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| {{Adams | | {{Adams |
| | number = ML20148K715 | | | number = ML20239A721 |
| | issue date = 01/19/1988 | | | issue date = 12/21/1987 |
| | title = Discusses 871230 Enforcement Conference Re Findings of Insp Repts 50-498/87-71 & 50-499/87-71 on 871101-30.Meeting Summary Encl.Meeting Beneficial | | | title = Notification of 871230 Enforcement Conference in Arlington, Tx to Discuss Recent Failures to Comply W/Tech Specs as Described in Insp Rept 50-498/87-71 |
| | author name = Callan L | | | author name = Constable G |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = Goldberg J | | | addressee name = |
| | addressee affiliation = HOUSTON LIGHTING & POWER CO. | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | docket = 05000498, 05000499 | | | docket = 05000498 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = EA-87-240, NUDOCS 8801280025 | | | document report number = NUDOCS 8712300048 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE |
| | page count = 17 | | | page count = 2 |
| }} | | }} |
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| In Reply Refer To:
| | and DEC 21 19BT NOTICE OF SIGNIFICANT LICENSEE MEETING Name of Licensee: Houston Lighting and Power Company Name of Facility: South Texas Project, Unit 1 Docket: 50-498 Date and Tine December 30, 1987, at 1:00 of Meeting: |
| Dockets: 50-498 M !O N 50-499 EA 87-240
| | Location of Meeting: Region IV Office, Arlington, Texas Purpose of Meeting: An Enforcement Conference to discuss recent failures to comply with Technical Specification requirements as described in NRC Inspection Report 50-498/87-71 dated December 18, 198 NRC Attendees: R. Martin, Regional Administrator J. Montgomery, Deputy Regional Administrator L. Callan, Director, Division of Reactor Projects A. Beach, Deputy Director, Division of Reactor Projects G. Constable, Chief, Project Section D D. Carpenter, Senior Resident Inspector H. Scott, Enforcement Assistant Licensee Attendees: J. Goldberg, Group Vice President G. Vaughn, Vice President, Nuclear Operations M. Wisenberg, Manager, Nuclear Licensing W. Kinsey, Plant Manager M. McBurnett, Manager, Support Licensing Note: Attendance by NRC personnel at the NRC/ licensee meeting should be made known by 4:00 p.m. on December 28, 1987, via telephone call to G. L. Constable (FTS 728-8151). |
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| Houston Lighting & Power Company ATTN: J. H. Goldberg, Group Vice President, Nuclear P.O. Box 1700 Houston, Texas 77001 Gentlemen: | |
| This refers to the enforcement conference conducted in the NRC Region IV office on December 30, 1987, with you and other members of your staff and Region IV staff members to discuss findings of'the NRC inspection conducted during the period of November 1-30, 1987, which were documented in NRC Inspection Report 50-498/87-71; 50-499/87-71, dated December 18, 198 The topics covered are described in the enclosed meeting summar It is our opinion that this meeting was beneficial and provided a better understanding of the concerns identified during the inspectior In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Roo Should you have any questions concerning this letter, we will be pleased to discuss them with yo
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| Sincerely, Original Signed By L J. Callan L. J. Callan, Director Division of Reactor Projects Enclosure:
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| Meeting Suntnary cc:
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| Houston Lighting & Power Company ATTN: M. Wisenberg, Manager Nuclear Licensing P.O. Box 1700 Houston, Texas 77001 c,b RIV:DRP/D % C:. RP E0 D:DR k HFBundy:gb stable DAP ers LJCallan
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| / //f/88 GL'q88 i/ i / 6 /88 I / ($ /88 -
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| 8801280025 880119 PDR G
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| ADOCK 05000498 PDR
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| Houston Lighting and Power Company 2 Houston Lighting & Power Company ATTN: Gerald E. Vaughn, Vice President Nuclear Operations P.O. Box 1700 Houston, Texas 77001
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| Central Power & Light Company ATTN: R. L. Range /R. P. Verret P.O. Box 2121 '
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| Corpus Christi, Texas 78403 City Public Service Board ATTH: R. J. Costello/M. T. Hardt P.O. Box 1771 San Antonio, Texas 78296 City of Austin ATTN: M. B. Lee /J.-E. Malaski P.O. Box 1088 Austin, Texas 78767-8814 Texas Radiation Control Program Director
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| bec distrib. by RIV:
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| *DRP *RRI-0PS-R. D. Martin, RA *RRI-CONS '
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| Section Chief (DRP/D) RPSB-DRSS
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| *RIV File
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| *Lisa Shea, RM/ALF *RSTS Operator R. Bachmann, 0GC *H. Bundy ,
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| *P. Kadambi, NRR Project Manager *R. Taylor
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| *DRS D. Powers i
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| | Approved By: |
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| | G. L. ConstabTe',~~ChWf~ |
| | Project Section D j |
| | '{ L RI :D D E0 DRP 4 GL nstable:gb DPowers LJCallan i ( ! |
| | (7 /'11/87 |
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| | )1 / 11/87 s2/11/87 W{lY k 0712300048 871221 PDR ADOCK 05000498 |
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| MEETING SUMMARY - DECEMBER 30, 1987 Licensee: Houston Lighting and Power Company (HL&P).
