IR 05000322/1979008
| ML19208B921 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/19/1979 |
| From: | Caphton D, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19208B918 | List: |
| References | |
| 50-322-79-08, 50-322-79-8, NUDOCS 7909240156 | |
| Download: ML19208B921 (8) | |
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U.S. NUCLEAR REGUL* TORY COMMI% ION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-322/79-08 Docket No.
50-322 License No. CPPR-95 Priority Category B
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. Licensee:
Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801
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Facility Name:
Shoreham Nuclear Power Station, Unit 1 Inspection at:
Shoreham, New York'
Inspection conducted:
June 25-28, 1979 I/.14.
J 7//77f Inspectors:
H. H. Micholas, Reactor Inspector
'fatefigndd date signed
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date signed Approved by:
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t', h 7//f/7f
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D. L. Caphton/ Chief, iluclear Support Section
/ dat'e si'gned No. 1, RO&NS Branch Inspection Summary:
Inspection on June 25-28,1979 (Report P!o. 50-322/79-08)
Areas Inspected; Routine, unannounced inspection by a regio"al based inspector of the overall preoperational test program requirements including training, test and measurement equipment, equipment protection and cleanliness, and plant and preventive maintenance; preoperational test procedures, test sequencing, and test witnessing; quality assurance and quality control functions and interface; tours of the facility; and, followup on previous inspection items.
The inspec-tion involved 27.5 inspector-hours onsite by one regional based inspector.
Results; No items of noncompliance were identified.
383260 Region I Form 12 (Rev. April 77)
7 909250[f(
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DETAILS 1.
Persons Contacted Long Island Lighting Company
- Mr. D. Durand, Operating QA Engineer
- Mr. T. Gerack, QA Manager
- Mr. L. Lewin, Assistant Startup Manager
- Mr. J. Novarro, Project Manager Mr. A. Muller, QC Engineer
- Mr. J. Rivel10, Plant Manager
- Mr. J. Taylor, Startup Manager Stone and Webster Corporation
- Mr. J. Baker, Lead Advisory Engineer The inspector also interviewed other licensee personnel during the course of the inspection.
- denotes those present at the exit interview.
2.
Status of Previous Inspection Findings (Closed) Open Item (322/77-03-01):
Implementation of FSAR commitments regarding preoperationa' test requirements.
Acceptance tests were changed to preoperational tests as reflected in chapter 14 of the FSAR.
(Closed) Open Item (322/77-03-03):
Plant maintenance during preoperational test phase.
Procedures and instructions have been implemented as reflected in section 4 of the Startup Manual.
(0 pen) Unresolved Item (322/79-05-01):
Verify that the time frame within which the startup manual will be periodically reviewed and updated is specifically designated.
This resolution is in progress and will be examined on a subsequent inspection.
(0 pen) Deficiency Item (322/79-05-02):
Failure to review and update EQAP's annually as required by EQAP 5.1.
Action is being taken to prevent a reoccurrence and will be reviewed on a subsequent inspection.
(0 pen) Unresolved Item (322/79-05-03):
Verify that the startup manual was revised to be consistent with the QA organization and May 1979 FSAR re-3832.
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vision.
This revision is in progress and will be examined and reviewed during a subsequent inspection.
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3.
Overall Preoperational Test Program a.
Preoperational Test Program Requirements Discussion:
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The inspector met with the startup manager and his staff and discussed various phases of the preoperational test program requirements including:
Training,
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Test and measurement equipment,
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Equipment protection and cleanliness, and,
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Plant and preventive maintenance.
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The following areas were highlighted and are to be reviewed in subse-quent inspections:
Test program,
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Test organization, Test program administration,
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Document control, and, Design changes and modifications.
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Areas and items also discussed during meetings, and to be expanded upon in future inspections, are :
Component and pipe expansion,
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Testing pipe supports and restraint systems, Inservice inspections,
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Loose parts monitoring system,
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Vibration (equipment, components, piping), and,
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RPV internals vibration.
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Of concern in these areas will be procedures, testing, and, documenta-tion.
References:
Review of the following references was initiated during this inspection:
Startup Manual,
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Final Safety Analysis Report, Chapter 14,
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Station Operations Manual,
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Quality Assurance Manual,
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Quality Assurance Procedures,
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System Description Manual, and,
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Regulatory Guide 1.68, Initial Test Program for Water Cooled
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Nuclear Power Plants.
Findings:
As a result of the initial review of these references and discussions with the startup manager and his staff, no discrepancies were noted, and the inspector had no further questions at this time.
