IR 05000322/1979022
| ML19294B383 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 01/09/1980 |
| From: | Caphton D, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19294B378 | List: |
| References | |
| 50-322-79-22, NUDOCS 8002280270 | |
| Download: ML19294B383 (10) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-322/79-22 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 Facility Name:
Shoreham Nuclear Power Station, Unit 1 Inspection At:
Shoreham, New York Inspection Con ucted: _ December 3-6, 1979 s
Inspectors:
@t
V'
[O R. H. Nicholas, Reattor Inspector
' date date i
date M/ d
/9 Approved by:
e
<
D. L. Caphten', Chief, Nuclear Support Section
/ date No. 1, RO&NS Branch Inspection Summary:
Inspection on December 3-6, 1979 (Report No. 50-322/79-22)
Areas Inspected:
Routine unannounced inspection by a regional based inspector of the overall preoperational test program including test program requirements, test program implementation, test program status, test procedure verification and test procedure review; tours of the facility, and, followup on previous inspection items.
The inspection involved 28.5 inspector-hours onsite by one regional based inspector.
Results: No items of noncompliance were identified.
e 8 o 0 2 280Mo,
Region I Form 167 (August 1979)
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DETAILS 1.
Persons Contacted Long Island Lighting Company
- Mr. L. Levin, Assistant Startup Manager
- Mr. J. Taylor, Startup Manager Mr. D. Terry, Lead Startup Engineer Stone and Webster Corporation Mr. J. Baker, Lead Advisory Engineer Mr. R. Gillis, Test Engineer Mr. D. Giannelli, Lead Startup Engineer General Electric Corporation Mr. R. Moody, Test Engineer Mr. A. Federson, Operations Manager Mr. J. Riley, Lead Startup Engineer U.S. Nuclear Regulatory Commission
- Mr. J. Higgins, Senior Resident Inspector 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 Items (Closed) Inspector Followup Item (322/76-10-11):
RHR service water, tcsted in preoperational test.
This item is now addressed in approved procedures exanined by the inspector.
This item is closed.
(Closed) Inspector Followup Item (322/76-10-12):
Safeguards area cooling, tested in individual ECCS preoperational tests.
This item is now addressed in approved procedures examined by the inspector.
This item is closed.
(0 pen) Inspector Followup Item (322/76-10-14):
Certification of liquid radioactive waste tank capacities, included in liquid radioactive waste preoperational test.
This item is included in a forthcoming procedure, and will remain open until the approved procedure is received and reviewed.
(0 pen) Inspector Followup Item (322/76-10-16):
Effluent and process radia-tion monitors tested in liquid or gaseous radioactive waste or process radiation monitoring system preoperational tes.
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This item is included in a forthcoming procedure, and will remain open until the approved procedure is received and reviewed.
(0 pen) Inspector Followup Item (322/76-10-19):
Personnel radiation monitor-ing and survey instruments, preoperational and acceptance tests need to be defined.
This item is included in forthcoming procedures, and will remain open until the approved procedures are received and reviewed.
(0 pen) Inspector Followup Item (322/76-10-20):
Radiochemistry laboratory equipment checkout and testing, preoperational and acceptance tests need to be defined.
This item is included in forthcoming procedures, and will remain open until the approved procedures are received and reviewed.
3.
Overall Preoperational Test Program a.
Preoperational Test Program Requirements Discussion:
The inspector met with the startup manager and his staff and concluded discussions on all phases of the preoperational test program require-ments.
The following areas were included in the discussions:
Test program description;
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Test program organization;
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Test program administration
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Document control;
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Design changes and modifications;
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Plant maintenance and preventive maintenance;
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Equipment protection and cleanliness;
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Test and measurement equipment; and,
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Training.
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Findings:
As a result of the discussions with the startup manager and his staff, the inspector ascertained that the applicant's administrative controls over preoperational testing have been developed in accordance with Final Safety Analysis Report commitments and Regulatory requirements.
No discrepancies were noted with the test program reauirements, and the inspector had no further questions in this are.
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b.
