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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217D0201999-10-12012 October 1999 Requests Assistance in Determining If Info Submitted by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C9671999-10-12012 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C6151999-10-0707 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu, Inc Meets Criteria Set Forth in 10CFR20 Subpart E for Release of Property to Be Sold by Gpu ML20207H3721999-06-10010 June 1999 Informs That Attached Draft Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding, Was Transmitted by Facsimile to G Busch of Gpu Nuclear to Be Discussed in Conference Call Scheduled for 990614 ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20202H6011999-02-0303 February 1999 Notification of 990218 & 19 Meetings with Util in Forked River,Nj Re Overview & Discussion of Licensee Efforts Concerning Possible Early Shutdown & Decommissioning of Plant ML20154K9781998-10-15015 October 1998 Notification of 981103 Meeting with Gpu Nuclear,Inc in Rockville,Md to Discuss Planning for Possible Shutdown of Oyster Creek & Related Decommissioning Activities ML20154J0271998-10-13013 October 1998 Notification of 981028 Meeting with Gpu Nuclear Inc,In Rockville,Md to Discuss Licensee Calculations Re 980505 Licensing Basis Change Request ML20154B3731998-09-29029 September 1998 Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments ML20236T0891998-07-21021 July 1998 Notification of Significant Licensee Meeting 98-64 W/Util on 980804 in Forked River,Nj to Discuss NRC SALP for Period of 961201-980613 ML20247N5021998-05-14014 May 1998 Notification of Significant Licensee Meeting 98-46 W/Util on 980529 in King of Prussia,Pa to Conduct pre-decisional Enforcement Conference Re Three Apparent Violations Re Automatic Depressurization Sys Issues ML20216G6261998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-24 W/Util on 980323 Predecisional Enforcement Conference to Discuss Apparent Violation in NRC Integrated Insp Rept 50-219/97-11 (EA-98-049) ML20217C1041997-09-18018 September 1997 Notification of 970930 pre-decisional Enforcement Conference W/Gpu Nuclear,Inc in King of Prussia,Pa to Discuss Five Apparent Violations Re Three Control Issues & One Control of Matl in Emergency Swp Issue ML20210J6161997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Possible Plant Operating Scenarios,Current Status & Planning Activities Associated W/Scenarios ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20137R4531997-04-0101 April 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of LBP-97-01 Expired. Decision Became Final Agency Action on 970326.W/Certificate of Svc.Served on 970401 ML20132F7651996-12-16016 December 1996 Forwards Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response in Support of Licensee Motion for Summary Disposition. Document Replaces Unsigned Affidavit Which Was Filed on 961206 ML20132F7571996-12-13013 December 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision LBP-96-23 Has Expired. Commission Declined Review & Decision Became Final Agency Action on 961204.W/Certificate of Svc.Served on 961213 ML20135F4841996-12-10010 December 1996 Informs That Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response to Licensee Motion for Summary Disposition Filed on 961206,will Be Provided as Soon as Possible ML20134M6331996-11-21021 November 1996 Discusses TIA Re 10 CFR 50.59 Evaluation Prepared by Licensee to Allow Movement of Spent Fuel from SFP to Dry Storage Facility While Plant Is in Cold Shutdown ML20134L4891996-11-12012 November 1996 Forwards Copy of 961107 Amend 187 to License DPR-16 & Safety Evaluation for Facility ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129F6401996-10-25025 October 1996 Requests That Encl Handout for Nuclear Energy Inst/GPUN-OG/ NRC Conference Call on Nuclear Energy Inst/Epri Revised Source Term Task Force for Plant,Be Placed in Docket File 50-219 ML20134G1731996-10-24024 October 1996 Informs Commission That Final No Significant Hazards Consideration Determination & License Amend Will Be Issued on or About 961030 to Gpu Nuclear Corp,Per Util 960415 Request to Revise TS 5.3.1.B ML20128L7191996-10-0909 October 1996 Forwards from Jc Fornicola to K Cozen Re Consideration of Oyster Creek as Pilot Plant for Submittal of Revised Source Term ML20129G7861996-10-0101 October 1996 Discusses 960923 Telcon from P Gunter Re Listed Topics. Update of Status of SPF 2.206 & Memo to Commission from Taylor, Resolution of Sf Storage Pool Action Plan Issues, Also Discussed ML20132A9681996-06-12012 June 1996 Forwards Copy of Ltr Requesting NRC to Investigate & Correct Highly Inaccurate Public Statement That Appeared