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| | number = ML17262A775 | | | number = ML17262A775 |
| | issue date = 03/23/1992 | | | issue date = 03/23/1992 |
| | title = Interim Part 21 Rept Re Deficiencies W/Movs V826B,V738B & V871A & Two Two Inch Velan Manual 1500 ASME Class Ii Valves. Further Investigation Being Conducted by Noncompliance Repts Processing Group | | | title = Interim Part 21 Rept Re Deficiencies W/Movs V826B,V738B & V871A & Two Two Inch Velan Manual 1500 ASME Class II Valves. Further Investigation Being Conducted by Noncompliance Repts Processing Group |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:'ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULA.Y INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9203300092 DOC.DATE: 92/03/23 NOTARIZED: | | {{#Wiki_filter:'ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULA . Y INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G ARITH.NAME AUTHOR AFFILIATION MECREDY,R.C. | | ACCESSION NBR:9203300092 DOC.DATE: 92/03/23 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 ARITH.NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. |
| Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET 05000244 | | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Interim Part 21 rept re deficiencies w/MOVs V826B,V738B S V871A 6 two two inch Velan manual 1500 ASME Class II valves.Further investigation being conducted by noncompliance repts processing group.DISTRIBUTION CODE: IE19D COPIES RECEIVED:LTR I ENCL J SIZE: TITLE: Part 21 Rept (50 DKT)D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | Interim Part 21 rept re deficiencies w/MOVs V826B,V738B S V871A 6 two two inch Velan manual 1500 ASME Class II valves. |
| 05000244/RECIPIENT ID CODE/NAME PD1-3 LA JOHNSONFA INTERNAL: AEOD/DSP/ROAB NRR/DRIS/RVIB9D RES/DSIR/EIB RGN2 RGN4 SECY VANDERMEL EXTERNAL: INPO RECORD CTR NSIC SILVERFE COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NR+RDOEA/OGCB 1 1 lREG'=.FILE | | Further investigation being conducted by noncompliance repts processing group. |
| +BI F~RGNZ" RGN3 RGN5 NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
| | DISTRIBUTION CODE: IE19D COPIES RECEIVED:LTR TITLE: Part 21 Rept (50 DKT) |
| D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17
| | I ENCL J SIZE: |
| >'s jf/BIEN)l ii~K'/ir 4iJil/IZ IIIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C MECREDY Vice President Cinna Nuclear Production TELEPHONE AstErt cooE 7 re 546.2700 March 23, 1992 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555'ubject:
| | D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 / |
| 10 CFR Part 21 Interim Report R.E.Ginna Nuclear Power Plant Docket No.50-244 The revision to 10 CFR Part 21, Section 21(a)made effective on 10/29/91, requires an.interim report;of any deviation for which an evaluation to determine reportahility impact is.unable to be completed.
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-3 LA 1 0 PD1-3 PD 1 1 JOHNSONFA 1 1 D INTERNAL: AEOD/DSP/ROAB 1 1 NR+RDOEA/OGCB 1 1 2 2 NRR/DRIS/RVIB9D RES/DSIR/EIB 1 |
| within 60 days of discovery.
| | 1 1 |
| A recent RG&E audit found that.evaluations for several deviations were not timely and.that the need for interim reports had not yet been considered.
| | 1 lREG'=.FILE F~RGNZ" |
| It further, determined the cause of the problem to be implementation deficiencies corresponding'to'he rule change.The magnitude of the problem was 28 evaluations exceeding the 60 day duration.This total was derived from an audit sample, from the nearly 200 open Nonconformance Reports (NCR), and further investigation by.the NCR processing group.During the past four weeks a concerted effort was undertaken to complete the 28 evaluations.
| | +BI 1 1 |
| The following, tabulation presents the current status:~Evaluation Completed--No Reportable Defect--25~Evaluation In Progress--Included in Interim Report--2~Evaluation Completed;
| | 1 1 |
| --Reportable Defect--1**Notice dated February 24 sent by facsimile The two deviations requiring additional evaluation time are described in Attachment A.The actual discovery date for'ach preceded the rule change that became effective 10/29/91.For these deviations, the 10/29/91 date which augments the actual discovery'ate was used to initiate the 60 day evaluation requirement..Although these deviations were discovered prior to the rule change date, interim reports became necessary prior to 12/28/91 for evaluations continuing into 1992.9203300092 920323~d'DR ADOCK 05000244 ritirigtr'S PDR yjgS'f/
| | RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 SECY VANDERMEL 1 1 EXTERNAL: INPO RECORD CTR 1 1 NRC PDR 1 1 NSIC SILVERFE 1 1 D |
| C'~~
| | D D |
| (2)In addition to the review of NCRs, other corrective action systems which involve evaluations under.10 CFR Part 21 have also been reviewed and found to be free of timeliness problems..
