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| {{Adams | | {{Adams |
| | number = ML20141E500 | | | number = ML20215E065 |
| | issue date = 02/05/1986 | | | issue date = 10/08/1986 |
| | title = Insp Rept 50-382/85-31 on 851202-06.Violation Noted:Failure to Adequately Evaluate & Rept Defective GE AKR-50 Circuit Breakers in Accordance w/10CFR21 | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/85-31.Ltr Forwarded to Div of Qa,Vendor & Technical Ctr Programs for Review of 10CFR21 Applicability |
| | author name = Boardman J, Ireland R | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Dewease J |
| | addressee affiliation = | | | addressee affiliation = LOUISIANA POWER & LIGHT CO. |
| | docket = 05000382 | | | docket = 05000382 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-382-85-31, NUDOCS 8602250270 | | | document report number = NUDOCS 8610150014 |
| | package number = ML20141E456 | | | title reference date = 03-21-1986 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | package number = ML20215E069 |
| | page count = 6 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | | page count = 2 |
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| {{#Wiki_filter:. _ . . | | {{#Wiki_filter:. |
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| | In Reply Refer To: |
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| | OCT 8 l986 Docket: 50-382/85-31 |
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| | Louisiana Power & Light Company ATTN: J. G. Dewease, Senior VP Nuclear Operations 317 Baronne Street P. O. Box 60340 New Orleans, Louisiana 70160 Gentlemen: |
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| | Thank you for your letter of March 21, 1986, in response to our letter and the attached Notice of Violation dated February 20, 1986. -As a result of our review, we continue to feel this item was reportable in accordance with 10 CFR 21;.however, we are forwarding your letter to the NRC Division of Quality Assu ance, Vendor, and Technical Center Programs for program office review cf 10 CFR 21 applicabilit t Sincerel Original Signe'd k |
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| | | ..*" ll J. E. Gagliardo, Chief Reactor Projects Branch cc: |
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| | Louisiana Power & Light Company ATTd: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: R. P. Barkhurst, Plant Manager P. O. Box B . |
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| | Killona, Louisiana 70066 |
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| ' APPENDIX B c
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| ..U.S. NUCLEAR REGULATORY COMISSION i -
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| [ REGION IV ,
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| NRC Inspection Report: 50-382/85-31 Operating License: NPF-26'
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| ; Docket:~ 50-382 3 ,
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| LLicensee: Louisiana Power and Light Company (LP&L) ~
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| 142 Delaronde Street New Orleans, Louisiana 70174 .
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| Facility Name: Waterford Steam Electric Station,, Unit 3 .,
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| Inspection At: Taft, Louisiana Inspection Conducted: December 2-6,-1985
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| Inspector: ,
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| 4? 30ardman,
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| / .CN Reactor b d Inspector, Operations .2/S/r2 '
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| p J. R.Section, Reactor Safety Branch Date ,
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| ' | | RIV/RSB/OS C/OS C/RSB C [C B j f JRBoardman:yhchm TFWesterman G onstable &g ardo /t, [ |
| l l Approved: N:. /Ireland,
| | i,1 nDMHunnicutt 10/ 6 /86 f 10/']/86 10/ 7/86 10/ 7 /86 .:.0/ g /86 goq%8ti Bth8)h2 /f 0 I N' |
| . c I Acting s /e Chief, M Operations 4/5/vd, j Date i Section, Reactor Safety Branch
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| l Inspection Summary l 7 ,
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| . Inspection Conducted December 2-6, 1985 (Renort 50-382/85-31)
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| Areas Inspected: Reactive, announced inspection of the licensee preventive maintenance program and nonlicensed staff training. The inspection involved 36
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| inspector-hours onsite by one NRC inspecto Results: Within the one area inspected (corrective maintenance), one violation was identified (failure to adequately evaluate and report defective General .