in Gpu June 1996 Neighborhood Update ML20059J8431994-01-11011 January 1994 Notification of Significant Licensee Meeting 94-02 W/Util on 940125 Re Enforcement Conference to Discuss NRC Operational Safety Team Insp Findings ML20059M7931993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Oyster Creek Safety Related Piping ML20059F9551993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Plant Safety Related Piping.Meeting Time Changed as Listed ML20059J5661993-11-0909 November 1993 Notification of 931119 Meeting W/Util in Rockville,Md to Discuss Proposed ISFSI & to Receive Status Rept on Staff Effort to Issue Certificate of Compliance for Standardized NUHOMS Sys & to Discuss License Requirements ML20058P9701993-10-18018 October 1993 Notification of Significant Licensee Meeting 93-133 W/Util on 931029 in Forked River,Nj to Discuss Operational Safety Team Insp Public Exit ML20057B4751993-09-16016 September 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20057D7141993-08-0303 August 1993 Requests Assistance in Determining Adequacy of Plant Methodology for Determining Reportability of Plant Operation Above Licensed Core Thermal Limit ML20128K9051993-02-0303 February 1993 Notification of Significant Licensee Meeting 93-15 W/Util on 930208 to Discuss Results of NRC Review of Plant Operation W/Degraded Shutdown Cooling ML20127F3661993-01-0505 January 1993 Notification of Significant Licensee Meeting 93-002 W/Util on 930126 to Discuss Integration of Simulator Into Training Program ML20126J8041993-01-0404 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Matters Re Core Spray Downcomer Leak (Weld L3a) ML20126J9941993-01-0404 January 1993 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20126F4571992-12-18018 December 1992 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Reactor Bldg Access Modification for Facility ML20217B0841991-03-0505 March 1991 Forwards AEOD Diagnostic Evaluation Team Rept for Plant for Info.Rept Documents Team Findings & Conclusions & Includes Discussions of Licensee Strengths & Weaknesses ML20058D5561990-10-31031 October 1990 Notification of 901114 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058D5721990-10-26026 October 1990 Notification of 901107 Meeting W/Util in Rockville,Md to Discuss Matters Re Fuel Channel Box Bowing ML20058A3411990-10-18018 October 1990 Notification of 901029 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20058N9351990-08-13013 August 1990 Notification of 900816 Meeting in Bethesda,Md W/Util to Discuss Emergency Response Data Sys ML20058M4071990-08-0808 August 1990 Notification of 900829 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058L5781990-07-31031 July 1990 Notification of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion Problem ML20055C3341990-02-0909 February 1990 Notification of 900216 Enforcement Conference Meeting 90-19 W/Util in King of Prussia,Pa Re Safety Concern Process & Degraded ADS Logic ML20247K8611989-09-15015 September 1989 Notification of 890927 Meeting W/Util in Rockville,Md to Discuss site-specific Response Spectra & Methodology to Develop New Seismic Floor Response Spectra 1999-06-10
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217D0201999-10-12012 October 1999 Requests Assistance in Determining If Info Submitted by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C9671999-10-12012 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C6151999-10-0707 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu, Inc Meets Criteria Set Forth in 10CFR20 Subpart E for Release of Property to Be Sold by Gpu ML20207H3721999-06-10010 June 1999 Informs That Attached Draft Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding, Was Transmitted by Facsimile to G Busch of Gpu Nuclear to Be Discussed in Conference Call Scheduled for 990614 ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20202H6011999-02-0303 February 1999 Notification of 990218 & 19 Meetings with Util in Forked River,Nj Re Overview & Discussion of Licensee Efforts Concerning Possible Early Shutdown & Decommissioning of Plant ML20154K9781998-10-15015 October 1998 Notification of 981103 Meeting with Gpu Nuclear,Inc in Rockville,Md to Discuss Planning for Possible Shutdown of Oyster Creek & Related Decommissioning Activities ML20154J0271998-10-13013 October 1998 Notification of 981028 Meeting with Gpu Nuclear Inc,In Rockville,Md to Discuss Licensee Calculations Re 980505 Licensing Basis Change Request ML20154B3731998-09-29029 September 1998 Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments ML20236T0891998-07-21021 July 1998 Notification of Significant Licensee Meeting 98-64 W/Util on 980804 in Forked River,Nj to Discuss NRC SALP for Period of 961201-980613 ML20247N5021998-05-14014 