Preoperational Test Progran - Imolementation Discussion:
The ~ 1pector met with the startup manager and held preliminary dis-cussions on the implementation of the test program and its require-ments.
The following items were addresse.d in the preliminary discussions:
Test program verification;
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Test organization and personnel qualifications;
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Test program administration; Document control;
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Design changes, modifications and retesting;
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Plant maintenance during preoperational testing;
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Equipment protection, cleanliness and chemistry controls;
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Test and measurement equipment; and,
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Training.
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References:
Startup Manual;
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Final Safety Analysis Report;
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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;
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Preoperational Test Procedures;
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Acceptance Test Procedures; and,
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Regulatory Guide 1.68, Initial Test Programs for Water Cooled
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Nuclear Power Plant.
Findings:
As a result of reviews of references and discussions with the startup manager, no discrepancies were noted in these preliminary discussions of toe preoperational test program implementation, and the inspector had no further questions in this area at this time.
The items in this area will be followed up in detail on subsequent inspections.
c.
Preoperational Test Program Status Discussion:
The inspector met with the startup manager, his staff, and other licensee representatives, and held discussions on the following areas and items:
Construction schedule;
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Testing schedule; Delays and turnovers;
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Interface between construction and preoperational testing:
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Status of integrated flush;
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RPV internals vibration testing;
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Status of ci culating and service water systems; and,
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Status of ECCS systems.
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Findings:
As a result of reviews of status flow charts, schedules and procedures; and preliminary and detailed discussions with the startup manager, his staff and other selected licensee representatives, no discrepancies were noted, and the inspector had no further questions in these areas at this time.
These areas and items w'll be followed up on subsequent inspections.
d.
Test Procedure Verification The following procedures were reviewed to verify that adequate testing is planned to satisfy regulatory guidance and licensee commitments:
PT 120.001 Revision 0, Approved November 21, 1979
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Reactor Recirculation System PT 136.00 Revision 0, Approved September 27, 1978
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Jet Pump Instrumentation PT 202.001 Revision 0, Approved July 25, 1979
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High Pressure Coolant Injection System PT 203.001 Revision 0, Approved February 21, 1979
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Core Spray PT 410.001-2B Revision 2, Approved June 16, 1976
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Battery Room Ventilation System PT 410.001-2C Revision 2, Approved June 16, 1976
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Battery Room Ventilation System PT 411.001-1 Revision 1, Approved September 21, 1977
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Relay Room, Computer Room, Emergency Switchgear Rooms, Chiller Equipment Room, HVAC Equipment Room PT 412.001 Revision 0, Approved May 16, 1978
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Control Room AC - Control Room Leak Test
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PT 414.001-1A Revision 1, Approved April 20, 1977 Diesel Generator Room Ventilation System PT 414.001-1B Revision 1, Approved April 20, 1977
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Diesel Generator Room Ventilation System PT 414.001-1C Revision 1, Approved April 20, 1977
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Diesel Generator Room Ventilation Sy ; tem PT 418.001 Revision 0, Approved June 20, 1979
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Reactor Building Standby-Normal Ventilation System, Secondary Containment Leak Test PT 421.001 Revision 0, Approved August 30, 1979
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RBSVS and CRAC Chilled Water System PT 606.001-1 Revision 1, Approved May 19, 1978
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Rod Block Monitoring System PT 607.001 Revision 0, Approved May 2, 1979
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Rod Worth Minimizer iT 608.001 Revision 0, Approved July 19, 1978
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Rod Drive Control System
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PT 610.001 Revision 0, Approved August 23, 1978
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Rod Position Information System PT 611.001 Revision 0, Approved August 23, 1978
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Ractor Protection System PT 652.001 Revision 0, Approved May 16, 1978
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Power Range Reactor Recirc Flow Units PT 654.002 Revision 0, Approved June 28, 1978
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Primary Containment Leak Rate Test Type B PT 654.003 Revision 0, Approved June 28, 1978
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Primary Containment Leak Rate Test Type C The inspector verified that the licensee had a procedure written, reviewed and approved.
Management approval wa s in accordance with established licensee procedures and test objectives were consistent with test titles.
