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| {{Adams | | {{Adams |
| | number = ML20136G505 | | | number = ML20140A833 |
| | issue date = 11/01/1985 | | | issue date = 03/07/1986 |
| | title = Insp Rept 50-458/85-71 on 851007-11.Violation Noted: Procedures STP-051-4228 & STP-051-4201 Permitted Trip Setpoint to Be Calibr Outside Tech Spec Limits | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/85-71.No Addl Response Requested Per 860221 Telcon W/Reed.Violation Addressed Separately |
| | author name = Harbuck C, Jaudon J, Skow M | | | 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 = Cahill W |
| | addressee affiliation = | | | addressee affiliation = GULF STATES UTILITIES CO. |
| | docket = 05000458 | | | docket = 05000458 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-458-85-71, NUDOCS 8511220374 | | | document report number = NUDOCS 8603210239 |
| | package number = ML20136G493 | | | title reference date = 12-04-1985 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | package number = ML20140A839 |
| | page count = 4 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | | page count = 1 |
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| | y~ MAR 0 7.1988 pr . |
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| | , f, In Reply Refer ~To:7 ; |
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| | ; Docket: ;50-458/85-71' s - |
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| | -Gulf' States Utilities- |
| | -ATTN:. William J.?Cahill, J . |
| | . Senior-Vice President 4 |
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| | . River Bend Nuclear Group P. 0. Box 2951-4 Beaumont, Texas' 777.0 , |
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| | : Gentlemen: U |
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| | J Thank you for your letter of December 4,1985~,-in response to our letter and Notice of. Violation dated November 5, 1985. We' have reviewed your reply and - |
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| | found it responsive to the concerns raised in our. Notice of Violation,excep that it did not adequately address.the reason for the-violation. Since the reason for this violation has been addressed separately as confirmed in a telephone.. call with your'Mr. Reed .on February 21,'1986,~ no additional response- |
| ' | | -is requested. We;will review the implementation of your. corrective actions during a future inspection to determine that full compliance'has been achieved , |
| APPENDIX B
| | and will be. maintaine . , |
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| U.S. NUCLEAR REGULATORY COMMISSION
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| ==REGION IV==
| | Sincerely, |
| NRC Inspection Report: 50-458/85-71 Docket: 50-458 License: NPF-40 Licensee: Gulf States Utilities P. O. Box 2951 Beaumont, Texas 77704 Facility Name: River Bend Station Inspection At: St. Francisville, Louisiana Inspection Conducted: October 7-11, 1985 Inspectors: /0/Jo/F.5" M. E. Skow, Project Engineer, Project Da'te '
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| Section A, Reactor Projects Branch (pars. 2, 3, 4, 5)
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| J .jarfuck, Project 7ngineer, Project Date w Section A, Reactor Projects Branch (pars. 3)
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| : Approved: , A M /[ f
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| .(Jaupon, Chief,'ProjectSectionA, Date Rea& tor Projects Branch w
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| Inspection Summary Inspection Conducted October 7-11, 1985 (Report 50-458/85-71)
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| . Areas Inspected: Routine, unannounced inspect 1on of various open items and license conditions for follow-up for possible closur The inspection involved 58 inspector-hours onsite by two NRC inspector Results: Within the areas inspected, one violation was identified (and is-discussed in paragraph 3). | | Crig!:u' S!3ned By J. E. Gagliardo ' |
| | | J. E. Gagliardo, Chief |
| 8511220374 851105 PDR ADOCK 05000458 G PDR
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| | Reactor Projects Branch |
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| | Gulf States Utilities |
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| | -ATTN: J. E.. Booker, Manager-Engineering, Nuclear Fuels & Licensing c- |
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| | .P. O. Box 2951' |
| DETAILS Persons Contacted Gulf States Utilities
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| *J. Deddens, Vice President, River Bend-Nuclear Group
| | 3 Beaumont, Texas 77704 i Lou'isiana State University, Government Documents Department Louisiana Radiation Control Program Director bec distrib. by'RIV: |
| *D. R. Gipson, Assistant Plant Manager
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| *A. D. Kowalczuk, Assistant Plant Manager
| | DRSP Resident' spector R. D. Martin, RA Section of(RPB/A)' D. Weiss, LFMB (AR-2015) |
| *T. C. Crouse, QA Manager
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| *P. E. Freehill, Superintendent
| | RSTS 0 er or R&SP RIV F' |
| *E. R. Grant, Licensing | | 'RIV: ByA RPB- } |
| *E. R. Oswood, QA Engineer | | ton /1k JEGagl- a do JPJap/86- '5/6/p |
| * V. King, Plant Services Supervisor H. M. McClellan, Compliance Group B. E. Hey, Licensing S. R. Radebaugh, Superirtendent A. O. Fredien, Operations J. E. Spivey, Operations QA Engineer P. D. Graham, Assistant Plant Manager R. Kosmala, Technical Staff Engineer Others D. Hill, Stone & Webster, Staff Specialist H. E. Stubbs, Stone & Webster, Supervisor Field QC 0. V. B. Rice, GE, Technical Staff Engineer | | /g 0-9603210239Bh00450 PDR ADOCK O PDR |
| * Denotes those present at exit interview Technical Specifications and Implementing Procedures The objective of this follow-up inspection to the NRC inspection conducted April 19 through May 3, 1985 (NRC Inspection Report 50-458/85-35), was to determine whether the Technical Specifications (TS)
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| will be properly implemented through the approved facility procedures.
