IR 05000322/1980005
| ML19318B286 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/09/1980 |
| From: | Mcgaughy R, Narrow L, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19318B284 | List: |
| References | |
| 50-322-80-05, 50-322-80-5, NUDOCS 8006250205 | |
| Download: ML19318B286 (9) | |
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.nV U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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Region I Report No.
50-322/80-Li Docket No.
50-322 License No.
CPPR OS Priority Category B
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Licensee:
Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 Facility Name:
Shoreham reaclear Power Station, Unit No.1 Inspection at:
Shoreham, New York Inspection conducted:
r 17-20, 1980 g//M If-[/ y[ k Inspectors:
<>fe L. Nar w,' Reactor Inspector date signed 146 W&
$)tW/y', ifEO R. J./aolino, Reactor Inspector date stgned
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H. B. Kister. Chief. Reactor Pro.iects section gi-RO&NS Branch date signed Approved by:
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R.' Q'. McCausb/, Chief, Projects Section,
JMth/ signed RC&ES Branch Inspection Summary:
Inspection on March 17-20,1980 (Report No. 50-322/80-05)
Areas Inspected:
Routine, unannounced inspection by two regional based inspectors of work activities and quality verification records of instrument cable and components; and the status of outstanding items.
The inspection involved 44 inspector-hours on site by two regional based inspectors.
Results:
No items of noncompliance were identified.
i Region I Form 12 (Rev. April 77)
g 8006250
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DETAIQ l.
Persons Contacted Long Island' Lighting ~ Company R. DiRoche QA Specialtst D. M. Durand, Operations QA Engineer
- T. F. Gerecke, Engineering QA Manager
- J. M. Kelly, Field QA Manager T. Koch, QA Engineer W. Lamb, Operations QA Engineer J. McCarthy. Assistant Instrument Supervisor
- W. J. Muselar, Assistant Project Manager
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D. Walsh, Electrical Supervisor (Unico)
E. J. Nicholas, Section Supervisor, Field QA Stone and Webster Engineering (S&W)
T. Arnett, Assistant Instrument Supervisor
- T. T. Arrington, Superintendent Field QC J. Carney, Assistant Project Engineer (Boston)
J. Doyon, Site Engineering Office
- J. Hassett, Senior QC Inspector J. A. Smith, Construction Manager J. Vitelli, Instrument Supervisor Comshock - Jackson (C-J)
A. Shenski, Sub-foreman
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- Denotes persons in attendance at the exit interview.
The inspector also interviewed other licensee and contractor personnel during the inspection.
2.
Plant Tour The inspector observed work activities in progress, completed work and construction status in several areas.
Work items were examined for obvious defects and for noncompliance with regulatory requirements and licensee commitments.
Specific activities and completed work observed by the inspector included installation of pipe supports, cable terminations, storage of equipment and general housekeeping.
No items of noncompliance were identifie *
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3.
Instrument Components / Systems Work Observations The inspector reviewed work performance, partially completed work and completed work pertaining to selected process variables associated with the reactor protection system and engineering safeguards systems.
The inspector verified that the requirements of applicable specifications, drawings, work procedures and inspection procedures were met in areas relating to Welder qualification, installation, welding, material requirements and inspections.
a.
For this determination the inspector examined the following items for the RHR pump seal cooler B and D.
line Ell 1/2K - 1002 ICN-9-2
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line E11 1/2K - 1017 ICN-9-2
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line Ell 1/2K - 1018 ICN-9-2
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Weld inspection procedure QAP-10.5 revision 0
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Weld procedure 081-AA
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Material control document nos. AA-128, AA-075 and AA-216
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Pressure Switch Nos.1 Ell *PS134A,1E11*PS135A,1E11*PS134B,
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1E11*PS135B,1 Ell *PS135D and lEll*PS135D Drawing Nos. FK-la, FK-1B, FP-8D, FM-20A and FM-208
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Welder - Symbol Nos. KQ, LE, LL, PX and EL
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Liquid penetrant procedure QAD-9.31 and QAD-9.32
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Material Requistion Control Nos. C-01256, C-01058, C-6773,
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C-10051, C-02267 and C-10778 Field Weld sheets
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No items of noncompliance were identified.
4.
