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| | number = ML20247K337 | | | number = ML20196K715 |
| | issue date = 03/24/1989 | | | issue date = 06/28/1988 |
| | title = Ack Receipt of 890306 Supplemental Ltr Responding to Violations Noted in Insp Rept 50-458/88-08 | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/88-08 |
| | author name = Callan L | | | author name = Callan L |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
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| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 8904050228 | | | document report number = NUDOCS 8807070088 |
| | | title reference date = 06-01-1988 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 2 | | | page count = 2 |
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| , . | | JUN 2 81988 In Reply Refer To: |
| , | | Docket: 50-458/88-08 Gulf States Utilities ATTN: Mr. James C. Deddens (RBNG) |
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| | P.O. Box 220 St. Frcncisville, Louisiana 70775 Gentlemen: |
| In Reply Refer To: | | Thank you for your letter of June 1,1988, in response to our letter and |
| Docket: 50-458/88-08 gyg Gulf States Utilities ATTN: Mr. Janes C. Deddens Senior Vice President (RBNG) | | ' |
| P.O. Box 220 St. Francisville, Louisiana 70775 Gentlemen: | | Notice of Violation dated May 2, 1988. We have reviewed your reply and find it 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 |
| Thank you for your letter of March 6,1989, which revised your letter of June 1,1988, in response to our letter and Notice of Violation dated May 2, 1988. 'Je have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions durir.g a future inspection to determine that full compliance has been achieved and vill be maintaine | |
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| Sincerely, Drlgfnal sgrd ny E E / d e S Ye nr7 & 1 L. J. Callan, Director Division of Reactor Projects cc: | | Sincerely, Orldinag signed By |
| Gulf StatesJ Itilities ATTN: J. E. Bc,oker, Manager-River Bend Oversight P.O. Box 2951 Beaumont, Texas 77704 Gulf States Utilities ATTN: Les England, Director Nuclear Licensing - RBNG P.O. Box 220 St. Fra,1cisville, Louisiana 70775 Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director J g | | '3,u. Beach L. J. Callan, Director Division of Reactor Projects cc: |
| RIV:DRP/ CAM C:DRP/Cf 0:DRP3 GLMadsen;df GLConstab LJCallan 3/p/89 3/Ap/89 3/sq/89 hpi | | Gulf States Utilities ATTN; J. E. Booker, Manager-River Bend Oversight P.O. Box 2951 Beaumont, Texas 77704 Gulf States Utilities ATTN: Les England, Director Nuclear Licensing - RBNG P.O. Box 220 St. Francisville, Louisiana 70775 Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director W |
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| | RIV:DRP/C g DRP/Cshy'[ |
| 8904050228 890324
| | J DRPhdM GLMadsen; GLConstabfe LJCallhn |
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| | /,/p7/88 6/p7/88 h/p88 i 9 8807070088 DR 880628 ~ TIJ/ |
| PDR ADOCK 05000458 Q PDC
| | ADOCK 05000458 PDC |
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| I Gulf States Utilities -2-I bectoDMB(IE01)
| | Gulf States Utilities -2-bec to DMB (IE01) |
| bec distrib. by RIV: | | bec distrib. by RIV DRP Resident Inspector R. D. Martin, RA Section Chief (DRP/C) |
| i DRP RRI R. D. Martin, RA SectionChief(DRP/C) !
| | Lisa Shea, RM/ALF MIS System RPSB-DRSS RSTS Operator Project Engineer, DRP/C RIV File W. Paulson, NRR Project Manager DRS G. Sanborn |
| I Lisa Shee, RM/ALF MIS System RPD-DRSS RSTS Operator }
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| Project Engineer, DRP/C RIV File W. Paulson, NRR Project Manager (MS: 13-D-18) DRS I ; | |
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| March 6,1989 RBG- 30250 File Nos. G9.5, G15. $$55$YYlc '
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| U. S. Nuclear Regulatory Commission ,, ,
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| Document Control Desk Washington, D.C. 20555
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| MAR I 3198 i)-[
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| Gentlemen: l River Bend Station - Unit 1 Refer to.: Region IV Docket No. 50-458/ Report 88-08 This letter revises Gulf States Utilities Company's (GSU)
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| response to the Notice of Violation-contained in NRC -Inspection Report No. 50-458/88-0 The inspection was performed by Messr Chamberlain and Jones during the period of February 16 - March 31, 1988 of activities authorized by Operating License NPF-47 for River Bend Station - Unit GSU's revised response to Notice of Violation 8808-01,
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| " Inadequate Alarm Response Procedure", is provided in the enclosed attachment pursuant to 10CFR2.20 Changes to the '
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| original response are noted with sidebars in the right margi This completes GSU's response to this ite .
