ML19209A510: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(One intermediate revision by the same user not shown)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:...Jersey Central Power & Ught Company-r ,- qq.-:---( )Madison Avenue at Punch Bow' Road
{{#Wiki_filter:..
.Morristown, New Jersey 07960
  -r            ,- qq.                                                   Jersey Central Power & Ught Company
-~ - - -(201)455-82C3
    ~---
.0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-30/3L-0 Report Date Septtmber 24, 1979 (Revised Attachment)
                      --       - ()                                       Madison Avenue at Punch Bow' Road Morristown, New Jersey 07960 (201)455-82C3 0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-30/3L-0 Report Date Septtmber 24, 1979 (Revised Attachment)
Occurrence Date August 12, 1979 Identification of Occurrence"A" Control rod drive pump was removed f rom service for repair of pump vent piping.This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.
Occurrence Date August 12, 1979 Identification of Occurrence "A" Control rod drive pump was removed f rom service for repair of pump vent piping. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.
Conditions Prior to Occurrence The plant was operating at steady state power.
Conditions Prior to Occurrence The plant was operating at steady state power.
Power: Generator, 645 MWe Reactor, 1907 MWt Flow: Recirculating, 15.4 x 104 gpm Feedwater, 7.137 x 106 lb/hr 4 Stack Gas Activity:
Power:                   Generator, 645 MWe Reactor, 1907 MWt Flow:                   Recirculating, 15.4 x 104 gpm Feedwater, 7.137 x 106 lb/hr Stack Gas Activity:     2.79 x 104 pCl/sec Description of Occurrence On August 12, 1979, at 0331 hours, "A" control rod drive pump was removed from service due to excessive leakage from the pump vent piping. The piping was found to be cracked at the bushing where it enters the pump casing. After completion of the corrective maintenance, "A" CRD pump was placed into service at 1300 hours on the same date.
2.79 x 10 pCl/sec Description of Occurrence On August 12, 1979, at 0331 hours,"A" control rod drive pump was removed from service due to excessive leakage from the pump vent piping.
Aoparent Cause of Occurrence Vent piph:g was found to be cracked at the bushing where it enters the pump casing at the inboard end. The cracking appesrs to be caused by an operator using the vent line as a foot support.
The piping was found to be cracked at the bushing where it enters the pump casing.
Analysis of Occurrence                                           jg()G       ])2 In addition to supplying drive cooling and accumulator charging pressure, the control red drive hydraulic system can provide high pressure coolant injection 7910040268
After completion of the corrective maintenance,"A" CRD pump was placed into service at 1300 hours on the same date.
 
Aoparent Cause of Occurrence Vent piph:g was found to be cracked at the bushing where it enters the pump casing at the inboard end.
Reportable Occurrence No. 50-219/79-30/3L-0                               Page 2 September 24, 1979 (Revised Attachment) capaollity. For break sizes up to 0.002 ft.2, a single control rod drive pump with a flow of 110 gpm is adequate for maintaining the reactor . water level
The cracking appesrs to be caused by an operator using the vent line as a foot support.
                          ~
Analysis of Occurrence jg()G])2 In addition to supplying drive cooling and accumulator charging pressure, the control red drive hydraulic system can provide high pressure coolant injection 7910040268  
nearly five feet above the core, thus alleviating the necessity for electromatic relief valve actuation. The safety significance of this event is considered to be minimal, since the redundant CRD pump was operable.
. .,.Reportable Occurrence No. 50-219/79-30/3L-0 Page 2 September 24, 1979 (Revised Attachment) capaollity.
Corrective Action "A'' CRD pump was removed f rom service and isolated. The bushing and a short pipe nipple in the inboard casing vent line were replaced.     "A" CRD pump was placed in service after corrective meintenance. A memorandum will be issued stressing
For break sizes up to 0.002 ft.2, a single control rod drive pump with a flow of 110 gpm is adequate for maintaining the reactor . water level
~nearly five feet above the core, thus alleviating the necessity for electromatic relief valve actuation.
The safety significance of this event is considered to be minimal, since the redundant CRD pump was operable.
Corrective Action"A''CRD pump was removed f rom service and isolated.
The bushing and a short pipe nipple in the inboard casing vent line were replaced."A" CRD pump was placed in service after corrective meintenance.
A memorandum will be issued stressing
* hat operators should not use snell piping as a foot support.
* hat operators should not use snell piping as a foot support.
Failure Data Not applicable.
Failure Data Not applicable.
t090 II3}}
t090     II3}}

Latest revision as of 06:39, 2 February 2020

Revised Attachment to LER 79-030/03L-0:on 790812,control Rod Drive Pump a Removed from Svc for Repair of Pump Vent Piping.Piping Cracked at Bushing at Entry to Pump Casing. Caused by Operator Carelessness.Bushing Replaced
ML19209A510
Person / Time
Site: Oyster Creek
Issue date: 09/24/1979
From:
JERSEY CENTRAL POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19209A507 List:
References
LER-79-030-03L-01, LER-79-30-3L-1, NUDOCS 7910040268
Download: ML19209A510 (2)


Text

..

-r ,- qq. Jersey Central Power & Ught Company

~---

-- - () Madison Avenue at Punch Bow' Road Morristown, New Jersey 07960 (201)455-82C3 0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-30/3L-0 Report Date Septtmber 24, 1979 (Revised Attachment)

Occurrence Date August 12, 1979 Identification of Occurrence "A" Control rod drive pump was removed f rom service for repair of pump vent piping. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.

Conditions Prior to Occurrence The plant was operating at steady state power.

Power: Generator, 645 MWe Reactor, 1907 MWt Flow: Recirculating, 15.4 x 104 gpm Feedwater, 7.137 x 106 lb/hr Stack Gas Activity: 2.79 x 104 pCl/sec Description of Occurrence On August 12, 1979, at 0331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br />, "A" control rod drive pump was removed from service due to excessive leakage from the pump vent piping. The piping was found to be cracked at the bushing where it enters the pump casing. After completion of the corrective maintenance, "A" CRD pump was placed into service at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on the same date.

Aoparent Cause of Occurrence Vent piph:g was found to be cracked at the bushing where it enters the pump casing at the inboard end. The cracking appesrs to be caused by an operator using the vent line as a foot support.

Analysis of Occurrence jg()G ])2 In addition to supplying drive cooling and accumulator charging pressure, the control red drive hydraulic system can provide high pressure coolant injection 7910040268

Reportable Occurrence No. 50-219/79-30/3L-0 Page 2 September 24, 1979 (Revised Attachment) capaollity. For break sizes up to 0.002 ft.2, a single control rod drive pump with a flow of 110 gpm is adequate for maintaining the reactor . water level

~

nearly five feet above the core, thus alleviating the necessity for electromatic relief valve actuation. The safety significance of this event is considered to be minimal, since the redundant CRD pump was operable.

Corrective Action "A CRD pump was removed f rom service and isolated. The bushing and a short pipe nipple in the inboard casing vent line were replaced. "A" CRD pump was placed in service after corrective meintenance. A memorandum will be issued stressing

  • hat operators should not use snell piping as a foot support.

Failure Data Not applicable.

t090 II3