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| {{Adams | | {{Adams |
| | number = ML20153C018 | | | number = ML20247K337 |
| | issue date = 04/29/1988 | | | issue date = 03/24/1989 |
| | title = Insp Rept 50-458/88-08 on 880216-0331.Violation Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings, Status of Facility OL Conditions,Nrc Bulletin 80-70,10CFR21 Repts & Surveillance Test & Maint Observations | | | title = Ack Receipt of 890306 Supplemental Ltr Responding to Violations Noted in Insp Rept 50-458/88-08 |
| | author name = Chamberlain D, Holler E, Jones W | | | author name = Callan L |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Deddens J |
| | addressee affiliation = | | | addressee affiliation = GULF STATES UTILITIES CO. |
| | docket = 05000458 | | | docket = 05000458 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-458-88-08, 50-458-88-8, IEB-80-70, NUDOCS 8805060132 | | | document report number = NUDOCS 8904050228 |
| | package number = ML20153C013
| | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | page count = 2 |
| | page count = 15 | |
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| | In Reply Refer To: |
| | 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: |
| | 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: |
| ' | | 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 |
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| | RIV:DRP/ CAM C:DRP/Cf 0:DRP3 GLMadsen;df GLConstab LJCallan 3/p/89 3/Ap/89 3/sq/89 hpi |
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| | 8904050228 890324 |
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| | PDR ADOCK 05000458 Q PDC |
| APPENDIX B
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| U. S. NUCLEAR REGULATORY COMMISSION
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| ==REGION IV==
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| NRC Inspection Report: 50-458/88-08 Docket: 50-458 Licensee: Gulf States Utilities Company (CSU)
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| P. O. Box 220 St. Francisville, Louisiana 70775 Facility Name: River Bend Station (RBS)
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| Inspection At: River Bend Station, St. Francisville, Louisiana Inspection Conducted: February 16 through March 31, 1988 Inspectors: ,' 88
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| D. D.VChamberlain, Senior Resident Inspector Date Project Section C, Division of Reactor Projects
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| _M o k 3. b W. B. Jones, ResidenthInspector 4hirr Datb '
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| Project Section C, bivision of Reactor Projects Approved:
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| E. J.' Holler, Chief, Project Section C Dite '
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| Division of Reactor Projects 8805060132 880502 PDR ADOCK 05000459 Q DCD
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| -2-Inspection deport
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| ~ Inspection Conducted February 16 through March 31, 1988 (Report 50-458/88-08)
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| Areas Inspected: Routine, uncnnounced inspection of licensee action on previous inspection findings, status of facility operating license conditions, NRC Bulletin 80-70, 10 CFR Part 21 Reports, surveillance test observation, maintenance observation and operational safety verificatio Results: Within the areas inspected, one violation was identified (inadequate alarm response procedure, paragraph 8).
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| DETAILS Persons Contacted
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| * L. Andrews, Director, Nuclear Training W. J. Beck, Supervisor, Reactor Engineering J. E. Booker, Manager, Oversight
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| *E. M. Cargill, Supervisor, Radiation Programs
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| *J. W. Cook, Lead Environmental Analyst, Nuclear Licensing
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| *T. C. Crouse, Manager, Quality Assurance
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| *J. C. Deddens, Senior Vice President, River Bend Nuclear Group
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| *D. R. Derbonne, Assistant Plant Manager, Maintenance
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| *L. A. England, Director, Nuclear Licensing R. W. Frayer, Director, Projects P. E. Freehill, Outage Manager A. O. Fredieu, Supervisor, Operations P. D. Graham, Assistant Plant Manager, Operations J. R. Hamilton, Director, Design Engineering
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| *G. K. Henry, Director, Quality Assurance Operations B. E. Hey, Nuclear Engineer, Design Engineering
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| *G. R. Kimmell, Director, Quality Services R. J. King, Supervisor, Nuclear Licensing A. D. Kowale;uk, Director, Oversight-J. W. Leavines, Director, Field Engineering I. M. Malik, Supervisor, Quality Systems J. H. McQuirter, Licensing Engineer
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| *T. G. Murphy, Supervisor, Planning and Scheduling
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| *V. J. Normand, Supervisor, Administrative Services W. H. Odell, Manager, Administration
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| *T. F. Plunkett, Plant Manager C. A. Rohrmann, Training Systems Coordinator
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| *M. F. Sankovich, Manager, Engineering
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| *J. P. Shippert, Operations Engineer
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| *K. E. Suhrke, Manager, Project Management R. J. Vachon, Senior Compliance Analyst
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| *J. Venable, Assistant Operations Supervisor
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| *T. L. Weir, Director R. G. West, Supervisor, General Maintenance NRC i
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| *E. J. Holler, Chief, Project Section C, Division of Reactor Projects
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| *D. D. Chamberlain, Senior Resident Inspector
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| The NRC inspectors also interviewed additional licensee personnel during !