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| ; The NRC inspectors reviewed the specific inspection findings documented l on the data sheets attached to NRC Inspection Report 50-458/85-35 that were left open and renumbered in NRC Inspection Report 50-458/85-58 as open items 8558-01 through 8558-24. The NRC inspectors reviewed the procedures for adequacy and to ensure the specific issues identified in the Data Sheets had been resolved. As a result of this review, the NRC inspectors considered the following items CLOSED:
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| 8558-01, 8558-03, 8558-07, and 8558-09 through 8558-2 ~
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| -3- Previously Identified Open Items (Closed) Open Items 8558-25 and 8558-27: Changes have been made to
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| ! STP-051-4201, Revision 3, to reflect changes in the TS. However, both STP-051-4201 and STP-051-4228, Revision 0 have set points with a tolerance specified arcund the set points. The TS list the set points as a limit, using the notation 2 (greater than cr equal to) in some cases or s (less than or equal to) in other case Although there had apparently been no calibrations conducted outside of
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| ' Technical Specifications, this situation allows the aossibility that, should the trip point be found to exceed the " allowable value" of the TS and thus require resetting, the reset trip point could be set within the tolerance band of the procedure but not within the " trip setpoint" liniit of the TS. This is is an apparent violation (8571-01). Open Items 8558-25 and 8558-27 are close (Closed) Open Item (8563-02): Review of Revision 1 to startup procedure ST-14 " Reactor Core Isolation Cooling." This item was open because of the many changes being made to this procedure by the licensee. The f4RC inspector reviewed a draft copy of Revision 1 and determined that it appeared to meet all FSAR test cornitments and wculd provide for adequate testing of the RCIC system. This item is Close (Closed) Open Item (8554-01): Control Room E&DCR files and drawings used for training of control room operator This item was open to track a licensee commitment to conduct uscage familiarization training for licensed control room operators on the E8DCR files and system drawings in the control room. The fiRC inspector verified that of the persons designated to be trained to meet this cornitment, all 9 shift supervisors, all 9 shif t foremen, and 18 out of 21 fluclear Control Operators (fiC0s) had received this training. The 3 remaining NCOs had not received this training because administrative reason It appeared that they would be trained prior to initial criticality. The NRC inspectors concluded that GSU appeared to have met their commitment. This itcm is Close . IE Bulletins IE Bulletin fio. 83-03, " Check Valve Failures in Rcw 1:cter Cooling Systems of Diesel Generators." This bulletin required licensees to ensure certain check valves were tested not only in the fon<ard ficw conditions, but also in a means to ensure internal integrity of the valve. STP-256-3301 and STP-256-3302, Division I and II Standby Service Water Valve Operability Tests, test the check valves in the standby service water lires to the diesel generators. The valves are tested with both forward flow and back flow means. These are also routinely checked surveillance tests. This item is Close *
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| 5.- Licensee Identified Construction Deficiency Review This area of inspection was conducted to review action taken on the following licensee identified construction deficienc (Closed) Deficiency P. port'DR-313: "E :essive Temperature in Excitation Cabinets" .
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| e Initial NRC notification date: June 7, 1985 e Final report: GSU letter RBG-21453 of July 3,1985
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| .The corrective action for this reportable deficiency was to provide a source of ventilation to the subject panels, procure necessary material, and implement the required modification. .A review of documentation by the NRC inspector revealed that all activities related to this modification had been completed. This item is Close . Exit Interview An exit interview was held on October 11, 1985, with the Mr. Deddens and other. personnel as denoted in paragraph 1 of this report. The NRC senior resident inspector also attended this meeting. At the meeting, the scope of the inspection and findings were summarize .