May 1998 Notification of Significant Licensee Meeting 98-46 W/Util on 980529 in King of Prussia,Pa to Conduct pre-decisional Enforcement Conference Re Three Apparent Violations Re Automatic Depressurization Sys Issues ML20216G6261998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-24 W/Util on 980323 Predecisional Enforcement Conference to Discuss Apparent Violation in NRC Integrated Insp Rept 50-219/97-11 (EA-98-049) ML20217C1041997-09-18018 September 1997 Notification of 970930 pre-decisional Enforcement Conference W/Gpu Nuclear,Inc in King of Prussia,Pa to Discuss Five Apparent Violations Re Three Control Issues & One Control of Matl in Emergency Swp Issue ML20210J6161997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Possible Plant Operating Scenarios,Current Status & Planning Activities Associated W/Scenarios ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20137R4531997-04-0101 April 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of LBP-97-01 Expired. Decision Became Final Agency Action on 970326.W/Certificate of Svc.Served on 970401 ML20132F7651996-12-16016 December 1996 Forwards Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response in Support of Licensee Motion for Summary Disposition. Document Replaces Unsigned Affidavit Which Was Filed on 961206 ML20132F7571996-12-13013 December 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision LBP-96-23 Has Expired. Commission Declined Review & Decision Became Final Agency Action on 961204.W/Certificate of Svc.Served on 961213 ML20135F4841996-12-10010 December 1996 Informs That Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response to Licensee Motion for Summary Disposition Filed on 961206,will Be Provided as Soon as Possible ML20134M6331996-11-21021 November 1996 Discusses TIA Re 10 CFR 50.59 Evaluation Prepared by Licensee to Allow Movement of Spent Fuel from SFP to Dry Storage Facility While Plant Is in Cold Shutdown ML20134L4891996-11-12012 November 1996 Forwards Copy of 961107 Amend 187 to License DPR-16 & Safety Evaluation for Facility ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129F6401996-10-25025 October 1996 Requests That Encl Handout for Nuclear Energy Inst/GPUN-OG/ NRC Conference Call on Nuclear Energy Inst/Epri Revised Source Term Task Force for Plant,Be Placed in Docket File 50-219 ML20134G1731996-10-24024 October 1996 Informs Commission That Final No Significant Hazards Consideration Determination & License Amend Will Be Issued on or About 961030 to Gpu Nuclear Corp,Per Util 960415 Request to Revise TS 5.3.1.B ML20128L7191996-10-0909 October 1996 Forwards from Jc Fornicola to K Cozen Re Consideration of Oyster Creek as Pilot Plant for Submittal of Revised Source Term ML20129G7861996-10-0101 October 1996 Discusses 960923 Telcon from P Gunter Re Listed Topics. Update of Status of SPF 2.206 & Memo to Commission from Taylor, Resolution of Sf Storage Pool Action Plan Issues, Also Discussed ML20132A9681996-06-12012 June 1996 Forwards Copy of Ltr Requesting NRC to Investigate & Correct Highly Inaccurate Public Statement That Appeared in Gpu June 1996 Neighborhood Update ML20059J8431994-01-11011 January 1994 Notification of Significant Licensee Meeting 94-02 W/Util on 940125 Re Enforcement Conference to Discuss NRC Operational Safety Team Insp Findings ML20059M7931993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Oyster Creek Safety Related Piping ML20059F9551993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Plant Safety Related Piping.Meeting Time Changed as Listed ML20059J5661993-11-0909 November 1993 Notification of 931119 Meeting W/Util in Rockville,Md to Discuss Proposed ISFSI & to Receive Status Rept on Staff Effort to Issue Certificate of Compliance for Standardized NUHOMS Sys & to Discuss License Requirements ML20058P9701993-10-18018 October 1993 Notification of Significant Licensee Meeting 93-133 W/Util on 931029 in Forked River,Nj to Discuss Operational Safety Team Insp Public Exit ML20057B4751993-09-16016 September 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20057D7141993-08-0303 August 1993 Requests Assistance in Determining Adequacy of Plant Methodology for Determining Reportability of Plant Operation Above Licensed Core Thermal Limit ML20128K9051993-02-0303 February 1993 Notification of Significant Licensee Meeting 93-15 W/Util on 930208 to Discuss Results of NRC Review of Plant Operation W/Degraded Shutdown Cooling ML20127F3661993-01-0505 January 1993 Notification of Significant Licensee Meeting 93-002 W/Util on 930126 to Discuss Integration of Simulator Into Training Program ML20126J8041993-01-0404 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Matters Re Core Spray Downcomer Leak (Weld L3a) ML20126J9941993-01-0404 