RBG-22-740, Responds to Violations Noted in Insp Rept 50-458/85-71. Corrective Actions:All Procedures Identified as Having Calibr Limits Outside Tech Spec Requirements Being Revised to Incorporate Correct Requirements
Responds to Violations Noted in Insp Rept 50-458/85-71. Corrective Actions:All Procedures Identified as Having Calibr Limits Outside Tech Spec Requirements Being Revised to Incorporate Correct Requirements
RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in
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ML20195G312
ML20195G367
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RBG-45035, 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
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 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 Output
ML20196K067
ML20196K685
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ML20196L050
05000458/LER-1999-002-01, 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
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,Encl
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),encl
ML20210E900
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 GL
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RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept
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ML20211C510
IR 05000458/1999007
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 Evaluation
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 Valves
ML20211P412
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 Status
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RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted
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RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp
RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47
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,Encl
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 Required
ML20217J375
RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams
RBG-44783, Provides Entergy Operations,Inc Input as Discussed in Call, for Consideration by NRC in Enforcement Process Re Insp Rept 50-458/98-13
RBG-44787, Informs That Entergy Has Determined That Exemption Request from 10CFR50,App R Should Be Withdrawn.River Bend Is Proceeding to Install Addl Suppression Sys in Fire Area C-16 Consistent with Evaluation
RBG-44795, Forwards Results of GE Reanalysis Rept & Validation of Cycle 8.Mid-cycle Rev 1 to RBS COLR for Cycle 8,which Was Revised According to Results of Reanalysis Is Encl
RBG-44770, Agrees to Participate in Informal Public Hearing Re Ucs Petition Per 10CFR2.206,if Meeting Could Be Held During Wk of 990222,with Exception of 990224.Alternate Time Frame for Date of 990224 Is During Wk of 990301.Addl Info Requested
RBG-44808, Informs That RBS Is Pursuing Power Uprate Project That Would Increase Power Output of Plant.Rbs Is Requesting That Project Be Assigned Tracking Number So RBS & NRC May Meet to Discuss License Amends
RBG-44818, Forwards Revised Page 7 to Rev 13 to River Bend Station Security Training & Qualificaton Plan,Revising Last Sentence of Item 5 (Addition of Barricade to Rifle Course of Fire), Question 2 Change Rationale in 981208 Submittal
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RBG-44785, Forwards Proprietary Rev 1 to NEDC-32549P, Safety Review for RBS Cycle 7 Final Feedwater Temp Reduction (Ffwtr),In Support of Util 980409 LAR 97-16,allowing FFWTR to Extend Fuel Cycle.Proprietary Rept Withheld Per 10CFR2.790
RBG-44829, Forwards Ten Copies of RBS Annual Emergency Plan Info Brochures for 1999,per Administrative Ltr 94-07.Without Encl
ML20203C420
RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition
RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216
RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air
RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check
RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations
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RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed
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RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr
RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl
RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage
RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC
05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1
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RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224
RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl
ML20206N192
RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl
RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in
RBG-45035, 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
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 Output
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 Rept