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl 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) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation 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 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation 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 ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 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 ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G5771990-11-23023 November 1990 Forwards Insp Rept 50-458/90-31 on 901105-09.No Violations or Deviations Noted IR 05000458/19900151990-11-21021 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/90-15 ML20062E4031990-11-15015 November 1990 Discusses Util Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers ML20058H5481990-11-14014 November 1990 Informs That Util 900529 Changes to Physical Security Plan Unacceptable Under Provisions of 10CFR50.54.Proposed Changes Decrease Effectiveness of Physical Security Plan ML20217A3511990-11-0909 November 1990 Forwards Insp Rept 50-458/90-25 on 900924-28 & 1015-19. Violation Noted But Not Cited ML20058D0401990-10-29029 October 1990 Forwards Physical Security Insp Rept 50-458/90-24 on 900910-14. Violations Not Cited Per 10CFR2 IR 05000458/19900161990-10-20020 October 1990 Ack Receipt of 900830 & 1011 Ltrs Responding to 900730 Notice of Deviation & 900907 & 22 Telcons,Per Insp Rept 50-458/90-16 ML20058B0131990-10-19019 October 1990 Forwards Insp Rept 50-458/90-28 on 901009-12.No Violations or Deviations Noted ML20058D9531990-10-18018 October 1990 Forwards Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams Scheduled for 901114 ML20058A5421990-10-17017 October 1990 Forwards Insp Rept 50-458/90-23 on 900910-14.No Violations or Deviations Noted ML20058A2191990-10-11011 October 1990 Forwards Summary of 900917 Mgt Meeting at Licensee Site Re Activities Conducted Under License NPF-47 IR 05000458/19900021990-10-0808 October 1990 Ack Receipt of Re Violations Noted in Insp Rept 50-458/90-02 ML20059N4721990-10-0303 October 1990 Forwards Insp Rept 50-458/90-22 on 900827-31.No Violations or Deviations Noted ML20059D6411990-08-29029 August 1990 Forwards Insp Rept 50-458/90-15 on 900611-15.No Violations or Deviations Noted ML20056B2461990-08-22022 August 1990 Forwards Insp Rept 50-458/90-20 on 900723-26.No Violations or Deviations Noted.However,Inability to Acquire & Retain Seasoned Instructors W/Substantial Operations Experience Apparently Affecting Quality of Operator Training IR 05000458/19900061990-08-21021 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Weaknesses Noted in Insp Rept 50-458/90-06 ML20056B2921990-08-14014 August 1990 Requests Submittal of Final Analysis of Combustible Gas Control Sys,Per 10CFR50.44,by 910301,addressing Key Elements in Encl SER IR 05000458/19892001990-08-0909 August 1990 Discusses Insp Rept 50-458/89-200 on 891023-27 & 1113-17 & Forwards Notice of Violation ML20056A7521990-08-0303 August 1990 Discusses Util 891220 Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance. Util Schedule for Completing Phase I of motor-operated Valve Program in Four Refueling Outages Acceptable ML20056A7681990-08-0202 August 1990 Ack Withdrawal of Proposed Amend to License NPF-47,allowing One Loop of RHR to Be Used for ECCS & for Shutdown Cooling. Util Resubmittal of Proposed Amend Following Completion of Generic Study Recommended ML20058L5361990-08-0101 August 1990 Forwards Electrical Distribution Sys Functional Insp Rept 50-458/90-200 on 900521-0622 & Notice of Violation ML20055G5241990-07-18018 July 1990 Forwards Fr Notice Re Util Withdrawal of 900202 Amend to License NPF-47,per .Amend Modifies Tech Specs Re Div I & II Diesel Generator Crankshaft Insp Scheduling & Surveillance Requirements IR 05000458/19900411990-07-0505 July 1990 Ack Receipt of 900614 & 0209 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/90-41 ML20055F1861990-06-27027 June 1990 Forwards Safety Evaluation Accepting Util Proposed Changes Re Scram Accumulator Check Valves ML20055D5211990-06-27027 June 1990 Forwards Insp Rept 50-458/90-14 on 900521-22.One self-identified Violation Noted But Not Cited ML20055D0981990-06-25025 June 1990 Reviews Util 900406 Response to Violation Noted in Investigation Rept 50-458/90-43 Re Unescorted Access for Two Welding Svcs,Inc Employees to Plant Protected Area. Violation Properly Classified as Severity Level IV ML20055D6581990-06-20020 June 1990 Ack Receipt of 900531 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-31 ML20059M9441990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055D0021990-06-11011 June 1990 Discusses Util 900514 Application for Amend to License NPF-47,increasing Suppression