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| Facility: South Texas Project (STP), Units 1 and 2 Dockets: 50-498 Operating License: NPF-71 50-499 Construction Permit: CPPR-128 Subject: Enforcement Conference Concerning NRC Inspection Findings (HRC Inspection Report 50-498/87-71; 50-499/87-71) and Related Concerns On December 30, 1987, representatives of HL&P met with NRC Region IV and NRR personnel in the NRC office in Arlington, Texas to discuss the findings documented in NRC Inspection Report 50-498/87-71; 50-499/87-71, dated December 18, 1987. Other recent events of mutual concern were also discussed. The attendance list and summary of the licensee presentatice are attached. The meeting was held at the request of the NRC, Region I The licensee discussed root causes for selected events, corrective actions taken to preclude recurrence, and results achieved to-dat The NRC staff expressed particular concern regarding the two events discussed below: Plant Entered Mode 4 on October 31, 1987, with High Head Safety Injection (HHSI) System Valves Shut The licensee agreed that this was the most serious of the events selected for discussion. There was no direct safety impact because the reactor core has not been operational and no decay heat was present. Accordingly, the major NRC concern was with regard to the evident weaknesses in the licensee operating practices which allowed this condition to continue for 51 hours prior to discovery. Many operators, supervisors and managers had opportunities to question the off-normal valve positions during this perio Pressurizer Pressure-Low Trip Septpoint Was Set lass Conservatively than Technical Specification (TS) Requirement on November 24, 1987
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| This setpoint error had the effect of rendering all four. channels of the safety injection actuation system inoperable. The staff questioned the efficiency of the licensee's procedure review and approval process in allowing the incorrect setpoint to be inserted in the procedure. This setpoint had been changed as result of engineering analysis by the vendor and HL&P had requested the TS change as a result of this analysis. NRC Inspection Report 50-498/87-27 discussed this change as a followup to HL&P Incident Review Committee Item 333. Also NRC Inspection Report 50-498/
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| 87-39, Open Item 498/8739-10, identified specific TS setpoint errors for annunciators and suggested further verification of instrument setpoint Despite these references and subsequent TS audits performed by the licensee, the setpoint error was not corrected prior to entry into Mode Another concern the NRC staff had was the fact that HL&P in Licensee Event Report (LER) 87-017, dated December 21, 1987, failed to recognize the ;
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| change to Mode 3 with incorrect setpoints as a TS violation. This point was clarified in the meetin . _ ___ __ _ _ ___
| | J. M. Taylor, DEDRO |
| _ _ _ _ _ _ _ _ _ _ . _ . _ _ | | ~ T. E. Murley, D/NRR ' |
| | | F. J. Miraglia, ADP/NRR R. W..Starostecki, ADT/NRR' |
| . | | J. Lieberman, D/0E L. J. Chandler, Asst. GC for En Project Manager, NRR T. O. Martin, DEDRO Staff R. D. Martin, RIV R. E. Hall, RIV J. Gilliland, PAO, RIV ' |
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| | NRC' Attendees |
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| The NRC staff explained to licensee representatives the enforcement polic The licensee was commended for his candor in reporting and discussing the above described event Attachments:
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| A. Enforcement Conference Attendance Outline of HL&P's Presentation
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| Attachment A Enforcement Conference Attendance December 30, 1987 Name Title Organization J. H. Goldberg Group VP Nuclear HL&P G. E. Vaughn VP Nuclear Operations ' 'HL&P W. H. Kinsey Plant Manager, STP HL&P-M. Wisenburg Manager, Engineering & Licensing HL&P M. A. McBurnett Manager, Operations Support HL&P Licensing L. Joe Callan Director, Division of Reactor NRC, RIV Projects J. L. Milhoan Director, Division of Reactor NRC, RIV Safety A. Bill Beach Deputy Director, Division or NRC, RIV Reactor Projects H. L. Scott Enforcement Staff NRC, RIV G. L. Constable Chief, Reactor Projects Section D NRC, RIV-D. M. Hunnicutt Chief, Test Programs Section NRC, RIV M. T. Hardt Director, Nuclear Division City Public Service San Antonio D. R. Carpenter Senior Inspector-STP NRC, RIV H. F. Bundy Project Engineer NRC, RIV N. P. Kadan61 Project Manager NRC, NRR J. 1. Tapia ProjectEngineer(SectionA) NRC, RIV