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| Electric AKR-50 circuit breakers in accordance with 10 CFR Part 21,' paragraph 3).-
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| -2-DETAILS
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| = Persons Contacted Principal Licensee Employees
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| *R. P. Barkhurst, Plant Manager
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| *L. W. Myers, Operations Superintendent
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| *S. Alleman, Assistant Plant Manager Technical Service
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| *F. J. Englebracht, Manager Plant Administrative Services
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| ,*A. S. Lockhart, Site Quality Manager l *R. B. Willis, Manager, Engineering and Nuclear Safety
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| , *D. Packer, Manager, Training l *H. A.-Trigg',s Records and Administration Manager
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| ! *P. V. Prasankumar, Technical Support Supervisor t
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| * V. Seidle, Engineering and Nuclear Safety I * L. Brewster, Onsite Licensing
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| ! L. Laughlin, Technical Support ( J. Mahoney, Maintenance ,
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| * Denotes those attending the exit interview on December 6, 198 The NRC inspector also interviewed other licensee personne . Followup on Previously Identified Items (0 pen) (382/8425-01) Licensee Document Controls for Vendor Manuals and Technical Data The NRC inspector began the inspection on licensee corrective action for the subject violation by reviewing the following licensee pro-cedures relating to the review and control of vendor manuals:
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| * PMI-016, " Vendor Manual Program," Revision 1, dated July 31, 1985
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| * PPP-306, " Engineering Review," Revision 0, dated June 13, 1984, and Revision 1, dated September 21, 1984
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| * PMP-004, " Control of Vendor Manuals," Revisions 0, 1, and 2, dated April 16, 1984, November 15, 1984, and May 27, 1985 respectively l
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| * PMP-002, " Document Control," Revision 1, dated October 22, 1985
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| The NRC inspector found no apparent programmatic problems or concerns l in these procedures, except as follows:
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| . * During review by the NRC inspector of potentially reportable events (PRE's)'for possible maintenance and training causes, a'.
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| case was discovered on Condition Identification Work
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| Authorization (CIWA) 01740 where the incorrect hydraulic fluid , ,
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| was added to the valve operator of safety-related feed' water
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| isolation valve FW-1848. Based on-technical evaluation of this '''
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| I error by the licensee, the use of incorrect fluid could have adversely affected elastomeric parts of the valve, and consequently valve operatio m* Thelicensee'svendormanualforvalveFW-1848andits'operEtor did not identify the hydraulic fluid to be used. Since a l primary purpose of controlled vendor manuals is maintenance, the ,
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| NRC inspector, during a subsequent inspection, will evaluate documentation of the licensee's technical review of vendor l manuals to assure that vendor instructions exist for required
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| ; preventive and corrective maintenance.
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| l The NRC inspector also reviewed Vendor Technical Information
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| l (VTI) for Agastat Relays used7 tn safety-related applications.
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| l The VTI identified by the Emergency Diesel Generator (EDG) ,
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| ! supplier was for originally provided nonsafety related relays.
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| i used for safety-related applications. Licensee personnel stated
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| ! that original relays were qualified by the EDG supplie Replacement relays will be safety-related (E-series). The '
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| licensee will verify that no unqualified relays have been .
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| Installed as replacements. Maintenance instructions will require j the periodic replacement specified for E-series relays. This will remain an open item (382/8531-01) pending further review
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| during a subsequent inspection.
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| l Further review by the NRC inspector of the licensee's response I
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| ! to 382/8425-01 will be accomplished during a subsequent l l
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| inspection.
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| ! (Closed) (382/8527-01) Microflim identification of safety-related preventive maintenance records showing required l designations, such as Equipment Qualification (EQ). The.
