rev. 3, dated 7/28/89, Containment Spray System Automatic Actuation
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Test Data Sheet
i DPI-532-0005, System 1 ESW Flow Indicator Instrument Data decord/ Calibration Data / Maintenance History l
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L Appendix III
DPI-532-0006, System 2 ESW Flow Indicator Instrument Data Record / Calibration i
Data / Maintenance History
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Ob7505, dated 1/5/88, Emergency SW System Field Questionnaire Change Request / Change Notice / Design Change Notice
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053140, dated 9/16/87, Document Release Form - Containment Spray Heat Exchanger Delta Pressure Gauges i
OC-MM-402571-001, Rev, 0, dated 9/17/87, Installation Specification for Containment Spray Heat Exchanger Delta Pressure Gauges
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OC-MM-402571-001, dated 9/17/87, Construction Release Checklist for B/A
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- 402871 (Containment Spray Heat Exchanger Delta Pressure Gauges)
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2000-0PS-3024.05, Rev. 3, dated 4/22/89, Containment Spray System, Diagnostic and Restoration Actions 5000-ADM-7350.05, Rev. 1-01, dated 10/2/86, Mint-Mods 5000-ADM-7313.01, Rev. 3-03, doted 6/1/89, Modification and System Design Descriptions 5000-ADM-7311.02, Rev 3-00, dated 4/18/88, Design Verification
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APPENDIX IV (
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NRC INSPECTION MODULES Portions of the'following NRC inspection modules were used in the conduct of the SSFI, gv b
30703 - Entrance and Exit Meetings
35701 - QA Program Annual Review 37700 - Design, Design Changes and Modifications 37701 - Facility Modifications.
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L 37702'- Design Changes and Modifications Program 41701 - Licensed Operator Training
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L 42700 - Plant Procedures 61700 - Surveillance Procedures and Records 61725 - Surveillance Testing and Calibration Control Program 61726 - Monthly Surveillance Observations
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62702 - Maintenar.ce Program
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62703 - Monthly Maintenance Observations 62704 - Instrument Maintenance (Components and Systems) Observation of Work, Work Activities, and Review of Quality Records
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62705 - Electrical Maintenance (Components and Systems) Observation
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of Work', Work Activities, and Review of Quality Records 71707 - Operational Safety Verification
71710 - ESF System Walk Down 72701 - Modification Testing
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73051 - Inservice Inspection - Review of Program
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73755 - Inservice Inspection - Data Review and Evaluation
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