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| PROJECT
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| NRC ENFORCEMENT CONFERENCE ,
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| i i i ARLINGTON, TEXAS i
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| DECEMBER 30,1987 i i
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| AGENDA
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| e Introduction - J. H. Goldberg e Technical Specification - W. H. Kinsey Violations e Management initiatives - W. H. Kinsey e Questions / Answers
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| EVENT e Plant entered Mode 4 on 10-31-87 with HHSI system valves isolate * Discovered during shift tumover on 11-02-8 e immediately opened Train "B" and "C" valve ROOT CAUSE e Poorly planned evolution. Operations Management in effort to verify plant lineup did not understand procedural relationships and operator performing evolution did not understand "big picture."
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| CORRECTIVE ACTION e Remedial training for operators and management on compliance with procedures, selection of procedures, proper planning and attention to detai * Revise specific involved procedures and review others for similar weaknes O Enhance shift tumover information on status of Safety Related equipmen e Simulator training with emphasis on mode changes and accompanying requirements.
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| EVENT e Plant staff discovered that Reactor Containment Building (RCB)
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| Atmosphere monitor 1-131 channel was not tested in accordance with
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| technical specifications on 09-18-8 e Grab sampling of RCB initiated and the channel tested within 24 hour ROOT CAUSE e Process for review of last minute technical specification changes and incorporation of technical specifications into surveillance procedures was not ngorous. Management relied on responsible individuals to perform last minute changes without verification.
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| e Review technical specification surveillances and LCO numbers, with exception of ESF and RTS setpoints, against surveillances.
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| i e implementation of future technical specification changes will be performed using a detailed process that incorporates independent verification.
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| EVENT e Plant staff discovered Pressurizer Pressure-Low Trip Setpoint was set less conservatively than technical specification requirement on 11-24-8 * Plant conditions required for function never achieve e Instruments recalibrated within 24 hour ROOT CAUSE '
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| e Process for review of last minute technical specification changes and incorporation of technical specifications into surveillance procedures !
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| was not ngorous. Management relied on responsible individuals to perform last minute changes without verificatio CORRECr1VE ACTION e Review Engineered Safety Features and Reactor Trip System setpoints against surveillance procedures to ensure no other items were misse e implementation of future technical specification changes will be ,
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| EVENT e Plant staff discovered that the slave relay contact for train "A" containment spray actuation was not tested on 11-24-8 * Performed test within 24 hour ROOT CAUSE e Superficial review of procedure field change and absence of written interpretation of technical specification requirement CORRECTIVE ACTION e Reviewed trains "B" and "C" to ensure identical error was not mad e Remedial training for I&C Division Supervision on independent verification of procedure changes and on attention to detai _ _ _ _ ________ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _
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| EVENT e Plant staff discovered the 4160 degraded voltage and the degraded voltage coincident with safety injections contacts were not tested on 12-12-8 * Performed tests within 24 hours ROOT CAUSE e Technical preparation and independent review were not rigorou Absence of written interpretation of technical specification requirements.