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| l licensee now stamps preventive maintenance documents with the -
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| special designation (EQ) prior to their issue, (Closed) (382/8527-05) Possible Use of Preventive Maintenance
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| , (PM) Task Cards to Perform Corrective Maintenance. The NRC inspector reviewed a sampling of PM task cards having a 3 and 5 ,
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| , year accomplishment periodicity that had two or more recorded i accomplishments in the first year of operation, with the following l-
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| findings:
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| l * Partial accomplishments of PM tasks were entered in the
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| !, licensee's maintenance information system as complete t~ ,
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| -4-accomplishments, indicating erroneous multiple accomplishment * In some cases, task cards were lo , and replacement task cards issued. Subsequently, the licensee determined that both task cards were accomp14shed, and both were entcred in the licensee's maintenance management information syste * In some cases, upon recalibration, measuring and test equipment (M&TE) used for PMs subsequently was determined to be out-of-calibration and the PM task was redon * In one case, there were two identical pieces of equipment having a 5 year PM periodicity based on Technical Specification requirements. FSAR requirements were purported by licensee personnel to be the accomplishment of 10% of this equipment every 18 months. The licensee interpreted this to require PM on one of the two pieces of equipment every 18 month The NRC inspector suggested to licensee personnel that they assure that similar practices resulting in much more frequent PMs than required do not degrade safety-related equipmer.t. The licensee's new maintenance information management system, having the acronym "SIMS" (Station Information Management System), can eliminate unnecessarily redundant accomplishment of PMs. SIMS is scheduled to go "on line" in calendar year 198 . Licensee Corrective Maintenance Program The NRC inspector reviewed the licensee's program for corrective maintenanc This review included licensee procedures, and licensee potentially reportable events (PRES), to determine if they were caused by, or adversely affected by, licensee maintenance practice The licensee is evaluating and accomplishing site-specific, modifications to the Middle South version of the SIMS which is presently used for control of maintenance at Arkansas Nuclear One (ANO) for both units. The ifcensee has targeted to have this system, with site-specific modifications, on-line by October 1, 1986. Review of the Arkansas Power and Light (AP&L) version of SIMS indicates that this program can provide effective management visibility and control of maintenance, Corrective Maintenance Administrative Procedures Overall programmatic control of licensee maintenance activities is covered by Administrative Procedure MD-1-014. " Conduct of Maintenance," Revision 1, approved November 21, 198 _ _ _ - _ _ _ _ _ _
| | l Louisiana Power & Light Company -2-Middle South Services ATTN: Mr. R. T. Lally P. O. Box 61000 |
| | | , New Orelans, Louisiana 70161 Louisiana Power and Light Company ATTN: K. W. Cook, Nuclear Support l and Licensing Manager 317 Baroone Street P. O. Box 60340 New Orleans, Louisiana 70160 bec to DMB (IE01) |
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| | RPB D. Weiss,LFMB(AR-2015) |
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| | Resident Inspector R. D. Martin, EA Section Chief (RPB/C) DRSP R&SPB RSB |
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| Corrective maintenance is performed using a work control document entitled a " Condition Identification and Work Authorization (CIWA)."
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| The governing procedure is UNT-5-002, " Administrative Procedure . +
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| ; Condition Identification and Work Authorization," Revision 4, dated l September 5, 1984.
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| Plant engineering technical review and processing of CIWAs is *
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| Procedure PE-2-005, " Plant Engineering CIWA Processites." Revision 5, approved June 21, 198 .
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| The NRC inspector noted no programmatic violations or deviations in these procedure , Review of Licensee Potentially Reportable Events (PRES) for Events That May Have 8een Caused, or Adversely Af fected, by Licensee Maintenance Practices !
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| The NRC inspector reviewed all licensee PRES for maintenance ,
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| implications. Administrative Procedure UNT-6-010 " Event Evaluation and Reporting," Revision 1 (approved November 26, 1984), provides .
