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| {{Adams | | {{Adams |
| | number = ML20137C700 | | | number = ML20153F204 |
| | issue date = 11/05/1985 | | | issue date = 02/19/1986 |
| | title = Insp Rept 50-382/85-23 on 850805-09.Violation Noted: Personnel Assigned to Emergency Organization Not Adequately Trained | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/85-23.Two Shift & Control Room Supervisors Inadequately Trained to Perform Emergency Response Duties.Violation Remains Valid |
| | author name = Hackney C, Yandell L | | | 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 = Leddick R |
| | addressee affiliation = | | | addressee affiliation = LOUISIANA POWER & LIGHT CO. |
| | docket = 05000382 | | | docket = 05000382 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-382-85-23, NUDOCS 8511260582 | | | document report number = NUDOCS 8602250336 |
| | package number = ML20137C682 | | | title reference date = 12-13-1985 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | package number = ML20153F207 |
| | page count = 6 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | | page count = 2 |
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| . . | | FEB l 91986 |
| APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION
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| | In Reply Refer To: |
| | Docket: 50-382/85-23 |
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| | Louisiana Power & Light Company ATTN: R. S. Leddick, Sr. Vice President Nuclear Operations 142 Delaronde Street New Orleans, Louisiana 70174 Gentlemen: |
| | Thank you for your letter of December 13, 1985, in response to our letter and ano the attached Notice of Violation dated November 14, 198 In response to your comment on the validity of the Notice of Violation, the NRC inspectors determined by observation during the operational walk-through that the two shift supervisors and control room supervisors had not been adequately trained to properly perform emergency response duties; therefore, a violation of the requirement did occur. We have reviewed the corrective actions that you have proposed and find them responsive to the concerns raised in our Notice of Violation. We will review the, implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine |
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| ==REGION IV==
| | Sincerely, f0th;inal signed by;" |
| NRC Inspection Report: 50-382/85-23 License: NPF-38 Docket: 50-382 Licensee: Louisiana Power & Light Company
| | J. E. Gagliardo, Chief Reactor Projects Branch cc: (continued on next page) |
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| | RIV: EP h C:EP&SP 0:[ |
| 142 Delaronde Street
| | f5 LAYande S C/RPS' C:RPB / ff3 |
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| | . CAHackney/ RL rt GL0tfr$ stable JEGagli 1do // |
| New Orleans, Louisiana 70174 Facility Name: Waterford 3 Steam Electric Station (SES)
| | g/11/86 A/is /86 g)([(/86 |
| Inspection At: Waterford 3 SES site near Killona, Louisiana Inspection Conducted: August 5-9, 1985 Inspector: M -a li Llcbds e ll T-is C. A. Hackney, Emergency Preparedness Analyst Date w
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| Accompanying Personnel: D. Schultz, Comex Corporation Approved: b nu II-s~ - f s'
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| L. A. Yandell, Chief, Emergency Preparedness Date and Safeguards Programs Section
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| Insjecticn Summary Inspection Conducted August 5-9, 1985 (Report 50-382/85-23)
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| i Areas Inspected: Routine, unannounced inspection of the licensee's emergency preparedness program in the areas of knowledge and performance of emergency response duties. The inspection involved 92 inspector-hours onsite by two l NRC inspector '
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| Results: Within the emergency response areas insoected, one violation was l identified (personnel assigned to emergency organization not adequately trained paragraph 3).
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| 8511260582 DR 851114
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| #iDOCK 05000382 PDR
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| DETAILS Persons Contacted Principal Licensee Personnel'
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| , *R. P. Barkhurst, Plant Manager
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| *S. A. Alleman, Assistant Plant Manager, Plant Technical Services | | ; Louisiana Power & Light Company -2- |
| *R. G. Azzarello, Emergency Planning Coordinator
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| *J. O'Hern, Ganeral Training Superintendent | |
| *J. Lewis, Onsite Emergency Planning-Coordinator | |
| *P. Prasankumar, Technical Support Superintendent
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| *A. Roberts, Quality Assurance C. Gaines, Training Department Instructor
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| *J. Messina, Quality Assurance
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| *L. Meyers, Operations Superintendent i
| | cc: Louisiana Power & Light Company |
| *K. Brewster, Onsite Licensing
| | : ATTN: G. E. Wuller, Onsite 1 Licensing Coordinator - |
| *D. Packer, Training Manager T. Brown, Shift Supervisor D. Miller, Nuclear Plant Operator 11. Pendergrass, Reactor Operator M. Bourgeois, Shift Supervisor A. Bowers, Control Room Supervisor R. Brinkley, Control Room Supervisor J. Hampton, Reactor Operator K. Chester, Nuclear Auxiliary Operator C. Fugate, Control Room Supervisor D. Jory, Nuclear Auxiliary Operator G. Davie, Shift Supervisor M. Jones, Control Room Supervisor G. Wemett, Nuclear Plant Operator J. Hoffpauir, Shift Supervisor D. Schultz, Control Room Supervisor H. Miller, Nuclear Plant Operator NRC
