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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20028H3861990-12-26026 December 1990 Ro:On 901126,fuel Oil Leak Discovered in Standby Diesel Generator 23 During Standby Diesel Generator Actuation Test. Caused by Crack Across Threaded Portion of Delivery Valve Holder.Valve Holder & Valve Spring Replaced ML20042E6561990-04-18018 April 1990 Final Special Rept:On 891128,diesel Generator Valid Failure Occurred.Caused by Presence of Improperly Drilled & Repaired Oil Passage Hole Serving Articulated Rod Pin Bushing in Master Connecting Rod Assembly.Crankshift Webs Repaired ML20012F1271990-03-29029 March 1990 Supplemental Special Rept:Correcting Design Description of Jacket Water Temp Switch,Per Two Nonvalid Failures of Standby Diesel Generator on 880813 & 26.Design Affects Extent of Corrective Action Taken to Prevent Recurrence ML20012E1881990-03-19019 March 1990 Special Rept:On 891227 & 900116,pressurizer Level Channel L-0466 Read Approx 10% Higher than Three Other Channels. Caused by Failure of Kerotest Valve to Fully Open,Preventing Steam from Entering Ref Leg.Ref Leg Filled ML20012C2631990-03-0909 March 1990 Special Rept:On 900209,standby Diesel Generator 11 Failed. Caused by Carbonization of 3UP Relay Socket & Base Due to Short Circuit During Tightening of Lug.Relay Socket & Base Cleaned & Diesel Successfully Tested ML20012B7361990-03-0505 March 1990 Special Rept:On 900202,discovered That Overspeed Fuel Shutoff & Governor Lever Valve Tripped.Caused by Operator Leaving Valve in Tripped Position While Performing Maint Activity on 900201.Valve Reset & Tested ML20005E1881989-12-27027 December 1989 Special Rept:On 891128,valid Failure of Diesel Generator Occurred.Caused by Improperly Drilled Oil Passage on Master Rod.Remedial Actions to Restore Standby Diesel Generator 22 Includes Crankshaft Straightening & Remachining ML19354D7401989-12-21021 December 1989 Special Rept:On 891121,generator Voltage Regulator Transformer in Standby Diesel Generator 22 Local Control Panel Overheated.Caused by Missing Insulation Between Transformer Core & Mounting Bolt.Transformer to Be Replaced ML20011D2301989-12-0606 December 1989 Special Rept:On 891029 & 1104,Train C of Reactor Vessel Water Level Sys Observed Alternating Indicating Wet & Dry Conditions in Display Processing Sys in Control Room.Caused by Failure of Fiber Optic Link.Fiber Optic Modum Replaced ML19332E8391989-12-0404 December 1989 Special Rept:On 891103,test Declared Valid Failure When Standby Diesel Generator 22 Attained Output Frequency of 58 Hertz.Caused by Oxidation of Relay 4EX3 in Governor Control Circuit.Contacts Cleaned & Burnished ML19325D7011989-10-19019 October 1989 Special Rept:On 890919,nonvalid Failure of Standby Diesel Generator Occurred.Caused by Failure of Reactor Operator to Read Correct Instrument Prior to Synchronization of Diesel Generator.Synchronization Procedure Revised ML19320A7911980-06-26026 June 1980 Ro:On 800529,during Design Review,Seismic Qualification of Essential Cooling Water Intake Structure Gantry Crane & Diesel Generator Fuel Storage Tank Found W/Deficient Response Spectra Values.New Seismic Evaluation in Progress 1990-04-18
[Table view] Category:LER)
MONTHYEARML20028H3861990-12-26026 December 1990 Ro:On 901126,fuel Oil Leak Discovered in Standby Diesel Generator 23 During Standby Diesel Generator Actuation Test. Caused by Crack Across Threaded Portion of Delivery Valve Holder.Valve Holder & Valve Spring Replaced ML20042E6561990-04-18018 April 1990 Final Special Rept:On 891128,diesel Generator Valid Failure Occurred.Caused by Presence of Improperly Drilled & Repaired Oil Passage Hole Serving Articulated Rod Pin Bushing in Master Connecting Rod Assembly.Crankshift Webs Repaired ML20012F1271990-03-29029 March 1990 Supplemental Special Rept:Correcting Design Description of Jacket Water Temp Switch,Per Two Nonvalid Failures of Standby Diesel Generator on 880813 & 26.Design Affects Extent of Corrective Action Taken to Prevent Recurrence ML20012E1881990-03-19019 March 1990 Special Rept:On 891227 & 900116,pressurizer Level Channel L-0466 Read Approx 10% Higher than Three Other Channels. Caused by Failure of Kerotest Valve to Fully Open,Preventing Steam from Entering Ref Leg.Ref Leg Filled ML20012C2631990-03-0909 March 1990 Special Rept:On 900209,standby Diesel Generator 11 Failed. Caused by Carbonization of 3UP Relay Socket & Base Due to Short Circuit During Tightening of Lug.Relay Socket & Base Cleaned & Diesel Successfully Tested ML20012B7361990-03-0505 March 1990 