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| guidance for licensee review, evaluation, and reporting of event The inspector identified two problems with the evaluation of events as follows:
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| * One maintenance-related' PRE reviewed was.for the addition of hydraulic fluid to safety-related feed water isolation valve FW-1848. This is discussed previously in this report in ,
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| Section 2.(a). 1 | |
| * PRE 85-150, failure of B charging pump, GE AKR-50 circuit . . | |
| breaker to make contact on one phase resulting in failure of the pump motor to start was reviewe ;
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| The failure of the AKR-50 breaker to make contact was caused by rotationofaphasecontactadjustingscrewduringbreakeroperatio The cause was a low thread torque (less than 40 inch pounds) for the adjusting scre The event occurred May 18, 1985, General Electric (GE) provided to ;
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| the licensee on June 6, 1985, an evaluation and engineering analyses and specified corrective actions which required the application of
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| " LOCTITE-220" to the adjusting screw and verification of adequate torquing. To implement GE's recommendation for breakers having an above average number of close-open operations CIWA 021716 >
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| was approved and issued August 26, 1985, but the action had not been accomplished at the time of the NRC inspection. The licensee committed i to accomplish this'CIWA prior to the next startup for those breakers which had "an above average number of CLOSE-OPEN operations."
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| Subsequent to the inspection, the licensee committed to review all other similar safety-related GE breakers (AKR-30 and AKR-50) to ",
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| assure provision of timely corrective maintenance for this potential failure. This matter will be an open item (382/8531-02) pending review of the licensee actions during a subsequent inspectio Failure to Adequately Evaluate and Report the Defects GE AKR-50 Circuit Breakers Under 10 CFR Part 21 The failure of the 8 charging pump breaker, as noted in b. above, l was not reported under 10 CFR 50.73. The breaker failure had been-evaluated under 10 CFR 21 by the licensee and determined not to be a reportable defect. However, the defect identified by GE to the l licensee was generic to all AKR-50 an AKR-30 breakers as noted in a l June 6, 1985 letter to the licensee. Additionally, GE issued a
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| revision to publication GEK-64459 (applicable to all AKR-30 and AKR-50 breakers) to provide maintenance instructions for checking and correcting the potential defec This breaker failure (rotation of a phase contact adjusting screw during breaker operation) represented a defect in a basic component that could create a substantial safety hazard. The failure of the licensee to adequately evaluate and report this defect to the NRC is a violation of 10 CFR 21,(382/8531-03). Training of Nonlicensed Staff The NRC inspector reviewed licensee Potentially Reportable Events (PRES)
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| ! No events appeared to have been negatively influenced by training.
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| t Exit Interview The NRC inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on December 6,198 The NRC inspector summarized the purpose, scope and findings of the inspection.
