ML20011A307
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| ML20011A307 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/01/1981 |
| From: | Aswell D LOUISIANA POWER & LIGHT CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, W3K81-0363, W3K81-363, NUDOCS 8110090280 | |
| Download: ML20011A307 (1) | |
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. 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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. 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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. 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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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Text
1 6-O- )$
I Louisiama POW 2R & LIGHT
,42 DelmeONoe s1n<<1 P O BOX 6000 + NEW ORLEANS. LOUISIANA 70174 * (504) 366-2345 UTiuTIES SYSTEM October 1, 1981 v.c. %s.oent so e %ouct on W3K81-0363 Q-3-A35.07.26 Q-3-A35.02.01 Mr. K. V. Seyfrit, Director, Region IV U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
Subject:
Waterford SES Unit 3 Second Interim Report of Significant Construction Deficiency No. 26 "Feedwater Isolation Valves - Temperature Maintenance of Actuators, Anchor Darling"
Reference:
- 1) LP&L Letter W3K-81-0162 dated April 30, 1981
- 2) Telecon, L. L. Bass (LP&L) to B. Hubacek (NRC) on September 30, 1981
Dear Mr. Seyfrit:
A report on the subject item was due to the NRC on September 30, 1981. Ebasco Quality Assurance has informed LP&L that additional material has to be procured and contractor secured for the installation of this material.
The supplier of these feedwater isolation valves, Anchor Darling, has submitted drawings for shrouds and space heaters to be installed on these valves. This equipment is expected to be delivered by October 1, 1981.
Based on the above, Ebasco anticipates a lead time of approximately six (6) months for procurament of material with construction installation to follow.
A final report will be submitted to the NRC by June 15, 1982. Al N0lD38 38N SI If you have any questions, please let us know.
00W 6-M M Very truly yours, -
,aca ae D. L. Aswell fy;qkp
[C (,,
omm DLA/LLB/grf 63 00T 8g- # #,
cc: 1) Director N q Office of Inspection & Enforcement b U. S. Nuclear Regulatory Commission Washington, D. C. 20555 \ b(./,_fs Mj
- 2) Director l Office of Management Information and Program Control [h3) l
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U. S. Nuclear Regulatory Commission 0110090280 811db1 'ington, D. C. 20555 hi f PDR ADOCK 050C7382 e
S PDR _ j
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