Abnormal Occurrence 50-289/75-43:on 751218,one of Six Pressure Switches Tripped at Less Conservative Limits than Tech Specs During Channels Surveillance Test.Caused by Calibr Drift in Associated Pressure Switch PS-290| ML19210A158 |
| Person / Time |
|---|
| Site: |
Three Mile Island  |
|---|
| Issue date: |
12/26/1975 |
|---|
| From: |
Arnold R
METROPOLITAN EDISON CO. |
|---|
| To: |
|
|---|
| References |
|---|
| GQL-0159, GQL-159, NUDOCS 7910240883 |
| Download: ML19210A158 (4) |
|
|
|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19210A1511976-02-12012 February 1976
Abnormal Occurrence 76-7/1P:on 760212,empty Snubber Fluid Reservoir Found at Location DHH-198.Leakage Due to Damaged Seal.Snubber Removed & Replaced
ML19322A4301976-02-0505 February 1976
Abnormal Occurrence 76-6/1P on 760204:radiation Leak Detection Sys Out of Svc for 22-h.No Reactor Bldg Atmospheric Samples Taken.Caused by Cover Plate to Monitor Left Open Following Insp.Procedures Reviewed W/Personnel
ML19210A1581975-12-26026 December 1975
Abnormal Occurrence 50-289/75-43:on 751218,one of Six Pressure Switches Tripped at Less Conservative Limits than Tech Specs During Channels Surveillance Test.Caused by Calibr Drift in Associated Pressure Switch PS-290
ML19210A1451975-12-19019 December 1975
Abnormal Occurrence 50-289/75-42:on 751210,outside Containment Isolation Valve for Steam Generator Sample Line CA-V5B Failed to Close.Caused by Valve Manual Operator Inadvertently Left Open by Reactor Personnel
ML19210A1731975-11-25025 November 1975
Abnormal Occurrence 50-289/75-40:on 751112,stuck Contacts on Diesel Generator 1A Voltage Relays Threatened Function of Engineered Safety Feature.Caused by Pitting of Relay Contact.Relays Checked at Each Startup Pending Design Mods
ML19261F1481975-11-24024 November 1975
Abnormal Occurrence 50-289/75-41:on 751114,personnel Failed to Strictly Follow Drain & Blanketing Procedure.Vented Center Control Rod Drive Mechanism Allowed Radioactive Gas Into Reactor Bldg.Personnel Counseled on Proper Procedures
ML19210A1831975-11-21021 November 1975
Abnormal Occurrence 50-289/75-39:on 751112,control Rod 4 in Group 7 Dropped Into Core,Resulting in Asymmetrical Rod Signal & Automatic Power Reduction.Caused by Failure of Stator Winding.Stator Winding Replaced & Tested
ML19210A1891975-10-31031 October 1975
Abnormal Occurrence 50-289/75-38:on 751021,control Rod Verification Program Not in Compliance W/Tech Specs.Caused by Procedure Misinterpretation.Revised Surveillance Program Will Clearly State Requirement of Individual Rod Movement
ML19210A1911975-10-31031 October 1975
Abnormal Occurrence 50-289/75-37:on 751021,blocked Strainer on Outlet to Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Improper Design Allowing for One Strainer W/No Bypass Caused Blockage
ML19210A2021975-10-29029 October 1975
Abnormal Occurrence 50-289/75-36:on 751019,auxiliary Operator Failed to Obtain Radiation Work Permit & Carry Monitoring Device.Caused by Improper Administrative Procedures
ML19210A1971975-10-21021 October 1975
Abnormal Occurrence 75-37:on 751021,blocked Strainer on Outlet of Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Plant Returned to Svc in 15 Minutes
ML19210A2151975-10-20020 October 1975
Abnormal Occurrence 50-289/75-35:on 751010,improper Mix of Boric Acid Crystals Caused Blockage in Mix Tank.Crystals Settling to Bottom of Tank Clogged Line to Reclaimed Boric Acid Storage Tank.Mixture Mod Should Correct Failures
ML19210A2211975-10-10010 October 1975
Abnormal Occurrence 75-37:on 751010,during Transfer of Boric Acid from Storage Tank to Reclaim Tank,Blockage Noticed in Outlet Line.Caused by Boric Acid Crystals Settling to Drain Due to Improper Mixture
ML19210A2241975-10-0808 October 1975
Abnormal Occurrence 50-289/75-34:on 750928,inoperative Hydraulic Shock Suppressor Threatened Function of Engineered Safety Feature.Low Fluid Level in Snubber Caused Failure. All Other Snubbers Checked Satisfactorily
ML19322A4371975-09-30030 September 1975
Abnormal Occurrence 75-34 Re Disconnected Hydraulic Snubber within Reactor Bldg Secondary Shield.Investigation of Circumstances Incomplete.Snubber Replaced During Ongoing Seal Replacement Program