| | I Gulf States Utilities -2-I bectoDMB(IE01) |
| the inspection perio , t
| | bec distrib. by RIV: |
| * Denotes those persons that attended the exit interview conducted on
| | i DRP RRI R. D. Martin, RA SectionChief(DRP/C) ! |
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| | 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 ; |
| April 6, 198 l
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| ' Licensee Action on Previous Inspection Findings (Closed) Violation (450/8729-01): Failure to follow procedure for -
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| control of locked valve This violation resulted when'a nuclear equipment operator unlocked [
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| and closed a normally locked open valve using the emergency key t without notifying the control room staf The operator was !
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| transferring the control rod drive (CRD) pump suction path from the s
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| condensate storaga tank to the condenser, utilizing the station operating procedure, when he misunderstood the directiens provided and closed the condensate storage tank suction line. The Assistant Plant Manager-Operations issued a memorandum reiterating the licensee's policy for adherence to all procedures and to ensure that !
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| all individuals involved in an evolution understand the task to be performe Station Operating Procedure (50P) SOP-0002, "Control Rod :
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| Drive Hydraulics," was revised to add a caution statement for the transfer of the CRD pump suction path. The remaining SOPS were also !
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| reviewed to detertaine if additional instructions or cautions were ;
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| needed for other plant evolutions. Finally, licensee management ;
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| personnel reviewed the precedures for controlling locked valves with ;
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| each shift crew. The resident inspector attended three of these r discussions and found the review to be adequat (
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| This violation is close l
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| ; f (Closed) Violation (458/8531-01): Failure to identify all valves in
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| ' the valve lineup check sheet, required to conduct the integrated leak
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| The licensee has revised Surveillance Test Procedure STP-057-3703,
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| "Primary Containment Integrated Leak Rate Test," to include the six
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| ; differential pressure instruments and the one motor operated valve . | |
| l that were omitted from the original valve lineup in i L preoperational/ acceptance test procedure 1-PT-57-1. These valves ! | |
| i have been added to the valve lineup in STP-057-3703, utilizing f Temporary Change Notice 87-174 [
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| ! This violation is close :
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| l (Closed) Violation (458/8727-02): Failure to initiate hot work ;
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| This violation involved the failure to secure a valid Hot Work Permit i
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| ! and to establish a designated fire watch for grinding activities on l
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| the Inboard Main Steam Isolation Valve 1821*A0V022B, The Assistant Plant Manager-Maintenance issued Memorandum Number APM-M-87-342 which promulgates the licensee's requirement for adherence to procedure The NRC inspectors have observed similar activities requiring a Hot Work Permit and establishment of a designated fire watch since the issuance of the above memorandum,- No further problems in this area have been identifie This violation is closed, (Closed) Violation (458/8716-01): Failure of followup action by the licensee to assure that specified corrective action for an NRC violation and a deviation had been complete The specified corrective actions have now oeen ccmpleted and verified. The licensee established a task force to review all previously identified corrective actions for NRC findings. Overdue items identified by the task force have all been completed. Field engineering has implemented a work tracking system which includes corrective actions for NRC items. Individual departments have assigned department coordinators to assure prompt attention and high priority to corrective actions for NRC items and other item Monthly trend information is provided to senior managemen The additional tracking and management attention should prevent recurrence of this proble This violation is close (Closed) Violation (458/8720-05): Failure to verify diesel fuel oil properties within 31 days as required by Technical Specification Subsequent verification by the licensee revealed that all required TS fuel oil properties were met. The licensee has entered TS fuel oil analysis requirements in the River Cend Surveillance Test Procedure Tracking Program to prevent future occurrences of this nature. TS training has been completed for the chemistry supervisor and applicable staff member This violation is close (Closed) Unresolved Item (458/8720-07): Two instances of misaligned instrument valves identified by the license Both of these instances of misaligned instrument valves were evaluated by the NRC to determine enforcement action for a subsequent case of misaligned instrument valves. This is documented in NRC Inspection Report 458/8728. Violation 8728-01 was issued for this subsequent case. Licensee corrective actions will be documented in response to this violatio This unresolved item is close __ ___ _