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| I Sincerel ,
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| J. C. Deddens Senior Vice President
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| g River Bend Nuclear Group i JCD/ /t / K/ ch cc: U. S. Nuclear Regulatory Commission Region IV
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| 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector P. O. Box 1051 St. Francisville-, LA 70775 i
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| UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA )
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| PARISH OF WEST FELICIANA )
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| Docket No. 50-458
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| In the Matter of )
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| GULF STATES UTILITIES COMPANY )
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| (River Bend Station - Unit 1)
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| AFFIDAVIT Deddens, being duly sworn, states that he is a Senior Vice President of Gulf States Utilities Company; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belie I J. C.vU6ddens Subscribed and sworn to before me, a Notary Public in and I
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| for the State and Parish above named, this 6 Y( - day of 7M da;}l , 19 $ Y . My Commission expires with Lif GL +,
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| Claudia F. Hurst l$ W Notary Public in and for West Feliciana Parish, Louisiana
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| ATTACMENT Response to Notice of Violation 50-458/8808-01 REFERENCE:
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| Notice of Violation - Letter from L. J. Callan to J. C. Deddens, dated May 2, 198 INADEQUATE ALARM RESPONSE PROCEDURE:
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| River Bend Station Technical Specifications, paragraph 6.8.1.a. requires that procedures for activities identified in Appendix A of Regulatory Guide 1.33 Revision 2, February 1987 be established, implemented and maintaine Pa ragraph 5 to Regulatory Guide 1.33 requires that alarm annunciator procedures "contain: (1) the meaning of the annunciator, (2) the source of the signal, (3) the immediate action that is to occur automatically, (4) the immediate operator action and (5) the long-range actions."
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| Contrary to the abcVe, it was discovered on March 10, 1988, that the source of the signals defir.ed in alarm response procedure ARP-601-19, "P601-19 Alarm Responses," Revision 2, were incorrect in that the alarm setpoints were incorrectly stated for alarm numbers 2403 and 240 These alarms are for main steam tunnel ambient temperature high and main steam tunnel ventilation differential temperature hig In addition, the immediate and long range actions were inadequate in that actions for alarm 2403 defined the temperature at which the main steam tunnel temperature should be maintained below 180 degrees F rather than the correct value of '130 degrees F. If cooling systems cannot prevent the temperature from approaching the main steam valve isolation setpoints, no additional operator actions were specified to prevent a full main steam line isolation at high reactor power level REASON FOR VIOLATION:
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| The alarms in question are initiated by non-safety related recorders, and thus are not classified as safety related. However, the alarms are designed to alert the operator to high temperature conditions in an area protected by high temperature isolation logic, and are operational aids for that reaso Setpoints are included in the River Bend Station (RBS) alarm response procedures (ARPs) in excess of RG 1.33, " Quality Assurance Program Requirements (0perations)", guidelines as a supplementary source of information for the operator. Thus, the errors cited in the potential violation are considered to have no safety significance as related to the procedur Review of the procedural error, undertaken as immediate corrective action and as discussed with the NRC Senior Resident Inspector, revealed that in the-past the ARP was correct but the setpoint information was changed to incorrect values during one of the revision cycles. Both of the alarms had been actuated for an extended period due to unreasonably low setpoint selection. At the time the ARP errors were discovered, modification request (MRs)85-1154and86-1035 were in process of being worked to raise the Page 1 of 3 e__ . _ _ _ - - - _ _ _ .
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| setpoints of the alarms in question to values within two degrees of the erroneous value Corrective action for the specific errors has been completed and TCNs were issued correcting the inaccurate ARP The root cause of the error is determined to be lack of understanding of the system alarm design details during procedure development. As designed, each
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| leak detection thermowell contains two thermocouple, each identified with i the same mark numbe One thermocouple provided input to the Riley j tempera ture switch, which in turn supplies a trip signal at the isolation setpoint to the trip logic, the isolation alarm, and the meter modul The other thermocouple inputs to the temperature recorder, which actuates the l pre-isolation alarm at a lower setpoint. The ARPs in question listed as the l
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| initiating device both the temperature switch and the temperature recorder l that are fed by the thermocouple with identical mark numbers. The isolation setpoint, rather than the correct pre-isolation setpoint, was listed in the AR Contributing factors to the lack of understanding of the system design details during procedure development is the method of identifying two thermocouple with the identical mark numbe CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND RESULTS ACHIEVED:
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| i A 100% review of thirty-one high temperature leak detection alarms was performe Errors similar to those cited were identified and correcte Thirteen ARPs contained errors based on the same confusion between the temperature switch / temperature recorder as the alarm initiating device. For pre-isolation alarms, when the temperature switch was erroneously included as an initiating device, the temperature switch's setpoint was invariably listed !
