IR 05000289/1981014
| ML20005B179 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/11/1981 |
| From: | Ebneter S, Sassani A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20005B176 | List: |
| References | |
| 50-289-81-14, NUDOCS 8107060411 | |
| Download: ML20005B179 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
- Report No. 81-14 Docket No. 50-289
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Category C
License No. DPR-50 Priority
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Licensee:
Metropolitan Edison Company P.O. Box 480
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Middletown, Pennsylvania 17057 Facility Name:
Three Mile Island Nuclear Station, Unit 1 Inspection at:
Middletown, Pennsylvania Inspection conducted: May 18-21,1981 Inspectors: O.O b d.
4 - 9 - 8"/
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A.D. Sassani Jr., Reactor Inspector date signed
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date signed 6/# 8/
Approved by:
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S.D. Ebneter, Chief, Plant Systems Section,
. Engineering Inspection Branch Inspection Summa 1:
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Inspection on May 18-21, 1981, (Report No. 50-289/81-14)
Areas Inspected:
Routine, unannounced inspection by a regional-based in-spector of work activities, docueentation, and records associated with the Unit 1 Restart Program, including: electrical and instrumentation work activities, documentation, and records associated with cable trays and supports (Task NM-48), coolant saturation meter (Task LM-1), and automatic initiation of emergency feedwater (RM-13E) modifications.
The inspection involved 30 inspection hours onsite by one NRC regional-bcsed inspector.
Results : No item of noncompliance was identified.
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f 8107060411 01061F PDR ADOCK 050002139
pgyt Region I Form 12
'(Rev. April 77)
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DETAILS 1.
Persons Contacted General Public Utilities Nuclear (GPUN)
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Adams, Quality Assurance Auditor T.
Hedegor, Instrument and Control Site Laison Engineer G.
Lehmann, Sen'ir Mechanical System Supervisor D.
Mitchell, Li ising Engineer R.
Prahbaker, TM1 QA Engineering Manager
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Smyth, Supervisor of Licensing G.
Steverwauld, Senior Electrical Engineer Catolytic Engineering and Constructors D.
Graham, Electrical Supervisor L.
Moyer, Electrical Supervisor T.
Reddington, Electrical Superintendent Gilbert Associates Incorporated
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C.
Goodwin, Instrument and Control Site Laison Engineer D.
Knepper, Design Engineer
- denotes personnel present at exit interview.
2.
Cable Tray and Support (Task NM-48)
The inspector reviewed quality related work activities, documentaEion, and records relative to the modification to ascertain whether applicable requirements have been met.
Documentation reviewed for this determination include:
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Control Tower Electrical Cable Tray Drawing, E-214-039, Revision IA-1.
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Engineering Change Memorandum, SECM-158, Revision 0 and DCN-DT0177, Hangers.
Engineering Change Memorandum, SECM-161, Revision 0 and DCN-
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DT0165, Hangers.
Engineering Change Memorandum, SECM-251, Revisions 0 and I and
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DCN-DT0179, Cable Trays.
Work Authorization Notice, WAN-397, Revision 0 and 1.
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Support Orawing, SS-205-005, Revision 0, and DCN-0T0177, Revision
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0, Sheet 4.
Support Drawing, SS-205-010, Revision 0, and DCN-0T0177, Revision
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0, Sheet 5.
Support Drawing, SS-205-011, Revision 0, and DCN-0T0177, Revision
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0, Sheet 6.
Support Dra.ing, SS-205-012, Revision 0 and OCN-0T0177, Revision
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0, Sheet 7.
Support Orawing, SS-205 014, Revision 0 and DCN-DT0177, Revision
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0, Sheet 8.
Support Drawing, SS-205-122, Revision 0, and DCN-0T0016, Revision
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0, Sheet 43.
Control Building Elevation 338 feet, Support Section and Detail
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Drawing, SS-205-004, Revision 0, Sheet 2 and DCN-0T0177, Revision 0, Sheet 3.
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Purchase Order No. 100188 and QCIR No. RLL-0585-81 Cable Trays.
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No item of noncompliance was identified.
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Areas examined for this determination include:
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Partially installed cable trays 966, 986, 241, 243, 244, 981, and 982.
Elevation 338 feet-Relay Room.
Partially installed supports for support drawings SS-205-004,
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005, 010, 011, 012, 014, and 122.
Elevation 338 feet-Relay Room.
No item of noncompliance was identified.
The inspector requested analysis and calculation documentation and design verification records for elevati.on 121-121 support.
Because this documentation was not on site, the inspector identifed this as an inspector follow-up item.
This item will be the subject of a further review by an NRC inspector during a subsequent IE inspection (81-14-01).