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058E8621990-11-0101 November 1990 Forwards Understanding of Current Status of Unimplemented GSIs at Facility,Per 900626 Response to Generic Ltr 90-04. Timely Completion of Encl GSIs Urged ML20058G1561990-10-31031 October 1990 Requests That Matl Listed in Encl 1, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams, Be Furnished by 901207 for Retake of Operating Exams Scheduled for 910122 ML20058B3101990-10-23023 October 1990 Forwards Insp Rept 50-382/90-22 on 900905-1001 & Notice of Violation IR 05000382/19900231990-10-17017 October 1990 Submits Revised Schedule for Electrical Distribution Sys Functional Insp 50-382/90-23.Insp Team Will Arrive at Plant Site on 910107 ML20058B2681990-10-17017 October 1990 Informs That Util Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058A6711990-10-16016 October 1990 Forwards Insp Rept 50-382/90-21 on 900910-14.No Violations or Deviations Noted ML20058A4771990-10-16016 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-17 ML20062B6231990-10-12012 October 1990 Confirmation of Action Ltr CAL-90-06,confirming That Plant Will Not Enter Mode 2 Until NRC Confirms Actions Assuring That Adequate Safety Exists for Continued Power Operation IR 05000382/19900151990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-15.NRC Unable to Clearly Determine Actions Intended to Address Overall Retest & Program Weaknesses ML20059N7041990-10-10010 October 1990 Ack Receipt of Util 900717 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20059K8651990-09-14014 September 1990 Forwards Interfacing Sys LOCA Insp Rept 50-382/90-200 on 900730-0810.Deficiencies in Availability of Design Calculations,Check Valve Maint & Plant Equipment Labeling Noted ML20059K3601990-09-14014 September 1990 Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise ML20059D5901990-08-28028 August 1990 Forwards Insp Rept 50-382/90-17 on 900625-29.No Violations or Deviations Noted.Exercise Weakness Re Performance of Emergency Responders Noted ML20056B4841990-08-22022 August 1990 Forwards Errata to Amend 62 to License NPF-38,consisting of Revised Bases Page Re Time Intervals for Surveillance Requirements,Per 900717 Application & Generic Ltr 89-14 ML20056B2731990-08-16016 August 1990 Ack Receipt of 900720 & 0803 Ltrs Re Objectives & Guidelines for Annual Emergency Preparedness Exercise.Objectives Appear Reasonable.Exercise Scenario & Associated Matls Should Be Submitted at Least 60 Days Prior to Exercise for NRC Review ML20058P3441990-08-15015 August 1990 Advises That Although Adequate Info Provided to Justify Continued Plant Operation Until Plant Completes Final Rept Per Schedule Delineated by NRC Bulletin 88-11,adequate Bases Not Provided for 40-yr Plant Life ML20056A0301990-07-30030 July 1990 Forwards Insp Rept 50-382/90-11 on 900625-29.No Violations or Deviations Noted IR 05000382/19900021990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-02 ML20055G7951990-07-19019 July 1990 Forwards Insp Rept 50-382/90-14 on 900625-29 & Notice of Violation.Actions Taken Re Previously Identified Insp Findings Also Examined ML20055E6501990-07-0909 July 1990 Discusses Generic Implications & Resolutions of Control Element Assembly (CEA) Failures at Maine Yankee.Waterford Unit 3 Does Not Have Old Style CEAs Installed in Reactor Core & Does Not Plan to Use Any in Future ML20055C9751990-06-26026 June 1990 Forwards Page 6a for Insertion in Insp Rept 50-382/90-09 ML20055C7781990-06-15015 June 1990 Forwards Insp Rept 50-382/90-09 on 900501-31.No Violations or Deviations Noted.One Unresolved Item Identified.Licensee Test Acceptance Criteria Did Not Appear to Account for Effect of Flow on Valve Closing Time ML20059M9171990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4121990-03-0202 March 1990 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Imposed by NRC 900202 Order.Corrective Actions Will Be Examined During Future Insp ML20055C2991990-02-23023 February 1990 Advises That 890410 Changes to Emergency Plan,Acceptable ML20248G1871989-10-0202 October 1989 Forwards Insp Rept 50-382/89-25 on 890828-0901.No Violations or Deviations Noted ML20248C6531989-09-27027 September 1989 Forwards Insp Rept 50-382/89-23 on 890801-31.Violations Noted.Enforcement Conference Scheduled for 891011 in Region IV Ofc to Discuss Violation,Reason for Occurrence & Corrective Actions ML20248A4091989-09-26026 September 1989 Requests That Jl Pellet Be Removed from Distribution for Controlled Documents Updates & Revs ML20247Q4211989-09-22022 September 1989 Provides Results of Review of Amend to Rev 5 of Inservice Testing Program for Pumps & Valves.Amend to Rev 5 Acceptable for Implementation & That Testing Requirements Impractical for Item for Which Relief Being Granted ML20247R5681989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-92,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, for Signature ML20247J6851989-09-15015 