W3P85-0509, Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 850329
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| ML20108D017 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/26/1985 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 180, W3P85-0509, W3P85-509, NUDOCS 8503080213 | |
| Download: ML20108D017 (2) | |
Similar Documents at Waterford | |
|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 March 1999
[Table view]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 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp ML20203J2521997-12-0101 December 1997 Deficiency Rept Re Failed Mdr Relays at Entergy Operations Inc,Waterford 3 Nuclear Generation Station.Caused by Contaminated Grease.Housekeeping Procedures Formalized & Added Enclosed Booth Isolating Mdr Final Assembly LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20117K9731996-09-10010 September 1996 Follow-up Part 21 Rept of Re Failures of Waterford 3 Dedication Testing Process of Seven Commercial Grade Barksdale Pressure Switches ML20116C7031996-07-29029 July 1996 Part 21 Rept Re Failures Identified by Waterford 3 Dedication Testing Process of 7 Commercial Grade Barksdale Pressure Switches ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept LD-94-019, Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info1994-03-16016 March 1994 Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info LD-93-177, Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested1993-12-23023 December 1993 Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993 Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. 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Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127M5201992-11-24024 November 1992 Final Part 21 Rept Re Reject Lot Serial Numbers of Defective Fuel Nozzle Tips,Consisting of Corrected Page 6 of 921102 Rept Re Reject Lots for Fuel Injector Assembly ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20115D6331992-10-15015 October 1992 Part 21 Rept Re Nuclear Logistics Inc 10CFR21 Notification for Gnb Industrial Battery Co Batteries.Util Will Obtain Replacement Batteries from C&D Power Sys,Inc & Alarm Features to Be Tested by End of Refuel 5 ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20101Q9311992-07-0808 July 1992 Part 21 Rept Re Failure to Comply w/1 Minute Rating of NCX-17 Cells Mfg by Gnb Battery Co (Formally Gould).Addl Testing of Cell Sizes & End Voltages Scheduled to Begin on 920713 & Be Completed on 920815 L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl W3P85-1442, Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e)1985-08-0101 August 1985 Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e) ML20133G9741985-07-31031 July 1985 Part 21 Rept Re Anchor/Darling Valve Co Swing Check Valves W/Loose Set Screws &/Or Missing Lock Welds,Reported by Palo Verde Nuclear Generating Station.All Customers W/Similar Valves Notified.Ltr Re Waterford 3 Valves Encl W3P85-1420, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 8508011985-06-27027 June 1985 Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 850801 W3P85-1400, Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 8507011985-05-29029 May 1985 Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 850701 ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC W3P85-1240, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 8505311985-04-29029 April 1985 Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 850531 W3P85-0785, Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 8504301985-03-25025 March 1985 Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. 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[Table view]Drill 99-08 Emergency Preparedness Exercise on 991013 ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for 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Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195E5161998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Waterford 3.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K0801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with ML20151W8331998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with ML20237B6831998-08-17017 August 1998 LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved ML20237C5661998-08-17017 August 1998 Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting 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Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20247F6761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/ ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216B1751998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Waterford 3 Ses ML20217M1411998-03-0303 March 1998 Rev 2 of Waterford 3 Cycle 9 Colr 1999-09-30 |
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$1USl$ EY February 26, 1985 W3P85-0509 Q-3-A35.07 3-A1.01.04 A4.05 Mr. Robert D. Martin ,- 1 !
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Dhk T
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611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
{g_gg U '
Dear Mr. Martin:
l
Subject:
Waterford 3 SES Docket No. 50-382 POTENTIALLY REPORTABLE DEFICIENCY NO. 180
" Failure to Maintain Adequate Document Control of Vendor Manuals" Extension of Report Schedule
References:
- 1. W3P85-0083 from K.W. Cook (LP&L) to R.D. Martin (NRC),
dated 1/14/85.
- 2. W3P84-2386 from K.W. Cook (LP&L) to J.T. Collins (NRC),
dated 9/13/84.
In accordance with 10CFR50.55(e), LP&L provided telephone notification on September 18, 1984 of the subject deficiency. Reference 1 requested an extention for submittal of a written report on PRD-180 to February 28, 1985. Reference 2 provided LP&L's response to related Violation 8425-01 which specified details on corrective actions planned and underway to resolve this violation.
LP&L requires additional time to evaluate the safety significance of PRD-180 for reportability determination of the deficiency per 10CFR50.55(e) guidance. LP&L has, therefore, rescheduled the submittal of the written report on PRD-180 for March 29, 1985.
R503000213 850226 PDR ADOCK 05000382 8 PDR
[b i I b
Mr. Robert D. Martin W3P85-0509 Page 2 9
If you have any questions, please contact Mr. G. E. Wuller (Onsite Licensing Unit Coordinator) at (504) 464-3499.
a .
j Very truly.yours, !
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K.W. Cook Nuclear Support & Licensing Manager
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KWC:CEW:sms 1
cc: NRC, Director, Office of I&E G.W. Knighton, NRC-NRR '
D.M. Crutchfield, NRC-NRR NRC Resident Inspectors Office
- INPO Records Center (D.L. Gillispie)
- E.L. Blake W.M. Stevenson
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