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| | GULF STATES UTELITIES COMPANY |
| 5 (Closed) Violation (458/8724-02): Failure to utilize the proper revision of a surveillance test procedure for daily fire door position check The licensee has performed the surveillance test to the correct procedure and a review of past surveillance tests conducted revealed that no other tests had been conducted to the incorrect revisio Security personnel have received additional training to provide instruction on obtaining the correct procedure. Plant security has also been placed on distribution for procedure changes to the daily fire door position' surveillance tes This violation is closed, (Closed) Violation (458/8724-01): Inadequate 50P for the fuel pool cooling and cleanup syste This procedure allowed a siphen path of the upper fuel pool to be established to the condensate storage tank. The problem was compounded with inadequate controls on anti-siphon device The fuel pool siphon event and licensee corrective actions are fully described in NRC Inspection Report 458/872 The licensee has completed all corrective actions which included drilling redundant anti-siphon holes in the upper and lower fuel storage pool This violation is closed, (Closed) Unresolved Item (458/8640-03): Reactor core isolation cooling (RCIC)/ residual heat removal (RHR) steam lina break instrument setpoin The licensee had experienced problems with water formation in the instrument lines for the RCIC/RHR steam line break instrument. This water formation caused an instrument offset of negative 110 inches of water during RCIC system operation. During the first refueling outage in 1987, the licensee implemented a design modification to correct the problem. Testing conducted during plant startup in 1988 revealed that the water column formation condition has been corrected by the design modificatio This unresolved item is close (Closed) Violation (458/8636-01): Inadequate safety evaluation for a temporary modification to the control building ventilation syste The licensee identified that the safety evaluation for the temporary modification which removed a low air flow trip was inadequate. The evaluation failed to recognize that the automatic start of the redundant division of control building ventilation was also affected under certain conditions. The licensee took immediate action to restore the temporary alterations to the original uesign 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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| l configuration. The licensee also performed an engineering evaluation which verified that manual operator actuation of the redundant system after 20 minutes would have prevented any room temperatures from exceeding the design basis temperatures. A review of other temporary alterations and prompt design changes revealed no other problems with safety evaluations. The temporary alteration program has been discontinued at River Bend. Additional procedural controls and training have been implemented to strengthen the safety evaluation ,
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| process for design modification This violaticn is closed, (Closed) Violation (458/8620-02): Engineering piping and instrument drawing (P&ID) differences between the actual system configuration and procedure ,
| | 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, |
| The licensee has corrected the specific differences identified by the NRC inspector. Additional procedural controls to ensure replacement of vent and drain line pipe caps have been implemented. Locked valve criteria have been examined and consistency with procedures and i drawings have been established. A 100 percent review of 220 P& ids i
| | " Inadequate Alarm Response Procedure", is provided in the enclosed attachment pursuant to 10CFR2.20 Changes to the ' |
| have been completed and any discrepancies identified have been incorporated into design modifications to update the drawing This violation is close ; (Closed) Open Item (458/8040-04): Monitor licensee corrective actions for turning vane failures in ventilation system ductwor The licensee's corrective action for this problem included repair of i cracked dampers and removal of certain dampers of the annulus mixing system. The licensee also inspected other high velocity systems and no other turning vane problems were found. The dampers that were ,
| | original response are noted with sidebars in the right margi This completes GSU's response to this ite . |
| repaired in the annulus mixing system were replaced with a heavy duty ;
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| assembly designed to withstand the inherent high velocity and i turbulent flow conditions of this system. These repairs have performed satisfactorily for about 2 years. Based on the repairs and ,
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| inspections performed to date, the licensee has determined that the i turning vane problems were limited to the initial failures discovered <
| | J. C. Deddens Senior Vice President |
| in the annulus mixirg system. No further corrective actions or !
