IR 05000322/1981017
| ML20039B522 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/20/1981 |
| From: | Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20039B519 | List: |
| References | |
| 50-322-81-17, NUDOCS 8112230186 | |
| Download: ML20039B522 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT Region I
Report No. 50-322/81-12 Occket No. 50-322 License No. CPPR-95 __
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Category B
Licensee:
Long Island Lighting Corgany 175 East Old Country Road Hicksville, New York 11801 i
Facility Name:
Shoreham Nuclear Power Station, Unit 1
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Inspection At:
Shoreham, New York Inspection Conducted:
tober 27-30, 1981 Inspectors:
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R.J. Pao [no, Reactor Engineering Inspector date signed
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a date signed Approved By:
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l S.D~. Ebnet r, Chief, Plant Systems Section, date signed
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DETI Inspection Summary: Inspection on October 27-30,19M (Report No. 322/81-17)
Ap_as Inspected:
Routine, announced inspection by a regional based inspector
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of licensee corrective action pertaining to previously identified items, document review and observation of work activities pertaining to the installation of safety-related instrument cables /ccraponents.
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Results: The inspection i'volved 27 inspection hours onsite and ? hours direct
inspection effort offsite.
No items of noncompliance were identified.
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DETAILS 1.
Persons Contacted Long Island Lighting Company
- R. DeRocher, QA Specialist
- W. Hur.t, Systems Superintendent
- J. Kelly, Field QA Manager B. McCaffrey, Manager Project Engineer
- M. Milligan, Project Engineer J. Morin, Licensing Engineer (via telephone)
- T. Spatz, Assistant Project Engineer
- D. Terry, Assistant Project Engineer (startup)
J. Vitalli, Instrumentation Supervisor (UNICO)
$tene and Webster Engineering Company
- T. Arrington, FQC Superinter. dent D. Cooke, Senior Inspector (lead cable / term.)
Wm. Deemer, FQC Supervisor G. Dicks, Electrical Superintendent (UNICO)
- Wm. Matejek, Lead Advisory Engineer (startup)
R. Pietila, Construction Engineer General Electric Compay
- R. Pulsifer, Resident Site Manager
- J. Riley, Startup Engineer U.S. Nuclear Regulatory Commission
- J. Higgins, Senior Resident Inspector
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- denotes personnel present at exit meeting.
2.
Facili+v Tour The inn ector observed work act tvities in progress, completed work and construction status in several areas. Work items were examined for obvious defects and for noncompliance with regulatory requirements and
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licensee commitments, Specific activities and completed work observed by the inspector included hanger supports and spacers for instrument lines, cable routing and terminaticas, general housekeeping and maintenance of installed electrical equipment.
Par ticular note was taken regarding the presence of quality control inspectors and indications of quality i
control activities through visual evidence such as inspection records, material identifications, nonconformance and acceptance tags.
i No items of noncompliance were identified.
3.
Status of Previously Identified Items I
(0 pen) Item of Noncompliance 322/80-10-01 pertaining to the drywell atmosphere Radiation Monitor sample line installation.
The inspector reviewed licensee contractor drawing numbe'rs K-08F3-1, K-08F2-1, K-08F1-1, K-08F0-1, K-0824-3, K-08El-1, K-08E0-1, K-08D8-1, K-08D7-1, K-0809-1, and K-08D6-1 which outline the sample line route.
The inspector noted that the sample line right angle fittings are being replaced with the larger right angle radius bends and that the Radiation Munitor has been relocated at a higher elevation (from el. 95' to 112'). The inspector notad that the sanipie line penetrated the drywell at elevation i
104 -0, then extended vertically down into the drywell to elevation 75'-0.
No data was available or presented to show that the increase in sample line length or additional height would not have a negative effect in i
obtaining a representative sample.
In addition, the sample line terminates in the drywell atmosphere. This is contrary to the FSAR commitment of Section 12.3.4.2.3 which states, in part:
"... The unit is an off-line type which draws a representative sample from a ventilation duct in the drynell."
This item remains open.
i (0 pen) Unresolved Item 322/80-10-03 pertaining to the adequacy of the drywell atmosphere Radiation Monitoring equipment.
The licensee has not completed its engineering evaluation in determining adequacy of equipment to meet sensitivities stated in FSAR section 12.3.4.2 and 10 CFR 20.
This item remains open.
(0 pen) Licensee Identified Item 322/81-00-04 pertaining to defects in Rockbestos cable involving the nylon wrap.
The licensee is continuing to test various cable configurations to determine disposition of affected cable.
Completion of the test is scheduled for March, 1982.
However, rather than wait for final test results, the licensee has decided to replace all category 1 cables in which the insulation thickness has been reduced by.010 of an inch or aore.
This item remains open.
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4.
Instrumentation (Cables and Terminations) - Work Observations The inspector observed work performance, partially completed work and completed work, as appropriate, relative to select cables, raceways and conduit to determine whether the requirements of applicable specifications, work procedures and inspection procedures are being accomplished in accordance with NRC requirements and licensee commitments. Areas examined include, use of specified materials, wireway leading, grounding and bonding of wireways and conduit, location and routing, cable terminations.
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a.
Items examined for this determination:
Instrument Cable No.1E41ARX454 from panel 1H11*PNL-614,
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Control Room Area, elevation 63'-0 to component 1E41* TE-056A, Reactor Bldg, elevation 63'-0.
