Similar Documents at Ginna |
|---|
Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024
LLC - Integrated Inspection Report 05000244/2023004
ML24026A0112024-01-26026 January 2024
R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump
IR 05000244/20230102023-12-19019 December 2023
LLC - Age-Related Degradation Inspection Report 05000244/2023010
ML23348A0992023-12-15015 December 2023
R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23347A0092023-12-13013 December 2023
Annual Commitment Change Notification
ML23346A0142023-12-12012 December 2023
LLC - Senior Reactor and Reactor Operator Initial License Examinations
ML23341A1252023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
ML23321A1392023-11-17017 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000244/20230032023-10-25025 October 2023
LLC - Integrated Inspection Report 05000244/2023003
ML23292A0282023-10-19019 October 2023
LLC - Notification of Conduct of a Fire Protection Team Inspection
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
ML23258A1382023-09-18018 September 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010
IR 05000244/20230052023-08-31031 August 2023
Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005)
ML23158A1952023-08-30030 August 2023
R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications
ML23235A1722023-08-23023 August 2023
Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report
IR 05000244/20234012023-08-15015 August 2023
LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only)
IR 05000244/20230022023-08-0303 August 2023
LLC - Integrated Inspection Report 05000244/2023002
ML23191A0592023-07-21021 July 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
IR 05000244/20234022023-07-19019 July 2023
R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only)
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
ML23135A0412023-05-15015 May 2023
2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report
ML23121A0482023-05-0101 May 2023
R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
IR 05000244/20230012023-04-26026 April 2023
LLC - Integrated Inspection Report 05000244/2023001
ML23100A0302023-04-10010 April 2023
2023 10 CFR 50.46 Annual Report
ML23114A1152023-03-29029 March 2023
Electronic Reporting of Exposure Data for 2022
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23075A0872023-03-15015 March 2023
R. E. Ginna Nuclear Power Plant - Project Manager Assignment
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
IR 05000244/20220062023-03-0101 March 2023
Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006)
ML22364A0242023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246
ML23060A1622023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
ML23005A1762023-02-23023 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes
ML23005A1222023-02-22022 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023
Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
ML22287A0692023-02-0808 February 2023
R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
ML23031A2992023-02-0707 February 2023
R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request
ML23010A0112023-02-0101 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
IR 05000244/20223012023-01-20020 January 2023
Initial Operator Licensing Examination Report 05000244/2022301
IR 05000244/20220122023-01-12012 January 2023
LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012
ML22362A0382022-12-28028 December 2022
R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
ML22348A2062022-12-14014 December 2022
Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification
RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator
2024-02-05
[Table view]
Category:Licensee Event Report (LER)
MONTHYEAR05000244/LER-2017-0012017-06-16016 June 2017
During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction., LER 17-001-00 for R. E. Ginna re During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction