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| inspections are deeued necessar This open item is close (Closed) Violation (458/8720-06): Failure to include necessary quality assurance (QA) controls in a procurement document for analysis of emergency diesel generator fuel oi The existing vendor supplying laboratory analysis services did not have a program to implement applicable 10 CFR Part 50, Appendix B, requirements for services provided. The licensee has recently
| | 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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| contracted with E. W. Saybolt & Company, Inc. for diesel generator fuel oil analysis. This vendor has recently implemented a QA program which was surveyed and evaluated by Gulf States Utilities. A Contract for services has been released based on this preaward survey '
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| and resolution of outstanding issue This violation is close . Status of Facility License Condition
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| (Closed) License Condition (?.C.7): "Prior to startup following the first refueling outage, GSV shall implement design modifications to improve the capabilities of existing bypassed and inoperable status indication used to -
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| monitor the status of safety-related systems. The specific design changes '
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| to be implemented are identified in a GSU letter dated December 3,1984, j as clarified in a GSU letter dated March 5,1985." 1 The licensee has installed an additional plant alarm panel in the main control room to implement the additional bypass / inoperable status indications defined in USAR Table 7.5-12. This new alarm panel supplemented existing control room alarm These alarm indications were tested and placed in operation following the first refueling outage at River Ben ,
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| i License Condition 2.C.7 is close . Licensee Action on NRC Bulletin 80-70 This area of the inspection was conducted to review licensee actions relative to NRC Bulletin No. 80-70, "Cracking and Failure of Jet Pump Hold I Down Beam Assemblies." The licensee's action on this bulletin was addressed in NRC Inspectior Report 458/85-54, paragraph 4. This bulletin remained open pending issuance of the inservice inspection (ISI) pla '
| | UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA ) |
| The resident inspector reviewed Appendix J of the licensee's ISI Plan issued May 19, 1987. This appendix establishes the frequency for reactor vessel exams which includes the entire jet pump exam, jet pump sensing
| | PARISH OF WEST FELICIANA ) |
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| | Docket No. 50-458 |
| lines, jet pump riser brace, jet pump hold down beam, jet pump bolt and weld assembly, and reactor pressure vessel weld.
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| ; c j This NRC bulletin is closed, i 5. 10 CFR Part 21 Reports i
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| The resident inspector was provided copies of selected 10 CFR Part 21 I reports by NRC Region IV, which may be applicable to equipment or services ,
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| i supplied to River Bend. These reports were provided to the licensee, who verified that the reports either had been or were being evaluated for applicability at River Bend. Any reports that were not already entered into the licensee tracking system were immediately entered. A listing of j reports by date, manufacturer, and subject is provided below:
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| September 16, 1986 - General Electric Company - Potential defect with solenoid valve rebuild kits for control rod drive hydraulic control unit January 19, 1988 - Limitorque Corporation - Improperly sized terminal lugs to motor leads. (Report submitted by Gulf States Utilities)
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| The resident inspector will continue to provide copies of potentially applicable 10 CFR Part 21 reports for licensee evaluation and a followup of licensee action on selected 10 CFR Part 21 reports will be conducted during future NRC inspection No violations or deviations were identified in this area of the inspectio . Surveillance Test Observation During this inspection period, the resident inspector observed the performance of Surveillance Test Procedures STP-505-4503, "RPS/ Control Rod B'ock-APRM Weekly CHFUNCT, Weekly CHCAL (C51*K6050) and 18 Month LSFT,"
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| 6TP-508-4514, "Turbine Stop Valve Closure Monthly CHFUNCT (C71-N006 Channels A thru H," STP-110-0101, "Turbine Overspeed Protection System Weekly Operability Test," STP-051-0201 "RPS-Main Steam Isolation Valve-Closure Monthly CHFUNCT," and STP-509-0101, "Main Turbine Bypass System Valve Cycle Test." The following observations were made during the performances of the above surveillance tests:
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| STP-505-4503 - This surveillance procedure was performed on March 25, 1988, with the reactor in operational condition 1, to satisfy the weekly channel functional tests required by River Bend Station (RBS)