January 1993 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20126F4571992-12-18018 December 1992 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Reactor Bldg Access Modification for Facility ML20217B0841991-03-0505 March 1991 Forwards AEOD Diagnostic Evaluation Team Rept for Plant for Info.Rept Documents Team Findings & Conclusions & Includes Discussions of Licensee Strengths & Weaknesses ML20058D5561990-10-31031 October 1990 Notification of 901114 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058D5721990-10-26026 October 1990 Notification of 901107 Meeting W/Util in Rockville,Md to Discuss Matters Re Fuel Channel Box Bowing ML20058A3411990-10-18018 October 1990 Notification of 901029 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20058N9351990-08-13013 August 1990 Notification of 900816 Meeting in Bethesda,Md W/Util to Discuss Emergency Response Data Sys ML20058M4071990-08-0808 August 1990 Notification of 900829 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058L5781990-07-31031 July 1990 Notification of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion Problem ML20055C3341990-02-0909 February 1990 Notification of 900216 Enforcement Conference Meeting 90-19 W/Util in King of Prussia,Pa Re Safety Concern Process & Degraded ADS Logic ML20247K8611989-09-15015 September 1989 Notification of 890927 Meeting W/Util in Rockville,Md to Discuss site-specific Response Spectra & Methodology to Develop New Seismic Floor Response Spectra 1999-06-10
[Table view] |
Text
'
p***!vQ fg UNITED STATES 4
p, NUCLEAR REGULATORY COMMISSION
{ E WASHINGTON, D. C. 20555 E
\.....j JUL 2 31986 MEMORANDUM FOR: Stewart D. Ebneter, Director Division of Reactor Safety Region I FROM: Robert L. Baer, Chief Engineering and Generic Communications Branch Division of Emergency Preparedness and Engineering Response '
Office of Inspection and Enforcement
SUBJECT:
LOW OIL LEVEL IN ESSENTIAL UNIT SUBSTATION TRANSFORMERS AT OYSTER CREEK NUCLEAR GENERATING STATION
Reference:
Memorandum, Baer to Ebneter, 3-19-86, same subject This memorandum is to inform you of our review of the subject event. As we noted in our previous memorandum, we did not identify any similar transformer problems in our search of the LER, Part 21 or 50.55(e) reports. The previous memorandum also noted that we would visit the GE Medium Transformer Manufactur-ing Facility in Rome, Georgia to determine the scope of the problem and appro-
~
' '~
priate'IE action.
IE staff members from this branch and the Vendor Program Branch visited the manufacturing plant in June, 1986. They reviewed the manufacturing process, the quality control and the specific concerns involving this event. They also discussed previous transformer failures, corrective actions, and design detail with the GE staff. Based on this plant visit, the previous information pro-vided in the region inspection and discussions with the licensee, we believe 1 that this event was an isolated incident without major safety significance and therefore, an information notice is not required. However, some of the infor-mation obtained during this review could be of use in developing maintenancc programs. By separate memorandum we are providing copies of the Region I inspection report, the licensee's LER, and a summary of the information we i obtained during our review to the Maintenance and Training Branch, Division of !
Human Factors Technology, NRR for their use in the development of the generic !
maintenance programs. You are on distribution for that memorandum.
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Contact:
James C. Stewart, IE 492-9061 9yfN A
\
?
Stewart D. Ebneter -
We highlighted the following three items to NRR:
- 1) There was no record that the oil level had ever been checked except by the sight gage since it was delivered 17 years ago. Before the event, there was no scheduled plan to inspect the oil level for the duration of plant life.
- 2) The oil level gage was apparently trusted as accurate by the licensee without the necessary comparison with the oil temperature gage. Although GE stated that this has not been a major problem, they published an article (Ref. enclosure) in a trade magazine in 1971 on how to properly utilize transformer instrumentation.
- 3) The licensee did not keep complete records of the amount of oil removed for testing.
We do not plan any further action at this time.
Robert L. Baer, Chief Engineering and Generic Communications Branch Division of Emergency preparedness and Engineering Response Office of Inspection and Enforcement
Enclosure:
General Electric Reprint GER-2705 from April 1971 issue of Electrical South l
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Alert to transformer .