September 1989 Forwards Insp Rept 50-382/89-16 on 890717-21 & Notice of Violation ML20247D4781989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-05 ML20247F2211989-09-0808 September 1989 Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62 ML20247H8501989-09-0808 September 1989 Ack Receipt of 890531 & 0821 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07. NRC Disagrees W/Licensee Denial of Violation.Implementation of Corrective Actions Will Be Reviewed During Future Insp ML20246P6081989-09-0606 September 1989 Forwards Summary of 890712 Meeting w/C-E Owners Group & Utils Re General Design Features of Diverse ESFAS to Be Installed,Per 10CFR50.62.Safety Evaluation on Plant Design Expected to Be Issued in Near Future ML20246N3131989-08-31031 August 1989 Ack Receipt of Re Violations Noted in Insp Rept 50-382/89-08 & 890516 Notice of Violation.Requests Supplemental Response Re Examples 1-3 of Notice ML20247A5841989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.Agenda & List of Attendees Also Encl ML20246M6491989-08-29029 August 1989 Forwards Amend 56 to License NPF-38 & Safety Evaluation. Amend Increases Frequency of Channel Calibrs from Quarterly to Monthly on Waste Gas Holdup Sys Explosive Gas Monitoring Sys ML20245J0021989-08-14014 August 1989 Confirms 890808 Conversation W/Rp Barkhurst Re Util Participation in NRC Impact Survey Scheduled for 891010 & Submits Info Re Survey ML20245L3311989-08-11011 August 1989 Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation IR 05000382/19890121989-08-11011 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-12.Excluding Incident 1,Violation 382/8912-02 Should Stand as Cited. Response W/Corrective Actions Requested within 30 Days ML20245J2451989-08-0909 August 1989 Advises That Requalification Exams Scheduled for Wk of 890911 Changed to Wk of 890905 to Accommodate New INPO Schedule Issued in May 1989 IR 05000382/19890051989-07-31031 July 1989 Discusses Insp Rept 50-382/89-05 on 890213-17 & Forwards Notice of Violation.No Addl Info Was Provided to Change NRC Position & Therefore Util in Violation of Requirements.Basis for NRC Determination of Violation Provided IR 05000382/19890061989-07-28028 July 1989 Ack Receipt of 890706 Supplemental Response Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-06 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20196E6931999-06-22022 June 1999 Forwards Corrected Ltr Re Changes to Rev 19 to Emergency Plan.Original Ltr Had Error in Subject Line ML20196E0831999-06-21021 June 1999 Forwards Insp Rept 50-382/99-12 on 990524-27.No Violations Noted.Purpose of Insp Was to Conduct Assessment of Emergency Preparedness Program ML20196D9941999-06-18018 June 1999 Forwards Insp Rept 50-382/99-11 on 990524-28.No Violations Noted ML20195J8091999-06-17017 June 1999 Forwards Safety Evaulation Re First 10-yr Interval Inservice Insp Relief Request for Plant,Unit 3 ML20196C8711999-06-15015 June 1999 Discusses Insp Rept 50-382/99-08 & Forwards Notice of Violation Re Unescorted Access Which Was Mistakenly Granted to Individual Whose Background Investigation Indicated That He Had Failed Prior Drug Screening with Another Employer ML20196F3721999-06-0909 June 1999 Corrected Ltr Forwarding Rev 19 to Emergency Plan ML20195G3711999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981223,which Transmitted Waterford 3 Steam Electric Station Emergency Plan,Rev 24,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20207E8541999-06-0303 June 1999 Forwards SE Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressurizer Safety Valves at Plant,Unit 3 ML20207G3441999-06-0303 June 1999 Forwards Insp Rept 50-382/99-09 on 990411-0522 & Notice of Violation.One Violation Identified & Being Treated as Noncited Violation C ML20207D3771999-05-27027 May 1999 Ack Receipt of 990401 & 0504 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-01 on 990303 ML20207A5121999-05-24024 May 1999 Refers to Which Responded to NOV & Proposed Imposition of Civil Penalty Sent by .Violations A,B & E Withdrawn & Violations C & D Changed to Severity Level IV ML20206U7851999-05-18018 May 1999 Forwards Insp Rept 50-382/99-06 on 990405-09.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML20206N6961999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S4411999-05-10010 May 1999 Forwards Insp Rept 50-382/99-05 on 990228-0410.