ML19210A2461975-09-26026 September 1975
Abnormal Occurrence 50-289/75-31:on 750917,core Flood Tank Water Level Below Tech Specs Requirements.Caused by Incorrect Reading on Lower Reading Channel CF2-LT3.Channel Will Now Be Monitored & Personnel Informed on Procedures
ML19210A2411975-09-26026 September 1975
Abnormal Occurrence 50-289/75-33:on 750917,de-ice Makeup Valve NR-V-4A Failed in Open Position.Failure Caused by High Resistance Contact in Closing Control Circuit Not Fully Energizing.All Control Contacts to Be Checked & Cleaned
ML19210A2391975-09-26026 September 1975
Abnormal Occurrence 50-289/75-32:on 750918,incorrect Open Position of Air Supply Valves PP-V-47 & 179 Could Have Prevented Proper Functioning of Door Seals in Event of Emergency Safeguards Actuation.Jj Colitz 750919 Ltr Encl
ML19210A2451975-09-19019 September 1975
Abnormal Occurrence 75-33 Re Failure of de-ice Makeup Valve NR-V-4A to Close Using Control Room Remote Pushbutton.Caused by High Resistance Contact in Closing Control Circuit. Contact Cleaned,Tested & Returned to Svc
ML19322A4361975-09-18018 September 1975
Abnormal Occurrence 75-31 Re Low Borated Water Level in Core Flood Tank B.Caused by Improper Level Channel Transmitter LT3 Readout.Transmitter Adjusted
ML19210A1791975-09-0505 September 1975
Abnormal Occurrence 50-289/75-29:on 750827,reactor Bldg Purge Supply Valve AH-V-1D Failed to Close Prior to Engineered Safeguards Test.Caused by Corroded Robotarm Actuator.Robotarm Actuator Lubricated
ML19210A2251975-09-0505 September 1975
Abnormal Occurrence 50-289/75-30:on 750827,valve CF-V-2B of Core Flood Tank B Sample Line Isolation Failed to Close Upon Receipt of Engineered Safeguards Actuation Signal.Caused by Valve Binding Against Valve Stem
ML19210A1811975-09-0202 September 1975
Abnormal Occurrence 50-289/75-28:on 750823,MS-V-13A Valve Turbine Drive Emergency Feed Pump Failed to Remain Open. Caused by Control Circuit Pressure Switch Failure,Due Possibly to High Ambient Temp
ML19210A1871975-08-29029 August 1975
Abnormal Occurrence 50-289/25-27:on 750821,crack & Leak Found in Auxiliary Makeup Pump a Suction Vent.Caused by Fatigue Due to Vibration.Cracks Repaired & Hydrostatically Tested.Failed Pipe Section Replaced
ML19322A4351975-08-28028 August 1975
Abnormal Occurrence 75-30:on 750827,core Flood Tank B Sample Line Isolation Valve CF-V2B Failed to Close Following Engineered Safeguards Signal.Valve Manually Closed Using Handwheel
ML19210A1861975-08-27027 August 1975
Abnormal Occurrence 75-29:on 750827,reactor Bldg Supply Valve AH-V-1D Failed to Fully Close.Investigation Into Cause Underway
ML19210A1841975-08-23023 August 1975
Abnormal Occurrence 75-28:on 750820,during Test of Turbine Drive Emergency Feed Pump,Associated Valve Failed to Remain Open.Caused by Failed Pressure Switch
ML19210A1901975-08-21021 August 1975
Abnormal Occurrence 75-27 on 750821:leaks Found in Socket Weld Joint at Makeup Pump a & Suction Line Connection W/Pump Suction Header.Cause of Problem Under Investigation
ML19210A1941975-08-0101 August 1975
Abnormal Occurrence 50-289/75-26:on 750724,high Reactor Coolant Pressure Trip Set Points Less Conservative than Tech Specs.Caused by Calibr Drift.Specs Will Be Changed to Account for Instrument Error
ML19210A1951975-07-31031 July 1975
Abnormal Occurrence 50-289/75-25:on 750721,failure of Diesel Generator a Frequency Relay to Actuate,Threatening Nonperformance of Diesel Generator.Cause Presently Unknown
ML19210A2001975-07-25025 July 1975
Abnormal Occurrence 50-289/75-23:on 750716,auxiliary Relay to Generator 1B Failed to Energize on Demand.Caused by Mfg Defect.Failed Relay Replaced & Remaining Relays Inspected
ML19210A2071975-07-25025 July 1975
Abnormal Occurrence 50-289/75-24:on 750716,during Removal of River Water Pump NR-P1B from Svc,Discharge Valve Failed to Close.Caused by Open Phase on Winding Due to Severe Heat Resulting in Single Phasing of Other Windings
ML19210A1991975-07-22022 July 1975
Abnormal Occurrence 75-25:on 750722,three Frequency Relays to Steam Generator a Found in Dropped Out State.Relays Replaced & Returned to Svc.Cause of Failure Yet to Be Determined
ML19210A2171975-07-21021 July 1975
