IR 05000322/1980011
| ML19344F334 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/21/1980 |
| From: | Higgins J, Kister H, Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19344F333 | List: |
| References | |
| 50-322-80-11, NUDOCS 8009150161 | |
| Download: ML19344F334 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
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50-322 Report No.
Docket No. 50-322 Category B
License No. CPPR-95 Priority
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' Licensee: Lono Island Lightina Comoany 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 1 - July 6, 1980 Inspectors:
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/..~C'. Hg ins, Resident Inspector Yb
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h. C. Linville, Re$ctor Inspector
'date* si gned date signed Approved by:
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' PD H. B. Kister7 Chief, Reactor Projects Section Idat( signed No. 4, RO&NS Branch Insoection Summary:
Insoections on: June 1 - July 6, 1980 (Inspection Report No. 50-322/80-11)
Areas Insoected: Routine onsite regular and backshift inspections by the resident inspector (55 inspection hours) and a region-based inspector (15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />) of work activities, preoperational testing and plant staff activities including:
tours of the facility, test witnessing, review of plant fire protection measures, observation of intake canal excavation, quality assurance review, review of IE Bulletins and Circulars, and followup on previous inspection findings.
Results:
No items of noncompliance were identified.
Region I Form'12 (Rev.-April.77)
8009150 )f /
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DETAILS 1.
Persons Contacted _
D. Durand, 0QA Engineer (L)
T.Gerecke,OAManager(L)
J. Kelly, Field QA Manager (L)
L..Lewin,AssistantStartupManager(L)
B.McCaffrey,AssistantProjectManager(L)
M. Miele, Health Physics Engineer (L)
M.Milligan,ProjectEngineer(L)
J. Morin, Senice Licensing Engineer (L)
J. Novarro, Project Manager (L)
R. Perra, Chief Inspection Supervisor (S&W)
D. Pope, Asst. Structural Supt. (S&W)
R. Pulsifer, Resident Site Manager (GE)
J. Riley, Lead Startup Engineer, NSSS (GE)
J. Rivello, Plant Manager (L)
J. Taylor Startup Manager (L)
D. Terry, Lead Startup Engineer, BOP (L)
L---Long Island Lighting Company S&W-Stone and Webster GE--General Electric The inspector also interviewed other licensee and contractor personna during the course of the inspection including management, clerical, maintenance, operations, engineering, testing, qJality assurance, and construction personnel.
2.
Previous Inspection Item Uodate (open) Unresolved Item (322/79-05-05):
Response to 0QA Audit Findings:
The inspector reviewed all outstanding audit responses and selected, closed, audit findings.
Six of the open items either did not have specific completion dates or had passed their defined completion dates without establishing new ones.
Discussions with personnel indicated no ed"~se effects as a result of the items remaining open. Most of the it, involved relate to manual revisions. The licensee's representatik stated that additional emphasis would be placed on this area to ensure that the audited organizations estaliished dates for actions and complied with these dates. This item was also reviewed in report 322/80-06 and remairs open.
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(closed)UnresolvedItem(322/79-20-02):
Plant Review of IE Bulletins and Circulars:
The licensee revised procedure SP12.007.01 with revision 2, to modify his system for handling NRC correspondence.
Additionally, all past NRC Bulletins and Circulars reviewed were placed back into the system for review again to determine applicability and action required.
The inspector reviewed several completed document packages, documents still in the review cycle and the indexing and filing system in use.
The system now appears to be working to properly identify items for which action is required.
This item is considered closed.
Individual Bulletins and Circulars will be reviewed and closed separately.
(closed) Unresolved Item (322/80-02-03):
Environmental Qualification of Steam Tunnel RTD's: This item was also reviewed in inspection 322/80-06.
The licensee revised Quality Control Instruction (QCI) No. FSI-F12.1-08,
" Inspection of Raceway (Conduit) Installation" with revision E dated 6/16/80.
This procedure now specifies checks for physical integrity of equipment and tightness of components.
The sealing of the ends of open conduits is specified on E & DCR F-5750A.
The actual sealing will not take place until later in the job.
This item is considered clos:d.
(closed) Inspector Follow Item (322/80-09-03):
Pump and Valve Inservice Testing per ASHE Code, Section XI: The licensee's representative stated that procedures for Section XI pump and valve testing will be written, commented on by the Startup Staff and approved prior to their use.