| | . 'P. O. Box B Killona, Louisiana 70066 l Louisiana Power & Light Company ATTN: R. P. Barkhurst, Plant Manager P. 0. Box B K111ona, Louisiana 70066 i . Middle South Services i ATTN: Mr. R. T. Lally- |
| *T. A. Flippo, Resident Inspector
| | , P. 0. Box 61000 |
| * Jones, Resident Inspector The NRC inspectors also held discussions with other station and corporate personnel in the areas of, reactor operations, emergency response organization, and trainin * Denotes those present at the exit intervie . . | | . |
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| 3 Licensee Action on Previous Inspection Findings (Closed) Open Item (382/8402-03) - Training plans for offsite agencies had been finalized and initiated. This item is close (Closed) Open Item (382/8402-04) - The training lesson plan had been revised to include the use of the nomogram. This item is close (Closed) Open Item (382/8402-05) - Meteorological data selection hierarchy for dose projections had been included in EP-2-05 This item is close (Closed) Open Item (382/8402-06) - EP-2-050 had been revised to include meteorological tower heights in meters and fee This item is close (Closed) Open Item (382/8402-07) - Control room walkthroughs were completed February 27, 1985, using the specified procedures. This item is close . Knowledge and Performance of Duties The NRC inspector reviewed selected portions of the Emergency Plan, Emergency Plan Implementing Procedures (EPIP's), station normal operating procedures, station off-normal operating procedures, and portions of the emergency preparedness training program. The NRC inspector also compared selected station personnel training records with the required retraining program and determined that the reviewed personnel had received their required trainin Emergency response walkthroughs were conducted with selected operations shift supervisors, control room supervisors, reactor operators, nuclear plan operators and nuclear auxiliary operators. Prior to the walkthroughs a meeting was held with selected personnel from operations, training, and emergency preparedness to review the scenario. The scenario was adjusted to reflect conditions that would be plant specific for the operations personne Walkthroughs were conducted with operations representatives from all five shift The individuals were given various simulated conditions to determine their capability to detect and classify an incident. In addition they were to make offsite notifications and protective action recommendations to offsite agencies under simulated incident condition During the walkthroughs, the crews were requested to:
| | New Orleans, Louisiana 70161 Louisiana Power & Light Company |
| * React and respond to specific, simulated indications carrying out (simulate) actions of plant operating, annunciator response, abnormal, and emergency procedure * Classify the evolving plant conditions into one of the four emergency classifications based on the emergency action levels (EAL). | | . ATTN: K. W. Cook, Nuclear Support |
| | | ] and Licensing Manager 142 Delaronde Street New Orleans, Louisiana 70174 i |
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| . : . | | Louisiana Radiation Control Program Director- |
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| | bec to DMB (IE35) i bcc distrib. by RIV: |
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| | RPB D. Weiss, LFMB.(AR-2015) |
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| | j- Resident Inspector . R. D. Martin, RA * |
| * Perform all notification actions to site and offsite persons and agencies (some notifications were performed, some were simulated).
| | Section Chief (RPB/C) DRSP |
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| | ; MIS SYSTEM C. A. Hackney |
| Perform dose assessment calculations and evaluations for a General Emergency classification with no radiological release occurrin * Formulate protective action recommendations based on the dose assessment evaluations for transmittal to offsite authoritie * Crews were requested to use any procedure that would be referred to in an actual emergenc The performance of the crews in the areas mentioned above is detailed below:
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| * Operators were prompt and correct in their selection, application, and utilization of Technical Specifications, annunciator response, and normal /off-normal / emergency operating procedure * Most crews (3 out of 5) did not utilize " Protective Response Areas" when formulating protective action recommendations, but used | |
| "Affected Sectors" (22.5 degree sectors, A, B, C, etc.) in messages transnitted to offsite agencie Specifically,'they were unable to implement paragraph 5.1.2.3 and the succeeding " Note" of tab A.,
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| " Uncontrolled Release of Radioactivity," of EP-2-052, " Protective Action Guidelines." Further, one crew did not :Jnderstand that the
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| "Affected Sectors" are identified as the plume centerline sector and the two adjacent sectors. It was also noted that the initial and followup notification message forms (attachments 7.5 and 7.7 to EP-2-010) addressed only affected sectors and did not make provisions for considering " Protective Response Areas."
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| * Two of five crews were unable to make correct protective action recommendations (PAR) for the conditions of a General Emergency classification with no release occurring. . Most operators were not familiar w~ith attachment 7.5 to EP-2-052, " Protective Action Guidelines." One of five crews formulated the proper PAR, but none would have completed General Emergency notifications with the PAR in a prompt manner. The failure to demonstrate adequate familiarity with the Emergency Plan and procedures is considered a violation of the training requirements of 10 CFR 50.47 (b)(15) (382/8523-01).
