IR 05000322/1979014
| ML19262A640 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 09/25/1979 |
| From: | Caphton D, Higgins J, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19262A639 | List: |
| References | |
| 50-322-79-14, NUDOCS 7912070202 | |
| Download: ML19262A640 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-322/79-14 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 Conducted:
August.27-30, 1979 Inspectors:
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H. H. Nicholas, Reactor Inspector date
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[. C. g ns, Reactor Ins ector dath t. S. Ymh wm T. G. McNatt, Reactor Inspector date Approved by:
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-. L.'Caphton, Chief, Nuclear Support Section date No.(,RO&NSBranch Inspection Summary:
Inspection on August 27-30, 1979 (Report No. 50-322/79-14)
Areas Inspected:
Routine unannounced inspection by regional based inspectors of the overall preoperational test program including preoperational test program requirements, test sequencing and scheduling, test procedure verification, and test procedure review; pipe supports; chlorination system; load center transfor-mers; emergency-standby power systems; tours of the facility, and, followup on previous inspection items.
The inspection involved 68.5 inspector-hours onsite by three regional based inspectors.
Results:
No items of noncompliance were identified.
1522 030 Region I Form 167 (August 1979)
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DETAILS 1.
Persons Contacted Long Island Lighting Company
- Mr. D. Durand, OQA Engineer Mr. R. Gutman, Maintenance Engineer Mr. P. Hawkins, Lead Startup Engineer
- Mr. J. Rivello, Plant Manager Mr. T. Spatz, Test Engineer
- Mr. J. Taylor, Startup Manager Mr. D. Terry, Lead Startup Engineer Mr. R. Werner, Construction Administrator Stone and Webster Corporation Mr. J. Baker, Lead Advisory Engineer Mr. R. Etlinger, Test Engineer Mr. C. Fonseca, Assistant Project Engineer Mr. D. Giannelli, Lead Startup Engineer Mr. J. Pizzi, Electrical Engineer General Electric Corporation Mr. R. Moody, Test Engineer The inspectors 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 (322/78-04-03).
Project procedure P-304, Nonconformance Control, does not recognize the 0QA Lilco Deficiency Report (LDR) as a nonconformance report.
Revision E of procedure P-304, Nonconformance Control, Approved June 1, 1978, addresses this item.
Procedure P-304 now recognizes the 0QA-LDR as a nonconformance report.
This item is closed.
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3.
Overall Preoperational Test Prcaram a.
Preoperational Test Program Requirements Discussion:
The inspector met with the startup manager and his sta'f and dis-cussed selected phases of the preoperational test program and its requirements including:
Compressed air systems;
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Water pretreatment system;
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Moisture separators and reheaters;
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Freeze protection;
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Plant annunciators and radio communications;
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Personnel access monitors;
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All plant alarms;
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Primary containment inerting and instrument gas;
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Instrument AC power;
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Standby gas treatment and primary containment atmospheric con-
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trol and circulation; Turbine H.P. control (EHC);
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Reactor non-nuclear instrumentation; and,
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The entire scope of all cold functional testing.
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References:
The following references were used for reviews and discussions:
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; and,
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Regulatory Guide 1.68, Initial Test Programs for Water Cooled
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Nuclear Power Plants.
Findings:
As a result of reviews of references and discussions with the start-up manager and his staff, no discrepancies were noted with the test program requirements, and the inspector had no further questions in this area at this time.
b.
Test Sequencing and Scheduling Discussicn:
The inspector met with the startup manager and discussed the following:
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Test procedure status;
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Test procedure review and approvel;
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Test scheduling; and,
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Test sequencing.
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The discussion included a briefing of the test schedule and sequenc-ing by means of the latest copy of the Project Schedule Flow Chart.
Findings:
As a result of discussions with the startup manager and his staff, a review of the project schedule, procedure status, review and appro-val cycle, test scheduling and sequencing, no discrepanices were noted, and the inspector had no further questions at this time.
This area will be followed up on subsequent inspections.
c.