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| Technical Specification (TS) for the reactor protection system (RPS)
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| - average power range monitor (APRM) and control rod block-APRM instrument (CSI-APRM C). The APRMs are required to be operable when the reactor is in operational condition 1, 2, 3, 4 or The instrumentation and control (I & C) technicians obtained permission from the control operating foreman (C0F) prior to initiating this ST Communications were established between the two I&C technicians located at the instrument and the H13-P680 control panel. The at-the-controls (ATC) operator was notified prior to a RPS half-scram being inserted and was immediately notified when the RPS half-scram could be reset. The required jumpers were controlled in accordance with General Maintenance Procedure GMP-042, "Circuit Testing and Lifted Leads and Jumpers." During restoration, a 75 percent indicated power swing was observed on local power range monitor (LPRM) 4-C-30-15. After approximately 10 minutes, the LPRM returned to the expected indicated power. Maintenance Work Request (MWR) 115028 was initiated to investigate the cause for the erratic power swing '
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| * STP-508-4514 - This surveillance procedure was performed on March 26, ,
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| 1988, with the reactor at 79 percent power. This STP is required to I be performed monthly with the reactor in operational condition 1, to meet the TS requirements for channel fuxtional testing of the RPS ,
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| t turbine stop valve closure and the end of cycle recirculation pump t trip system turbine stop salve closure (C71-N006) Channels A !
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| through H. Thissurveillancetestwasperformedinconjunctionwith STP-110-0101, "Turbine Overspeed Protection System Weekly Operability
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| , Test." Direct communications were maintained between the I&C : | | In the Matter of ) |
| technicians and ATC operator to minimize the time the turbine stop valves remained closed. The licensee determined that all the acceptance criteria was met and the test results were properly
| | GULF STATES UTILITIES COMPANY ) |
| ; reviewed by the C0 [
| | (River Bend Station - Unit 1) |
| | 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 |
| | for the State and Parish above named, this 6 Y( - day of 7M da;}l , 19 $ Y . My Commission expires with Lif GL +, |
| | Claudia F. Hurst l$ W Notary Public in and for West Feliciana Parish, Louisiana |
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| STP-110-0101 - This STP was performed on March 26, 1988, with the :
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| reactor at 79 percent thermal power. This surveillance was performed !
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| to test each high pressure turbine stop valve, high pressure turbine !
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| control valve, low pressure turbine intermediate stup valve and low
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| : pressure turbine intercept valve. This surveillance is required to
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| ! be performed every 7 days when the plant is in operational condition 1 or 2 to satisfy TS 4.3.8.2.a. This activity was closely supervised by the shift supervisor and plant parameters were allowed , | |
| to steady out prior to cycling the next valve. The expected RPS !
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| half-scrams were received when the turbine control valves were l cycled. All test acceptance criteria were met and the test results !
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| reviewed and accepted by the C0F, :
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| * STP-509-0101 - This STP was performed on March 26, 1988, with the reactor aT79 percent thermal power. This surveillance test demonstrates the operability of each of the two turbine bypass valves by cycling each valve through one complete cycle. This surveillance must be performed at least once every 7 days with the reactor in !
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| 1 operational condition 1 as specified in TS 4.7.9.a. Full valve '
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| I travel was verified through indication of bypass valve position and a t decrease in megawatt electri'c output. Each valve was observed to ;
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| perform as expecte !
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| STP-051-0201 This surveillance was performed on March 26, 1988, with the reacIor at 79 percent rated thermal power. This monthly STP implements the requirement of TS Section 4.3.1.1 Table 4.3.1.1-1.6 to 4 perform a channel functional test of the RPS main steam line isolation valve (MSIV) closure instrumentation. The MSIVs were tested individually using the slow closure feature. The RPS
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| ; half-scram was observed to actuate prior to the MSIV indicating ,
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| mid position, which actuates at approximately 10 percent closed, as !