Abnormal Occurrence 50-289/75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump Suction Vent Line MU-PIA Leading to Valve MU-V156A.Caused by Improper Spacing Between Moving Anchor & First Pipe Restraint
ML19210A2051975-07-18018 July 1975
Abnormal Occurrence 75-23:on 750716,one of Three Auxiliary Relays of Diesel Generator 1B Breaker G11-02 Failed. Remaining Relays Tested Satisfactorily.Cause of Failure Under Investigation
ML19210A2121975-07-18018 July 1975
Abnormal Occurrence 75-24:on 750716,river Water Pump Discharge Valve Failed Due to Low Valve Motor Winding Resistance & Winding Motor Overheating
ML19210A2221975-07-11011 July 1975
Abnormal Occurrence 75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump a Suction Line Vent.Caused by Pump Vibration
ML19210A2311975-07-0303 July 1975
Abnormal Occurrence 50-289/75-21:on 750625,coolant Temp Trip Bistable Channel C Failed to Trip During Test of Reactor Protection Sys.Caused by Defective Printed Circuit Board Solder Joint in Signal Converter
ML19210A2371975-06-27027 June 1975
Abnormal Occurrence 50-289/75-19:on 750618,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Caused by Channel C Trip Setpoint Out of Calibr Due to Instrument Drift
ML19210A2301975-06-27027 June 1975
Abnormal Occurrence 75-03:on 750626,noble Gas Released to Auxiliary Bldg.Probable Cause:Evaporator Malfunction While Filling Makeup Tank or Coolant Bleed Tank.No Tech Specs Exceeded
ML19210A1621975-06-27027 June 1975
Abnormal Occurrence 50-289/75-18:on 750615,QA Documentation from Vendor Found Inadequate for Repaired Decay Heat River Water Pump Motor Shaft.Caused by Lack of Administrative Controls
ML19210A2351975-06-25025 June 1975
Abnormal Occurrence 75-21:on 750625,reactor Protection Sys Channel C Failed During Surveillance Test.Caused by Coolant Temp Trip Bistable Failure to Trip Due to Component Failure in Signal Converter
ML19210A1721975-06-25025 June 1975
Abnormal Occurrence 50-289/75-17:on 750615,reactor Bldg Purge Isolation Valve Failed Local Leak Rate Test.Caused by Improper Valve Adjustment Procedures & Matl Defects Not Allowing Long Term Retention of Adjustment
ML19308A5371975-06-23023 June 1975
Abnormal Occurrence 75-20:on 750622,while Returning to Full Power Operation After Forced Power Reduction,Reactor Power Increased Above Power Level Cutoff Before Xenon Reactivity Approached Stability.Procedures Under Review
ML19210A2431975-06-19019 June 1975
Abnormal Occurrence 75-19:on 750618,less Conservative Variable Low Reactor Coolant Sys Pressure Trip Setpoint for One Channel of Reactor Protection Sys Violated Tech Specs. Caused by Instrument Drift for Channel C Setpoint Calibr
ML19210A1661975-06-17017 June 1975
Abnormal Occurrence 75-18:on 750615,repaired Motor Shaft to Decay Heat River Water Pump Not Returned W/Proper QA Documentation.Caused by Lack of Administrative Control
ML19210A1751975-06-17017 June 1975
Abnormal Occurrence 75-17:on 750615,during Test of Reactor Bldg Purge Isolation Valve Local Leak Rate Test,Two Exhaust Valves Would Not Pressurize to Required Test Pressure.Caused by Valve AH-V1A Failing to Fully Close
ML19210A1771975-06-16016 June 1975
Abnormal Occurrence 50-289/75-16:on 750605,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Specific Cause Not Established. Setpoints Will Be Checked to Assure Proper Calibr
ML19291B5291975-06-13013 June 1975
Abnormal Occurrence 50-289/75-15:on 750605,pressure Transmitter Trip Setpoint of Reactor Protection Sys Channel B Tested Out of Calibr.Caused by Trip Setpoint Calibr Drift
ML19210A1801975-06-0606 June 1975
Abnormal Occurrence 75-16:improper Trip Setpoints on Variable Low Reactor Coolant Sys Pressure Sys Violated Tech Specs
1976-02-05
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for TMI-1.With
ML20211H5111999-08-31031 August 1999
Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis
ML20211Q3551999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With
ML20210R4791999-08-13013 August 1999
Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2
ML20210U4791999-07-31031 July 1999
Monthly Operating Rept for July 1999 for TMI-1.With
ML20209G0011999-07-0909 July 1999
Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1
ML20210K7651999-07-0909 July 1999
Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca
ML20209H8251999-07-0101 July 1999
Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station
ML20209H1421999-06-30030 June 1999
Monthly Operating Rept for June 1999 for TMI-1.With
ML20195H0751999-06-0808 June 1999
Drill 9904, 1999 Biennial Exercise for Three Mile Island
ML20195H9261999-05-31031 May 1999
Monthly Operating Rept for May 1999 for TMI-1.With
ML20209G0351999-05-31031 May 1999
TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo)
ML20207B6621999-05-27027 May 1999
SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05
ML20206R0571999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With
ML20206D4201999-04-20020 April 1999
Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2
ML20209G0071999-03-31031 March 1999
Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion)
ML20205K6851999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With
ML20210C0161999-03-0101 March 1999
Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246
ML20207M8461999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for TMI-1.With
ML20196K3561999-01-22022 January 1999
Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits
ML20207A9291998-12-31031 December 1998
1998 Annual Rept for TMI-1 & TMI-2
ML20196G4661998-12-31031 December 1998
British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl
ML20196F6861998-12-0202 December 1998
Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection
ML20198B8641998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for TMI-1.With
ML20195C6921998-11-12012 November 1998
Safety Evaluation Supporting Amend 52 to License DPR-73
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20196B7191998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for TMI-1.With
ML20203G1211998-10-30030 October 1998
Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt
ML20155E7511998-10-15015 October 1998
Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing
ML20154L5541998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for TMI Unit 1.With
ML20153A9941998-09-16016 September 1998
Safety Evaluation Denying Request to Remove Missile Shields from Plant Design
ML20151U8821998-09-0808 September 1998
SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2
ML20151V2811998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With
ML20237A8331998-08-12012 August 1998
Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1
ML20237C6411998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Tmi,Unit 1
ML20236R2201998-06-30030 June 1998
Monthly Operating Rept for June 1998 for TMI-1
ML20236W9961998-06-0909 June 1998
1998 Quadrennial Simulator Certification Rept
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20249A1061998-05-31031 May 1998
Monthly Operating Rept for May 1998 for TMI-1
ML20247G0761998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1
ML20212A2191998-04-22022 April 1998
Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2
ML20248H6991998-04-0808 April 1998
Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris
ML20216K1061998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1
ML20217E0811998-03-24024 March 1998
Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident
ML20212E2291998-03-0404 March 1998
Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected
ML20216F0981998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1
ML20202F8121998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1
ML20199G8371998-01-22022 January 1998
SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1
ML20198N2901998-01-12012 January 1998
Form NIS-1 Owners' Data Rept for Isi
ML20199J3251997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1
1999-09-30
[Table view] |
Text
NRC T"'9UTION FOR PART 50 DOCK M ATERI AL
'CONTROL NO:
->.-FILE: It:01DE :: nErenT r FROM: Met. Edison co.
DATE OF DOC DATE REC D LTR TWX RPT OTHER f**c.' ,,h * '
.'.12-26-75 1-2-76 xx'TO: ORIG CC OTHER SENT AEC POR I?E NRC 1 sigried SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
Ic<1 50-289 DESCRIPTION: Ler reporting A0-50-289/75-43 dn ENCLOSURES:
12-13-75 .re out of spec serp.oing"for a reactor building 30 psig c.hannel pressu:
e g g]ppgtg switch....