gage md. cat. ions by R J. Ristow I
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General Electnc Company Medium Transformer Products Department Rome, Georgia 30161 GENER AL h ELECTRIC t__ . _ - _ . _ _
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_ A ert to 0 5 transformer gage 32
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By R. J. Ristow, Design Engineer, Gen- a 65 degree C rise transformer car. One common cause of transformer rying rated kVA, this oil temperature failure is operation without sulTicient l
- N I partrnent o ne$c"ofgi gage will read approximately 90 liquid. This can happen casily if no degrees C. At this temperature, the one watches the transformer gages
" Don't let those gages fool you" oil in the middle of the winding will and if the unit does not have a low is a key idea in reviewing with be about 80 degrees C and the wind- liquid level alarm. Transformer cool-electrical maintenance and operating ings about 95 degrees C, This cor- ing depends on liquid expansion personnel the operation of gages on responds to a 65 degree C rise over forcing the hot liquid into the top l all indoor and outdoor liquid-filled an ambient of 30 degrees C. For a 55 of the tube headers, where the liquid i transformers. degree C rise transformer, the oil gives off its heat to the outside air All too often, a concerned electrical temperature gage should read about as it flows down through the tubes.
l superintendent will call the trans- 80 degrees C under normal load at The tubes should be hot at the top ,
former manufacturer when an oil an ambient of 30 degrees C. and get cooler as they progrew f temperature gage reads 65 degrees C Transformers aiso are supplied with dow nward. ;
and the transformer is carrying only two other gages, the liquid level gage if for some reason, such as a leak, half load. He is afraid to load his and the pressure vacuum gage. If there is insufficient liquid in the tank transformer any more, because the properly read and evaluated, these to reach the top opening of the tubes nameplate states that it is suitable gages can show when something is when it starts getting hot, the unit for a certain kVA at 65 degree C about to go wrong, thereby prevent- will burn itself up. The oil tempera-rise. ing an electrical outage. ture gage may not even indicate The key word, of course, is " rise." It is important to note that all any trouble, because the sensing bulb It means that the transformer wind- three gages must be read before one will be out of oil, reading only the ings will enjoy a normal life if their can accurately predict the condition temperature of the air space. Both the temperature does not exceed 65 de- of the transformer. Both the liquid pressure gage and the liquid level grees C over the ambient or surround- level and the pressure inside the gage also will read low. So for an ing temperature. If the surrounding transformer are determined by the inexperienced person.everything will air is 86 degrees F or 30 degrees C, temperature of the insulating liquid. appear normal with all gages reading then the actual temperature of the High temperatures are accompanied low. What he neglects to take into windings could be 65 degrees C + 30 by high liquid levels (because of consideration is the load on the degrees C, or 95 degrees C. liquid expansion) and, consequently, transformer.
This may not mean much, of high pressure. If, for instance, the if all gages are reading low, then course, to operating personnel. They oil temperature gage reads 90 de- the load should be very small or the see only an oil temperature gage; grees C and the liquid level gage day very cold. If the surrounding air no one has told them what it should reads high but the pressure gage is warm and the load is moderate ,
read. They know it has some rela- reads zero, then a transformer leak to heavy, then the oil temperature j tionship to the winding temperature, may exist. If no leaking liquid is gage should read a temperature in- l l but what that relationship is, often present, the leak is probably in the crease, the liquid level gage indicate is not known. As a general rule, for air space above the liquid. a high level, and the pressure gage I
1 4.
1
>** +
Potential trouble may be averted by the proper indicat'ons analysis of gage readings show some positive pressure. The the oil heats up. The temperature them, but not with some applied table illustrates normal gage readings of the oil can rise even after load is reasoning and analysis. A person with various conditions of ambient reduced because of this time lag. If can spot potential problems, avoid the ambient temperature falls below trouble, and assure himself of power temperature and load.
Sometimes it becomes necessary 30 degrees C (86 degrees F), then system reliability by being familiar to supply short time overloads to a overloads are permissible (approxi- with transformer gages.
transformer. When this happens, the mately one percent extra kVA per 1 oil temperature gage cannot serve one degree C lower temperature).
as a loading guide. It takes two to For ambients above 30 degrees C, ,
four hours before the full effect of a the kVA output must be decreased l load registers on an oil temperature 1.5 percent for cach one degree C gage. This is because first, the winding higher temperature.
and core have to heat up, and then Gages can fool, cven if one watches Oil temperature Liquid tevel Pressure l Ambient Load vacuum gage J gage gage 0
" - +
L H 30*C None 30' \ o o o
n 65* j _ j ,
Moderate o / /
30* C 0
90 L H - +
30*C Rated kVA / / /
0 35* - +
L H 0*C Moderate \
0
+
45'\
L 4
f H -
20*C' Rated kVA l
'At this tempera'ure, the transformer could carry 50 percent more load than the navneptate indicates.
The table shows normal gage readings with various conditions of ambient temperature and load.
Reprinted from April 1911 assue of ELECTRICAL SOUTH 1
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