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05000458/LER-1999-002-01, 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
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,Encl
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),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 GL
RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept
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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 Evaluation
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 Valves
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 Status
ML20211P412
RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted
RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp
RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47
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,Encl
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 Required
RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams
RBG-32507, Forwards Duke Engineering & Svcs,Inc to BC Fichtenkort Re Proposed Crankshaft Insp Variation & Recommends Variation Be Presented to Clearinghouse Members at 900111-12 Meeting
RBG-32509, Provides Updated Status for Corrective Actions Being Taken for Discrepancies Identified in Insp Rept 50-458/89-200. Thirty-six Items identified.Twenty-eight Items Completed. Three of Eight Remaining Items Require Evaluation of Stock
RBG-32511, Forwards Response to Violations Noted in Insp Rept 50-458/89-39.Response Withheld (Ref 10CFR73.21)
RBG-32524, Forwards Marsh & Mclennan Containing Summary of Property Insurance Coverage for Facility,Per 10CFR50.54(w)(2)
RBG-32527, Forwards Results of Ultrasonic Testing Conducted on N4A-2 Feedwater nozzle-to-safe End Weld During mid-cycle Outage at Plant.Circumferential Indication Identified in Buttered Area on Safe End Side of Weld During Second Refueling Outage
RBG-32575, Suppls 890411 Response to Violations Noted in Insp Rept 50-458/86-04.Operations QC Instructed QC Planners & Lead Inspector to Include Hold Point of Electrical Maint Work Request for Category I Electrical Equipment Panels
RBG-32583, Requests Extension Until 900601 to Submit Changes to Facility Tech Specs Re Leak Detection & Inservice Insp Program,Per Generic Ltr 88-01
RBG-32596, Forwards Evaluation of Unsatisfactory Performance by Dhhs Certified Lab Performing Drug Testing
RBG-32597, Submits Supplemental Info Re Util Response to Station Blackout Rule & Advises That Results of Plant Evaluations Demonstrate Ability to Cope W/Station Blackout for Proposed 4 H Duration W/O Reliance on Ac Power Sources
RBG-32662, Forwards Corrected Fitness for Duty Program Rept FFD90-F03, False Negative, Describing Unsatisfactory Test Results by Certified Lab Under Contract to Util.Personnel Info Deleted
RBG-32674, Responds to Violations Noted in Ofc of Investigations Rept 4-88-027,per Enforcement Action 90-043.Corrective Actions: Util Auditing self-screening Contractor Programs to Assure Compliance & Audit Will Be Evaluated for Acceptability
RBG-32706, Discusses Investigation of Effects of Fire Water Flooding Due to Automatic Fire Suppression Sys on Category I Areas of Facility.Only Equipment Potentially Affected Limited to Area of Sprinkler Discharge
RBG-32702, Provides Interim Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Participating in BWR Owners Group Effort for Response
RBG-32704, Forwards Corrected Tech Spec 3/4.2.1, Average Planar Linear Heat Generation Rate, to Support 900330 Application for Amend to License,Removing cycle-specific Parameter Limits from Tech Specs
RBG-32725, Forwards Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey
RBG-32730, Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Facility Does Not Currently Reuse Fuel Channels for Second Bundle Lifetime & Does Not Anticipate Reuse of Fuel Channels in Future
RBG-32748, Comments on SALP Rept 50-458/90-01 for Oct-Dec 1989.Util Increased Security Audit Frequency & Has Used Outside Expertise in Security Mgt to self-identify Needed Improvements or Hardware Deficiencies
RBG-32793, Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants
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RBG-32812, Responds to NRC Re Weaknesses Noted in Insp Rept 50-458/90-06 on 900220-23.Corrective Action:Software in Simulator Changed to Duplicate Software in Control Room & More Training Time on Computers Given to Operators
RBG-32834, Forwards Authorization of Util Board of Directors for Tf Plunkett & Wh Odell to Sign Ltrs to NRC Transmitting Amends to OL or Responses to Insp Repts
RBG-32872, Forwards Rept Re Investigation Involving Unsatisfactory Performance Test Result by Dhhs Certified Lab Under Contract to Util to Perform Drug Screen Testing Under 10CFR26, Fitness-For-Duty Program
RBG-32904, Forwards Rev 12 to Physical Security Plan.Rev Reflects Current Activities of Plant Security Programs.Rev Withheld (Ref 10CFR73.21.)
