ML17252A986
ML17252A986 | |
Person / Time | |
---|---|
Site: | Dresden ![]() |
Issue date: | 04/17/1973 |
From: | Worden W Commonwealth Edison Co |
To: | Giambusso A US Atomic Energy Commission (AEC) |
References | |
WPW Ltr. #308-73 | |
Download: ML17252A986 (2) | |
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Category:Letter
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Should Remain in Service or a Qualified Person Must Verify All Control Rod Movement Through 20% Power ML17252B4191976-12-0202 December 1976 Letter Confirming a 12/02/1976 Conversation Concerning Receipt of an Empty Spent Fuel Shipping Cask from GE Morris Operation Which Had Some Areas of Removable Surface Contamination ML17252B4571975-11-17017 November 1975 Letter Confirming a Conversation Concerning Quarterly Closure Timing of IC Main Steam Isolation Valve in Which the Closure Time Was Found at 2.7 Seconds ML17252B4581975-11-0404 November 1975 Letter Confirming a Conversation Concerning Discovery of High Level in the Torus While Running a HPCI Surveillance Check ML17252A4461975-07-31031 July 1975 Incident Notification Concerning Location of Broken Tack Welds on Jet Pump Restrainer Clamp Bolt Keepers During Tv Camera Examination of Unit 3 Jet Pumps - Dresden Unit 3 ML17252A9121975-04-25025 April 1975 Letter Confirming a 04/25/1975 Conversation Concerning Excessive Leakage Through Torus to Drywell Vacuum Breaker 3-1601-32B During Refuel Outage Local Leak Testing - 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Should Remain in Service or a Qualified Person Must Verify All Control Rod Movement Through 20% Power ML17252B4191976-12-0202 December 1976 Letter Confirming a 12/02/1976 Conversation Concerning Receipt of an Empty Spent Fuel Shipping Cask from GE Morris Operation Which Had Some Areas of Removable Surface Contamination ML17252B4571975-11-17017 November 1975 Letter Confirming a Conversation Concerning Quarterly Closure Timing of IC Main Steam Isolation Valve in Which the Closure Time Was Found at 2.7 Seconds ML17252B4581975-11-0404 November 1975 Letter Confirming a Conversation Concerning Discovery of High Level in the Torus While Running a HPCI Surveillance Check ML17252A4461975-07-31031 July 1975 Incident Notification Concerning Location of Broken Tack Welds on Jet Pump Restrainer Clamp Bolt Keepers During Tv Camera Examination of Unit 3 Jet Pumps - Dresden Unit 3 ML17252A9121975-04-25025 April 1975 Letter Confirming a 04/25/1975 Conversation Concerning Excessive Leakage Through Torus to Drywell Vacuum Breaker 3-1601-32B During Refuel Outage Local Leak Testing - Dresden Unit 3 ML17252A9131975-04-23023 April 1975 Letter Confirming a 04/23/1975 Conversation Concerning Failure of Feedwater Check Valves, 3-220-58A and 62A, and 3A Feedwater Line to Pass Local Leak Rate Test During Refuel Outage Surveillance - Dresden Unit 3 ML17252A7871975-03-19019 March 1975 Note to Confirm a Conversation Concerning Routine Main Steamline High Radiation Monitor Surveillance in Which the a and B Monitors Were Found to Have Set Points in Excess of Technical Specification Values - Dresden Unit 3 ML17252A7891975-03-19019 March 1975 Note to Confirm a Conversation Concerning Routine Main Steamline High Radiation Monitor Surveillance in Which the a and B Monitors Were Found to Have Set Points Exceeding the Techspec Value of 3 Times Background - Dresden Unit 3 ML17252A8241975-02-18018 February 1975 Note to Confirm a Conversation Concerning Discovery of a Leaking Containment Inerting Isolation Valve A03-1601-21 During Local Leak Rate Testing - Dresden Unit 3 ML17252A8251975-02-18018 February 1975 Note Confirming a Conversation Concerning Failure of Bergen Patterson Piping Restraint Number 19 on the Unit 3 HPCI Main Steam Line in the Dry-Well - 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Dresden Unit 3 ML17252B0321974-06-10010 June 1974 Letter Confirming a 06/10/1974 Conversation Concerning a Failure of a Three Quarter Inch Nipple on Reactor Feed Pump Dispatch Line 3-3201-24 - Dresden Unit 3 2017-09-09 |
Text
50-249 Commonwealth_ Edison Company ONE FIRST NATIONAL PLAZA* CHICAGO. ILLINOIS Address Reply to' POST OFFICE BOX 767 *CHICAGO, ILLINOIS 60690 Dresden Nuclear Power station R. R. #1 Morris, Illinois 60450 WPW Ltr. #308-73 April 17, 197.3 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensiiig*
U. S. Atomic Ehergy Commission Washington, D.c. 20545 _
SUBJEX::T: UCENSE DPR . 25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SFCTION 6.6.B.3 OF.THE TEX::HNICAL SPECIFICATIONS.
Dear Mr. Giambusso:
This is to report a condition:-relating to the operation or the Unit in which on April 9, 1973, a main steam line pressure switch setting was found to have drifted. Pressure switch PSL-3-261-.30A was found tripping at 816 PSI which
.is below the Technical Specification limit of' 850 PSI as described in Section
.3.2.a.
PROBLEM AND INVESTIGATION During a slirveillance inspection of* t_he -main steam line low pressure switches the set poi.iit for Barksdale switch 3-261-.30A was found to have drifted
- to 816 PSI~ The switch had been previously set at 871 PSI. The purpose of the pressure switch is to sense a drop in pressure due to a break in a ins.in steam line, and initiate a group I isolation. The electrical arrangement for a group I isolation initiation from a main steam line break is a one-out-of-two-twice logic. Therefore, it would have required two switch failures to prevent an isolation at 850 PSI.
../
Had a maiD steam line break occurred While the pressure setting of the PSL-3-261-JOA switch was 816 PSI all the main steam isolation valves would have closed at 850 PSI. Thus, the failure of switch .3-261-.30A did not present a hazard to.the public safety since an isolation would have occurred at 850 PSI as designed.
2602
CORRECTIVE ACTION The immediate corrective action was to reset the pressure switch setting to 872 PSI. The PSL-3-261-JOA swit~h will be replaced prior to the*
unit-startup due to its failure history {Reference our letter dated December 29, 1972).
- In addition, this switch type is presently under investigation by the manufacturer and the Station Instrument Department to determine the cause of set point drift. Fd;nciings of the investigation will dictate future corrective actions.
- f-"*
Sincerely,
~~- JJ(,(~ ,. -
/) ""' W. .P. Worden
.fW '< Superintendent
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