The review of documents and discussions with licensee representatives will continue during future inspections.
b.
Test Procedures, Test Sequencing and Test Witnessing Discussion:
The inspector met with the licensee's representatives and discussed availability, status, and test sequencing of the following types of procedures:
Preoperational Test Procedures,
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Acceptance Test Procedures, and,
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Startup Test Pr cedures.
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The inspector also discussed tests and test witnessing, and provided to the startup manager a list of tests for potential witnessing by NRC inspectors.
The startup manager stated that the NRC would be notified in a timely manner in order to assure the witnessing of scheduled testing.
The following approved copies of preoperational test procedures were received for review and verification:
PT 119.001, Revision 0, Approved November 14, 1978, Reactor Core
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Isolation Cooling System.
PT 120.002, Revision 0, Approved November 14, 1978, Reactor
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Pressure Vessel Internals Vibration Test.
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PT 121.001, Revision 0, Approved January 26, 1979, Residual Heat Removal System.
PT 195.001, Revision 0, Approved June 15, 1977, Standby Liquid
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Cont al System.
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PT 133.001, Revision 0, Approved November 14, 1978, Remote Shutdown Panel.
PT 413.001, Revision 0, Approved November 14, 1978, Primary
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Conta:nment Cooling System.
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PT 117.001-3, Revision 3, Approved August 10, 1978, Instrument and Service Air.
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PT 136.001, Revision 0, Approved February 21, 1979, Nuclear Boiler Process Instrumentation.
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PT 504.001, Revision 0, Approved March 21, 1979, Smoke, Flame and Temperature Detection.
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PT 102.001, Revision 0, Approved August 23, 1978, Circulating Water System.
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PT 107.001-3, Revision 3, Approved March 16, 1977, Makeup Demineral-izer and Transfer System.
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PT 117.002, Revision 0, Approved May 23, 1979, Loss of Instrument
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Air.
PT 118.001, Revision 0, Approved May 16, 1979, Reactor Building
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Closed Loop Cooling Water.
PT 122.001, Revision 0, Approved August 23, 1978, Service Water
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System.
PT 312.001 A, Revision 0, Approved May 2, 1979, 120 VAC-RPS-MG-
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SETS.
PT 312.001 B, Revision 0, Approved May 2, 1979, 120 VAC-RPS-MG-
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SETS.
PT 319.001, Revision 0, Approved April 25, 1979, Plant Communi-
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cations.
PT 415.001 B-1, Revision 0, Approved March 16, 1977, Screenwell
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Pump House Ventilation System.
PT 651.001, Revision 0, Approved December 20, 1978, Process
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Computer.
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PT 654.005, Revision 0, Approved July 19, 1978, Drywell Floor Seal Pressure Monitoring System.
PT 655.001, Revision 0, Approved June 20, 1979, Seismic Monitoring
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System.
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PT 703.001, Revision 0, Approved May 25, 1979, Fuel Handling and Vessel Servicing Equipment.
Findings:
The licensee's representatives assured the inspector that procedures will be provided in a timely manner to afford timely inspector reviews.
Areas of concern in procedure reviews will be addressed in subsequent inspections.
Tne inspector had no further questions regarding these procedures at this time.
c.
Quality Assurance and Control Discussions:
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The inspector met with the operating quality assurance engineer and discussed the following areas:
Quality assurance program,
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Quality assurance organziation, and,
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Quality assurance and quality control functions, areas, and interface throughout the preoperational test program.
References:
The following documents were reviewed during this inspection:
Startup Manual,
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Quality Assurance Manual, and,
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Quality Assurance Procedures.
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Findings:
As a result of discussions with the operating quality assurance engineer and review of documents, no discrepancies were noted and the inspector had no further questions at this time.
Review in this area will be continued during subsequent inspections.
4.
Plant Tours The inspector made tours of the facility including the following areas:
Containment,
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Reactor building, Turbine building,
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Diesel generator rooms, Battery rooms and battery chargers,
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Computer room, 383266
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Cable spreading and relay room,
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Control room, and,
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Emergency shutdown outside of control room station.
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The inspector observed work in progress, housekeeping, cleanliness controls, storage and protection of components, piping and systems.
No items of noncompliance were identified and no discrepancies were noted.
5.
Exit Interview At the conclusion of the site inspection on June 28, 1979, an exit meeting was conducted with the licensee's senior site representatives (denoted in Paragraph 1).
The findings were identified and previous unresolved items were discussed.
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