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| The following actions have been undertaken to ensure timely evaluation and interim reporting in, the future.1.Assigned responsibilities and methods.for.processing an/statusing deviations have been'larified in all applicable procedures, including Ginna Station and.Quality Performance.
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| 2.Assigned responsibilities and instructions for performing 10 CFR 21 evaluations and.related interim reports have been clarified in existing Ginna.Station', Quality Performance and Nuclear Engineering Services procedures.
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17 |
| These clarifications include.utilization of 10CFR 50.72 and, 50.73 criteria for performing evaluations of installed.
| |
| basic components.
| |
| 3.Responsibilities and requirements for 10 CFR 21, evaluations and related interim reports have been clarified.
| |
| in relevant portions of Quality Assurance Manual Sections 15 and 16.4.Target completion dates are assigned and tracked, for potential deviations to'ssure timely evaluations.
| |
| 5.Training has been scheduled.
| |
| for appropriate groups.In the interim, closer monitoring of the evaluation timeliness will be provided by the Quality Performance department.
| |
| In summary, corrective actions are sufficiently implemented, to assure timely evaluation of 10 CFR 21 deviations.
| |
| Interim actions will remain until required.training is completed.
| |
| Further correspondence on the 2 items described in Attachment A will not be issued unless the evaluations are not completed as scheduled or the deviations require reporting per 10 CFR Part 21.Very Truly Yours, RCMNcem%005 Robert C.Mecredy zc: Regional Administrator U.S.Nuclear Regulatory Commission Region 1 475 A'llendale Road.King of Prussia, PA Ginna USNRC Senior Resident: Inspector
| |
| ~'~1 I P
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| ~~vS~'1 l Attachment A 10 CFR 21 Deviation Evaluation Extensions Deviation Discovery Date: 5/10/91 (10/29/91)
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|
| ==
| | >'s jf/BIEN) l ii~K'/ir 4iJil/IZ IIIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE Vice President AstErt cooE 7 re 546.2700 Cinna Nuclear Production March 23, 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 10 CFR Part 21 Interim Report 20555'ubject: |
| Description:==
| | R. E. Ginna Nuclear Power Plant Docket No. 50-244 The revision to 10 CFR Part 21, Section 21(a) made effective on 10/29/91, requires an. interim report; of any deviation for which an evaluation to determine reportahility impact is. unable to be completed. within 60 days of discovery. |
| | A recent RG&E audit found that. evaluations for several deviations the need for interim reports had not yet were not timely and. |
| | been considered. |
| | to be implementation Itthat further, determined the cause of the problem deficiencies corresponding'to'he rule change. |
| | The magnitude of the problem was 28 evaluations exceeding the 60 day duration. This total was derived from an audit sample, from the nearly 200 open Nonconformance Reports (NCR), and further investigation by. the NCR processing group. During the past four weeks a concerted effort was undertaken to complete the 28 evaluations. The following, tabulation presents the current status: |
| | Evaluation Completed -- No Reportable Defect -- 25 Evaluation In Progress -- Included in Interim Report -- 2 |
| | ~ |
| | ~ |
| | ~ |
| | Evaluation Completed; -- Reportable Defect -- 1 * |
| | * Notice dated February 24 sent by facsimile The two deviations requiring additional evaluation time are described in Attachment A. The actual discovery date for'ach preceded the rule change that became effective 10/29/91. For these deviations, the 10/29/91 date which augments the actual discovery'ate was used to initiate the 60 day evaluation requirement. .Although these deviations were discovered prior to the rule change date, interim reports became necessary prior to 12/28/91 for evaluations continuing into 1992. |
| | 'S 9203300092 920323 ADOCK 05000244 PDR |
| | ~ ritirigtr d'DR yjgS'f / |
|
| |
|
| | C' |
| | ~ ~ |
| | |
| | (2) |
| | In addition to the review of NCRs, other corrective action systems which involve evaluations under. 10 CFR Part 21 have also been reviewed and found to be free of timeliness problems.. |
| | The following actions have been undertaken to ensure timely evaluation and interim reporting in, the future. |
| | : 1. Assigned responsibilities and methods. for. processing an/ |
| | statusing deviations have been'larified in all applicable procedures, including Ginna Station and. Quality Performance. |