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3841999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamental Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam,With Answer Key,Encl for Info.Without Encl ML20206K0951999-05-0606 May 1999 Discusses Insp Rept 50-382/99-08 Issued 990503 Without Cover Ltr Documenting EA Number & Subject Line Indicated NOV Which Was Incorrect.Corrected Cover Ltr Encl ML20206F4701999-05-0303 May 1999 Forwards Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Re Failure to Review & Consider Derogatory Access Authorization Background Info as Required by PSP Identified & Being Considered for Escalated Enforcement Action ML20206K1211999-05-0303 May 1999 Corrected Cover Ltr Forwarding Insp Rept 50-382/99-08 on 990405-07.One Violations Noted & Being Considered for Escalated EA ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M0561999-04-0909 April 1999 Forwards Insp Rept 50-382/99-04 on 990301-19.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20205J8781999-04-0505 April 1999 Forwards Insp Rept 50-382/99-02 on 990117-0227.No Violations Noted.Inspectors Determined That Six Violations Occurred & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20205J0901999-04-0202 April 1999 Informs That Info Submitted by & 970313 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) ML20205A4681999-03-26026 March 1999 Forwards Insp Rept 50-382/99-03 on 990308-12.Two Violations of Radiation Protection Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205A6141999-03-25025 March 1999 Forwards SE Accepting Request to Use Mechanical Nozzle Seal Assemblies (Mnsas) as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Application at Plant,Unit 3 ML20205F3311999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Plant,Unit 3 PPR Review,Which Was Completed on 990211.Performance at Plant,Unit 3 Was Acceptable ML20204E4941999-03-17017 March 1999 Discusses TSs Bases Change Re 3/4.4.1,3/4.6.1.7,3/4.6.3, 3/4.7.12 & 3/4.8.4.Forwards Affected Bases Pp B 3/4 4-1, B 3/4 6-3,B 3/4 6-4,B 3/4 7-7 & B 3/4 8-3 ML20207F1251999-03-0303 March 1999 Forwards Insp Rept 50-382/99-01 on 990125-29 & 0208-12 & Notice of Violations ML20203H8501999-02-17017 February 1999 Forwards SE Accepting Licensee 970701 Submittal of Second Ten Year ISI Program & Associated Relief Request for Plant, Unit 3.Nine Relief Requests Had Been Authorized Previously & Proposed Alternatives Remain Authorized ML20203D7211999-02-11011 February 1999 Forwards Request for Addl Info Re Licensee 970317 & 990111 Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Response Should Be Provided within 60 Days 1999-09-09
[Table view] |
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In Reply Refer To:
OCT 8 l986 Docket: 50-382/85-31
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Louisiana Power & Light Company ATTN: J. G. Dewease, Senior VP Nuclear Operations 317 Baronne Street P. O. Box 60340 New Orleans, Louisiana 70160 Gentlemen:
Thank you for your letter of March 21, 1986, in response to our letter and the attached Notice of Violation dated February 20, 1986. -As a result of our review, we continue to feel this item was reportable in accordance with 10 CFR 21;.however, we are forwarding your letter to the NRC Division of Quality Assu ance, Vendor, and Technical Center Programs for program office review cf 10 CFR 21 applicabilit t Sincerel Original Signe'd k
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..*" ll J. E. Gagliardo, Chief Reactor Projects Branch cc:
Louisiana Power & Light Company ATTd: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: R. P. Barkhurst, Plant Manager P. O. Box B .
Killona, Louisiana 70066
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l Louisiana Power & Light Company -2-Middle South Services ATTN: Mr. R. T. Lally P. O. Box 61000
, New Orelans, Louisiana 70161 Louisiana Power and Light Company ATTN: K. W. Cook, Nuclear Support l and Licensing Manager 317 Baroone Street P. O. Box 60340 New Orleans, Louisiana 70160 bec to DMB (IE01)
bec distrib. by RIV:
RPB D. Weiss,LFMB(AR-2015)
Resident Inspector R. D. Martin, EA Section Chief (RPB/C) DRSP R&SPB RSB
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MIS SYSTEM RSTS Operator RIV File
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