3.
Saturation Meter (Task LM-1)
The requirements for this task are detailed in NUREG-0578, Page A-11, NUREG-0680, Page C8-16, and GPUN TMI-1 Restart Report, Section 2.1.1.
6.3.3.
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The inspector reviewed quality related work activities, documentation, and records relative to the modification to ascertain whether app-licable requirements have been met.
Document reviewed for this determination include:
Engineering Change Memorandum, SECM-129, Revisions 0,1, 2, 3,
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and 4.
Electrical Block Diagram, SS-202-020, Revision IA-2.
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Electrical Schematic Diagram, B-210-955, Revision IB-1.
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Electrical Connection Diagram, B-210-967, Revision IA-1.
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Electrical Connection Diagram, C-600-409, Revision IA-1.
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Conduit and Cable Layout Drawing, 0-215-044, Revision IA-2.
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Electrical Schematic Diagram, B-210-958, Revision IB-1.
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Elementary Diagram-Annunciator, C-209-956, Revision IH-0.
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Remote Shutdown Cabinet, Channel A & B Signal Conditioning, C-421-234, Revision IA-0.
Specification SP-1101X-35, Revision 1, Class IE Process Instrumentation.
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Schematic Diagram, 79N-69305, CD-23, Revisic.7 0.
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Purchase Order 86666, Instrumentation.
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Purchase Order 86122, Cabinets.
Purchase Order 89145, Cable.
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Inspection Reports, QCIR-JCR-0195-81, QCIR-HEF-0045-80, and QCIR-
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KRK-0046-80.
No item of noncompliance was identified.
The inspector examined the poured foundation for the signal con-ditioning cabinets, Spec. No. 200 Seismic Class I Nuclear Service Racks and the in-place storage at elevation 338 feet.
No item of noncompliance was identified.
4.
Automatic Initiation of Emergency Feedwat.er System (Task RM-13E)
The requirements for this task are detailed in NUREG-0578, Page A-30,
NUREG-0680, Page C8-34 and GPUN TMI-1, Restart Report, Section 2.1.2.
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The inspector reviewed quality related work activities, documentation, and records relative to the modification to ascertain whether applicable requirements have been met.
Documentation reviewed for this determination include:
Engineering Change Memorandum, SECM-076, Revision 0,1, 2, 3, 4,
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5, 6, and 7.
Electrical Elementary Diagram, SS-209-755, Revision IC-4.
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DC Elementary Diagram, SS-209-756, Revision IC-4.
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4kv Elementary Diagram, SS-208-169, Revision ID-0.
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4 kv Elementary Diagram, SS-208-168, Revision 10-0.
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4 kv Elementary Diagram, SS-208-205, Revision IB-1.
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Reactor Coolant Pump Power Monitoring Elementary, SS-209-660
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through 667, Revision 1.
EFW Auto Start Computer Input Block Diagram, SS-202-012, Revision
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IA-1.
Auxiliary Relay Cabinet XCL, E-210-114, Revision ID-3.
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Inspection Report, QCIR-JCR-0633-81, Relays.
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Purchase Order 100192, Relays.
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Inspection Report, QCIR-RLL-0212-80 DP Switches.
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Purchase Order 86199, DP switches.
Work Authorization Notice, WAN 333, Revisions 0,1,2,3,4,5,
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6, and 7, Dated May 13, 1981.
No item of noncompliance was identified.
The inspector verified by drawing review that the reactor coolant pump trip and the feedwater differential pressure switch trip were in-corporated.
The licensee has indicated in Amendment 25 of the Restart Report, dated May 13, 1981 that the steam generator steam-feed mis-match will not be incorporated at this time.
This feature was detailed in Revision 7 of SECM-076.
No item of noncompliance was identified.
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The inspector questioned the purchase of relays under P0 100192.
These relays are installed in Class IE cabinets and powered from a Class IE bus.
They were purchased commercial grade and the manufacturer's Certificate of Conformance indicated 10 CFR Appendix B does not apply.
The licensee indicated that these relays were qualified during initial construction. The inspector indicated that the licensee could not provide objectiva evidence of the initial qualification documentation and objective evidence that the purchased relays are identical to the relays installed during initial construction.
The inspector identified this as an unresolved item to be the subject of a further review by an NRC inspector during a subsequent IE inspection.
(81-14-02)
5.
Unresolved Items
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Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. The unresolved item reviewed during this inspection is discussed in Paragraph 4.
6.
Exit Interview The inspector met with the licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on May 21, 1981.
The inspector summarized the purpose, scope and findings of the inspection and the unresolved item was discussed.
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