.., j cmum PLANT N AME:
Three Mile Ilsand Unit 1
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SALTZMAN GOSSICK/ STAFF KNIGHT KASTNER E. GOULBOURNE (L)
MELTZ CASE PAWLICKl BALLARD P. KREUTZER (E) f SHAO SPANGLER J. LEE (L)
PLANS _BOYD** . STE L LO' M. RUSHBRCCK (L)
MCDONALD , S. REED (E)
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,.NOVAK MULLER DEYOUNG (L)
,.ROSS DICKER S. SHEPPARD (L)
E. COUP E GOLLER (L) (Ltr) lPPOLITO KN'GHTON M. SLATER (E)
PET ERSON f P. COLLINS.fTEDESCO YOUNGBLOOD H. SMITH (L)
HARTFIELD (2)
DENISE J. COLLINS REGAN S. TEETS (L)
KLECKER REG OPR LAIN AS PROJECT LDR G. WILLI AMS (E)
EISENHUT/Fil E &TEGION (2)
BENAROYA V. WILSON (L)
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,,VOLLMER HARLESS Vil. INGRAM (L)
F. WILLIAMS STEELE M. DtmCAll M- MAN /UO_EXTERNAL DISTRIBUTION
_uarrisburg, Pa.
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~~~METROPOLITAN EDISON COMPANY
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POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 92N601 N'December 26, 1975
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"*Washington, D.C.
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Dear Sir:
'g ! i n s g/Decket :To. 50-EM '
Opers. ting License No. DPR-50 In acecrdance with the Technical Specificatiens of our Three Mile Island Nuclear Station Unit 1 (TMI-1), we are reporting the following abner =al occurrence.
(1) Report Nu=ber: A0 50-289/75 h3 (2a) Report Date:
December 26, 1975 (2b) Occurrence Date: December 18, 1975 (3) Facility: Three Mile Island Nuclear Station Unit 1 (h) Identification of Occurrence:
Title: Out-of-Specificatien Setpoint for a Reactor Building 30 psig Channel Pressure Switch Tvpe: An abnormal occurrence as defined by the Technical Specifications, paragraph 1.8a, in that the trip setpcint for one of the six (6) pressure switches for the Reacter Building 30 psig channels was fcund to be less conservative than the setpoint listed in Technical Specification 3.5.3.1.
, (5) Conditions Prior to Occurrence:
The reactor was at cold shutdem conditien with major plant parameters as follevs: Power: Cere: 0 ", Elec.: 0 M'ie RC Flev: 0 lbs/hr.14]Cil-RC Pressure: O psig 1490 092 '..,.-,'RC Temp.: 150 F PRZR Level:
L2 inches PR2R Te=p.:
1500F (6) Description of Occurrence:
Cn Dece=ber 18, 1975, while conducting the Refueling Interval Reactor Building 30 psig Channels Surveillance Tes;, cne or the six (6) pressure switches was found to trip at a pressure less conservative than the trip setpcint listed in Technical Specificatien 3.5 31.
The required and actual trip setpoints for the pressure switch out-of-specification, PS-290, were < 30 pais and 30 5 psig respectively.
_The cut-of-specification pressure switch was recalibrated and retested and the resulting trip setpoint was verified as being within Technical Specification limits. The remaining five (5) similar pressure switches were determined to be within the Technical Specification limits.
(7) Designation of Apparent Cause of Occurrence:
The cause of this occurrence has been determined to te material in that the out-of-specification trip setpoint was due to ciner calibraticn drift experienced in the associated pressure switch, PS-290.
This pressure switch was last calibrated en January 15, 1974.
(8) Analysis of the Occurrence:
It has been determined that this occurrence did not constitute a threat to the health and safety of the public in that the setpoints for the other five (5) Reactor Building 30 psig channels pressure switches were within the Technical Specifications 11=its end .tuld have performed their protective function had an overpressure condition occurred.
(9) Corrective Action:
In addition to the i= mediate action described above, the Plant Operaticns Review Cc=rittee evaluated the present ncminal setpv.at and determined that
-it is sufficiently conservative. Since subsequent refueling intervals vill be shorter than the present initial cycle, these pressure switches vill be calibrated more frequently, with resultant less chance of setpcint drift beyond the Technical Spec!fications limits.
(10) Failure Data:
Square D Co. Pressure Switch Type 9013 - AMG5 Form "R" 1490 093 0-100 psig Range
+ 25 Accuracy
.,-3--.--. . . .Similar Occurrences: Ncne Sincerely, si , R. C. Arncid Vice President RCA:JFE:tas ec: Office of Inspection and Enforcement, Region 1 1490 094