IR 05000346/1979009
| ML19261D837 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 04/30/1979 |
| From: | Hayes D, Jablonski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19261D836 | List: |
| References | |
| 50-346-79-09, 50-346-79-9, NUDOCS 7906260502 | |
| Download: ML19261D837 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-346/79-09 Docket No. 50-346 License No. NPF-3 Licensee:
Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 Inspection At: Davis-Besse Site, Oak Harbor, OH Inspection Conducted: April 10-11, 1979 f
YcYLL.
Inspector:
F. J.
ablonski
- 8O-U Approved By:
D. W. Hayes,j c l[- 20 - 7 /
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Ch Engineering Support Section 1 Inspection Summan Inspection on April 10-11,1979 (Report No. 50-346/79-09)
Areas Inspected: Licensee action on IE Circular No. 78-08.
This inspection involved a total of 16 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance were identified.
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DETAILS 1.
Persons Contacted M. D. Calcamuggio, Plant Electrical Systems Engineer L. C. Stalter, Electronic Systems Engineer E. M. Wilcox, Field QA Specialist G. W. Eichenhauer, Field QA Engineer 2.
IE Circular No. 78-08 - Environmental Qualifications of Safety Related Electrical Equipment at Nuclear Power Plants a.
Circular review responsibility was given to the Plant Electrical Systems Engineer and Electronic Systems Engineer via the "AIF" stamp applied to the Circular.
Further review responsibility was given to the licensee's architect-engineer, Bechtel Corporation.
b.
A synopsis of Toledo Edison's review of Circular No. 78-08 and/or activities, and related NRC activities follows:
(1)
IE Bulletins 77-05,77-05A and 77-06, concerning connectors and penetrations, are discussed in IE Inspec-tion Report 50-346/78-12. A carry over from that report concerned covering of neutron flux monitor Amphenol type bulkhead connectors with Raychem WCSF shrink tubing.
Maintenance work order No. 78-1346 has been prepared.
Work is not scheduled to be completed until the 1980 refueling outage. NOTE:
The licensee stated connectors are not required to mitigate consequenses of an accident.
(2)
Bechtel Corporation has prepared lists of safety related equipment, including instruments, motors, motor oper-ated valves, solenoid operated valves, etc.
The lists contain several apparent mistakes and inconsistencies.
Further, no basis is provided on how the lists were devel-oped nor that the lists are complete. Review is hampered because of the numerous methods of equipment identification.
EXAMPLE - Motor MC-0562 is also C56-2; Valve MVDHil is also MVDH110 and HVDHil.
NOTE:
The lists have preliminary information for reporting on IE Bulletin 79-01.
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(3) Manufacturer's equipment qualification data was reviewed for motors, cables, motor operated valves, solenoid operated valves, limit switches, hermetic seals and terminations listed below.
088-2-
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Motors - MC0011, MC0012, MC0013, MC0561, MC0562
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Cable types - BG5, C20, LIT
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Solenoid Valve - SV229B
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Motor Operated Valves - MV1411A, MVRCO2, MV5010A,
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MVDHil Limit switches - ZS229B
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Hemertic seals - Conax
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Terminations - Raychem WCSF
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(a) Qualification data appeared acceptable for: Motors MC0011, MC0012, MC0013; Cable types BGS, C20, LIT; Motor operated valves MV1411A, MVRCO2, MV5010A; Terminations Raychem UCSF.
NOTE: Raychem WCSF termination materials had been reviewed during previous inspections.
(b) Qualification data did not appear acceptable for:
Motors MC0561 and MC0562 (Containment Recir-
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culation Fans) - Certification of Compliance is not traceable to Joy Manufacturing bill of materials, specification requirements, etc.
Motor operated valve MVDHil (Decay Heat removal
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suction line) - This valve has a type SMB-3 Limitorque operator. No documentation was available to establish that the SMB-3 type operator was qualified.
(Limitorque types SMB-0, 00, 000 have been certified by Limitorque to be qualified by Franklin Institute report F-C3441)
Subsequently, the licensee stated that Limitorque test report No. 600456 provides evidence of environmental qualification of the SMB-3 type operator. This test report is to be made available for NRC review at the plant site.
Solenoid valves - a generic letter from the
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manufacturer, ASCO, states in part:
"In regard to the radiation level, we can only rely on published data concerning the materials involved
... however, we have not conducted any tests under these conditions.
." The solenoids
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use "viton" materials which are sgsceptible to damage from radiation at 9.5 x 10 Rads; gcci-dent environment may be as high as 1 x 10 Rads.