Instrument Components / System - Quality Record Review The inspector reviewed pertinent work and quality records for selected instrument components to determine whether records meet established procedures and whether the records reflect work accomplishments consistent with NRC requirements and licensee comitments noted in SAR chapter i
nos.1, 3, 6, 7, 8, and 17 (including pertinent codes and standards l
referenced therein) for the following areas:
receipt inspection,
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materials certification, nonconformances, installation and testing.
a.
Items examined for this detennination include:
Electronic Transmitter No.1C61*PT-011
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Pressure' Switch No.lC71*PS-003A
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Pressure Switch Nos.lC71*PS-005A,1C71*PS-005B,1C71*PS-005C and i
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1C71*PS-005D.
Receiving Report Nos. MRR-78-0095, MRR-77-10029, MRR-78-13081
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and MRR-77-7997.
Certificate of Compliance No. 346181
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Hydrostatic Test Report
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Specification Nos. SH-1-406 and SH-1-348
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Purchase Order Nos. 10072, 310010 and 310773
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Quality' Control Instruction No. FSI-F9.1-07B
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Drawing No. FX-1, FK-2A, FM-29B and FM-47A
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Engineering Design Cnange Request No. P-3364
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No items of noncompliance were identified.
b.
The inspector reviewed EDCR No. F-19353A pertaining to flow transmitter IEll*FT-006A, el 13'-0 column 4 and pressure transmitter 1Z93*PT-004a, el 40'-0" column 10.
The EDCR authorized removal of instrument components from manufacturers qualified rack installation to a free standing support.
The inspector requested that the licensee furnish engineering evaluation cnd analysis of the new instrument component installation to ensure that the instrument components will perform their required safety function during the design bases seismic event in conformance with the requirements of IEEE standard 344-1971.
The licensee stated that data was not readily available on site.
This item is unresolved pending NRC review of licensee data.
(80-05-01)
5.
Instrument Cables / Terminations - Work Observation The inspector examined select instrument control cables from safety-related systems to determine whether the requirements of applicable specifications, drawings, work procedures and inspection procedures were accomplished in accordance with NRC requirements and licensee commitments noted in SAR chapters 1, 3, 6, 7, 8 and 17 (including pertinent codes and standards therein) for the following areas:
receipt inspection, materials certification, installation, nonconformances and deviations.
a.
For this determination the inspector examined the following:
Control Cable Nos.1B21 ARC 509,1821 ARC 510,1821 ARC 511,
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1821 ARC 512, IB21 BBC404, 1821 BBC405, 1821 BBC406, 1 C71 AAC150, 1C71BCC150, 1C71CSC150 and 1C71DTC150.
Terminations from IE11*PS-134A (el 8'-0" area RB), to
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IH11*PNL-628 (el 44'-0" area RR), from 1 Ell *PS-135A (el 8'-
0" area RB) to lHll*PNL-628 (el 44'-0" area RR), from 1 Ell *PS-134B (el 8'-0" area RB) to lH11*PNL-631 (el 44'-0" area RR),
from lH11*PNL-609 (el 63'-0" area CR) to 1C71*PS-003A (el l
38'-0" area TB), from 1H11*PNL-611 (el 63'-0" area CR) to 1C71*PS-003B (el 38'-0" area TB).
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Wiring Diagram nos. FE-3GE, FE-3GF, FE-3BJ, FE-3BQ and FE-
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Termination tool nos. 293-I, 298-I, 292-I, 286-I and 376-I.
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Routing per cable pull ticket.
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No items of noncompliance were identified.
b.
The inspector examined cable splices.in penetration nos. 1JBPO*W-B4,1JBPO*E-06, lJBPO*W-C4 and control room panel no.1H11*PNC-608.
(1) The inspector noted that the fabrication of cable splices in i
the electrical penetration appeared to be non-uniform.
The sealing area surfaces.for the splices varied from 3/4 inch
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to 2 inch.
The manufacturer's instructions for LOCA qualified
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nuclear splices (NPKI-100-03) specifies a minimum of "2 inen seal area at each end".
Section 3.2.8.1 of electrical installation specification SH1-159 states, in part:
cable
terminations and splices shall be made... in strict conformance with specfic instructions provided by engineers or by the cable manufacturer.
In addition, electrical craftsmen fabricating splices in the control room and at the electrical penetration stated they do not abrade the cable prior to applying the heat shrink sleeve and that only a chemical cleaning solvent is used.
