ML20207H806
| ML20207H806 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/19/1986 |
| From: | Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Williams J TOLEDO EDISON CO. |
| Shared Package | |
| ML20207H811 | List: |
| References | |
| NUDOCS 8701080128 | |
| Download: ML20207H806 (4) | |
See also: IR 05000346/1986024
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
December 19, 1986
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Docket No.: 50-346/86-024
Toledo Edison Company
ATTN: Mr. Joe Williams, Jr.
Senior Vice President - Nuclear
Edison Plaza
300 Madison Avenue
Toledo, Ohio 43652
Gentlemen:
SUBJECT:
INSPECTION NO. 50-346/86-024
Enclosed is the report of the team inspection conducted by Mr. R. C. Wilson and
other NRC representatives on August 4 to 7, 1986 at the Davis-Besse Nuclear
Power Station, Unit No.1 of activities authorized by NRC License No. NPF-3.
This inspection was a continuation of the inspection begun on February 24 to
28, 1986 and described in Inspection Report No. 50-346/86-024 dated June 13,
1986. These inspections reviewed your implementation of a program as required
by 10 CFR 50.49 for establishing and maintaining the qualification of electric
equipment within the scope of 10 CFR 50.49. Within these areas, the inspection
consisted of examinations of selected procedures and records, interviews with
personnel, and observations by the inspectors.
In February the inspectors
determined that the Davis-Besse equipment qualification program was not suffi-
ciently far along to determine its compliance with 10 CFR 50.49, and the initial
inspection report listed numerous unresolved items.
Based on the August continuation of the inspection we have determined that you
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have implemented a program to meet the requirements of 10 CFR 50.49. Three
deficiencies in your program implementation, summarized in Appendix A, are
classified as Potential Enforcement / Unresolved Items and will be referred to
the NRC Region III office for further action. These deficiencies involve
failure to demonstrate qualification of the high range radiation monitor cable,
Amphenol penetration assemblies, and two ASCO solenoid valves.
Four additional
concerns are classified as Open Items, and a future NRC inspection will review
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your actions concerning them. Details of all the deficiencies and concerns are
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discussed in the enclosed inspection report.
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8701090128 861219
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ADOCK 05000346
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Toledo Edison Company
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December 19, 1986
The Amphenol and ASCO Potential Enforcement / Unresolved items were corrected by
August 7.
In a November 17, 1986 telephone conversation you advised that the
other Potential Enforcement / Unresolved Item was corrected, and that virtually
all of the Open Items were completed. Your corrective actions regarding any
remaining concerns and the completion of other planned efforts should not be
delayed pending a future NRC inspection or further action by the NRC Region
III office.
We are available to discuss any questions you have concerning this inspection.
Sircerely,
.a
Robert F. Heishman, Chief
Vendor Program Branch
Division of Quality Assurance, Veador
and Technical Training Center Programs
Office of Inspection and Enforcement
Enclosure:
Inspection Report No. 50-346/86-024
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Toledo Edison Company
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December 19, 1986
DISTRIBUTION:
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JTaylor, IE
RStarostecki, IE
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JStone, IE
LParker, IE
ADeAgazio, NRR
NLe, NRR
MYost, INEL
DJackson, INEL
MJacobus, SNL
AGautam, RIII
RSmeenge, RIII
JMuffett, RIII
JJHarrison, RIII
RdeFayette, RIII
JThomas, DPC
Davis-Besse Resident Inspector, 5503 N. State Route 2, Oak Harbor, OH 43449
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APPEODIX A
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Potential Enforcement / Unresolved Items
As a result of the special equipment qualification inspection on February 24
to 28 and August 4 to 7, 1986, the following items have been referred to NRC
Region III as Potential Enforcement / Unresolved Items (section references are
to detailed portions of the inspection report).
1.
Contrary to paragraph (j) of 10 CFR 50.49, at the time of the inspection
Toledo Edison Cenpany's (TED) files did not adequately document qualifi-
cation of Rockbestos coaxial cable used in the high range radiation monitor
because the ability to reet specified performance requirements during
accident conditions was not shown. Specifically, the ability to satisfy
footnote 9 to Table 3 of Reg. Guide 1.97 was not demonstrated for low
radiation levels at high containment temperatures.
(Section 4.D.(1),
Item 50-346/86-024-01)
2.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and section 5.2.5 of
the D0R Guidelines, at the time of the inspection TED's files did not
adequately document qualification of Amphenol penetration assembifes
because the ability to meet plant performance requirements during
accident conditions was not shown. Specifically, electrical performance
during accident testing was not measured and shown to be acceptable.
(Section 4.D.(2), Item 50-346/86-024-02)
3.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and section 5.2.6 of
the D0R Guidelines, at the time of the inspection TED's installation of
ASCO solenoid valves, plant ID SVICS11B1 and 2, was not shown to be
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qualified. Specifically, the use of qualified cable entrance seals was
not demonstrated as required by the type test report for the steam
service conditions (235 F) documented in the files.
(Section 4.D.(3),
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Item 50-346/86-024-03)
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