05000346/LER-1979-098-03, During Performance of Component Cooling Water Monthly Test,Decay Heat Cooler 1 Component Cooling Outlet Valve CC1467 Would Not Operate. Caused by Valve Linkage Slippage.Linkage Realigned: Difference between revisions

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{{Adams
#REDIRECT [[05000346/LER-1979-098-03, /03L-0:on 791004,during Component Cooling Water Monthly Test,Decay Hear Cooler 1 Component Cooling Outlet Valve CC 1467 Would Not Operate.Caused by Slippage of Valve Linkage.Linkage Realigned & Calibr]]
| number = ML19305E122
| issue date = 10/30/1979
| title = During Performance of Component Cooling Water Monthly Test,Decay Heat Cooler 1 Component Cooling Outlet Valve CC1467 Would Not Operate. Caused by Valve Linkage Slippage.Linkage Realigned
| author name = Deakyne K
| 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-79-098-03L, LER-79-98-3L, NUDOCS 8004220772
| package number = ML19305E119
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = During Performance of Component Cooling Water Monthly Test,Decay Heat Cooler 1 Component Cooling Outlet Valve CC1467 Would Not Operate. Caused by Valve Linkage Slippage.Linkage Realigned
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000346
| LER year = 1979
| LER number = 98
| LER revision = 3
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:NRC FORM 36G U. S. NUCLEAR REGULATORY COMMISSION 4 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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60 61 DOCA ET NUUSER 68 trJ EVENT DATE 74 4
REPORT DATE 80 EVENT DESCRIPTION AND PHOBABLE CONSEQUENCES h 8 lOn October 4 1979 at 1007 hours during the performance of Component Cooling Water l
o 3 l Monthly Test, ST 5074.01, the Decay Heat Cooler 1 Component Cooling Outlet Valve I
t o l4 l l CC1467 would not operate.
This rendered Decay Heat and Low Pressure Injection Train l I'oT 1 11 inoperable placing the station in the action statement of Technical Specification I
o oe 13.5.2.
This required the inoperable train be made operable within 72 hours. There 1
I was no danger to the health and safety of the public or station personnel. Redundant I o 7 i o Is I l Train 2 was available.
(NP-33-79-114) 1 7
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CODE SUBC E COMPONENT CODE SUSC DE S
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lA l g lH l0 l3 l5 l g 33 34 Jb 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l1 l 0 l l The inoperability of CC1467 was due to slippage of the valve linkage.
The slippage l
LLL1_J l was due to a design deficiency which allows vibrations to loosen the bolt that retains l l
y I the two linkage arms.
The linkage was realigned, calibrated and successfully tested 1[E l under ST 5074.01 on 10/4/79.
On 12/10/79 the design deficiency was corrected via l
[E l the implementation of Facility Change Request 79-347.
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% POWE R OTHER STATUS IS O RY DISCOVERY DESCRIPTION [t [5,,,,j W @ l1l0l0l@l NA l
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==DESCRIPTION==
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;7 8 9 11 12 LOSS OF OR OAMAGE To FACILITY 80 TYPE DE SCRIPTION
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==DESCRIPTION==
ISSUSEL 81 o
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111111-lll11111 8 9 to 8 004220 7((h 68 69 60 E DVR 79-145 NAME OF PREPARER Kenneth Deakyne 419-259-5000, E'xt. 231g
 
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-114 DATE OF EVENT: October 4, 1979 FACILITY: Daivs-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Decay Heat Cooler 1 Component Cooling Outlet Valve CC1467 would not operate Conditions Prior to occurrence:
The unit was in Mode 1, with Power (MWT) = 2770, and Load (Gross MWE) = 920.
Description of Occurrence: On October 4,1979 at 1007 hours during the performance of ST 5074.01, Component Cooling Water Monthly, CC1467 would not move. Component Cooling Pump 1 was shut off. Additional attempts to mov e the valve were unsuccessful.
The operator suspended the test and CC1467 was declared inoperable which rendered Decay Heat and Low Pressure Injection Train 1 inoperable.
This placed the unit in the Action Statement of Technical Specification 3.5.2 which requires the inoperable train be made operable within 72 hours or be in Hot Shutdown within the next 12 hours.
Designation of Apparent Cause of 0:currence: The improper operation of valve CC1467 was attributed to slippage of the valve linkage.
This was caused by a design defi-ciency which allowed vibrations to loosen the bolt that retains the two linkage arms together.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. An inspection of the Decay Heat / Low Pressure Injection Train 2 was performed to assure its availability.
 
==Corrective Action==
Under Maintenance Work Order IC-455-79, the valve linkage was realigned and calibrated. The applicable portions of ST 5074.01, Component Cooling Water Monthly Surveillance Test and ST 5074.02, Component Cooling Water Syr. tem Refuel-ing Test were performed to verify operability. The valve and train 1 were declared 3
operabic at 1415 hourn on October 4, 1979.
Facility Change Request 79-347 was implemented on December 10, 1979 to prevent vibra-tions from loosening the retaining bolts on CC1467 and CC1469. This Facility Change Rtquest is identical to Facility Change Request 79-151 which resolved the vibration problems on Service Water Valves SW1429,1434 and 142.4.
Failure Data:
There have been three previously reported occurrences with valves of this type of actuators. They were reported in Licensee Event Reports NP-33-78-120, NP-33-78-147 and NP-33-79-74.
l l
LER #79-098 6
}}
 
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Latest revision as of 09:23, 4 January 2025