Pool Temp from 95 F to 100 F. Requests That Util Demonstrate Applicability of Items Addressed in Encl Hatch Safety Evaluation to Facility ML20055C3071990-02-23023 February 1990 Advises That 891027 Changes to Emergency Plan,Acceptable ML20248A3051989-09-26026 September 1989 Forwards Insp Rept 50-458/89-33 on 890801-31.No Violations or Deviations Noted ML20247Q7221989-09-22022 September 1989 Forwards FEMA Exercise Evaluation Rept of Plant Emergency Preparedness Exercise on 890301.No Deficiencies Observed During Exercise.W/O Encl ML20248E5681989-09-21021 September 1989 Forwards Amend 3 to Indemnity Agreement B-104,reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance ML20247P4951989-09-19019 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-28 IR 05000458/19890181989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-18 ML20247D4661989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-27. Understands That Comparison of Expanded Unreviewed Safety Question Committee Data Base Will Be Reviewed by Committee ML20247B0381989-09-0101 September 1989 Forwards Insp Rept 50-458/89-31 on 890701-31 & Notice of Violation ML20247C3081989-09-0101 September 1989 Summarizes 890822 Meeting W/Util in Region IV Ofc to Discuss Results of INPO Evaluation of Facility.List of Attendees Encl ML20247A1241989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.No plant-specific Issues Discussed at Meeting. Agenda & Attendees List Also Encl ML20247A6751989-08-28028 August 1989 Advises That 890424 Rev 3 to ODCM Acceptable,Per Encl Eg&G Idaho,Inc Comments.Remaining Questions Re Rev 3 in Encl Should Be Considered in Next Rev ML20246J0751989-08-21021 August 1989 Forwards Insp Rept 50-458/89-30 on 890619-23.Violation Noted ML20245H6631989-08-0707 August 1989 Forwards Insp Rept 50-458/89-32 on 890717-21.No Violations or Deviations Noted ML20245K0101989-08-0606 August 1989 Forwards Summary of 890727 Meeting W/Licensee in Region IV Ofc Re Plant Security Enhancement Program & Personnel Changes ML20247N7601989-07-31031 July 1989 Informs That 890719 Request for Withdrawal of Proposed Tech Specs 3.5.2,3.7.1.1,3.7.1.2 & 3.9.11.1 Changes,Submitted by Ltr W/Other Proposed Changes,Approved.No Addl Work Will Be Performed by NRC ML20247R2641989-07-28028 July 1989 Forwards Insp Rept 50-458/89-28 on 890601-30 & Notice of Violation.Notice of Violation Will Not Be Issued for Item Identified by Licensee ML20247M2581989-07-27027 July 1989 Forwards Insp Rept 50-458/89-25 on 890710-14.No Violations or Deviations Noted ML20247H4611989-07-26026 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 50-458/89-11 ML20247N6181989-07-24024 July 1989 Forwards Info Re Requirements for Licensing Exams Scheduled During Wk of 891016.Requests That Ref Matl Listed in Encl Be Furnished by 890816 ML20247E7501989-07-21021 July 1989 Discusses Insp Rept 50-458/89-18 on 890501-05 & 15-19 & Forwards Notice of Violation ML20247L3201989-07-18018 July 1989 Forwards Insp Rept 50-458/89-29 on 890619-23.No Violations or Deviations Noted 1990-08-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation 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 ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 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 ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations ML20195G3121999-06-0909 June 1999 Ack Receipt of Re Changes to River Bend Station Emergency Plan,Rev 19.No Violations of 10CFR50.47(b) Were Identified ML20195G3671999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981016,which Transmitted River Bend Station Emergency Plan,Rev 18 Under Provision of 10CFR50, App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D6041999-06-0303 June 1999 Discusses EOI Request That Attachment 4,NEDC-32549P, Safety Review for River Bend Station Cycle 7 Final Feedwater Temp Reduction, Rev 0,be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20206U4321999-05-18018 May 1999 Forwards Notice of Withdrawal of Licensee 961106 Request for Approval of Deviation from Approved Fire Protection Program to Extent Program Incorporated Technical Requirements of Section III.G.2 of App R to 10CFR50 ML20206U6081999-05-18018 May 1999 Forwards Insp Rept 50-458/99-03 on 990307-0417.Eight Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20207A8051999-05-15015 May 1999 Forwards Insp Rept 50-458/99-06 on 990419-23.No Violations Noted.Inservice Insp Activities at River Bend Station Were Being Implemented in Accordance with ASME Code & Regulatory Requirements ML20206N7081999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206N8811999-05-12012 May 1999 Forwards Notice of Withdrawal of 981120 Amend Request for License NPF-47.Proposed Amend Would Have Established New TS 