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| as the alarm setpoin In some of the thirteen ARPs, pre-isolation alarms erroneously included the automatic, operator, and long term actions appropriate to the isolation alarm In addition, two ARPs were found to
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| contain random setpoint errors. Corrective action for the above deficiencies is complete, and consisted of portions of TCNs 88-0296, 88-0298, 88-0303, and l 88-030 Nine additional alarm deficiencies were detected during the corrective action review that are attributed to design documentation errors. Four alarm windows, for Divisions 1, 2, 3, and 4 turbine shield wall high temperature, l had been installed without the installation of the alarms themselves.
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| ; Corrective action to remove the four alarm windows is work complete via MR j 88-013 Five alarms contained incorrect wording. Three of the five describe the isolation as originating in a specific division, rather~than the correct I origination in either divisio The remaining two incorrectly list the area experiencing the high tempera ture. Corrective action for the five alarm wording deficiencies is included as a portion of MR 88-014 The ARP deficiencies, and the design documentation errors described above, are considered to have no safety significanc Automatic plant responses would have occurred as require Furthermore, the availability of actual area temperature data, and other diverse indications of plant system operations continued to provide the operator with a comprehensive plant statu Page 2 of 3
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| l Information for both elements of each dual element thermocouple originally discovered has been combined into a single loop calibration report (LCR).
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| The instrument loop for each thermocouple was originally addressed by three different LCR The consolidation into a single LCR provides clear identification of the mark numbers, setpoints and trip functions of each ,
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| bi-stable device using the thermocouple as sensors. When operating or !
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| maintenance personnel use the LCR, they will have all of this information summarized in one convenient documen Furthermore, the LCRs are used extensively as reference documents in the preparation of Alarm Response Procedures (ARPs). This consolidation of LCRs will help minimize the possibility of confusion during the preparation of ARPs. It will be obvious in the LCR which alarm is energized by a particular bi-stable devic CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS:
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| Corrective action to prevent reoccurrence will consist of training and required reading for all licensed personnel. The training will consist of a review of leak detection system design drawings and loop calibration report The required reading will consist of the TCNs that corrected the ARP error This corrective action will be complete in September 1988. The two ARPs with random setpoint errors are considered to be isolated human errors, thus no specific corrective action to prevent reoccurrence is addresse Additional corrective action shall consist of a 100% review of ARPs for main control room alarms. The review will be performed in accordance with plant procedure OSP-005, " Operations' Procedure Review and Revision", and will include verification of alarm name, initiating device, setpoint, automatic actions, operator actions, long term actions, possible causes, and references. This review will be complete in March 1989.
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| l Each of the other ARPs containing errors based on the same confusion between the temperature switch / temperature recorder as the alarm initiating device will have its associated LCRs incorporated into a single LCR by September 1, 198 I J
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| DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED:
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| Corrective action will be completed by September 1, 198 l
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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] |
Text
. .
~
~
JUN 2 81988 In Reply Refer To:
Docket: 50-458/88-08 Gulf States Utilities ATTN: Mr. James C. Deddens (RBNG)
P.O. Box 220 St. Frcncisville, Louisiana 70775 Gentlemen:
Thank you for your letter of June 1,1988, in response to our letter and
'
Notice of Violation dated May 2, 1988. We have reviewed your reply and find it 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, Orldinag signed By
'3,u. Beach L. J. Callan, Director Division of Reactor Projects cc:
Gulf States Utilities ATTN; J. E. Booker, Manager-River Bend Oversight P.O. Box 2951 Beaumont, Texas 77704 Gulf States Utilities ATTN: Les England, Director Nuclear Licensing - RBNG P.O. Box 220 St. Francisville, Louisiana 70775 Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director W
RIV:DRP/C g DRP/Cshy'[
J DRPhdM GLMadsen; GLConstabfe LJCallhn
/,/p7/88 6/p7/88 h/p88 i 9 8807070088 DR 880628 ~ TIJ/
ADOCK 05000458 PDC
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Gulf States Utilities -2-bec to DMB (IE01)
bec distrib. by RIV DRP Resident Inspector R. D. Martin, RA Section Chief (DRP/C)
Lisa Shea, RM/ALF MIS System RPSB-DRSS RSTS Operator Project Engineer, DRP/C RIV File W. Paulson, NRR Project Manager DRS G. Sanborn
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