| | : 2. Assigned responsibilities and instructions for performing 10 CFR 21 evaluations and. related interim reports have been clarified in existing Ginna. Station', Quality Performance and Nuclear Engineering Services procedures. These clarifications include. utilization of 10CFR 50.72 and, 50.73 criteria for performing evaluations of installed. basic components. |
| | : 3. Responsibilities and requirements for 10 CFR 21, evaluations and related interim reports have been clarified. in relevant portions of Quality Assurance Manual Sections 15 and 16. |
| | : 4. Target completion dates are assigned and tracked, for potential deviations to'ssure timely evaluations. |
| | : 5. Training has been scheduled. for appropriate groups. In the interim, closer monitoring of the evaluation timeliness will be provided by the Quality Performance department. |
| | In summary, corrective actions are sufficiently implemented, to assure timely evaluation of 10 CFR 21 deviations. Interim actions will remain until required. training is completed. |
| | Further correspondence on the 2 items described in Attachment A will not be issued unless the evaluations are not completed as 21. |
| | scheduled or the deviations require reporting per 10 CFR Part Very Truly Yours, Robert C. Mecredy RCMNcem%005 zc: Regional Administrator U. S. Nuclear Regulatory Commission Region 1 475 A'llendale Road. |
| | King of Prussia, PA Ginna USNRC Senior Resident: Inspector |
| | |
| | ~ ' |
| | ~ |
| | 1 I |
| | P |
| | |
| | ~ ~ |
| | vS |
| | ~' |
| | l1 Attachment A 10 CFR 21 Deviation Evaluation Extensions Deviation Discovery Date: 5/10/91 (10/29/91) |
| | |
| | == Description:== |
| Several deficiencies with motor operated valves were noted as follows when test data was compared with calculations: | | Several deficiencies with motor operated valves were noted as follows when test data was compared with calculations: |
| *V826B-Measured thrust exceeded calculated weak link'hrust.*V738B-Calculated dp thrust exceeds thrust measured.by a static test.*V871A-Measured thrust in differential pressure test exceeds calculated motor stall thrust.Valves have been found to be acceptable for interim use until further testing or repair is performed.(NCR 91-362)Scheduled Evaluation Completion Date: 7/15/92 Deviation Discovery Date 8/21/91 (10/29/91) | | * V826B Measured thrust exceeded calculated weak link |
| | 'hrust. |
| | * V738B - Calculated dp thrust exceeds thrust measured. by a static test. |
| | * V871A Measured thrust in differential pressure test exceeds calculated motor stall thrust. |
| | Valves have been found to be acceptable for interim use until further testing or repair is performed. (NCR 91-362) |
| | Scheduled Evaluation Completion Date: 7/15/92 Deviation Discovery Date 8/21/91 (10/29/91) |
|
| |
|
| == | | == Description:== |
| Description:== | | During receipt inspection, two two inch Velan manual 1500 5 ASNE Class II valves were identified with gouges. Valves are not installed in the plant. Depth and significance of gouges are being evaluated. ,(NCR 91-481) |
| | Scheduled Evaluation Completion Date: 7/15/92 m006 |
|
| |
|
| During receipt inspection, two two inch Velan manual 1500 5 ASNE Class II valves were identified with gouges.Valves are not installed in the plant.Depth and significance of gouges are being evaluated.
| | i f' |
| ,(NCR 91-481)Scheduled Evaluation Completion Date: 7/15/92 m006 i f'~i aC~~e C 4,, r I C}}
| | ~ |
| | aC ~ |
| | i~ e C |
| | 4,, |
| | r I C}} |
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Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7131999-07-22022 July 1999
Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7211999-07-19019 July 1999
ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp.
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A7661999-06-30030 June 1999
1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr
ML17265A7011999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17265A6681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation.
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr
ML17265A5951998-12-31031 December 1998
Rg&E 1998 Annual Rept.
ML17265A5001998-12-21021 December 1998
Rev 26 to QA Program for Station Operation.
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4761998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4531998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A4291998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr
1999-09-30
[Table view] |
Text
'ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULA . Y INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9203300092 DOC.DATE: 92/03/23 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 ARITH.NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Interim Part 21 rept re deficiencies w/MOVs V826B,V738B S V871A 6 two two inch Velan manual 1500 ASME Class II valves.
Further investigation being conducted by noncompliance repts processing group.