05000244/LER-2016-0012016-04-0707 April 2016
Loss of Station Auxiliary Transformer 12A resulting in automatic start of Emergency Diesel Generator A due to undervoltage signals to safeguards buses 14 and 18., LER 16-001-00 for R. E. Ginna Nuclear Power Plant Regarding Loss of Station Auxiliary Transformer 12A Resulting in Automatic Start of Emergency Diesel Generator A due to Undervoltage Signals to Safeguards Buses 14 and 18
ML0509600362004-12-17017 December 2004
Final Precursor Analysis - Ginna Grid Loop
ML0429403762004-10-12012 October 2004
LER 04-S01-00 for R. E. Ginna Regarding Safeguards Event
ML0202800752002-01-22022 January 2002
LER 01-S01-00 for R E Ginna Nuclear Plant Re Safeguards Event
ML18142A8511978-09-14014 September 1978
LER 1978-007-00 for R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator
ML18142A8761978-08-0303 August 1978
LER 1978-006-00 for R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom
ML18142A8771978-06-0606 June 1978
LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump
ML18142B2141978-05-0202 May 1978
LER 1978-005-00 for R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical
ML18142B2131978-03-31031 March 1978
LER 1978-004-00 for R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip
ML18142B2171978-02-10010 February 1978
LER 1978-002-00 for R. E. Ginna, Power Range Low Range Trip Set Point Test
ML18142B2191978-02-0808 February 1978
LER 1978-003-00 for R.E. Ginna, B Steam Generator Tube Leak
ML18142B2221977-07-18018 July 1977
LER 1977-008-00 for R.E. Ginna, B Steam Generator Tube Leak
ML18192A0761977-07-0707 July 1977
LER 1977-006-00 for R.E. Ginna, C Charging Pump Varidrive on 6/19/1977
ML18142B2281977-06-0808 June 1977
LER 1977-024-00 for R.E. Ginna, Accumulation of Borated Water Near a Valve in Safety Injection System Piping
ML18142B2291977-05-27027 May 1977
LER 1976-027-03 for R.E. Ginna, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak
ML18142B2351977-05-16016 May 1977
LER 1977-003-00 for R.E. Ginna, Abnormal Degradation of Steam Generator Tubes
ML18142B2211977-03-31031 March 1977
LER 1977-007-00 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump
ML18142B2381977-01-27027 January 1977
LER 1977-01-00 for R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump
ML18142B2401977-01-12012 January 1977
LER 1976-030-00 for R.E. Ginna, a Mixed Bed Demineralizer Inlet Piping Leak
ML18142B2431977-01-11011 January 1977
LER 1976-029-00 for R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition
ML18142B2421977-01-11011 January 1977
LER 1976-028-00 for R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work
ML18142B2441977-01-0404 January 1977
LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line
ML18142B2461976-12-0808 December 1976
LER 1976-026-00 for R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma
ML18142B2471976-11-0909 November 1976
LER 1976-025-00 for R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent
ML18142B2491976-10-22022 October 1976
LER 1976-024-00 for R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps
ML18142B2521976-09-14014 September 1976
LER 1976-023-00 for R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21
ML18142B2531976-08-19019 August 1976
LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods
ML18142B2571976-08-19019 August 1976
LER 1976-021-00 for R. E. Ginna, Unit 1, D Bank Group 2 Rcc'S G-3 and G-11 Partially Dropped Into Core
ML18142B2761976-07-19019 July 1976
LER 1976-20-00 for R.E. Ginna, a Accumulator Level Below Technical Specification Limit
ML18142B2721976-07-16016 July 1976
LER 1976-19-00 for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor
ML18142B2751976-07-16016 July 1976
LER 1976-20-00 for R.E. Ginna, Unit 1, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm
ML18142B2741976-07-16016 July 1976
LER 1976-20-00 for R. E. Ginna, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm
ML18142B2781976-06-21021 June 1976
R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing
ML18142B2801976-06-0404 June 1976
LER 1976-016-00 for R.E. Ginna, Rod Position Deviation Channel Was Found to Be Inoperable
ML18142B2821976-05-24024 May 1976
LER 1976-015-00 for R.E. Ginna, Air Ejector and Blowdown Radiation Monitors Alarmed
ML18142B2841976-05-11011 May 1976
LER 1976-013-00 for R.E. Ginna, Drop of Two Control Rods
ML18142B2851976-05-10010 May 1976
LER 1976-014-00 for R.E. Ginna, N44 Power Range Detector High Voltage Power Supply Failure
ML18142A9761976-04-23023 April 1976
LER 1976-012-00 for R.E. Ginna, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing
ML18142A9791976-03-22022 March 1976
LER 1976-010-00 for R. E. Ginna, Containment Purge Supply Value Excessive Leakage During Testing
ML18142A9781976-03-19019 March 1976
LER 1976-011-00 for R.E. Ginna, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System
ML18142A9801976-03-12012 March 1976
LER 1978-009-00 for R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay
ML18142A9811976-03-11011 March 1976
LER 1976-008-00 for R. E. Ginna, Abnormal Degradation of Steam Generator Tubes
ML18142A9831976-02-28028 February 1976
LER 1976-007-00 for R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch
ML18143A4971976-02-19019 February 1976
LER 1976-006-00 for R.E. Ginna, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976
ML18142B8941976-02-0606 February 1976
LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B8931976-02-0606 February 1976
LER 1976-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B8951976-01-26026 January 1976
LER 1975-013-00 for R. E. Ginna, 30 Day, B Steam Generator Tube Degradation
ML18142B8961976-01-0808 January 1976
LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak
ML18142B8971976-01-0808 January 1976
LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak
2017-06-16
[Table view] |
Text
T T F R A~IHC DISTRI-UTIG'I FOR PART 50 DOCI;ET HA i'R'IAL CONTROL NP.2285 R E:~ZQRX F RO;>>Roche a ter Gas and E lec tric Corp Rochester, NY L.D White r DATE, OF DOC 2~2 1~75 DATE R'EC'D 2>>28-75 L'TR XXX T"'X OTHER TO: Mr James P~O'Rei lly ORIG 1-si ned CC OTHER SEiXT AEC POR SENT LOCA'L PDR CLASS UNCLASS DESCRIPTION:
PROP!ixIFO INPUT NO CYS RFC'D ENCLOSURES:
DOCK"=T'NO: 50-244 Ltr trans the following:
-PCF" hT+R I~A!-',4<@333 X,d V.tL PLANT NAME: RE Ginna gl Abnormal Occurrence fP75-B4 on 2-13-75 concerning failure of solenoid test valves to operate on"A" Mafn Steam Isloation Valve during survillance test~,~~~FOR ACTICN/li'!
FOR,IATION "1-75 JGB REGAN (E)W/Copies LEAR (S}, W/Copies SPEIS (S)W/-Copies ZXEMANN (S)W/Copies DICKER (E}W/Copies KNXGHTON (E)W/Copies YOUNGBLOOD (E).BUTLER (S)W/Copies CLARK (S)W/Copies.PARR (S)W/Copies KNIEL (S)W/Copies SCHtPBNCER (S)W/Copies STOLZ (S}W/Copies VASSALLO (S)W/Copies MRPLE (S)W/+Copies~~e TICN INTF Rx'!AL DIST."I I:")V DENTON GRIMES GAMMILL TNER BALLARD SPANGLER TECH REVIEW O'NHC PDR+eCEEROEDER LQGC, ROOM P-506-A@ifACCARRY M~OSSICK/STAFF~XGHT KASE t@AWLICKI GXAliBUSSO Cmo BOYD@TELLO E/MOORE (S)(BWR)HOUSTON DEYOUNQ{S)(PWR)AOVAK SKOVHOLT (S){P%0SS GOLLER (S)APPOLITO PE COLLXNS TEDESCO~, DENISE{~IONG REG, OPR fpiAXNAS~gXLB®XON C()~+BENAROYA
>Z.Re WXLSOi'1 S STEELE~VOLIMER LIC.ASST..A/T XND DXGGS (.")ERAITNAN GEARXN (S)SALTZnn GOULBOURNE (S)BE HURT KREUTZER (E)LEE (S)PLANS NAIGRET (S)NCDONALD REED (E)CHAPMAN SE VICE (S)DUBE w/input IEPPARD (S)E.COUPE SLIER (E)We Har'tf ield (2)SMITH (S}" KLEIG.R TEETS{S)rgF.WILLIAMS'WILLXAMS (E)WXLSON (S)INGRAM{S)ENYIRO PMLLER DICKER KNXGHTON YOUNGBLOOD REGAN PROJECT LDR (s)L ElARLESS E);i ERI".'i(L DISTRIBUTION~!
iT", LOCAL PDR rynons, 4-TIC(ABERNATHY)
H."NSIC(BUCEIANAN) 1-ASLB 1-NEwroN AM)ERsoN~ACRS SENT TO LIC, S 1-PDR SAN/LA/NY 1>>BROOQQLVEN NAT LAB 1"Ge LLRIKSONS ORNL 1"AGIIED{RUTH GUSSMAN)RM B<<127 G,T.1-J.RULES)RM E-201 G.T~ASST.NY)Rochester(I)
(2)(IO)NATIONAL LASS NY 1-El.PENNINGTON, RM E-201 G.r.1<<CONSULTANTS NEMYWRK/BLUE/ABBABIAN
/t~~~~C g1!ISBN urVZS AHO z'qi'gz(sirzrzzsz ROCHESTER GAS AND ELECTRIC CORPORATION e 7I'np,'~op'q.