NOTE: Licensee stated that solenoid valves 2313 089-3-
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i serve no post accident function, however, solenoid valves used on safety related valves will be replaced. Refer to IE Bulletin 78-14.
Unqualified position indicating limit switches
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- type EA-170-31300, are installed on the pressurizer quench tank "out" isolation valve (229B) as well as other valves.
(The Bechtel prepared list indicated qualified type EA-180- 11302 limit switches were installed.)
This matter is documented on NCR-57-78.
The switches will be replaced when parts are received.
NOTE:
Licensee states redundant isolation valves are located outside contain-ment. Refer to IE Bulletin 78-04 and inspection report 50-346/78-29.
Hermetic sealing units - Conax, have been
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installed in instruments, limit switches etc.
There are several apparent problems associated with the installation as follows:
(1) There is a 48-inch length of helically wound Kapton insulated wire extending from one end of each connector. Kapton has failed previously conducted LOCA tests; Westinghouse Canada Limited test report CWAPD-332.
The failure was attributed to direct exposure of the Kapton insulation to the chemical spray. At Davis-Besse, the Kapton insulated conductors are installed in PVC coated, helically wound metal hose.
The hose provides flexibility; the PVC provides moisture resistance.
PVChasafunctionagdamagethresholdto radiation of 9 x IQ Rads; accident environ-ment may be 1 x 10 Rads. According to the licensee, tests performed for Arkansas Nuclear One-1 by Wyle Laboratories indi-cate Davis-Besse's installation to be more conservative. That is, Kapton insulation conductors installed in non PVC coated flexible metal hose survived LOCA tests.
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The test report is to be made available for NRC review at the site.
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(2) According to Bechtel letter BT:7139 dated May 24, 1977, nylon inserts provided with the Conax connectors were removed; no basis for the modification was provided.
Nylon has a functiogal damage threshold to radiationoffx10;accidentenvironment may be 1 x 10.
Licensee stated the nylon does not serve as part of the hermetic seal.
(3) According to Bechtel letter BT:7139, dated May 24, 1977, Conax connectors installed originally with Teflon insulated conductors were scheduled to be replaced. The RIII inspector observed installations with Teflon insulated connectors.
Installations include reactor coolant flow transmitters 1A1, IA2, 1A3, 1A4, IB1, 1B2, IB3, and IB4.
The instruments are required when offsite power is interrupted; no post accident operation is required.
Instrumentation installed as part of the B&W
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Supplied Nuclear Steam System has not been reviewed by the licensee relative to topical reports BAW 10003 and 10082. Review is being made in conjunction with several other B&W type plant owners; review scheduled for completion by April 30, 1979.
Lubricant used in motor operated valves is Gulf
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Crown Grease EP-2 and Beacon 325. Original equipment was Exxon Nembula EP-1.
Documenta-tion for the Gulf grease did not include radiation resistance information; Beacon 325 was reported in IE Information Notice 79-03.
Lubricants used in other rotating equipment will also be reviewed by the licensee.
Followup review by the inspector is planned.
(c) Terminal Blocks - wherever terminal blocks may have been installed, all terminations have been made with nut and bolt connections and covered with Raychem WCSF heat shrink tubing. Refer to Field Change Request (FCR)77-433.
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(d) Tapes - Also as part of FCR 77-433, Containment Fan Cooler motor leads had Scotch 334 tape and Scotchfill putty replaced with Raychem WCSF heat shrink tubing.
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3.
No exit meeting was held. The matters were discussed with the licensee by telephone on April 13, 19, 20, and 24, 1979. A synopsis of the discussion follows:
Corrected lists will be completed by April 30, 1979. The lists
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will include B&W supplied valves and instruments.
(Item 2b(2)
above)
Motors MC0561 and MC0562 were replaced, howesar, new docu-
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mentation cannot be located.
(Item 2b(3)(b) above)
Motor operated valve Limitorque type SMB-3.
Documentation
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from Limitorque will be made available.
(Item 2b(3)(b)
above)
Solenoid valves will be replaced.
(It em 2b(3)(b) above)
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Limit switches have beet. ordered but not received. (Item
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2b(3)(b) above)
Nuclear Instrumentation connectors may be covered during this
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outage.
(Item 2b(1) above)
Hermetic sealing units have been investigated relative to use
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of nylon, teflon and PVC.
(Item 2b(3)(b) above)
The licensee stated on April 24, 1979, that further information would be reviewed. For those items not having complete qualifi-cation data available, justification for operation would be made.
All information, including test results or engineering analysis, will be reviewed by NRC during subsequent inspections.
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