DISTRIBUTION CODE: IE19D COPIES RECEIVED:LTR TITLE: Part 21 Rept (50 DKT)
I ENCL J SIZE:
D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 /
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-3 LA 1 0 PD1-3 PD 1 1 JOHNSONFA 1 1 D INTERNAL: AEOD/DSP/ROAB 1 1 NR+RDOEA/OGCB 1 1 2 2 NRR/DRIS/RVIB9D RES/DSIR/EIB 1
1 1
1 lREG'=.FILE F~RGNZ"
+BI 1 1
1 1
RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 SECY VANDERMEL 1 1 EXTERNAL: INPO RECORD CTR 1 1 NRC PDR 1 1 NSIC SILVERFE 1 1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17
>'s jf/BIEN) l ii~K'/ir 4iJil/IZ IIIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE Vice President AstErt cooE 7 re 546.2700 Cinna Nuclear Production March 23, 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 10 CFR Part 21 Interim Report 20555'ubject:
R. E. Ginna Nuclear Power Plant Docket No. 50-244 The revision to 10 CFR Part 21, Section 21(a) made effective on 10/29/91, requires an. interim report; of any deviation for which an evaluation to determine reportahility impact is. unable to be completed. within 60 days of discovery.
A recent RG&E audit found that. evaluations for several deviations the need for interim reports had not yet were not timely and.
been considered.
to be implementation Itthat further, determined the cause of the problem deficiencies corresponding'to'he rule change.
The magnitude of the problem was 28 evaluations exceeding the 60 day duration. This total was derived from an audit sample, from the nearly 200 open Nonconformance Reports (NCR), and further investigation by. the NCR processing group. During the past four weeks a concerted effort was undertaken to complete the 28 evaluations. The following, tabulation presents the current status:
Evaluation Completed -- No Reportable Defect -- 25 Evaluation In Progress -- Included in Interim Report -- 2
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Evaluation Completed; -- Reportable Defect -- 1 *
- Notice dated February 24 sent by facsimile The two deviations requiring additional evaluation time are described in Attachment A. The actual discovery date for'ach preceded the rule change that became effective 10/29/91. For these deviations, the 10/29/91 date which augments the actual discovery'ate was used to initiate the 60 day evaluation requirement. .Although these deviations were discovered prior to the rule change date, interim reports became necessary prior to 12/28/91 for evaluations continuing into 1992.
'S 9203300092 920323 ADOCK 05000244 PDR
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(2)
In addition to the review of NCRs, other corrective action systems which involve evaluations under. 10 CFR Part 21 have also been reviewed and found to be free of timeliness problems..
The following actions have been undertaken to ensure timely evaluation and interim reporting in, the future.
- 1. Assigned responsibilities and methods. for. processing an/
statusing deviations have been'larified in all applicable procedures, including Ginna Station and. Quality Performance.
- 2. Assigned responsibilities and instructions for performing 10 CFR 21 evaluations and. related interim reports have been clarified in existing Ginna. Station', Quality Performance and Nuclear Engineering Services procedures. These clarifications include. utilization of 10CFR 50.72 and, 50.73 criteria for performing evaluations of installed. basic components.
- 3. Responsibilities and requirements for 10 CFR 21, evaluations and related interim reports have been clarified. in relevant portions of Quality Assurance Manual Sections 15 and 16.
- 4. Target completion dates are assigned and tracked, for potential deviations to'ssure timely evaluations.
- 5. Training has been scheduled. for appropriate groups. In the interim, closer monitoring of the evaluation timeliness will be provided by the Quality Performance department.
In summary, corrective actions are sufficiently implemented, to assure timely evaluation of 10 CFR 21 deviations. Interim actions will remain until required. training is completed.
Further correspondence on the 2 items described in Attachment A will not be issued unless the evaluations are not completed as 21.
scheduled or the deviations require reporting per 10 CFR Part Very Truly Yours, Robert C. Mecredy RCMNcem%005 zc: Regional Administrator U. S. Nuclear Regulatory Commission Region 1 475 A'llendale Road.
King of Prussia, PA Ginna USNRC Senior Resident: Inspector
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l1 Attachment A 10 CFR 21 Deviation Evaluation Extensions Deviation Discovery Date: 5/10/91 (10/29/91)
Description:
Several deficiencies with motor operated valves were noted as follows when test data was compared with calculations:
- V826B Measured thrust exceeded calculated weak link
'hrust.
- V738B - Calculated dp thrust exceeds thrust measured. by a static test.
- V871A Measured thrust in differential pressure test exceeds calculated motor stall thrust.
Valves have been found to be acceptable for interim use until further testing or repair is performed. (NCR 91-362)
Scheduled Evaluation Completion Date: 7/15/92 Deviation Discovery Date 8/21/91 (10/29/91)
Description:
During receipt inspection, two two inch Velan manual 1500 5 ASNE Class II valves were identified with gouges. Valves are not installed in the plant. Depth and significance of gouges are being evaluated. ,(NCR 91-481)
Scheduled Evaluation Completion Date: 7/15/92 m006
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