Section 2.3.9.2 of specification SH1-159, states, in part:
"all terminations and splicing work... all steps outlined in the tpplicable instruction shall be completed in the proper sequence and dimensions shown..."
The manufacturer's instructions (Raychem NPKI-100-03) provides detailed instructions tincluding tools for various type cable insulation which includes chemical cleaning and abrading of cable surfaces.
Item 4 of the manufacturers document (Raychem NPKI-100-03)
states "All warranties, expressed or implied shall be null and void under the following conditions:
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If these or the specific installation instructions are not followed... or by emission of instruction steps."
The licensee indicated he was not aware of the obove referenced
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This item is-unresolved pending NRC review of licensee evaluation and corrective action.
(80-05-02)
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(2) The inspector observed that the cable penetrations and the control panels using the Raychem WCSF-N heat shrink sleeve involved additonal fire loading due to the combustible red sealant material used in qualifying the splices to a LOCA environment. This additional fire loading had not been addressed by the licensee in his Fire Hazard Report.
This item is unresolved pending NRC review of licensee evaluation. (80-05-03)
6.
Instrument Cable /Tennination - Quality Record Review The inspector reviewed pertinent work and quality records for cables identified in the above paragraph to determine whether records meet estabitshed procedures and accompitshments consistent with NRC re and licensee commitments noted in chapters 1,' 3, 6, 7, 8 and 17 (quirements including codes and standards referenced therein) for the following areas:
size, type, tenninations, routing, bendradius, cable pull, inspections,
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nonconformances, legibility and retrieveability of records.
For this determination the inspector examined the following:
Cable pull tickets for cables listed in above paragraph;
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Continuity and Megger test records for cables listed in above
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paragraph; Issue cards, storage records and material qualification records
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for cable reels no. 553-52, 553-133, 55-3-54, 553-722; Installation inspection records listing routing, bend radius,
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material size / type, termination tool used, craftsman performing tennination and reference drawing.
The records appeared complete and current, were legible and easily retreived.
No items of noncompliance were identified.
7.
Seismic Qualification of Instrument Panel Installation The inspector _had previously questioned (Inspection Report 50-324/77-05) the substitution of fillet welds for bolts in mounting Reactor Vessel Pressure and Level Control racks as permitted by E&9CR's F-409 and F-4313. This item was resolved (Inspection Report 50-322/77-08)
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based on verification that the strength of the fillet welds was equivalent
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to that of 16 bolts originally specified.
However evidence is not available on site of seismic qualification in the new mounting configuration using fillet welds in lieu of bolts and at a different location on the panel base. This item is unresolved pending review of such seismic qualification by an NRC Inspector (80-05-04).
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8.
Construction of Seismic Category I Block Walls The inspector examined the specification and drawings listed below to determine whether the concrete block walls in the battery rooms had been designed to seismic category I requirements.
SHI-390 " Specification for Concrete Masonry" dated April 12, 1974
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which requires that masonry structures designed for seismic requirements shall contain a system of horizontally and/or vertically reinforced concrete block walls tied to concrete or steel beams and that such reinforcing shall be indicated on the Engineers drawings.
Drawing No. FA 10L Rev. 8, " Control Room and Diesel Generator
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Room Floor Plans".
Drawing No. FA 20F, Rev.4, " Masonry Walls, Control Room Building".
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Drawing No. FA 88, Rev. 6, " Control Room and Diesel Generator
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Room, Miscellaneous Details.
Drawing No. FA 8C, Rev. 6, " Control Room and Diesel Generator
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Room, Miscellaneous Details.
The above drawings did not show horizontal or vertical reinforcing steel in the concrete block wall around the battery rooms. The licensee's representatives expressed the opinion that these walls had been constructed to Category I requirement and they support some Category I electrical equipment.
This item is unresolved pending determination of the seismic requirements to wh'ch these concrete block walls were constructed.
(80-05-05)
9.
Review of Nonroutine Events Reported by the Licensee By letter dated April.28,1978 the licensee reported, as a significant deficiency in accordance with 10 CFR 50.55(e) a deficiency with snap rings for General Electric 4160 Volt circuit breakers.
Another deficiency was similiarly reported by letter from the licensee dated May 22, 1978.
