IR 05000322/1980018
| ML19345G328 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 01/20/1981 |
| From: | Higgins J, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345G324 | List: |
| References | |
| 50-322-80-18, NUDOCS 8103180190 | |
| Download: ML19345G328 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND E.1FORCEMEN~
Region I
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Report No. 50-322/80-18
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Docket No. 50-322 Category B
License No. CPPR-95 Priority
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- P 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
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Inspection at:
Shoreham, New York Inspection conduc* d: October 23, 1980-December 31, 1980 I
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Inspectors:
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. Sig Senior Resident Inspector cate signed
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date signed date signed JC f/
Approved by:. B. Kister,Dief, Reactor Projects Section
[date' signed No. 4, RO&NS Branch
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Inscection Summary:
Insoections on: October 23-December 31, 1980 (Inspection Report No. 50-322/80-18)
Areas Insoected: Routine onsite regular and backshift inspections by the resident inspector (53 inspection hours) of work activities, preoperational testing, and plant staff-activities. including:
tours of the facility; test witnessing; review of test
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d procedures and preoperational program practices; and, followup on previous inspection i
findings.
Results:
No * items of noncompliance were identified.
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810818o M O
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Region I Form 12-(Rev. April 77)-
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DETAILS 1.
Persons Contacted J. Carney, Site Engineering Representative (S&W)
D. Durand, 00A Engineer (L)
T. Gerecke, Quality Assurance Manager (L)
J. Kelly, Field 0A Manager (L)
L. Lewin, Assistant Startup Manager L)
B. McCaffrey, Asst. Project Manager L)
J. Marin, Senior Licensing Engineer L)
J. Novarro, Project Manager (L)
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L.Peyser,LeadTestEngineer(L)
J. Rivello, Plant Manager (L)
J. Taylor, Startup Manager (L)
D. Terry, Lead Startup Engineer (L)
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- Long Island Lighting Company S&W - Stone & Webster The inspector also interviewed other licensee and contractor personnel during the course of the inspection including management, clerical, maintenance, operations, engineering, testing, quality assurance and construction personnel.
2.
Previous Inspection Item Update (closed) Inspector Follow Item (322/79-11-01).
Loose Parts Monitoring System: The licensee has.added Procedure PT.622.001, " Loose Parts Monitoring System" to the Startup Procedure Status Listing (SPSL) and has included time in the Instrument and Control portion of the Project Schedule to accomplish this test. This item is closed.
(closed) Unresolved Item (322/80-14-02):
Remote Shutdown Panel Mimic: Based on the issuance of FDDR 819, E & DCR F-31904 and Repair / Rework C61-20, the incorrect mimics on the Remote Shutdown Panel and the Control Room Panel were removed and drawings were revised. -The inspector observed the corrected mimics on both panels. This item is closed.
3.
Plant Tour The inspector conducted periodic tours of accessible areas in the plant during normal l
and backshift hours.
During these tours, the following specific items were evaluated:
-- Hot Work: Adequacy of fire prevention / protection measures used.
-- Fire Equipment: Operability and evidence of periodic inspection of fire suppression equipment.
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-- Housekeeping:. Minimal accumulations of debris and maintenance of required clean-ness levels of systems under or following testing.
-- Equipment Preservation: Maintenance of soecial precautionary measures for
. installed equipmer.t, as applicable.
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-- Component Tagging:
Implementation and observance of equipment tagging for safety, equipment protection, and jurisdiction.
-- Instrumentation: Adequate protection for installed instrumentation.
-- Logs: Completeness of logs maintained.
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"ity: Adequate site construction security.
-- Prohibited Items: Observations to determine no smoking in restricted areas and no alcoholic beverages on site.
-- Weld Rod Control: Observations to determine weld rod was being controlled in accordance with site procedures.
Minor problem areas were discussed with licensee representatives throughout the inspection.
No items of noncompliance were identified.
4.
Test Witnessing The inspector witnessed portions of the below tests:
CG.Ud0.005 " Loop Check" Performed on the Reactor det Pump Instruments, and AT.419.001-2 " Turbine Building Ventilation System" Portions witnessed included:
Imposition of air test signals, recording of data both from installed. instruments and special test equipment, use of computer data, operation and shifting of fans, and local claap-on ammeter readings.
During the tests the inspector noted that:
- the test procedure was approved and released for performance as required; l
- test procedure was in use by personnel performing the test;
- test equipment was calibrated; l
- test personnel were suitably qualified; i
. test exceptions were appropriately documented;
- data was properly logged; and
- test acceptance criteria were met for portions observed.
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_ Test Procedure Review a.
Excess Flow Check Valves Instrument lines penetrating primary containment have check valves which shut on high flow (due to, say, a ruptured line downstream of the excess flow check valve).
The indication associated with these valves is tested in procedure AT.690.001.
Additionally this procedure references procedure CS.136.001 for possible mechanical testing of the excess flow valves.
The inspector reviewed the completed procedure CS.136.001 and noted that mechanical testing of the valves was not documented, although personnel involved stated that some checks were performed. This item is unresolved pending issuance of a procedure which will test and properly
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document the mechanical functioning of the excess flow check vavles and is designated as Item No. (322/80-18-01).
b.
Mechanical Snubbers Regulatory Guide 1.68-1973, paragraph C calls for preoperational tests of all equipment required by the Technical Specification (T.S). The latest issue of the General Electric Standard Technical Specifications (1980 Revision), to which the Shoreham T.S. are being written, contains requirements for visual inspections and functional testing of all hydraulic and mechanical safety related snubbers.
The preoperational test program currently has no provision for the functional testing of safety-related mechanical snubbers installed in the plant. This item is unresolved and is designated as Item No. (322/80-18-03).
6.
Jumpers and Lifted Leads The inspector reviewed the licensee's control of electrical jumpers and lifted leads.
Paragraph 4.4.2 of the Startup Manual generally describes the program used to control l
jumpers and specifies the ta' * system to be used with the jumpers.
The inspector also reviewed the jumper le a sampling of jumpers which were installed and leads that were lifted No disce#.,ieles were identified between the jumper logs and the
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actually installed jumpers.
During tours of the plant the inspector observed no unauthorized jumpers or lifted leads. With the exception of the below item, the inspector had no further questions in this area.
Details are not specified in the licensee's program as to who may approve or install individual jumpers during the preoperational period. Additionally, not all of the installed jumpers had the authorization lines on the jumper tag completed. This item is open pending definition in the program of appropriate responsibilities and is designated as Inspector Follow Item No. (322/80-18-02).
7.
Unresolved Items Areas for which more information is required to determine acceptability are considered unresolved. -Unresolved items are contained in paragraph 5 of this report.
8.
Management Meetings
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At periodic intervals during the course of this inspection, meetings were held with senior plant management to discuss the scope and findings of this inspection. The inspector also attended a region-based inspector's exit meeting and a meeting between the licensee and the Office of Nuclear Reactor Regulation held in Bethesda, Md.
regarding utility management structure and technical resources.
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