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| expecte The MSIV was immediately allowed to reopen once the ,
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| intermediate position was indicated. The ATC operator closely !
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| , monitored main steam line flow instrumentation to ensure that the [
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| MSIV was not traveling fully close Communications were maintained 5etween the ATC operator and the operator during the performaace of *
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| the MSIV channel functional surveillanc No violations or deviations were identified in this area of_the inspectio . Maintenance Observation On March 30, 1988, the licensee placed the Division II diesel generator in the maintenance mode to perform required preventive maintenanc The plant entered a 72 hour limiting condition of operation (LCO) as required by the RBS TS 3.8.1. All of the Division I and III emergency core cooling systems and support systems remained operable during this LC0 perio The ~
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| resident inspector verified that the required clearance had been initiated in accordance with Admini*:rative Procedure ADM-0027,"Protective Tagging."
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| Each of the valves and breakers identified on the clearance (88-0338) were observed to be in their correct positions as specified by the clearance order. After completion of the preventive maintenance activities, the clearance was released and a post-maintenance test performed to verify i diesel generator operability. No problems were identified during the performance of the maintenance activities that could have resulted in the diesel generator not being able to fulfill its safety functio The a following preventive maintenance work activities were observed and/or f maintenance packages reviewed:
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| i P516420 - This maintenance activity involved inspection of the
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| governor linkages for wear and loose parts. The licensee found the j linkage mechanism to be acceptable.
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| P516738 - This maintenance activity involved inspection of the ring oilers. No problems were identified by the licensee during the inspection.
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| P516538 - Lubrication and inspection of fuel oil pump couplin The puap coupling was cleaned, reassembled and greased in accordance with
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| the lubrication manua No problems were identified during the inspectio *
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| P516266 - The starting air manifold was inspected as required by this
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| ; maintenance work orde No problems were identified during the
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| | ATTACMENT Response to Notice of Violation 50-458/8808-01 REFERENCE: |
| | | Notice of Violation - Letter from L. J. Callan to J. C. Deddens, dated May 2, 198 INADEQUATE ALARM RESPONSE PROCEDURE: |
| ; No violations or deviations were identified in this area of the
| | 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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| inspectio I i Operational Safety Verification The resident inspectors observed operational activities throughout the inspection period and closely monitored operational events. Control room activities and conduct were generally observed to be well controlled.
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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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| Proper control room staffing was maintained and access to the control room operational areas was controlled. Selected shift turnover meetings were ;
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| ; observed and it was found that information concerning plant status was l being covered in each of these meetings. System walkdowns of the "B" low pressure coolant injection system and low pressure core spray system were
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| conducted to verify major flow path and proper breaker alignment for ,
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| system operability. Plant tours were conducted, and overall plant cleanliness was good.
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| General radiation protection practices were observed and no problems were noted. Personnel exiting the radiation control area were observed and
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| radiation monitors were being properly utilized to check for '
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| contaminatio Prompt security officer response to door alarms was observed and compensatory posts were established where required. Protected and vital area barriers were found to be intact, t l The resident inspectors also reviewed licensee actions on operational events and potential problems. The results of reviews of selected items i are described below: l Emergency Exercise: The resident inspectors participated in the j licensee conducted emergency exercise on February 24, 198 This
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| exercise included local, state and federal participatio The NRC
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| participation included NRC Region IV management personnel on site and activation of the Region IV emergency response facility. An NRC inspection team was also on site to evaluate the licensee's emergency response capability. The evaluation results are documented in NRC Inspection Report 50-458/88-07. While participating in the exercise, !
