05000346/LER-1980-074-03, /03L-0:on 801008,test Frequency for Containment Air Lock Test Exceeded.Caused by Procedural Deficiency.Mods to Plant Procedures Made to Provide Assurance of Completing Required Testing

/03L-0:on 801008,test Frequency for Containment Air Lock Test Exceeded.Caused by Procedural Deficiency.Mods to Plant Procedures Made to Provide Assurance of Completing Required Testing

ML19340B569
Person / Time
Site:	Davis Besse
Issue date:	11/05/1980
From:	Kocis R TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19340B564	List: 05000346/LER-1980-074, Forwards LER 80-074/03L-0 05000346/LER-1980-074-03, /03L-0:on 801008,test Frequency for Containment Air Lock Test Exceeded.Caused by Procedural Deficiency.Mods to Plant Procedures Made to Provide Assurance of Completing Required Testing
References
LER-80-074-03L, LER-80-74-3L, NUDOCS 8011110302
Download: ML19340B569 (3)

LER-1980-074, /03L-0:on 801008,test Frequency for Containment Air Lock Test Exceeded.Caused by Procedural Deficiency.Mods to Plant Procedures Made to Provide Assurance of Completing Required Testing

Event date:
Report date:
3461980074R03 - NRC Website

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bJ EVENT DATE 44 15 PE POHT DATE tiJ EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l (NP-33-80-95) On 10/8/80 during a review of the unit log by the Operations Supervisor,l a 2 gg l It was noticed that the test frequency for ST 5061.05, the Containment Air Lock Test, l In l4 ; lhad been exceeded. The test was run at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> on 10/3/80 but not again until 1550l 101sj l hours on 10/7/80.

This exceeded the surveillance requirement of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by 21.5 l

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The station had entered the action statement of T.S. 3.6.1.3.

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i;jollThe occurrence is attributed to a procedural deficiency. The control room area status l l'11] lboard was updated by the Shift Supervisor per procedure ST 5061.05. Modifications to l l plant procedures PP 1102.02, PP 1102.10 and ST 5061.05 have been made to provide

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL IN mRMATION FOR LER NP-33-80-95 DATE OF EVENT: October 8, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Surveillance requirements for the containment air lock were completed late Conditions Prior to Occurrence: The unit was in Mode 4 with Power (MWT) = 0 and Load (Gross MWE) = 0.

Description of Occurrence: When reviewing the unit log at 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> on October 8, 1980, the Operations Supervisor noticed that sequential entries for completed contain-ment air lock surveillance tests, ST 5061.05, extended beyond the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limitation of Technical Specification 4.6.1.3a.

The log entries showed ST 5061.05 completed at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> October 3,1980 in preparation for upgrading plant operations to Mode 4, and the subsequent ST 5061.05 completed 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> October 7, 1980 - a time lapse of approximately 93.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Exceeding surveillance requirements technically rendered the containment air lock inoperable, placing the station in the action statement of Technical Specification 3.6.1.3.

The action statement was satisfied by successful completion of ST 5061.05 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the due date (1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> October 7, 1980).

Designation c f Apparent Cause of Occurrence: This occurrence is attributable to a pro-cedural deficiency. As previously noted, ST 5061.05 was completed prior to entering Mode 4, which was required by the Mode 4 checklist. At that time, as prescribed by the

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acceptance criteria, the control room area status board was updated by the Shift Super-visor to show the recent completion date and the next due date for the surveillance test.

This board, located behind the Shift Supervisor, is also used by station staff to relay written or illustrated information. The deficiency exposed by this occurrence is that there is still a possibility of this method,of control not being sufficient.

j Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The surveillance test completed after the occurrence was succes-sful implying that the containment air lock was operable for the time duration since.the previous surveillance test.

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Corrective Action

Use of the status board was introduced from corrective action for.

a previcus Licensee Event Report relative to ST 5061.05 (see Failure Data).

Thouh...he I

status board was thought to be an obvious reminder of pending due dates, this corrective

[

tetion has not been foolproof.

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l LER # 80-074

- d

D TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-95 PAGE 2.

Therefore, as corrective action for this Licensee Event Report:

1.

A modification to the Plant Operating Procedure, PP 1102.02 and PP 1102.10, has been made to include requirements for the Shift Supervisor completing the checklist to inform the appropriate section that the ST 5061.05 is applicable and to be completed per their surveillance test schedule.

2.

The surveillance test schedule submitted to the appropriate section has been changed to include multiple entries for ST 5061.05 to reflect the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> requirement.

3.

ST 5061.05 has been modified to emphasize the changes noted above.

Failure Data: Two previous similar reportable events were reported in Licensee Event Reports NP-33-80-22 (80-016) and NP-33-78-98 (78-082).

LER# 80-074 Y

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