Special Rept:On 900202,discovered That Overspeed Fuel Shutoff & Governor Lever Valve Tripped.Caused by Operator Leaving Valve in Tripped Position While Performing Maint Activity on 900201.Valve Reset & Tested ML20005E1881989-12-27027 December 1989 Special Rept:On 891128,valid Failure of Diesel Generator Occurred.Caused by Improperly Drilled Oil Passage on Master Rod.Remedial Actions to Restore Standby Diesel Generator 22 Includes Crankshaft Straightening & Remachining ML19354D7401989-12-21021 December 1989 Special Rept:On 891121,generator Voltage Regulator Transformer in Standby Diesel Generator 22 Local Control Panel Overheated.Caused by Missing Insulation Between Transformer Core & Mounting Bolt.Transformer to Be Replaced ML20011D2301989-12-0606 December 1989 Special Rept:On 891029 & 1104,Train C of Reactor Vessel Water Level Sys Observed Alternating Indicating Wet & Dry Conditions in Display Processing Sys in Control Room.Caused by Failure of Fiber Optic Link.Fiber Optic Modum Replaced ML19332E8391989-12-0404 December 1989 Special Rept:On 891103,test Declared Valid Failure When Standby Diesel Generator 22 Attained Output Frequency of 58 Hertz.Caused by Oxidation of Relay 4EX3 in Governor Control Circuit.Contacts Cleaned & Burnished ML19325D7011989-10-19019 October 1989 Special Rept:On 890919,nonvalid Failure of Standby Diesel Generator Occurred.Caused by Failure of Reactor Operator to Read Correct Instrument Prior to Synchronization of Diesel Generator.Synchronization Procedure Revised ML19320A7911980-06-26026 June 1980 Ro:On 800529,during Design Review,Seismic Qualification of Essential Cooling Water Intake Structure Gantry Crane & Diesel Generator Fuel Storage Tank Found W/Deficient Response Spectra Values.New Seismic Evaluation in Progress 1990-04-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20210C9411999-07-31031 July 1999 Rev 1 to SG-99-07-002, South Tx,Unit 1 Cycle 9 Voltage- Based Repair Criteria 90-Day Rept, Jul 1999 ML20210R3631999-07-31031 July 1999 Monthly Operating Repts for July 1999 for South Tx Project, Units 1 & 2.With ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210D4821999-07-21021 July 1999 1RE08 ISI Summary Rept for Steam Generator Tubing of South Texas Project Electric Generating Station Unit 1 ML20210D4491999-07-21021 July 1999 Revised Chapters to Operations QA Plan, Including Rev 9 to Chapter 1.0, Organization & Rev 6 to Chapter 16.0, Independent Technical Review NOC-AE-000583, LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With1999-07-15015 July 1999 LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20216D7481999-07-0707 July 1999 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1 NOC-AE-000593, Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with NOC-AE-000570, LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With1999-06-28028 June 1999 LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With ML20196G5821999-06-23023 June 1999 LER 99-S02-00:on 990601,failure to Maintain Positive Control of Vital Area Security Key Was Noted.Caused by Lack of Attention to Detail.Discussed Event with Operator Involved IAW Constructive Discipline Program ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval ML20196A2391999-06-15015 June 1999 Change QA-042 to Rev 13 of Operations QAP, Reflecting Current Organizational Alignment for South Texas Project & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-000563, Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with ML20206U5411999-05-18018 May 1999 Non-proprietary Errata Pages for Rev 2,Addendum 1 to WCAP-13699, Laser Welded Sleeves for 3/4 Inch Diamete Tube Feedring Type & W Preheater SGs Generic Sleeving Rept ML20206A7721999-04-30030 April 1999 STP Electric Generating Station Unit 1 Cycle 9 Colr NOC-AE-000543, Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with ML20205H0321999-03-31031 March 1999 Change QA-040 to Rev 13 of Operations QA Plan NOC-AE-000507, Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with ML20205A3781999-03-22022 March 1999 STP Electric Generating Station Simulator Certification Four Yr Rept for Units 1 & 2 ML20204B2711999-03-15015 March 1999 Safety Evaluation Authorizing 990201 Request to Authorize Alternative to Regulations Per 10CFR50.55a(a)(3)(i) That Would Revise Start of Second 120-month IST Interval to No Later than 011201 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results NOC-AE-000468, Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With ML20207D1101999-02-24024 February 1999 Change QA-039 to Rev 13 of Operations QA Plan, for STP