This involved janning of the breaker closing latch which resulted in failure of the breaker to close upon receipt of an electrical signal.
Following investigation of the snap ring problem by General Electric Company all of the breakers were returned to the General Electric Company plant in Philadelphia for rework in order to correct both of the above problems.
The inspector examined copies of the LILCo Deficiency Reports (LDR's) No. 165, 166, 167, 181 and 239 Jad the additional LDR's for correction of minor miscellaneous damages to the breakers;
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the shop and test reports; the LILCo 0QA Surveillance Reports No.
IR22-129 through 159 and 104 through 106; LILCo Receivi..g inspection reports; S&W Procurement QC Certificates of compliance and Shipping Release Tags; and the General Electric Company certification stating that after reconditioning the 65 circuit breakers being returned will meet the original purchase specifications and requirements.
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The inspector had no further questions concerning this item.
10.
Review of Deficiency Reported by Vendors Bergen-Patarson (8-P) had reported potential problems with its Part 2540 Shut Assemblies in certain sizes of the Mechanical Shock Arrestors.
These problems; possible damage to rear dust covers and possible interference between shock arrestor and rear bracket were described and the assemblies involved identified by letters dated December 28, 1979 from B-P to the licensee.
These potential problems as well as an additional problem with the load capacity of the size 120 assemblies are also identified in IE Circular 79-25.
The inspector examined QC inspection reports dated February 6,1980 which reported the results of inspection of the assemblies on site and identified the assemblies which had not been received on site.
The results of this inspection were summarized in N&D No. 2875 which is still open.
The inspector was informed that all assemblies identified as unsatisfactory during the inspection have been returned to the vendor for repair or modification as required.
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This item remains unresolved pending completion of the repairs or modifications and review of the loads which may be imposed on the 2540-120 assemblies.
Transamerica DeLaval had reported a deficiency which could potentially lead to failure of the drive shaft for the engine driven jacket water pump of the Standby Diesel Generator.
The inspector was informed by the licensee that the pumps had been returned to the vendor for rework and had been received back at the site in apparently satsifactory condition.
However they were on hold for lack of evidence of PQC inspections.
The inspector examined N&D No. 2766 which reported the above.
This item remains unresolved pending disposition of N&D No. 2766.
11.
Licensee Action on Previous Inspection Findings
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(Closed) Unresolved Item (78-05-01):
Environmental qualification of NEMA 4 and NEMA 12 enclosures for terminal boxes.
The inspector examined E&DCR F-23438 which deletes the use of junction boxes in areas subject to a LOCA ervironment.
Wiring will be directly to and between switches.
(Closed) Unresolved Item (79-21-02):
Lack of complete inspection attributes for inspection of cable installation.
The inspector examined QC instruction FS1-F12.1-10G, dated January 30,1980, " Inspection of Cable Installation".
This revision identified the necessary inspection attributes and revised QCIR Attachment 3.1 to identify these attributes.
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(Closed) Unresolved item (80-01-01):
Lack of adequate protection of instrument tubing.
The inspector examined E&DCR F-25980 to prescribe routing and protection of tubing which revises specification SH1-343; and E&DCR No.1845 B which requires that inspection for damaged tubing will be made by S&W during the final walk-through inspection of the system.
The inspector also observed protection of a random selection of installed tubing.
(0 pen) Unresolved Item (78-08-01):
Undercut in structural steel welds. The inspector was informed by the licensee that after further review of this question they will submit on FSAR change which will state that the 0.01 inch undercut limit is applicable to all structural members where cyclic fatigue is considered a design parameter.
Implementation will be by notation of specific inspection criteria on approved fabrication and erection drawings.
Other welding will be inspected to the present criteria of W-200.
If the FSAR change is approved Engineering will identify all areas of cyclic loading for inspection by Field QC.
This item remains unresolved.
12. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, or items of
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noncompliance.
Unresolved items identified durine the inspection are discussed in Paragraphs 4, 5, 7 and 8.
13.
Exit interview The inspector met with licensee representatives (denoted in Paraoraph 1) at the conclusion of the inspection on March 20, 1980.
In addition, H. B. Kister, Chief, Reactor Projects Section #4 and the NRC Resident Inspector, Mr. J. C. Higgins attended the meeting.
The inspector summarized the scope and finding of the it.spection.