r rl~rkal Oell aaKIQ f V P',.>YORK,,.>i.Q fr:~, IYAYY l 89 EAST AVENUE, ROCHESTER, N.Y.l4649 LEON O.WHITE.JR.VICE PRESIDENT TELEPHONE AREA CODE TIO 546-2700 Mr.james P.O'Reilly, Director U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania
'19406 February 21, 1975./~P(!Pj/)/('t~eaj".'Ilgwu](A+'Qy~I1IIq g7
Subject:
Abnormal Occurrence 75-04, Failure of solenoid test valves to operate on NAN Main Steam Isolation Valve during surveillance test R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244
Dear Mr.O'Reilly:
In accordance with Technical Specifications, Article 6.6.2a, the attached report of Abnormal Occurrence 75-04 is hereby submitted.
Two additional copies of this letter and the attachment are enclosed.Very truly yours,/L.D.White, jr.Attachment cc: Mr.Donald F.Knuth (40)PFFIII P7h I~~/1A 80CKQPf)FEB 28 1975",
h I E 50-244/75-04 February 21, 1975 2b.Occurrence Date: 3.~Faciltt February 13, 1975 R.E.Ginna Nuclear Power Plant, Unit No.1 4.Identification of Occurrence:
This abnormal occurrence is defined by Technical Specifications Article 1.9d: Failure of one or more components of an engineered safety feature or plant protection system that causes or threatens to cause the feature or system to be incapable of performing its intended function.5.Conditions Prior to Occurrence:
The unit was operating at a steady state level of 100 percent power.6.Descri tion of Occurrence:
During the performance of the surveillance test, PT-20,"Main Steam Isolation Valve Solenoid Trip Test", upon actuating the Main'Control Board (MCB)control switch for the"A" Steam Line Isolation Valve, one of the two series air supply solenoids did not trip to the closed position although the coil armature did pick up.An immediate retest resulted in the repeated failure of the same air supply valve to trip and in addition, one of the air exhaust valves failed to operate at this time.The MCB control switch operation and necessary resets were then performed several times with similar and erratic failure results.Instrument and Control Repairman personnel witnessed the operation and then made a minor adjustment to the latching mechanism.
Following this the test was satisfactorily performed five times without failure.The test of the"B" Main Steam Isolation Valve trip was completed without incident.7.Desi nation of A arent Cause of Occurrence:
In all cases the coil armature operated as required.The failure of the"A" solenoid valves was in their mechanical operation.
It is believed that a flat spot or burr may have developed on the latching pin of the air supply valve trip mechanism.
Rotation of this pin from its fixed position produced the successful retesting.
The exhaust valve trip mechanisms appeared stiff in action and responded properly after the several test operations.'
I i~1J
~~AOR 50-244/75-04 ccr.8: Anal sis of Occurrence:
There was no hazard to plant personnel or the public.Due to the arrangement of the four solenoid valves, failure of the two solenoid valves in question would not have prevented closure of the"A" Main Steam Isolation valve.The solenoid valves are tested every two months and had operated properly during the last three tests of August, October and December of 1974.9.Corrective Action: As described above, a reposition of the latching pin and the exer-cising of the mechanisms to overcome any linkage friction or binding of valve packings apparently corrected the problem.The PORC met at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on February 13, 1975 to discuss the failure and recommended that the test be repeated prior to our scheduled outage on March 15, 1975 to determine the amount of maintenance to be performed on this system during the shutdown.10.Failure Data: Since the valves were mounted on the containment wall to reduce a vibration problem, there has been one other dissimilar failure of these solenoids prior to this occurrence.
This failure occurred on June 26,1974 and was reported as Abnormal Occurrence 74-11.The valves are Laurence Solenoid Valves, Cat.g 125434W (air vent valves), and Cat.g 110114W (air supply valves)for 125.ps'i.;
air.They are manufactured by the R.G.Laurence Company, Inc., Tenafly, New Jersey 07670.
.(I 4, J I G.q d$l