Test Procedure Verification The following procedures were reviewed to verify that adequate test-ing is planned to satisfy regulatory guidance and licensee commitments:
PT 316.001A Revision 0, Approved June 2, 1979
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24 VDC Power Distribution PT 316.0018 Revision 0, Approved June 20, 1979
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24 VDC Power Distribution PT 601.001 Revision 0, Approved December 21, 1977
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Source Range Neutron Monitoring System PT.602.001 Revision 0, Approved March 15, 1978
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Intermediate Range Neutron Monitoring System PT 604.001 Revision 0, Approved March 15, 1978
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Average Power Range N2utron Monitoring System PT 605.001 Revisi.i 0, Approved January 18, 1978
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Traversing Incore Probe Monitoring System The inspector verified that the licensee had a procedure writt'n, reviewed and approved.
Management approval was 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 administra-tive adequacy:
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PT 102.001 Revision 0, Approved August 23, 1978
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Circulating Watcr System PT 107.001-3 Revision 3, Approved January 26, 1979
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Makeup Demineralizer and Transfer System PT 117.001-3 Revision 3, Approved June 20, 1979
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Instrument and Air System PT118.001 Revision 0, Approved May 16, 1978
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Reactor Building Closed Loop Cooling Water System PT 122.001 Revision 0, Approved August 23, 1978
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Service Water System PT 136.001 Revision 0, Approved February 21, 1979
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Nuclear Boiler Process Instrumentation PT 117.002 Revision 0, Approved May 23, 1979
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Loss of Instrument Air PT 311.001A Revision 0, Approved November 14, 1979
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480V Emergency Bus Distribution - BUS 111 PT 311.0018 Revision 0, Approved November 14, 1978
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480V Emergency Bus Distribution - BUS 112 PT 311.001C Revision 0, Approved November 14, 1978
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480V Emergency Bus Distribution - BUS 113 PT 312.001A Revision 0, Approved May 2, 1979
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120 VAC - RPS - MG Sets - 002A PT 312.0018 Revision 0, Approved May 2, 1979
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120 VAC - RPS - MG Sets - 0028 PT 415.001 A-1 Revision 0, March 16, 1977
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Screenwell Pump House Ventilation System PT 415.001 B-1 Revision 0, March 16, 1977
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Screenwell Pump House Ventilation System PT 315.001A Revision 0, Approved July 25, 1979
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125VDC Power Distribution PT 315.001B Revision 0, Approved July 25, 1979
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125VDC Power Distribution PT 315.001C Revision 0, Approvea July 25, 1979
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125 VDC Power Distribution PT 316.001A Revision 0, Appra ed June 20, 1979
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24 VDC Power Distribution PT 316.0016 Revision 0, Approved June 20, 1979
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24 VDC Power Distribution PT 402.001 Revision 0, Approved July 25, 1979
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Primary Containment Atmospheric Control PT 319.001 Revision 0, Approved April 25, 1979
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Plant Communications PT 601.001 Revision 0, Approved December 21, 1977
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Source Range Neutron Monitoring System PT 602.001 Revision 0, Approved March 15, 1978
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Intermediate Range Neutron Monitoring System PT 604.001 Revision 0, Approved March 15, 1978
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Average Power Range Neutron Monitoring System PT 605.001 Revision 0, Approved January 18, 1978
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Traversing Incore Probe Monitoring System
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PT 504.001 Revision 0, Approved March 21, 1379
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Smoke, Flame and Temperature Detection PT 651.001 Revision 0, Approved December 2'), 1978
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Process Computer PT 654.005 Revision 0, Approved July 19, 1978
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Drywell Floor Seal Pressure Monitoring PT 655.001 Revision 0, Approved June 20, 1979
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Seismic Monitoring System PT 703.001 Revision 0, Approved May 23, 1979
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Fuel Handling and Vessel Servicing Equipment PT 707.001 Revision 0, Approved December 21, 1977
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Fuel Pool Cooling System PT 709.001 Revision 0, Approved March 15, 1978
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Reactor Water Cleanup 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; Performance verification;
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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
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data; and, Independent verification of critical steps or paranatars.
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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 proceduras and the inspector had no further questions at this time.
c.
Emergency - Standby Power Systems Discussion:
The inspector interviewed licensees' representatives in the startup test group and held preliminary discussions ont the following:
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Diesel Generating Sets and Auxiliary Systems;
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125VDC Power Distribution Systcms;
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24VDC Power Distribution Systems; incit ding,
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Batteries; and,
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Battery chargers.
References:
Final Safety Analysis Report;
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Applicable Regulatory Guides;
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Institute of Electrical and Electronics Engineers Standards;
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and, Prints, Drawings and Diagrams.