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| l CORRECTIVE ACTION e Established station policy on relay testin * Performed two independent reviews of al! I&C and electrical surveillance tests for compliance with technical specification _- ___ _ - - _ - _ - - - - - - - _ - - - - - - - - -
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| EVENT e Plant staff discovered both toxic gas monitors out of service on 12-06-8 * Placed control room in recirculation mode and restored monitors to servic ROOT CAUSE e insufficient supervision and training of reactor operator student conducting routine log reading C_ORRECnVE ACTION e Conduct Plant Operations and Chemical Operations staffs crew briefings, stressing importance of conducting thorough indoctrination /tmining for students. Reemphasize responsibility for student action * Reprogram toxic gas monitors such that operators are only required to read computer printouts to perform channel operation check e Review and revise OJT training program for operator round * Review and revise operator logs for channel check recording requirement * Complete technical specification equipment "positive statusing" review.
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| EVEXT e NRC Resident insp'ector informed Plant Manager that, contrary to commitment, "A train Auxiliary Feedwater cross-connect volve was not tagged closed when plant entered mode ROOT CAUSE e Insufficient written guidance and training provided to shift personnel on implementation of "Night Order" assignments.
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| . e Revise "Night Order" administrative procedure and train shift
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| EVENT e Two fire protection dampers were found to be blocked open with electrical tie wraps and wire. These dampers were designed to be held open with fusible link * Fire watches immediately established in affected area ROOT CAUSE o Uakown. Quality assurance records indicate adequate installatio No evidence can be found of maintenance or in situ testing on the affected dampers following installatio CORRECTIVE ACTION e One damper has been restored to full service. Other damper is still inoperative awaiting replacement parts.
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| 't MANAGEMENT INITIATIVES O PLANNED e Executive management briefings with all supervision and management
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| * Additional review of recent plant startup events e increase emphasis on use of simulator for normal evolution training
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| * Peer involvement on personnel error investigations
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| e Root cause determination training for representative Department personnel e Continued high level management involvement in Station Operation
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| / Plan of Day Meetings
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| / Station Problem Reports
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] |
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and DEC 21 19BT NOTICE OF SIGNIFICANT LICENSEE MEETING Name of Licensee: Houston Lighting and Power Company Name of Facility: South Texas Project, Unit 1 Docket: 50-498 Date and Tine December 30, 1987, at 1:00 of Meeting:
Location of Meeting: Region IV Office, Arlington, Texas Purpose of Meeting: An Enforcement Conference to discuss recent failures to comply with Technical Specification requirements as described in NRC Inspection Report 50-498/87-71 dated December 18, 198 NRC Attendees: R. Martin, Regional Administrator J. Montgomery, Deputy Regional Administrator L. Callan, Director, Division of Reactor Projects A. Beach, Deputy Director, Division of Reactor Projects G. Constable, Chief, Project Section D D. Carpenter, Senior Resident Inspector H. Scott, Enforcement Assistant Licensee Attendees: J. Goldberg, Group Vice President G. Vaughn, Vice President, Nuclear Operations M. Wisenberg, Manager, Nuclear Licensing W. Kinsey, Plant Manager M. McBurnett, Manager, Support Licensing Note: Attendance by NRC personnel at the NRC/ licensee meeting should be made known by 4:00 p.m. on December 28, 1987, via telephone call to G. L. Constable (FTS 728-8151).
Approved By:
b/
G. L. ConstabTe',~~ChWf~
Project Section D j
'{ L RI :D D E0 DRP 4 GL nstable:gb DPowers LJCallan i ( !
(7 /'11/87
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)1 / 11/87 s2/11/87 W{lY k 0712300048 871221 PDR ADOCK 05000498
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O DCD _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ _ __
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Distribution:
J. M. Taylor, DEDRO
~ T. E. Murley, D/NRR '
F. J. Miraglia, ADP/NRR R. W..Starostecki, ADT/NRR'
J. Lieberman, D/0E L. J. Chandler, Asst. GC for En Project Manager, NRR T. O. Martin, DEDRO Staff R. D. Martin, RIV R. E. Hall, RIV J. Gilliland, PAO, RIV '
NRC' Attendees
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DMB I
h l
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