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| the resident inspectors monitored the licensee actions to control and i mitigate the consequences of the simulated emergency. These i
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| observations were made in the control room, technical support center, i
| | 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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| and emergency operating facility. Licensee actions were deemed to be 1 controlled and proper to control and siitigate the simulated | |
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| ' Inadvertent Activation of Emergency Sirens: At 7:31 p.m. CST on March 29, 1988, an emergency stren activated in West Feliciana Parish for approximately 3 minutes. The siren activation was caused by
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| lightning striking the siren. The Louisiana Office of Emergency Preparedness and the local radio station were notified of the
| | 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 |
| | | 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: |
| inadvertent siren activation. A message was transmitted over the emergency broadcast system at 7:49 p.m. CST stating that no actual ;
| | 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 |
| emergency existe ; Reactor Shutdown: During this inspection period, the licensee initiated a manual reactor shutdown as required by RBS T5s and !
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| received an automatic reactor scram during the subsequent reactor [
| | 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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| startu These reactor shutdowns are described below:
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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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| Manual Reactor Shutdown Required by TSs: During full power operation on February 19, 1988, the "A" reactor recirculation pump tripped on an over-current condition. Reactor thermal power was reduced to within the limits specified in RBS TS Figure 3.4.1.1-1 within 2 hours and placed in Hot Shutdown :
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| within the subsequent 12 hours. The licensee later determined that moisture had entered the pump motor conduit, which is i located in the drywell, resulting in the indicated ground at the i pump motor. The pump motor cable conduit was subsequently t cleaned and sealed and a reactor startup initiated on [
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| February 21, 198 *
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| Automatic Reactor Scram: During a reactor startup on February 21, 1988, with the reactor at approximately 4 percent thermal power, the reactor scram resulted from a main turbine trip signal. The reactor scram occurred during shell warming of '
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| the main turbine. Turbine first stage pressure was allowed to exceed the equivalent of 40 percent power and with the turbine stop valves closed, an automatic scram was initiated. The licensee has added a caution statement to the turbine shell warming procedure stating that a reactor scram will occur if (
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| turbine first stage pressure is allowed to exceed 40 percent indicated power. However, sufficient guidance was given in '
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| SOPS 50D-0080, "Turbine Generator Operation," Revision 4, to maintain turbine first stage pressure below 173 psig (40 percent power) and thus have prevented this reactor scra Reactor Core Isolation Cooling System: During this inspection period, the licensee experienced three events involving the reactor core isolation cooling (RCIC) system during surveillance testin ;
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| Two of these events involved repositioning of the RCIC suction line '
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| from the condensate storage tank (CST) to the suppression pool. The ;
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| third event involved an isolation of the RCIC system. These three ,
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| events are described below: ,i
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| STP-500-4550 - On March 8,1988, instrumentation and control (I&C) technicians were performing Surveillance Test Procedure STP-500-4550, "RPCS High and Low Power Setpoint Functional Test (C11-N654 A, D, C and D and C11-N655 A and B),"
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| when an unexpected actuation of relay E51-K79 energized, causing the RCIC suction path to transfer from the CST to the suppression pool. Similar occurrences have been identified in Condition Reports 86-1365, 86-1437, 87-0029, 87-0435, 87-0625, !
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| 87-1715, 88-0043, 88-0052, 88-0143 and 88-0218, where spurious transients in Panel H13*P629 have caused trips in Rosemount trip i units. A field review of Panel H13*P629 panel wiring from the !
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| power supply to the rack identified several discrepancies with !
