ML19329A962
| ML19329A962 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/01/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML19329A940 | List: |
| References | |
| 50-346-78-19, NUDOCS 8001270224 | |
| Download: ML19329A962 (3) | |
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Appendix A NOTICE OF VIOLATION
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Toledo Edison Company Docket No. 50-346 This refers to the inspection conducted by representatives of the Region-III (Chicago) office at the Davis-Besse Nuclear Power Station.-
Unit 1, Oak Harbor, Ohio, of activities authorized by NRC License No. NPFa3.
t During this inspection conducted on June 6-8, 13-15, 20-23,.and
.luly 17-19, 1978, the following apparertt items of noncomp.liance were identified.. Item 1 is a: violation. Items,2 and 3 are infraction.s.
1.
Section 3.8.1.l.b of the Technic ~al Specifications requires that two separate and-independent AC diesel generators be operable when the reactor is in Modes 1, 2, 3, and 4.
Saction 4.8.1.1.2.c.3, which states the requirement for demonstrating operability, requires s
that'the. diesel generator start on a loss of offsite power in con-junction with a safety injection signal, 'de-energize and load
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shed the essential buses and energize the auto-connected essential i
loads through the load sequencer. Section 3.3.2.1,. Table 3.3-3, k
item 4 of the Technical Specifications requires sequence-logic channels of the SFAS to be. operable when the reactor is in Modes 1, 2, 3 and 4.
Contrary to the above,.two separate and independent AC diesel generators were not operable when the reactor was operated in
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' Modes 1, 2, 3, and 4 for startup testing purposes during the period August 12,1977'through ' April 28. 1978. Because of inoperability of the sequence logic channels of the SFAS, the diesel generators were 9
not capable of auto-connecting essential loads to essential buses
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C-1 and D-1 for all conditions of safety injection signals in con-
.jur.ction with a loss of.offsite' power.-
This violation had 'the potential for co.tributing to an occurrence related to health-and safety.
2.
The requirements of 10 CFR Part 50, Appendix B, Criterion XI, and i
Section 17.2.11 of the FSAR as implemented by the Toledo Edison Quality Assurance Procedure No. 2110. " Test Control," state that a test program shall be established to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily'in service is identified and performed in accordance with written' test procedures which incorporate the l
requirements and acceptance limits contained in applicable design documents.
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' Appendix A -
t Contrary to the ab'ove, a test program was not adequately established.
Specifically, Thepreoperationaltestis310.02,."IntegratedSFASTest,"
a.
perfomed February 19-23, 1977 did not adequately. test the.
featum of the SFAS' designed to cope with a loss of offsite power followed by a safety injection (SFAS) signal.:
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'b. - The' scheme check dated March 15,-1977, perfomed in conjunc-
- - tion.with the design modifications.to the Safety Features Actuation System completed 'under System Revision Motice 221E dated February '14,1977 did not meet the requiremerits of. the Calibration'and Functional Testing Procedures 1-C, " Scheme
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Verification Procedure," Revision 1, steps 6.5 and 6.6 in that the scheme check did not identify 'the circuit abnormalities.
discovend in June 1978 nor insure proper control over modifications of the diesel generator circuitry.
3 '..Section 6.8.1 of the Technical Specifications requires that
- written procedures be established,-implemented and maintained.
Administrative Procedure 1823.00 " Jumper and Lift Uire Control N
Procedure," requires a monthly review by the Operations qngineer or
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his representative of the jumper and lifted wire log to prevent i
_ carrying. entries for a long period.
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Contrary to the above, monthly reviews of the jumper and lifted I
wire log were not adequate to. prevent carrying entries for a long period in that during June 1978, lifted wire tags which had been installed?in March-1977 for testing purposes were found in cabinets
- CDF llA-2 and CDE llc on open slide links. The quality of the monthly mytews was not' adequate in that these open sitde links would have prevented valves MS 106 and MS 106A from' closing in the event that the steam supply lines to the auxiliary feedwater pumps ruptured.,
As you are aware from the " Criteria for Detemining Enforcement Action,'
which was pmvided to the NRC licensees by letter dated December 31~,
~1974,. the enforcement actions available to the NRC include administra-tive actions in the fom of written notices of violation, civil monetary penalties, and orders pertaining to the modification, suspension or
~revocation of the license. After careful' evaluation of the items of -
noncompliance set forth.above and the enforcement history at the
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j Davis-Besse facility, we conclude tha't this Motice of Violation is the appropriate action at this-time.
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Appenaix A.
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This notice-is sent to you pursuant to the provision of Section 2.201 of the flRC's Rules of Practice, Part 2, Title 10, Code' of Federal Regulations..Section 2;201 requires you to submit to this office within
-d twenty (20) days of your receipt of this notice, a written statement or 3-explanation in reply, f acluding:
(1) the corrective steps which have ~
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been taken and the resuiL achieved; (2) corrective steps which will be taken to avoid further noncompliance; and (3) the-date when full com -
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pliance will be achieved.
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