Similar Documents at Perry |
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Category:NRC TECHNICAL REPORT
MONTHYEARML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20248D1941989-09-25025 September 1989 AEOD/T915, Ground Fault Detection & Trip Circuit at Perry Unit 1 ML20148B3291988-03-14014 March 1988 Headquarters Daily Rept for 880314 ML20245B4801988-01-19019 January 1988 AEOD Technical Review Rept. Review Documents Results of Event at Unit 1,involving Unexpected Closure & Subsequent re-opening of Outboard MSIVs 1999-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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~AEOD TECHNICAL REVIEW REPORT
I sVNIT: , Perry, Unit 1- TR REPORT NO.: AE0D/T915 1
- ' DOCKET NO.:' 50-440'. DATE: 1989
- n LICENSEE: Cleveland Electric Company ' September 25,S.
EVALUATOR / CONTACT:
Mazumdar
- NSSS/AE: GE/ Gilbert:
SUBJECT:
GROUND FAULT DETECTION AND TRIP CIRCUIT AT PERRY UNIT 1 EVENT.'DATE: May.25, 1989 A
SUMMARY
0n May 25 1989, the licensee discovered that with the existing high resistance grounded scheme a single line-to-ground fault on an individual load could trip
'the EDG breaker before the individual load would trip. In this plant, certain
- non-safety buses are fed from safety-related buses and a licensee investigation
- , indicates that certain fire or seismic events can cause loss of offsite power j with a concurrent loss of Division 1 and 2 EDGs. As a corrective action, the y
- ' licensee.has disabled the EDG trip operation on single line-to-ground fault C .'and has added control room and local alarms to alert the operator of a ground
~ fault.
9
~ DESCRIPTION OF: EVENT In this; plant, the EDG neutrals are high resistant grcunded to limit single
.line-to-ground faults to 2 Amps using a neutral grounding transformer and a
- grounding resistor. -The original design of the EDG protection circuit would initiate.the EDG trip ~whenever a voltage above a preset valve is sensed across.the grounding. resistor.
~On'May 25,'1989 during plant design engineering review, the licensee discovered v ithat with the original,EDG protection scheme, a single ground fault anywhere in the EDG distribution system could trip the EDG withou; tripping the faulty
< feeder breaker.
Furthermore,.in this plant certrin non-safety buses are fed from safety-related buses fed by Division'I and 2 ELGs. A license investigation has established that' because of.the phy.sical arrangement of non-safety electrical equipment in the plant ,a' single fire or seismic event could cause a loss of offsite power as well as, simultaneous ground faults on non-safety related loads supplied by each EDG.:'Thus,'a single event could cause loss of offsite power with a y . concurrent. loss of Division.1 and 2 EDGs.
SIMILAR EVENT SEARCH.
l Dak' Ridge National Laboratory (ORNL) conducted a search of the SCSS for events
, involving relays or control circuitry in the Emergency Power Generation
, . Systems, similar to the cvent at Perry described in LER 89-017. This search
- This document supports ongoing AE0D and NRC activities and does not represent the. position or requirements of the responsible NRC program office.
8910040152 890925 '
- i. , PDR ADOCK 05000440
- 'P PDC n
G._&_ .
3; _
, e
-identified'441LERs. ORNL letter, July 28, 1989, specifying the search commands
, 'is attached. Our review of these LERs has. identified only one event (Surry 1,
,, LER87-028)inwhichanEDGtrippedbecausetheinstantaneousovercurrenttrip setting was not properly co-ordinated. -Thus, this issue appears to be limited in' extent.
IMPLICATION OF DISABLING GROUND FAULT TRIP
'In solid or. low resistance grounded systems every effort is made to isolate a faulty circuit at the earliest opportunity to minimize equipnent damage, fire
.and personnel hazard.
In a high resistance grounded system similar to the one in this plant in which
~
the single line-to-ground fault current is limited to two amperes, the system can continue to operate for extended period with a single line-to-ground fault.
The major draw back of. such extended operation with single line-to-ground fault is that in the event of a second fault between another phase and the ground, heavy fault current can flow in the system. Normally, the phase
'overcurrent devices protect the system against heavy faults. However, to avoid occurrence of such heavy faults, it is desirable to limit the operation with single line-to-ground fault to the shortest duration possible. This is achieved
-by initiating an alarm on the occurrence of the first line-to-ground fault which alerts the operator to' isolate the faulty circuit at the earliest opportunity. Thus, the licensee is now using the most desirable scheme for resistance grounded EDGs.
CONCLUSION As a high resistance grounded system can operate for extended period with a single line-to-ground fault,_the original protection scheme to trip the EDG imediately on-occurrence of the first line-to-ground fault is unnecessary.
On the other hand, the proposed change to disable the_EDG overcurrent trip and provide local and control room alarm in the event of a single line-to-ground c fault, permits continuation of EDG operation with orde.rly isolation of the faulty circuit. A_ search of SCSS indicates that this issue is plant specific and not a generic problem and no further AEOD action is required.
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