Testing per these procedures will then be completed by the Shoreham Operating Staff prior to fuel load.
This item is considered closed.
3.
Plant Tour The inspector conducted periodic tours of accessible areas in the plant during normal and backshift hours.
During these tours, the following specific items were evaluated:
-- Hot Work: Adequacy of fire prevention / protection measures used.
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-- Fire Equipment: Operability and evidence of periodic inspection of
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fire suppression equipment.
-- Housekeeping: Minimal accumulations of debris and maintenance of required cleanness levels of systems under or following testing.
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-- Equipment preservations: Maintenance of special precautionary measures for installed equipment, as applicable.
-- Component Tagging:
Implementation and observance of equipment tagging for safety, equipment protections and jurisdictio <
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-- Instrumentation:
Adequate protection for installed instrumentation.
-- Logs:
Completeness of logs maintained.
-- Security: Adequate site construction security.
-- Prchibited items: Observations to determine no smoking in restricted areas and no alcoholic beverage usage onsite.
Minor problem areas were discussed with licensee representatives throughout the inspection.
No items of noncompliance were identified.
4.
Intake Canal Excavation The inspector reviewed the following documents:
Shoreham Specification SH1-443 for " Construction of Intake Canal - Stage III" Dated January 29, 1979; Drawing FY-28-11. Excavation and Grading, Intake Canal-Dredging, SH2; and Survey results for excavated areas. Additional excavation down to elevation 10 feet above mean low water was required on the east bank of the intake canal to satisfy NRC concerns about soil liquefaction during a design basis earthquake and subsequent blockage of the intake canal.
The inspector observed portions of the earth removal and stone placement and noted that the excavation was proceeding in accordance with design documents.
No discrepancies were identified.
5.
IE Bulletins and Circulars a.
Review Complete
.The inspector reviewed the below listed Bulletins and Circulars and the licensee's responses to them in order to determine that the documents had been reviewed by the appropriate personnel, applicability correctly determined, and that all necessary actions had been taken or planned.
Some details of the revie.* of each document are included below. The inspector had no further questions at this time regarding these documents.
Bulletin 76-01:
BWR Isolation Condenser Tube Failure - This bulletin does not apply to Shoreham since the plant does not utilize an isolation condenser or similar component.
Bu11etin'76-02:
Relay Coil Failures - GE Tupe HFA, HGA, HKA, D1A Relays -
This Bulletin was reviewed in inspection report 78-02.
Due to past checks and revised specifications no GE relays with nylon versus Lexan spools should be.in equipment onsite. As equipment currently is turned over to the Startup Group, checks are mads during the C & 10 phase in procedure CG.000.033-3 to verify that the subject relays have the newer Lexan spools.
Additionally a random check of relays by the inspector revealed none of the old relay spools.
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Bulletin 76-03:_ Relay Malfunctions - GE Type STD relays - The licensee has determined that no GE Type STD relays are used or planned for use on site.
Random checks by the inspector revealed none of the subject relays.
Belletin 76-05:_ Relay Failures - Westinghouse BFD Relays - The licensee has determined that no Westinghouse BFD relays are used or planned for use on site. Random checks by the inspector' revealed none of the subject relays.
Bulletin 76-06: Diaphragm Failures in Air Operated Auxiliary Actuators for Safety / Relief Valves - The licensee's valves have newly designed diaphragms which should not be subject to the problem discussed in the Bulletin. Additional installation problems with these particular valves are discussed in Circular 79-18 and will be reviewed at a later date.
Circular 76-02:
Relay Failures - Westinghouse BF (ac) and BFD (dc) Relays -
The licensee has determined that no Westinghouse BF or BFD relays are'
used or planned for use on site.
Random checks by the inspector revealed none of the subject relays.
Circular 76-03:
Radiation Exposures in Reactor Cavities - Procedures and access control program supplemented by training are designed to ensure necessary control through the Radiation Work Permit (RWP). Additionally, specific maintenance and operating procedures, which could result in high exposures, have appropriate precautions.
Circular 76-05:
Hydraulic Shock and Sway Suppressors - The licensee has not included any hydraulic shock and sway suppressors (snubbers) in his plant design. All snubbers to be used are the mechanical type.