ML20203H8361999-02-17017 February 1999 Safety Evaluation Supporting Request for Relief from ASME Code Requirements for Class 3 Piping for Plant ML20202H9621999-02-0303 February 1999 SER Accepting Change to EALs Used in Classification of Emergency Conditions ML20202E8471999-01-31031 January 1999 2RE06 ISI Summary Rept for SG Tubing of STP Electric Generating Station,Unit 2 ML20216G2011999-01-31031 January 1999 City Public Svc of San Antonio Annual Rept 1998-1999 ML20199G5961999-01-31031 January 1999 Cycle 7 Voltage-Based Repair Criteria Rept for Jan 1999 ML20199K7711999-01-21021 January 1999 Safety Evaluation Accepting ISI Program Request for Relief for ASME Cose Repair Requirements for Code Class 3 Piping ML20199G8161999-01-19019 January 1999 SER Accepting Util 970707 Response to NRC 970509 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Finds No Significant Safety Hazards Based on Application of Util Ampacity Derating Methodology ML20199H4981999-01-11011 January 1999 2RE06 ISI Summary Rept for Welds & Component Supports of Stp,Unit 2 ML20206Q3751999-01-0404 January 1999 2RE06 ISI Summary Rept for Sys Pressure Tests (Class 1 & 2) ML20206Q3721999-01-0404 January 1999 2RE06 ISI Summary Rept for Repairs & Replacements ML20216G2171998-12-31031 December 1998 Houston Industries 1998 Annual Rept. App a 1998 Financial Statements & Us Securities & Exchange Commission Form 10-K Encl NOC-AE-000403, Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With ML20216G1521998-12-31031 December 1998 Central & South West Corp 1998 Summary Annual Rept & Securities & Exchange Commission Form 10-K ML20198M3431998-12-28028 December 1998 SER Accepting Util Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping for South Texas Project,Unit 2 1999-09-09
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COBtpting Houston Lig & PoweranySouth Temas Projut Eledric P.O.Bos209 Gmroting Wadsworth. Tesas 77483 Stati i
March 29, 1990 ST-HL-AE-3415 :
File No.: 002 10CFR50.36(c)(5)
U. S. Nuclear Regulatory Commission Attention: Document Control Desk ,
Washington, DC 20555 l f
South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 Supplemental Special Report ,
Regarding Two Nonvalid Failures of #13 Standby Diesel Generator on Aur.ust 13 and 26, 1988 ;
On September 12, 1988 Houston Lighting & Power submitted a Special i
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Report regarding two'nonvalid failures of the #13 Standby Diesel Generator under letter number ST-HL-AE-2776. We have subsequently discovered an error in the description of the design of the jacket water temperature switch which affected the extent of the corrective action taken to prevent recurrence of the event. Therefore, pursuant to Technical Specification 4.8.1.1.3 and '
6.9.2, HL&P submits the attached supplemental report.
If you should have any questions on this matter, please contact Mr. C. A. Ayala at (512) 972-8628 or myself at ($12) 972-7921.
#f f G. E. Vaughn Vice President Nuclear Operations BEM/n1
Attachment:
Supplemental Special Report ?
Regarding Two Nonvalid Failures of #13 Standby Diesel Generator on August 13 and 26, 1988 9004100193 900329 PDR ADOCK 05000498 S PDC NL.89.346.01 A Subsidiary of flouston Industries incorporated [[M ,
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ST*HL' AE 3415 Nouston Lighting & Power Compan)-
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Regional Administrator, Region IV Rufus S. Scott I Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drivo, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 >
Houston, TX 77208 Coorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 Circle 75 Parkway J. I. Tapia Atlanta, GA 30339 3064 Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. llendric Commission 50 Be11 port Lane P. O. Box 910 Bellport, NY 11713 Bay City, TX 77414 D. K. Lacker ,
J. R. Newman, Esquire Bureau cf Radiation Control
'Newman & lloltzinger, P.C. Texas Department of llealth 1615 L Street, N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78704 D. E. Ward /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 J. C. Lanier Director of Ceneration City of Austin Electric Utility i 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M T. Hardt City Public Service Board P. O. Box 1771
. San Antonio, TX 78296
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Page 1 of 3 j
South Texas Project Electric Generating Station '
Unit 1 Docket No. STN 50-498 Supplemental Special Report :
Regarding Two Nonvalid Failures of #13 !
Standby Diesel Generator on August 13 and 26. 1988 .