Findings:
No discrepancies were noted in the review of these procedures and the inspector had no further questions at this time.
d.
Test Procedure Review The following procedures were reviewed for technical and administrative adequacy:
PT 120.001 Revision 0, Approved November 21, 1979
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Reactor Recirculation System
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PT 136.004 Revision 0, Approved September 27, 1978 Jet Pump Instrumentation PT 202.001 Revision ?, Approved July 25, 1979
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High Pressure Coolant Injection System
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PT 203.001 Revision 0, Approved February 21, 1979 Core Spray
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PT 410.001-28 Revision 2, Approved June 16, 1976 Battery Room Ventilation System
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PT 410.001-2C Revision 2, Approved June 16, 1976 Battery Room Ventilation System PT 411.001-1 Revision 1, Approved September 21, 1977
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Relay Room, Computer Room, emergency Switchgear Rooms, Chiller Equipment Room, HVAC Equipment Room
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PT 412.001 Revision 0, Approved May 16, 1978
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Control Room AC-Control Room Leak Test PT 414.001-1A Revision 1, Approved April 20, 1977
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Diesel Generator Room Ventilation System PT 414.001-1B Revision 1, Approved April 20, 1977
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Diesel Generator Room Ventilation System PT 414.001-1C Revision 1, Approved April 20, 1977
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Diesel Generator Room Ventilation System PT 418.001 Revision 0, Approved June 20, 1979
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Reactor Building Standby - Normal Ventilation System, Secondary Containment Leak Test PT 421.001 Revision 0, Approved August 30, 1979
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RBSVS and CRAC Chilled Water System PT 606.001-1 Revision 1, Approved May 19, 1978
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Rod Block Monitoring System PT 607.001 Revision 0, Approved May 2, 1979
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Rod Worth Minimizer PT 608.001 Revision 0, Approved July 19, 1978
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Rod Drive Control System
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PT 610.001 Revision 0, Approved August 23, 1978 Rod Position Information System PT 611.001 Revision 0, Approved August 23, 1978
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Reactor Protection System PT 652.001 Revision 0, Approved May 16, 1978
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Power Range Reactor Recirc Flow Units PT 654.002 Revision 0, Approved June 28, 1978
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Primary Containment Leak Rate Test Type 8 PT 654.003 Revision 0, Approved June 28, 1978
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Primary Containment Leak Rate Rest Type C The procedures were reviewed for the following:
Management review and approval;
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Procedure format;
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Test objectives clearly stated;
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Prerequisites;
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Environmental conditions;
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Acceptance criteria;
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References;
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Initial conditions;
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Test objectives are met;
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Performance verification;
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Recording conduct of test;
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Recording conduct of test;
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Restoration of system to normal after test;
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Identification of personnel conducting and evaluating test data;
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and, Independent verification of critical steps or parameters.
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The inspector ascertained by review of the above procedures that they are consistent with regulatory requirements, guidance and licensee commitments.
Findings:
No discrepancies were noted in the review of these procedures and the inspector had no further questions at this time.
e.
The following procedures supporting the preoperational test program were received for review:
CF 130.001 Revision 0, Approved November 21, 1979
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Main Turbine Lube Oil System Flush CG 000.001-4 Revision 4, Approved November 21, 1979
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Rotating Equipment CG 000.014-4 Revision 4, Approved November 21, 1979
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MOV Static Test CG 000.032-5 Revision 5, Approved September 18, 1979
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Medium Voltage Power Circuit Breakers
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4.
Plant Tours The inspector made tours of the facility during the course of the inspection including the containment drywell reactor building, steam tunnel, turbine building, control structure, control room, and a walk through of the ECCS systems and the circulating and service water systems.
In all areas inspected, observation by the inspector included work in progress, house-keeping, cleanliness controls, storage and protection of components, piping and systems.
No discrepancies were noted and no items of noncompliance were identified.
5.
Exit Interview At the conclusion of the site inspection on December 6, 1979, an exit meet-ing was conducted with the licensee's senior site representatives (denoted in Paragraph 1).
The findings were identified and previous unresolved and open items were discussed.
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