IR 05000155/1987015
| ML20215G236 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/16/1987 |
| From: | Falevits Z, Gardner R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20215G220 | List: |
| References | |
| 50-155-87-15, NUDOCS 8706230173 | |
| Download: ML20215G236 (5) | |
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I U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Repcrt No.- 50-155/87015(DRS)
Docket No. 50-155-License No. DPR-06
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Licensee: Consumers Power Company 212 West Michigan Avenue
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f Jackson, MI 49201 i
Facility Name: Big Rock Point Nuclear Plant j-u Inspection At: Charlevoix, Michigan Inspection Conducted: June 3-4, 1987 Mh k h'
b>!/ k/87 Inspector: Z._Falevits Date M hI Approved By:
R. N. Gardner, Chief b[/
N Plant-Systems Section Date
Inspection Summary Inspection'on June 3-4, 1987 (Report No. 50-155/87015(DRS)).
Areas Inspected:
Special inspection and review of the EQ cable replacement program; review of applicable procedures and Vendor cable data; and training (25576,41400).
Results: Of the three areas inspected, no violations or deviations were identified.
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E 8706230173 870616 PDR ADOCK 05000155 :
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L DETAILS
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Persons Contacted Consumers Power Company
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- T. W. Elward, Plant Manager
- E. M. Evans, Senior Engineer
- G. C. Withrow, Superintendent, Engineering and Maintenance
- R. L Krchmar, Quality Assurance Engineer
- R. H. Brady, Senior Technical Analyst
- Denotes'those attending the exit interview on June 4, 1987.
2.
History of Environmental Qualifications (EQ) of Electrical Cables at Big Rock Point a.
During past EQ inspections and audits the NRC staff had identified
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deficiencies in the licensee's EQ program in meeting the requirements of 10 CFR 50.49.
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In an August 8, 1984, inspection report documenting a June 5-7, 1984,
,f EQ audit at Big Rock Point, the NRC audit team had concluded that
"the electrical cables reviewed in Appendix B (of the report) should be tested as originally. planned or a more positive effort to show
'i qualification through testing already completed should be initiated."
Appendix B of this August 8, 1984 report had referenced electrical cables having Butyl Rubber (BR) and Polyethylene (PE) insulations located inside the containment.
During a recent audit, the NRC staff observed that the licensee had not performed testing of similar or identical kinds of PE or BR insulated cables, but had attempted to qualify them through reference
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to an analysis of generic industry tests of PE and BR cables.
Subsequently, the NRC team reviewed the licensee's generic
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qualification of these cables and determined that the PE and BR cables were unqualified due to the failure of the licensee tc, establish adequate similarity between the tested cables in the generic reports and the plant cables.
b.
In a Consumers Power Company (CPC) letter to the NRC dated April 23, 1987, the licensee provided a detailed plan to resolve the NRC staff's cable qualification concerns. The letter also provided a history of licensee correspondence with the NRC staff on this issue and the qualification methods used for the Big Rock Point cables.
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'Duringameetingbetween-CPCand'theNRCstaffonMarch3andL4, 1987, the NRC informed the licensee of the following three options which would resolve the cable qualification concerns:
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(1)' Perform' qualification tests on each of the vendor / cable types in~ question to' assure acceptability.
.(2) Replace all' of the cable in question, ~or
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(3)' Collect additional test or qualification data to show cable-
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The licensee elected to replace the BR and PE cables located inside_
the containment. Relative to the cables located outside the.
containment, the licensee elected to evaluate the formulation of each cable insulation type and the variations between the known manufacturers of Big Rock's cables. This information would be used to establish the link for similarity to cables which were qualified for EQ conditions which envelope Big Rock LOCA conditions.
3.
Inspection ~and Review of the E.Q. Cable Replacement program During this inspection, the inspector conducted a visual. field inspection of licensee ongoing activities relative to the replacement of the BR and PE cables' located inside the containment. The inspector examined selected installed new cables and conduits, where accessible, and verified that the method of_ installation conformed to plant requirements and specifications; i
that appropriate procedures were used for the conduit installations, cable pulling, and cable termination activities;'that the new cables installed were qualified, certified, and successfully tested to withstand a LOCA'
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IEEE Standards, NRC requirements and industry codes and standards; that the cables used are suitable for their intended application; that activities were preplanned and technically sound.
l As of June 4,1987, the licensee had completed the' installation of approximately 40% of the cables to be replaced in the containment. The
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licensee planned to replace a. total of 35 (type BR and' PE) cables. The new cables installed will be Rockbestos Cross-Linked Polyethylene or
Raychem EQ cables. The licensee expected to complete the installation and testing requirements by June 12, 1987. The inspector determined that the
cable replacement program appeared to have been adequately preplanned and
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executed, j
No violations or deviations were identified.