RBG-32928, Provides Suppl to 890929 Response to Violations Noted in Insp Rept 50-458/89-31.Safety Tagging Administrative Procedure Being Revised to Make Clearance Program Easier to Understand & Follow
RBG-32931, Forwards Addendum to River Bend Station - Unit 1,Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989
RBG-32935, Provides Status of Actions Re Insp Rept 50-458/89-45 Which Dealt W/Dual Coil Solenoid Operated Valves Used to Control MSIVs
RBG-32937, Provides Update to 900125 & 0315 Responses to Insp Rept 50-458/89-200.Util in Process of Performing Retrofit Review of in-stock Items Purchased Between 850101-900101
RBG-32951, Forwards Response to NRC 890731 Request for Addl Info Re Util 890731 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09.Justifications for Use of Proposed Tech Spec 3.0.4 Will Be Submitted Separately
RBG-32952, Forwards Addl Info Re 880930 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09 Requirements Re Preplanned Use of Addl Operating Flexibility
RBG-33012, Forwards Rev 5A to Pump Valve Inservice Testing Plan,For Review.Rev Provides Addl Info & Clarification for Requests for Relief Noted in Rev 5
RBG-33066, Responds to 900509 Request for Addl Info Re 900209 Response to Violations Noted in Insp Rept 50-458/89-41.Procedure Being Developed to Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys
RBG-33100, Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 1990
RBG-33120, Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads
RBG-33114, Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon
RBG-33113, Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License
RBG-33132, Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs
RBG-33143, Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 1990
RBG-33150, Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed
RBG-33196, Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-16
RBG-33294, Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank
RBG-33300, Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting
RBG-33310, Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages
RBG-33372, Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified
RBG-33424, Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 900929
RBG-33460, Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.21
RBG-33450, Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-900301
RBG-33496, Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment
RBG-33466, Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range
RBG-33517, Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed
Region IV Docket No. 50-458/ Report 85-71 This letter responds to the Notice of Violation contained in NRC I&E Inspection Report No. 50-458/85-71.
The inspection was performed by Messrs.
M.
E.
Skow and C. C. Harbuck during the period October 7-11, 1985 of activities authorized by NRC Operating License NPF-40 for River Bend Station Unit No. 1.
Gulf States Utilities Company's (GSU) response to the Notice of Violation 85-71-01,
" Calibration of Instrument Functions Outside of Technical Specification Limits," is provided in the enclosed attachment.
REASON FOR THE VIOLATION Licensee procedures STP-051-4228 (Revision 0) and STP-051-4201 (Revision 3) required that various instrument functions be set "plus or minus" from a specified.value, thus allowing them to be calibrated outside of the Technical Specification limits.
CORRECTIVE ACTIONS AND RESULTS ACHIEVED The failure of surveillance test procedure STP-051-4228 and STP-051-4201 to meet technical specification requirements
~
occurred as a
result of nominal setpoint requirements being misinterpreted by Plant Staff.
The nominal setpoints and error-bands used were the design document values and were identified as nominal values by the design documents.
However, the Technical Specification values have been interpreted to be absolute limits.
The calibration limits indicated in surveillance test procedure STP-051-4228 and STP-051-4201 have been revised per temporary change notice 85-4342 and 85-3985, respectively.
These procedures' are now in full compliance with the technical specification requirements.
CORRECTIVE ACTIONS TAKEN TO AVOID FURTHER VIOLATIONS In addition to the procedures identified during the NRC Inspection, Plant Staff has performed a
review of all surveillance test procedures involving instrument setpoint functions.
As a result of this
review, additional procedures have been identified as deviating from the technical specification setpoint limits.
All the procedures identified as having calibration limits outside of those required by the technical specifications are presently in the process of being revised to incorporate the correct requirements.
The required changes-are being accomplished by procedure revisions and/or the issuance of temporary change notices.
Procedures are being revised as they are performed to reflect the new setpoint, u
4
p.
Page 2 December 4, 1985 RBG- ~22,740 Affected setpoints have been verified to be within maximum allowable limits specified in technical specifications. by reviewing test data or performing channel functional tests.
The technical specification nominal setpoint requirements have been clarified as a
result of meetings' held among Plant Staff Management and members of' the NRC Staff during the recent inspection in which the subject violation was identified.
The corrective actions discussed above have also been established to prevent further violation of technical specification requirements.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED All of.the surveillance test procedures identified as allowing instruments to be calibrated outside of the technical specification requirements shall be corrected by April 1, 1986.
UNITED STATES OF AMERICA NUCLEAR REGULATORY CO MISSION STATE OF LOUISIANA PARISH OF WEST FELICIANA-In the Matter of I
Docket Nos. 50-458 50-459 CULF STATES UTILITIES COMPANY (River Bend Station, Unit 1)
Deddens, being duly sworn, states that he is a 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 belief.
J. C. Ddddens Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this day of P/w b e r, 19 b l.
1ul bIciIU w
foanW.Middlebrooksq M otary Public in and for West Feliciana Parish, Louisiana My Commission is for Life.