3.10.9, Control Rod Pattern - Cycle 8, Added to Section 3.10, Special Operations ML20206H9191999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operators Licensing Exam.Facility Did Not Participate in Exam,However Copy of Master Exam with Key Encl.Without Encl NUREG-1434, Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-2261999-05-0505 May 1999 Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-226 ML20206J2291999-05-0303 May 1999 Discusses Responding to NOV Issued on 990105.NOV Was Based on NRC Conclusions That Licensee Provided NRC Inspector with Info Licensee Knew Was Inaccurate & Incomplete ML20206E6381999-05-0303 May 1999 Ack Receipt of 990305,990315 & s Responding to NOV & Proposed Imposition of Civil Penalty, .EOI Paid Civil Penalty & Requested Withdrawal of NOV & Civil Penalty for Reasons Stated.Finds NOV & Civil Penalty Appropriate ML20206E4531999-04-27027 April 1999 Discusses Request That Attachment 4, Final Calculation of RBS Cycle 9 SLMCPR (Safety Limit for Mcpr), Submitted with 981216 License Amend Request,Be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20206A2031999-04-21021 April 1999 Discusses EOI Second 10-year IST Program for River Bend Station Submitted on 980106 & 980910 Which Included One Pump Relief Request & Two Valve Relief Requests.Forwards SE Authorizing Pump Relief Request & One Valve Relief Request 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 ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K0681999-04-0505 April 1999 Submits Summary of 990325 Meeting Re Engineering Performance at Site & Assessment of Organization Strengths & Opportunities for Improvement.List of Attendees & Matl Used in Presentation Enclosed ML20205A4531999-03-26026 March 1999 Forwards Insp Rept 50-458/98-10 on 990222-26.Violation Noted & Being Treated as Non-Cited Violation.Concludes That Radiation Work Permit Program Poorly Implemented Until July 1998 Because of Inadequate Program Implementing Procedures ML20205D7691999-03-26026 March 1999 Forwards Insp Rept 50-458/99-02 on 990124-0306.One Violation Identified & Being Treated as non-cited Violation.Licensee Conduct of Activities During Insp Generally Characterized by safety-conscious Operations & Sound Engineering ML20205D5361999-03-26026 March 1999 Forwards Ser,Accepting Util 980107 Request for Alternative to Augmented Reactor Pressure Vessel Exam Requirements for Plant,Unit 1 Pursuant to 10CFR50.55a(g)(6)(ii)(A) for First 10-year Insp Interval.Technical Ltr Rept Also Encl ML20204G8081999-03-24024 March 1999 Refers to 990303 Reply to NRC NOV & Proposed Imposition of Civil Penalty .Since Licensee Paid Civil Penalty & C/A Found Responsive to NRC Concerns,Matter Considered Closed ML20205A4021999-03-23023 March 1999 Forwards Insp Rept 50-458/99-301 on 990222-0303.No Violations Noted.Insp Included Evaluation of Three Applicants for Senior Operator Upgrade & for Senior Operator Instant & Eight Applicants for Reactor Operator License ML20205F3131999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from River Bend PPR Review,Which Was Completed on 990211.Performance of River Bend Staff During Assessment Period Was Acceptable 1999-09-09
[Table view] |
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-ATTN:. William J.?Cahill, J .
. Senior-Vice President 4
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. River Bend Nuclear Group P. 0. Box 2951-4 Beaumont, Texas' 777.0 ,
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- Gentlemen: U
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J Thank you for your letter of December 4,1985~,-in response to our letter and Notice of. Violation dated November 5, 1985. We' have reviewed your reply and -
.
found it responsive to the concerns raised in our. Notice of Violation,excep that it did not adequately address.the reason for the-violation. Since the reason for this violation has been addressed separately as confirmed in a telephone.. call with your'Mr. Reed .on February 21,'1986,~ no additional response-
-is requested. 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,
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Crig!:u' S!3ned By J. E. Gagliardo '
J. E. Gagliardo, Chief
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Reactor Projects Branch
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Gulf States Utilities
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-ATTN: J. E.. Booker, Manager-Engineering, Nuclear Fuels & Licensing c-
.P. O. Box 2951'
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3 Beaumont, Texas 77704 i Lou'isiana State University, Government Documents Department Louisiana Radiation Control Program Director bec distrib. by'RIV:
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