ML20041F126
| ML20041F126 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/17/1982 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML20041F127 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8203160213 | |
| Download: ML20041F126 (2) | |
See also: IR 05000313/1981035
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In Reply Refer To:
Dockets: 50-313/81-35
f.fB 17 1982
50-368/81-35
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Arkansas Power and Light Company
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ATTN: Mr. William Cavanaugh III
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Senior Vice President
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P. O. Box 551
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Little Rock, Arkansas 72203
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Gentlemen:
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This refers to the inspection conducted under the Resident Inspection Program
by Messrs. W. D. Johnson and L. J. Callan, of this office, covering the period
of November 22 - December 31, 1981, of activities authorized by NRC Facility
Operating Licenses DPR-51 and NPF-6 of the Arkansas Nuclear One, Units 1 and 2,
and to discussion of the findings by the inspectors with members of your staff
at the conclusion of each segment of the inspection.
Areas examined during the inspection and our findings are discussed in the
enclosed inspection report. Within these areas, the inspection consisted of
selective examination of procedures and representative records, interviews
with personnel, and observations by the inspectors.
During this inspection it was found that certain of your activities were not
conducted in full compliance with NRC requirements. Consequently, you are
required to respond to this matter, in writing, in accordance with the pro-
visions of Section 2.201 of the NRC% " Rules of Practice," Part 2, Title 10
Code of Federal Regulations. Your response should be based on the specifics
contsined in the Notice of Violation enclosed with this letter.
The NRC determined that the Unit 1 Emergency Diesel Generators, while in the
" standby" mode were rendered inoperable whenever any one of the three High
Speed Differential Relays in the control circuit operated. After review of
the seismic qualification data (Reference: Paragraph 2.0 of this report),
the licensee determined that the High Speed Differential Relays were
seis21cally qualified in the energized state only. Failure to meet this
seismic qualification requirement is an apparent violation of Criterion II of
Appendix A to 10 CFR 50. AEC/NRC guidance at the time the licensee purchased
the Emergency Diesel Generator High Speed Differential Relays was not as
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comprehensive as the current NRC guidance. Hence, this item will not be cited
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as a violation. Region IV is concerned with the generic aspects of these
High Speed Differential Relays that permitted these deficiencies to occur
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and the neeri for corrective action.
Please describe the corrective actions "y
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to assure resolution of this generic safety problem.
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OFFICIAL RECORD COPY
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Arkansas Power and Light Company
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In accordance with 10 CFR 2.790*a), a copy of this letter and the enclosure
will be placed in the NRC Public Document Room unless you notify this office,
by telephone, within 10 days of the date of this letter and submit written
application to withhold infonntion contained therein within 30 days of the
date of this letter. Such application must be consistent with the require-
ments of 2.790(b)(1).
The responses directed by this letter and the accompanying Notice are not
subject to the clearance procedures of the Office of Management and Budget as
required by the Paperwork Reduction Act of 1980, PL 96-511.
Should you have any questions concerning this inspection, we will be pleased
to discuss them with you.
Sincerely,
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G. L. Madsen, Chief
Reactor Projects Branch
Enclosures:
1.
Appendix A - Notice of Violation
2.
Appendix B - NRC Inspection Reports
50-313/81-35; 50-368/81-35
cc w/ enclosures:
Arkansas Nuclear One
ATTN:
J. P. O'Hanlon, General Manager
P. O. Box 608
Russellville, Arkansas 72801
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bec distrib. by RIV:
W. D. Johnson, RRI
D. M. Hunnicutt, RPS2
K. V. Seyfrit, IES
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