Control Cable No. IE41BBC020 from panel IH11*PNL-620, Relay
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Room, elevation 44'-0 to panel 1H21*102B, Relay Room, elevation 44'-0.
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Control Cable No.1E41BBC395 from junction box IJB*505E.
Reactor Bldg, elevation 78'-0 to panel 1H11*PNL-620, Relay Room, elevation 44!-0.
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Control Cable 1E51NRC055 from panel 1R42*MCC-0A2, Reactor Bldg, elevation 112'-0 to panel 1C61*DNL-RSP, Reactor Bldg, elevotion 63'-0.
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Control Cable No. IC71AJC258 from component 1C11*HCU1811, Reactor Bldg, elevation 78'-0 to component IC11*HCU2207, Reactor Bldg, elevation 78'-0.
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Instrument Cable No.1C71AAX003 from panel 1H21*PNL101A, Control Room, elevation 63'-0 to panel 1H11*PNL-601, Control Room, elevation 63'-0.
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Control Cable No.1E51NRC056 from panel IC61*PNL-RSP, Reactor Bldg, elevation 63'-0 to panel 1H11*PNL-602, Control Room, elevation 63'-0.
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Instrument Cable hc. 1E51NRX362 from junction box IJB*517A, Reactor Bldg, elevation 8'-0 to panel IC61*PNL-RSF, Reactor Bldg, elevation 63'-0.
No items of noncompliance were identified.
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During the inspection of panel 1H11*PNL-620 the inspector noted that the wires that make up Cable No. 1E41NRC258 (red division)
were enclosed in flex conduit on one side of the terminal block I
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and the wires coming from the opposite side of the terminal block
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were bundled with wires from the blue division. 'The licensee indicated the cable installation was one of a number of General
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Electric FDDR/FDI charges and that the installation and ins'pection criteria for the changes was defined in E&DCR No. F-28317.. The t
inspector reviewed the engineering design change report which states, in part, under problem solution:
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Intercel wiring
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separation shall be as specified by G.E. is identified on applicable
drawi ng s." The inspector examined the applicable G.E. drawing No. 807E562TF. The drawing contains no instruction pertaining to-
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separation of different color divisions.
However, FSAR section' ~
3.12.3.5.2 paragraph 6d, states, in part:
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.wherever wiring
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of two different divisions exist in a single panel section, '
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separate boards are provided, and spacing of terminal boards and wiring is such as to preclude the possibility of fire propagation
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from one division of wiring to another."
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Discussions with the licensee indicates some confusion as to separation requirements for FDDR/FOI changes to vendor equipment.
This item is unresolved pending NRC review of licensee evaluation
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and corrective action.
(322/81-17-01)
5.
Instrumentation (Cable and Terminations) - Records Review s
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The inspector reviewed pertinent work and quality records for safety related cables associated with the HPCI s:./ety injection system and the Reactor Protection System (ref. paragraph 4a) to determine whether
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records meet established procedures and accomplishments consistent I
with i;RC requirements and licensee commitments noted in chapters 1, 3, 6, 7, 8 and 17 (including codes and standards referenced therein).
Items examined for this determination:
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Cable pull tickets for Cable Nos. 1C71AJC258, IC71AAX003, IE41ARX454, 1E41BBC020, 1E41BBC395, 1E51NRC055, and IE51NRC056.
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Megger and continuity test records for cables noted above.
Qualtiy Control Inspection Reports for the above listed cables.
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(The reports provide inspection verification of routing, separation,
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cleanliness, wire size / type, lug size / type, bend radius, termination and tool identification, cable length, and cable identification).
Issut: control of cable for reel nos. 553-1019, 553-1195, 553-50,
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664-44, 553-195, and 553-629.
Wire diagram nos. FE-5C revision 1, FE-3D revision 9, FE-3AE
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revision 1, FE-18AP revision 2, FE-3GQ revision 6 and FE-4AA revision 5.
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'$&DCR0, N.E-25981.
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Rework authorization nos. 101089, 300743.
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.. Specification 'SH1-159 (electrical installation).
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Quality control. instruction FST-F12-1,-10F and FSI-F12-1-138.
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The records appeared complete and current, were legible, and easily J;
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retrievable.
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No items of noncompliance wereLidentified.
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Instrumentation (Components /Systsm) - Work Observations
The. inspector exami[ned work performance, partially completed work and
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completed work, pertaining to the RCIC steam line isolation /oy pass
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. valve installation to determine whether the requirements of applicable specifications, work procedures drawings and instructions have been
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mot. in areas relating to location, material requirements, logic power
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requirements and' electrical separation by division.
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Items examined for this determination:
H Inside. Containment - 480Vac - drawing no. FM-22A
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Isolation Valve IE51*MOV041.
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By pass Valve 1E51*MOV047.
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Cable Nos. 1E51NBK142 and 1E51NBK182.
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Outside Containment - 125Vac - drawing no. FM-22A t
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Isolation Valve 1E51*MOV042.
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.By pass Valve 1E51*MOV048.
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Cable Nos. 1E51NRK241 and 1E51NRK247.
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I No items of noncompliance were identified.
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7.
Unresolved Itent f
Unresolved items are matters about which more information is required-
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in order to ascertain whether they are acceptable items, or items of noncompliance. An unresolved item identified during this inspection is discussed in Details, paragraph 4b.
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8.
Exit Meeting The inspector met with licensee and construction representatives (denoted in Details, Paragraph 1) at the conclusion of the inspection on October 30, 1981 to summarize the scope of the inspection and the inspection findings.
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