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Findings:
The major portion of the inspection on emergency - standby power systems centered upon discussions and tours of the Diesel Generators Rooms.
As a result of inspections of the diesel generator sets and their auxiliaries, review of referenced documents, and discussions with uersonnel, no discrepancies were noted with exception of the follow-ing item.
Upon inspecting the diesel generator sets, the inspector observed that on the three DG sets, the external movable control linkages making up the fuel rar;ks of the fuel pumps were exposed and uncovered.
These precision parts were observed to De coated with dirt including the teeth on the fuel racks which were coated with a foreign substance.
The licensees' representative acknowledged the inspector concerns and agreed to look into this matter further.
This item is unresolved and is designated Item No. (322/79-14-01).
A further review of the emergency power systems, the.3e procedures, completions and turnovers, will continue during subsequent inspections.
f.
RPV Hydrostatir; Test and Integrated Flush Discussion:
The inspector met with the startup manager and his staff and dis-cussed the reactor pressure vessel hydrostatic test and the system integrated flush.
Discussions included items such as procedures, diagrams, boundaries, scope of test, test witnessing and areas of responsibility.
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References:
CS 136.001 Reactor Pressure Vessel and Main Steam Line
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Hydrostatic Test CF 109.001 Integrated Flush of Systems
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Utilizing the Reactor Pressure Vessel Shoreham Proposed Technical Specifications
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Flow Diagrams:
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M-13211-2 FM 83A-2 M-10127-8 FM 29A-8 M-10128-10 FM 298-10 M-10132-10 FM 32A-10 M-10130-8 FM 31A-8 Findings:
As a result of discussions with the startup manager and his staff, and review of the referenced documents, no discrepancies were noted at this time.
Review and observations will continue in this area as preparations are made for the hydrostatic test.
The inspector had no further questions regarding these items at this time.
4.
Pipe Supports During a tour of the Reactor Building the inspector observed that many of the pipe and component supports in the steam tunnel were attached to steel platas embedded in the ceiling.
The inspector questioned the licensee as to the design and construction of these plates.
The licens-ee's representative provided the inspector with documentation showing that the plates are one inch thick and contain, as an example, forty 7/8 inch welded stud anchors 7 5/16 inches long.
The inspector also reviewed the quality control verification of the embedments and of the concrete pour.
The inspector had no further questions in this area.
5.
Chlorination System In Appendix 38 of the FSAR the licensee states that no appreciable quan-tities of chlorine gas will be maintained on site and hence the additional steps of Regulatory Guide 1.95 are not required.
The inspector reviewed the licensee's system for contro' of marine growth in the Circulating Water and Service Water Systerns.
This sytem will use Sodium Hypochlorite which will be delivered by tank truck and stored in a 20,000 gallon tank on site.
Thus no chlorine gas will be involved and no extra pr tective systems are needed.
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6.
Load Center Transformers The inspector reviewed the licensee's design documents, drawings, test proc e and preventive maintenance programs for safety related load rent.
t~a formers.
The inspector discussed with architect-engineer arsonnM t..i methods used to ensure that bus loading is maintained within design limits.
With the exception of the below item the inspector had
" further questions at this time.
Paragraph 8.3-9 of the FSAR states that initial electrical system tests are designed to demonstrate that equipment operates within design limits.
Regulatory Guide 1.68 (11/73), Appendix A, paragraph A.6.b.,tates that the test program for the vital buses should include a full load test using all sources of power supplies to each bus.
The licensee's current test program does not include a full load test of the 4160 volt /480 volt load center transformers for the vital buses.
The licensees' representative acknowledged the inspectors concern in this area.
This item is unresolved and is designated Item No. (322/79-14-02).
7.
Plant Tours The inspectors cade tours of the facility during the course of the inspec-tion including the containment drywell, reactor building, turbine build-ing, control structure, control room and the diesel generator rooms.
The inspectors observed work in progress, housekeeping, cleanliness controls, storage and protection of components, piping and systems.
No items of noncompliance were identified.
8.
Unresolved Items Areas for which more information is required to determine acceptability are considered unresolved.
Unresolved items are contained in Paragraphs 3 and 6 of this report.
9.
Exit Interview At the conclusion of the site inspection on August 30, 1979, on exit meeting 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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