DESCRIPTION OF EVENT:
A nonvalid failure occurred on Standby Diesel Generator (SDG) #13 on August 13, and again on August 26, 1988. !
l At approximately 0332 hours on August 13, 1988, with Unit 1 in Mode 3 (Hot ;
Standby) and Standby Diesel Generator (SDG) #12 out of service for repair of a j.
leaking fuel nozzle, SDG #13 was started to meet the requirements of Technical !
Specification Action statement 3.8.1.1.b. SDG #13 started and attained i required voltage and frequency (4160 volte and 60 Hz) within ten seconds as ;
required. Approximately one minute later the SDG was placed in the test mode by actuating the " Release Emergency Mode Operation" pushbutton, and the SDG l tripped. Control panel indication showed that the trip was due to a jacket ;
water high temperature shutdown signal which has a trip setpoint of 205 o ,
degrees F. Immediate investigation by the diesel operator showed the actual l Jacket' water temperature to be npproximately 130 degrees F, normal temperature l at that: point in the operatior.. Furthermore, the jacket water temperature :
off-normal alarm, set at 190 degrees F increasing, had not actuated. Due to these observations, it was concluded that the high temperature _ trip signal was !
most likely due to a spurious failure of an air-operated pressure switch- ;
(Jacket Water High Temperature Shutdown Switch) to reset when the SDG was i started. The high temperature alarm cleared shortly afterward. and SDG #13 l was restarted at 0338 hours. The high temperature alarm did not actuatel SDG# 13 operated as required and was shut down at 0342 hours after the Technical Specification Action statement was satisfied. A Station Problem Report was generated to investigate the failure.
At approximately 1738 hours on August 26, 1988, SDG #13 started in response to i a Safety Injection (SI) signal associated with a reactor trip. The reactor trip and SI event are being reported separately as LIR 88-049. At 1757 hours, when the diesel operator actuated the " Release Emergency Mode Operation" ;
pushbutton in preparation for shutting down the diesel, the SDG tripped. As !
in the August I? event, control panel indication showed a jacket water high temperature shutdown signal was present, with no other indication of an actual jacket water high temperature condition. With the exception of the start signal to the SDG, the two events appear to be identical.
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Page 2 of 3 i Base,4 on a nonvalid isilure of SDG $12 on August, S, 1969 it has subsequently been determined that the nonvalid f ailures described in this report may have
- j. also been caused by setpoint drif t of the Jacket Water Temperature Valve which b actuate 6 the Jacket Water High Temperature Shutdown Switch. In the previous l- report of this f ailure, the Jacket Water ' temperature Valve was described as a fixed setpoint,. . fusible link type valve which required replacement each time it was,4ctuatsd. .The valve is actually an Amot model 2230C which has an adjust able setpoint and is reusable.
CAUSE OF OCC1'RRF.NCEt L
j The most protchie cause of these nonvalid failures was either failure of the
- j. Jacket Water High Temperature Shutdown Switch to reset uhen SDG #13 was i started or setpoint drif t of the Jacket Water Temperature Valve.
l ANALYSIS OF EVENT:
The jacket water high temperature signal provides protection for the SDG during testing. It is bypassed when the SDG is operating in the emergency mode. In accordance with section C.2.e.(2) of Regulatory Guide 1.108, these events are classified as nonvalid fa!!ures of SDG $13 because they are attributed to spurious operation of a trip that is bypassed in the emergency operating mode.
I CORRECTIVE ACTION:
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,( -' W 13 The trip ar4 renst tot 90irts, for the Jacket Water Nigh Tomparatura Shutdown .'
Switch bere ad?uat ed, and the 1D(i was tor.ted wuycessf ully.
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Further corrkotive actions regardirg Jacket Water Temperature Valve i
' :.) i .tellbrations ehd protective mr.intenance activities have been istntifief 9 thn i
% toport of twc. r.t.nn.'ad f ailurcs of SDJ W12 on August b and 7 19be 4 This i h, report was submit ted umt Y1R Ictter number ST-Hh-AE-3210 dated d4 $e ptetther % 1%. ,
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At t ac hment l 87-ML- AE- 3415 i Page 3 of 3 E ADDITIONAL INFORNATTON:
As of September 24, 1968 there had been twenty-one (21) valid testo performed L on $DG #13 since completion of the 100 hour run test on Augu&t 6.1987. There l- have been no valid failures. The test interval for SDG #13 remains at 31 days.
There was one previous nonvalid failure of SDG di) on March 16. 1988, but the cause of that event was unrelated to the most recent occurrences.
L The.Jackst Water High Temperature Shutdown $ witch is a DeLaval Parkdale model r F CD-28 M1889-S! pressure switch. The Jacket Water Temferature Valve is an Amot ;.
model 2230C.
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