4.
Review of Applicable procedures and Vendor Cable Data a.
The inspector examined the following procedures which were written and used by the licensee specifically for this cable replacement activity:
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(1)' Procedure No. FC-610-04P,_ Revision 0, dated May 20, 1987 "EEQ
Cable Replacement in Scheme 5414" j
i (2) Procedure No. FC-610-03P, Revision 0, dated May 29,'1987 "EEQ
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Cable Replacement in Schemes 5601, 5602, 6514 and 6515"
-(3) Procedure No. FC-610-02P, Revision 0, dated May 22, 1987 "EEQ i
Cable Replacement in Scheme 7501" (4) Procedure No. FC-610-01P, Revision 0, dated May 22, 1987 "EEQ Cable Replacement in Scheme 6505" l
Specific areas reviewed in these procedures included: precautions and limitation, administrative reviews and approvals, Q.C. inde[endent verifications, Hold Point requirements, method of replacement,-
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functional testing requirements, and provisions to identify problems
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and corrective action used to resolve them.
The procedures ' epicted a clear step by step sequence of activities d
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to be performed in which each of the old BR and PE cables were to be
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replaced with new Cross-Linked Polyethylene (CLP) or Raychem qualified cables. The inspector verified, during observations of-ongoing field activities, that portions of the above procedures were performed properly.
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The inspector reviewed the following Vendor data and reports associated with the new cables:
(1) Cables to be used inside containment (a) Rockbestos Company Report No. QR-5805, dated May 22, 1986.
" Report on Qualification Tests for Firewall III Irradiation Cross-Linked Polyethylene Construction for Class'IE Service in Nuclear Generating Stations."
(b) Cables purchased from the Rockbestos Company under CPC Purchase Order No. 2002-63850, dated April 24, 1987 for 3000' of 2/c No. 14 AWG FWL 3; 1500' of 3/c No. 14 AWG FWL 3; and 7500' of 5/c No. 14 AWG FWL 3.
(c) Certificates of Conformance for cables purchased under Purchase Order No. 2002-63850.,
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(d) Certified Test Reports for cables purchased under Purchase Order No. 2002-63850.
(e) Cables purchased from the Raychem Corp. under CPC Purchase Order No. 87683-Q, dated October 28, 1976 for 2000' of 2/c No. 14 shielded cable, class C (IPCEA) stranding.
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(f) LCertificates.of Conformance for cables purchased under purchase order.No. 87683-Q.
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(g)? Raychem -'. Flamtrol Qualification.to IEEE Standard No. 383
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dated August 2, 1976.
(Test Report).
(2) Cables used outside containment
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(a)- Wyle Laboratories Report No. 48818-01, dated May 27, 1987.
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~ " Assessment of Nuclear Environmental Accident i
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. Qualification of Class'IE Butyl Rubber Insulated / Polyvinyl
Chloride Jacketed cables for CPC Big Rock Point Nuclear l
Generating Station."
(b) Wyle Laboratories Report No. 48818-02, dated May 27,'1987.
" Assessment of Nuclear Environmental Accident.
Qualification of Class IE Polyethylene Insulated / Polyvinyl Chloride Jacketed cables for CPC Big Rock Point Nuclear
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- Generating Station."
- t No violations or deviations were identified.
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Training
The effectiveness'of the licensee's training program was reviewed by the inspector during the witnessing of the licensee's performance of field activities and during interviews with licensee staff.
Personnel appeared to be ' knowledgeable of the task being performed.
No violations or deviations were identified.
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Exit Interview The Region III inspector met ~with the. licensee representatives (denoted under Paragraph 1) at the conclusion of the inspection on June 4, 1987.
The inspector summarized the purpose and findings of the inspection and the licensee acknowledged this information.
The licensee did not identify and document / processes reviewed during the inspection as proprietary.
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