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| * A similar emergency action level (EAL) is listed for Alert. In trying to use Attachment 7.1, Tab C, EP-1-001 " Recognition and Classifi-cation of Emergency Conditions," the Shift Supervisor and chemistry personnel had no correlation devices available to permit them to readily determine percentage of failed fuel from observed plant
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| conditions or instrument readings. One Shift Supervisor experienced difficulty in classifying the EAL dealing with failed fuel when
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| | RSTS Operator L. A. Yandell RIV File f |
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| 'provided with reactor coolant sample isotopic analysis result Confusion resulted from being unable to evaluate the " Percentage Failed Fuel" words of the EAL. This situation would have resulted in a non-timely classification of Alert if the shift supervisor had not been prompted by the NRC inspecto :* Operators did not follow or understand all steps of EP-2-050,
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| " Nomogram Procedure" (Manual Dose Assessment), specifically step 2.8;" The Nomogram will only produce values for the Exclusion Area Boundary (EAB), go to attachment 7.3 and use appropriate worksheet. . . If other values are needed out to 2, 5, and 10 miles."
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| This resulted in operators recommending unnecessary evacuation of populations out to 10 miles radius (routinely), when dose rates and integrated doses were Iris than PAG for evacuation at distances much less than 10 miles. Ope.ators did not consider evacuation time estimates and plume travel times when formulating PAR' Based on the reviews and observations above, the following items were discussed with licensee representatives as items which should be considered for improvement of the emergency preparedness program:
| | ________-____________-_-__-_-___ _----____.__-__2_--_--_- _ _ _ _ _ _ _ _ - . _ - _ - _ . _ _ _ _ _ . - - . _ _ . _ _ - - - _ _ - - . _ _ . _ . - - - _ _ - . _ _ _ _ _ _ _ __ |
| * Operating Procedure, OP-500-007, "Annuciator Response for Control Room Cabinet G," did not refer the operator to OP-901-021, "High Activity in Reactor Coolant System," for further action step f
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| * Attachments 7.1 to 7.8 of EP-2-050, "Offsite Dose Assessment," as titled on the book separators were not the same as the title of the procedur * Plant Operating Manual Index, Volume 4, System Operating Procedure Section 10, Annunicator Response Procedures A.- Control Room, list Annunicator responses for control room cabinets A, B, C, et I (procedures numbered similarly) when in fact control room panels are designated and visibly marked as CP-1, CP-4, and et * 'As read meteorological conditions include wind speed in meters per second in the control room, however, manual computational methods employed by the~ control room operators utilize miles per hour wind speed. Having to make the conversion manually caused an error in computation of dose rate at the exclusion area boundary by one of the Crew * Attachment 7.7 to EP-2-010, the followup notification form for Parish, State, and secondary agencies does not contain all the information content of message format guidelines of NUREG-0654, II.E.4.1, specifically projected dose rates and integrated dose at the projected pea .
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| * ' Attachment 7.1, Tab C, EP-1-001,_" Recognition and Classification of Emergency Conditions," under Notification of Unusual Event, Item 4 states, " Fuel damage as indicated by Letdown Activity Hi Alarm, D-1 on CP-4, and verified by isotopic analysis indicating an increase of failed fuel greater than 0.1% in 30 minutes, or failed fuel greater than 1.0%." A similar emergency action level (EAL) was listed for Aler No correlation devices were available to the shift supervisors or chemistry personnel to readily make a determination if EAL had been exceeded based on plant conditions or instrument readings relating to percentages of failed fue ,
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| * " Essential Personnel Emergency Plan Training," attachment 1, to GE-EP-01, " Emergency Plan Training" does not require course instructions in protective action guidelines for the positions of Emergency Coordinator or Senior Reactor Operator (Shift Supervisor is not listed as an essential persor.nel position). Only the health
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| physics coordinator and assistant require course instruction in this topi . Exit Interview The exit interview was held August 9, 1985, at the Waterford 3 SES Administration Building. The exit interview was conducted by Mr. C. A. Hackney, Emergency Preparedness Analyst, with Mr. T. A. Flippo, Mr. W. Jones, the NRC resident inspectors, and Mr. D. Schultz in attendance. The licensee was represented by Mr. R. Barkhurst, Plant Manager, and his staff. The licensee representatives were given a verbal summary of the inspectors findings, observations, and comments. The licensee representative acknowledged the finding __ _ - _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
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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] |
Text
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FEB l 91986
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In Reply Refer To:
Docket: 50-382/85-23
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Louisiana Power & Light Company ATTN: R. S. Leddick, Sr. Vice President Nuclear Operations 142 Delaronde Street New Orleans, Louisiana 70174 Gentlemen:
Thank you for your letter of December 13, 1985, in response to our letter and ano the attached Notice of Violation dated November 14, 198 In response to your comment on the validity of the Notice of Violation, the NRC inspectors determined by observation during the operational walk-through that the two shift supervisors and control room supervisors had not been adequately trained to properly perform emergency response duties; therefore, a violation of the requirement did occur. We have reviewed the corrective actions that you have proposed and find them responsive to the concerns raised in our Notice of Violation. We will review the, implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
Sincerely, f0th;inal signed by;"
J. E. Gagliardo, Chief Reactor Projects Branch cc: (continued on next page)
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