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| the signal ground and chassis ground. Modification ;
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| Request (MR) 88-0118 has been issued to correct the wiring i discrepancies and a log is to be maintained identifying any
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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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| further spurious trips. The above identified panel wiring discrepancies will be an unresolved item pending further review by the NRC inspector (458/8808-02). ,
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| * STP-209-4206 - On March 10, 1988, I&C technicians were - | | 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. |
| performing STP-209-4206, "RCIC-Suppression Pool Water Level High Monthly CHFUNCT, 18 Month CHCAL, 18 Month LSFT (E51-N036A, E51-N636A) " when an incorrect lead was lifted from the adjacent panelspecIfiedintheSTP. This resulted in an unexpected switch of the RCIC '.uction path from the CST to the suppression poo The licensee's corrective actions to preclude reoccurrence will be to require the I&C technicians to give in-shop training on the event and the importance of ensuring actions required by the STP are first considered then correctly performe r STP-207-4538 - On February 23, 1988, during the performance of STP-207-4538, "RCIC Isolation-RCIC Steam Supply Pressure Low Monthly CHFUNCT," a lifted lead was relanded prior to the RCIC isolation being reset. This resulted in a RCIC turbine isolation and turbine tri This CTP had been revised per a temporary change notice (TCN) to identify a new lead to be lifted which is more readily accessible and will still prevent the turbine trip and isolatio Previous isolations have occurred because of shorting leads that were not easily accessibl However, the TCN required the I&C technicians to reland the lead prior to resetting the isolation signa A complete review of other applicable STPs was performed and no other instances where the lead was to be relanded prior to resetting the isolation logic were identified, e. Alarm Response Procedures - On March 10, 1988, the senior resident inspector was notified by the Office of Nu: lear Reactor Regulation that the setpoints given in Alarm Response Procedure [
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| (ARP) ARP-601-19, "P601-19 Alarm Responses," Revision 2, were incorrect for alarms 2403 and 20 9. This discovery was made during a review of a RBS TS change for main steam tunnel temprature isolations. Alarm numbers 2403 and 2409 are for main steam tunnel ambient temperature high and main steam tunnel ventilation differential temperature high. The immediate and long range actions to prevent the main steam isolation valves (MSIVs) from closing on high ambient temperature were reviewed by the resident inspectors, lhe immediate and long range actions were found to be inadequate for alarm 2403. The temperature at which the main steam tunnel ambient temperature should be maintained below was given as 180*F rather than the correct value of 130 F. A MSIV isolation will occur at 135* ;
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| In the event the main steam tunnel cooling systems can not maintain the ambient temperature from approaching the MSIV isolation setpoint, no additional operator actions are specified to prevent a full MSIV isolation. This failure to provide adequate ARPs for high main steam ;
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| l resident inspectors as an apparent violation (458/8808-01). The , | | 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 |
| licensee is presently reviewing the remaining ARPs for correct setpoint values. A condition report will be initiated by the licensee to identify and correct the identified deficiencie . Unresolved Item An unresolved item is an item about which additional information is required in order to determine if it is acceptable, a deviation, or a violation. There is one unresolved item in this repor Paragraph Item N Subject 8 458/8808-02 Panel Wiring Descrepancies I 1 Exit Intervfew An exit interview was conducted with licensee representatives identified i in paragraph 1 of this report. During this interview, the senior resident inspector reviewed the scope and findings of the inspectio t f
| | DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED: |
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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 ML20055D5211990-06-27027 June 1990 Forwards Insp Rept 50-458/90-14 on 900521-22.One self-identified Violation Noted But Not Cited ML20055F1861990-06-27027 June 1990 Forwards Safety Evaluation Accepting Util Proposed Changes Re Scram Accumulator Check Valves 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 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
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In Reply Refer To:
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:
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
Sincerely, Drlgfnal sgrd ny E E / d e S Ye nr7 & 1 L. J. Callan, Director Division of Reactor Projects cc:
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
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GULF STATES UTELITIES COMPANY
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March 6,1989 RBG- 30250 File Nos. G9.5, G15. $$55$YYlc '
U. S. Nuclear Regulatory Commission ,, ,
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)
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,
" Inadequate Alarm Response Procedure", is provided in the enclosed attachment pursuant to 10CFR2.20 Changes to the '
original response are noted with sidebars in the right margi This completes GSU's response to this ite .
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 )
PARISH OF WEST FELICIANA )
Docket No. 50-458
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In the Matter of )
GULF STATES UTILITIES COMPANY )
(River Bend Station - Unit 1)
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
for the State and Parish above named, this 6 Y( - day of 7M da;}l , 19 $ Y . My Commission expires with Lif GL +,
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:
Notice of Violation - Letter from L. J. Callan to J. C. Deddens, dated May 2, 198 INADEQUATE ALARM RESPONSE PROCEDURE:
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."
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:
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
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:
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 !
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.
- 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).
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 ,
bi-stable device using the thermocouple as sensors. When operating or !
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.
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
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED:
Corrective action will be completed by September 1, 198 l
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