ML19305A859

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LER 80-016/03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy
ML19305A859
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/12/1980
From: David Brown
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19305A854 List:
References
LER-80-016-03L, LER-80-16-3L, NUDOCS 8003180508
Download: ML19305A859 (3)


Text

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LICENSEE EVENT REPORT

.- CoNTHOL DLOCK: l l -l fl l (PLEASE FRINT oH T)PC ALL RtOUlHED INIORMAllON)

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i 8 63 til COC A E T NU' *e ER bd 6'J E\ ENT D A15 74 75 RUoAT DATE dJ EVENT DESCalPTION AND FROS ASLE CONSEQUENCES h lo lT] l On 2/13/80 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during a review of the station log, the Shift Foreman dis- l

' g l covered that ST- 5061.05, " Containment Airlock Seal Leakage Test" had not been performeq
o . lafter the last entry into containment during startup. This made the airlock inopera- l
r. 5 l ble and placed the station in the action statement of T.S. 3.6.1.3 which requires the l j o lq l l airlock be made operabic within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. There was no danger to the public or statior}

l 0 l 7 l l personnel. The previous test on 2/8/80 and the next test at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on 2/13/80 j t o Ia l Ishowed that containment integrity was preserved. (NP-33-80-22) l 7 8 9 60 SYSTE M CAUSE C AtAE CoVP. VALVE CoCE COOE SUCCODE Co'JPONENT CCDE SUCCODE SUGCCOE 12191 7 8 I Sl Al@ [ DJ@ ]@ l Pl El Nl El Tl Rlg 9 10 11 82 13 18 49 g ?J g

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'111 l o l l The occurrence is attributed to procedural inadequacy.

ST 5061.05 is done on an as- l it i 11 l l needed basis dependin?, on the airlock use. It is presently trat.ked on the Shift Fore-l

[i 2 l man's status board. There is no step in PP 1102.02, Station Startup, to do the test l

((i j a l l in Node 1 af ter entry to close steam generator secondary side drains. ST 5061.05 was l

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{j i [4 l l performed at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on 2/13/80. ST 5061.05 and PP 1102.02 have been revised. l 7 8 9 80 STA  % POWER OTHER STAT US I COV FY. DISCOVERY DESCRIPTION 4 3 l5 l d@ _ l 0l '9 l d@l" NA l l A l@l Shif t Foreman Review of Logs l 7

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?VR.80-034:. NAME OF PHEPAHLH piton E:

l TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE S'iPPLEMENTAL TNFORMATION FOR LER NP-33-80-22 DATE OF EVENT: February 13, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Failure to perform ST 5061.05, " Containment Air Lock Seal Leakage Test" af ter containment entry Conditions Prior to occurrence: The unit was in Mode 1, with Power (MWT) = T:749.5 and Load (Gross MWE) = 920.

Description of Occurrence: On February 13, 1980 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during a review of the station log, the Shift Foreman discovered that ST 5061.05, " Containment Airl'ock Seal Leakage Test" had not been performed af ter the last entry into containment.

The previous test had been performed on February 8, 1980 at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> and the final containment entry was made on February 9, 1980 to close the steam generator sceondary side drains.

Failure to perform ST 5061.05 af ter the last containment entry rendered the contain-ment personnel airlock inoperable and placed the unit in violation of Technical Speci-fication 3.6.1.3 which states that while in Modes 1 through 4, each containment air-lock must be operable or rectore the airlock to operabic status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the follow-ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Desienation of Apparent Cause of Occurrence: This incident can be attributed to pro-l cedural error for two reasons:

1. There is no approved procedure fer keeping track of ST 5061.05. At present, the Shif t Foreman relies on the 'hif t Foreman office status board for infor-mation on the last containment entry and the last time ST 5061.05 was per-formed. Ile plans his ST 5061.05 testing according to this information. If the information is not updated or in error, ST 5061.05 will be missed.
2. There is no statement in PP 1102.02, " Station Startup" plant procedure which clearly informs operations personnel when ST 5061.05 must be performed. This procedure tells the operator that ST 5061.05 must be performed after the con-tainment personnel airlock is chained and locked prior to Mode 2 (through the Mode 2 checklist) but does not tell the operator to perfirm this test after operations personnel have used the containment personnel airlock to close the steam generator secondary side drains. These drains are closed in Mode 1.

Analysis of Occurrence: There was no danger to the health and safety of the public or to_ station personnel. The containment personnel airlock was successfully tested before the occurrence on February 8,1980 and af ter the occurrence on February 13, 1980. Therefore, ' containment integrity was preserved during this occurrence.

LER E80-016

J TOLEDO ED1 SON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LFR NP-33-80-22 PAGE 2 Corrective Action: When the Shif t Foreman discovered that ST 5061.05 had not been performed after the last containment entry, he immediately declared the containment personnel airlock inoperable and direcced the instrument and control section to per-form ST 5061.03. The test was successfully completed and the containment personnel airlock was declared operable at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on February 13, 1980.

Several temporary modifications have been made to station procedures to ensure the operability of the containment personnel airlock after containment entry. These changes are as follows:

1. A note has been added to the ST 5061.05 acceptance criteria to require the person who has just performed the test to enter the completion time and date of the test and the time and date of the next test on the Control Room equip-ment status board and on the Shif t Foreman's office board. See Major Modifi-cation M-3738.
2. A note has been added to PP 1102.02, " Station Startup Procedure", Step ;B.1.9 to perform ST 5061.05 after the steam generator secondary side drains are closed. See Temporary Modification T-4454.

Failure Data: There has been one similar previous occurrence, see Licensee Event Report NP-33-78-98, 'ailure to perform testing on personnel lock, for details.

LER #80-016

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