05000346/LER-1978-083-03, /03L-0:on 780720,containment vessel-to-annulus Differential Pressure Exceeded Tech Spec Limit.Caused by Personnel & Procedural Error.Rate of Pressure Increase Too Great for Shift Check Monitoring.St 5099.01 Modified: Difference between revisions

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{{Adams
#REDIRECT [[05000346/LER-1978-083-03, /03L-1 on 780720:containment vessel-to-annulus Differential Pressure Exceeded Tech Spec Limit by 1 Inch. Purge of Containment Bldg Commenced.Caused by Inadequate Monitoring of Pressure Increase by Shift Check]]
| number = ML19326A072
| issue date = 08/15/1978
| title = /03L-0:on 780720,containment vessel-to-annulus Differential Pressure Exceeded Tech Spec Limit.Caused by Personnel & Procedural Error.Rate of Pressure Increase Too Great for Shift Check Monitoring.St 5099.01 Modified
| author name = Fulmer S
| author affiliation = TOLEDO EDISON CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
| docket = 05000346
| license number =
| contact person =
| document report number = LER-78-083-03L, LER-78-83-3L, NUDOCS 8001310642
| package number = ML19326A068
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 3
}}
{{LER
| Title = /03L-0:on 780720,containment vessel-to-annulus Differential Pressure Exceeded Tech Spec Limit.Caused by Personnel & Procedural Error.Rate of Pressure Increase Too Great for Shift Check Monitoring.St 5099.01 Modified
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000346
| LER year = 1978
| LER number = 83
| LER revision = 3
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:_
7 11} q LICENSEE EVENT REPORT V,
CONTROL SLOCX: l l
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l l lh (PLEASE PRINT oR TYPE ALL REQUIRED INFoRMATION) lH lD lB lS l1 l G l 0 l -l 0 i 0-l N l p l 7 l - l g l 3 l@l 4 l 1 l 1 l1 l 1 l@l l
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CCN'T 7S REPORT oATE SO to 68 69 EVENT oATE 60 61 CoCEET NUMBER F
4 EVENT DESCRIPTION AND PRC8ASLE CONSECUENCES h l o 121 l' At 0820 hours on 7/20/78, it was noted that containment vessel to annulus differential l l pressure exceeded the TS 3.6.1.4 limit of +25 inches water gage by 1 inch water gage.
I o 3 Contain-I gTlq l At 1047 hours on 7/20/78, the purge of the conta4=ent building commenced.
lo i s i I ment vessel to annulus differential pressure was within allowable limits at 1050 hours ;
There was no ' threat to the health and safety of the public or unit person g Io is 1 l on 7/20/78.
The slight increase above the TS limit would not cause contaiment vessel inter y fij-l7l l nel.
(NP-33-78-100) nal pressure to exceed the design pressure if a LOCA had occurred.
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[TTT] 1 The cause of this occurrence is both procedural and personnel error.
The l
li i i 1 I crease of pressure was too great to be adequately monitored by the shif t check.
g,,.,,l time span between preparation of the containment purge pernit and actual commencement Containment vessel to annulus differential l
l of the containment purge was excessive.
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p TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-78-100 DATE OF OCCURRENCE: July 20, 1978 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Containment Vessel to Annulus High Differential Pressure on Plant Startup Conditions Prior to Occurrence: The unit was in Mode 3, with Power (WT) = 0, and Load (MWE) = 0.
Description of Occurrence: At 0820 hours on July 20, 1978, it was noted that coneminment vessel to annuius differential pressure exceeded the Technical Speci-fication limit of +25 inches water gage by 1 inch water gage. This placed the unit in the Action Statement of Technical Specification 3.6.1.4.
Plant Startup Frocedure, PP 1102.02 was in progress. At 0350 hours on July 20, 1978, a courninment purge permit was initiated due to a containment vessel to annulus differential pressure of +23 inches water gage. At 0820 hours on July 20, V) At 1047 hours on July 1978, the containment vessel to annulus differential pressure exceeded +25 inches.
s 20, 1978, the purge of the containment building commenced.
Containment vessel to annulus differential pressure was within allowable limits at 1050 hours on July 20, 1978, which removed the unit from the Action Statement of Technical Specification 3.6.1.4.
Designation of Apnarent Cause of Occurrence: The cause of this occurrence is both procedural and personnel error. The containment vessel to annulus differential pressure was being monitored by ST 5099.01, " Miscellaneous Instrument Shift Check",
uhich is performed once every eight hours. The rate of increase of containment vessel to annulus differential pressure was too great to be adequately monitored by the shift check.
Additionally, the time span between initiation of corrective action (preparation of the containment purge permit) and actual commencement of die containment vessel purge (6 hours and 57 minutes) was ercessive. Proper urgency and followup with regard to the processing of the contaicment purge permit would have prevented e:.-
ceeding the technical specification limit.
l Analysis of Occurrence: There was no threat to the health and safety of the public or to unit personnel. The slight increase above the technical specification limit would not cause containment vessel internal pressure to exceed the design pressure of 40 psig during a loss of coolant accident condition.
V LER #78-083
 
~
~
r
,e TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION PAGE 2 SUPPLDfENTAL INFORE\\ TION FOR LER NP-33-78-100 ST 5099.01, " Miscellaneous Instrument Shift checks" has been
 
==Corrective Action==
modified to provide additional guidance to the operator concerning when to initiate Containment vessel to annulus corrective action to prevent exceeding the limit.
differential pressure has been added to the control room reading sheets (read approximately once every four hours) to provide the operator with trend information.
All affected personnel will be notified of the delay in implementing the release Permit and requested to accelerate this process.
the containment vessel to annulus differential Failure Data:. On October 18, 1977, pressure technical specification limit was exceeded (Licensee Event Report NP-33-7 It was believed the cause of the October,1977 occurrence was the operation of only j
j one contain= ant air cooler; therefore, the startup procedure was modified to assure Since both containrient air coolers two containment air coolers were in operation.
were in operation prior to this occurrence, this addit'ional operational experience has shown further corrective action was necessary.
LER #78-083 i
)
D
}}
 
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