The inspector verified this by review of various memoranda, letters, specifications, a tour of the snubber storage area and witnessing of installed snubbers.
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Additonal Review Required Bulletin 76-04:
Cracks in Cold Worked Piping at BWR's - No documentation was available onsite to determine applicability or actions taken or planned.
Circular 76-01:
Crane Hoist Control, Circuit Modifications - In light of recent changes in the FSAR describing the facility's crane, the inspector
questioned whether the licensee's reply from 1976 was still valid. The licensee's representative stated that a review would be performed to determine the applicability.
Circular 77-05:
1.iquid Entrapment in Valve Bonnets - The licensee's representative stated that many valves of the type described existed in the plant and further review was necessary to determine precisely which ones and what actions were needed.-
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6.
Fire Protection a.
Inspections
.The inspector toured various portions of the plant, including the reactor building, drywell, control room and relay room, and observed fire fighting equipment for operability.
Checks were made for accumulations of combustible materials in safety related areas.
The inspector also reviewed the results of the monthly fire inspections by the fire insurance company and the corrective actions taken for selected findings by the fire inspector.
No unacceptable areas were identified.
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Quality Assurance (QA)for Fire Protection
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The inspector reviewed the NRC requests for information relative to the FSAR and licensee responses to the same in the Fire Protection Area.
Request number 420.41 asks for a description of the quality assurance controls to be applied to the fire protection area.
It also specifies that these controls would apply to both the remaining construction activities and the-operations phase of the plant.
The licensee replied to this question on 2/29/80 and stated that the controls would be the same as described in Operational Quality Assurance Program with the exceptions listed in the Fire Hazards Analysis Report, Section 1.C.
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licensee has not established these QA controls for the fire protection program or equipment with the exception of the Preoperational Tests.
The issue of when these controls are to begin and exactly which portions of the fire protection systems are to be covered is unresolved and is designated item no. (322/80-11-01).
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The inspector observed the warehouse storage of mechanical snubbers, receipt testing of one '120,000 pound design load snubber, and the installed condition cf several snubbers already placed in their final location.
The inspector reviewed the special' receipt inspection and test requirements delineated in E & DCR No. F-12159 and noted that they were being followed.
The inspector also discussed past problems with the snubbers with Field QC personnel.
No unacceptable conditions were identified.
The area of snubber testing and installation will receive further review in future inspections.
8.
Quality Assurance a.
0QA Audit Program The inspector reviewed the pertinent controlling procedures and standards and the Operational Quality Assurance (0QA) Audits for the last 4 months.
Each Audit package contained check lists describing the areas audited and the
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specific items. reviewed. Also included were the Audit findings and corrective
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. actions for these findings submitted by the audited organization, when the responses to the items were already completed.
The inspector noted that the audits appeared comprehensive and thorough.
The area of response to audit findings is discussed in paragraph 2.
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b. ' Release Packages The inspector reviewed the Type B release package for the E41A subsystem, which is a portion of the High Pressure Coolant Injection (HPCI) System, and the QA documentation associated with it. The. package contained the appropriate material as described in the Startup Manual. The preliminary QA reviews of the release or turnover package identified several items which were corrected for the final version. The inspector also witnessed released components in the plant and noted jurisdictional tags were appropriate.
One released valve, E41-M0V-038, had a construction QA reject tag still on it.
Since the valve was not on the Master Punch List, the inspector questioned this.
The licensee's representative stated that the tag had incorrectly been left on the valve after the deficiency had been corrected, and that it would be removed.
The inspector had no additional questions in this area.
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Surveillance of Testing The inspector observed preoperational testing in progress and 0QA surveillance of the testing, including:
approved procedures in use, qualified personnel performing the test, proper documentation of test step completion, and discrepancies noted.
The test observed was being ~ performed on the Rod Drive Control System per Preoperational Test Procedure PT 608.001.
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Unresolved Items Areas for which more information is required to determine acceptability are considered unresolved. An unresolved item is contained in Paragraph 6 of this report.
10. 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 resident inspector also attended exit interviews of region-based inspectors conducted with plant management during the course of this inspection and a meeting held between the licensee, his contractors, the NRC and Suffolk County to discuss contentions related the issuance of an operating license for Shoreham.
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