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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20058K1871990-12-11011 December 1990
Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl
ML20062F1121990-11-15015 November 1990
Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility
ML20059N5951990-10-0303 October 1990
Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
ML20246L4001989-07-10010 July 1989
Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl
ML20245J7191989-06-20020 June 1989
Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20245J0141989-04-26026 April 1989
Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl
ML20235N0661989-02-21021 February 1989
Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl
ML20235H0521989-02-10010 February 1989
Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl
ML20195H9671988-11-23023 November 1988
Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions
ML20155F4801988-10-0606 October 1988
Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20207F4451988-08-0909 August 1988
Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl
ML20151L8991988-07-28028 July 1988
Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl
ML20150B3271988-07-0606 July 1988
Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans
ML20150C0101988-06-22022 June 1988
Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl
ML20195K0451988-06-16016 June 1988
Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl
ML20154C6511988-05-0909 May 1988
Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl
ML20196J9901988-03-0707 March 1988
Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl
ML20149L5861988-02-16016 February 1988
Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl
ML20149H8331988-02-10010 February 1988
Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl
ML20236W3801987-11-30030 November 1987
Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20239A6721987-09-11011 September 1987
Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl
ML20237K6461987-08-0606 August 1987
Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage
ML20235U3351987-07-14014 July 1987
Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl
ML20215K0041987-06-18018 June 1987
Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl
ML20214L1171987-05-22022 May 1987
Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207S3431987-03-13013 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl
ML20207S1651987-03-13013 March 1987
Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl
ML20207R9701987-03-0909 March 1987
Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl
ML20207Q0871987-01-14014 January 1987
Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl
ML20207N2271987-01-0505 January 1987
Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl
1999-07-29
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20058K1871990-12-11011 December 1990
Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl
ML20062F1121990-11-15015 November 1990
Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility
ML20059N5951990-10-0303 October 1990
Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
ML20246L4001989-07-10010 July 1989
Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl
ML20245J7191989-06-20020 June 1989
Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20245J0141989-04-26026 April 1989
Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl
ML20235N0661989-02-21021 February 1989
Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl
ML20235H0521989-02-10010 February 1989
Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl
ML20195H9671988-11-23023 November 1988
Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions
ML20155F4801988-10-0606 October 1988
Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20207F4451988-08-0909 August 1988
Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl
ML20151L8991988-07-28028 July 1988
Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl
ML20150B3271988-07-0606 July 1988
Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans
ML20150C0101988-06-22022 June 1988
Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl
ML20195K0451988-06-16016 June 1988
Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl
ML20154C6511988-05-0909 May 1988
Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl
ML20196J9901988-03-0707 March 1988
Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl
ML20149L5861988-02-16016 February 1988
Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl
ML20149H8331988-02-10010 February 1988
Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl
ML20236W3801987-11-30030 November 1987
Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20239A6721987-09-11011 September 1987
Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl
ML20237K6461987-08-0606 August 1987
Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage
ML20235U3351987-07-14014 July 1987
Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl
ML20215K0041987-06-18018 June 1987
Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl
ML20214L1171987-05-22022 May 1987
Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207S1651987-03-13013 March 1987
Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl
ML20207S3431987-03-13013 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl
ML20207R9701987-03-0909 March 1987
Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl
ML20207Q0871987-01-14014 January 1987
Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl
ML20207N2271987-01-0505 January 1987
Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl
1999-07-29
[Table view] |
Text
/ ~% UNITED STATES NUCLEAR REGULATORY COMMISSION h WASHINGTON, D. C. 20555
.o February 24, 1986 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station
SUBJECT:
JANUARY 23, 1986, MEETING WITH GPU NUCLEAR CORPORATION (GPUN) TO DISCUSS THE CHANNEL CHECKS FOR OPERABILITY OF THE LOW AND LOW-LOW REACTOR WATER LEVEL INSTRUMENTATION CHANNELS On Thursday, January 23, 1986, a meeting was held at NRC, Bethesda, Maryland, with GPU Nuclear (GPUN), the licensee, to discuss the channel checks for operability of the low and low-low reactor water level instrumentation trip switches, the staff's Safety Evaluation, Reactor Water Level Instrumentation Channel Check, dated November 30, 1985, and the licensee's response to the Safety Evaluation which is due before the commer. cement of the Cycle 11 Refueling (Cycle 11R) outage. The Cycle 11R outage is scheduled to begin in April 1986. Attachment 1 is the list of individuals that attended the meeting.
Attachment 2 is the material handed out by the licensee in the meeting for its presentation. The following is a sumary of the significant items discussed '
and the actions, if any, taken or proposed.
On November 30, 1985, the staff issued Amendment No. 95 to the Provisional Operating License for Oyster Creek. This amendment authorized the revision of the daily channel check for the low and low-low reactor water level instrumentation channels. This amendment was a one-time-only change which ,
was effective only from November 8, 1985, to the restart from the Cycle 11R '
outage. The Safety Evaluation (SE) attached to the amendment requested before the commencement of the Cycle 11R outage (1) a justification of the existing reactor water level instrumentation channels addressing the staff concerns about the revisions to the channel checks for operability of the channels or (2) a statement that a daily channel check of the chant.els will be installed in the Cycle 11R outage. If this amendrent is not changed by a future application, this amendment will revert to the previous requirement of a daily channel check for the channels at the restart from the Cycle 11R outage.
In the SE, the staff also requested the licensee to (1) report promptly any loss of operability of the low and low-low reactor water level instrument-ation channels and (2) provide an additional. level of administrative control to the existing procedures on returning the channels to service which will.
show the switches in the channels communicate with the reactor vessel. It is these switches which, at the low-low or low reactor water level setpoints, actuate to initiate engineered safety features functions. This is discussed in the SE. The additional administrative control, accepted by the staff, 8603040319 DR 860224 ADDCK 05000219 PDR
_- J
was to (1) open the isolation valve between the switch and the upper part of the reactor vessel (reference leg) which results in an indication in the control room of the reactor water level being less than low and low-low water level setpoints and (2) open the isolation valve between the switch and the lower part of the reactor vessel (measurement leg) which clears the above indication. This will be referred to as the communication test er C-test.
The agenda for this meeting was decided to be (1) the discussion of the switch that the licensee declared inoperable on January 21,1986,and(2) the discussion of the licensee's proposal for installing a daily channel check for the switches in the low and low-low reactor water level instrumentation channels.
On Friday, January 17, 1986, normal surveillance was conducted on the low reactor water level instrumentation channel switches. The setpoint for three of these switches was found to be outside the acceptance criteria. The switches were recalibrated, verified to be in comunication with the reactor vessel using the C-test described above and returned to service. Two of these three switches were again surveilled on Monday, January 21, 1986, and the drift in the setpoints were found to be insignificant, however, one switch would not reset during the C-test. The licensee declared this switch inoperable and decided to replace the switch.
The licensee stated that the C-test may have contributed to the failure of the switch to reset. The switch manufacturer had stated to the licensee that the C-test would cause a shift in the setpoint in the conservative direction but this would be temporary and the setpoint would return to its calibrated value. The licensee, however, has also decided to modify the C-test. On '
only the switch that was replaced, two additional valves, as shown in the figure on the next page, were added so that the pressure in the switch can be measured by a pressure gauge which is attached to either of the new valves.
By properly opening and closing the isolation valves, the pressure measured by the gauge would indicate that the switch was in proper comunication with the reactor vessel. The new method was explained to the staff by the licensee and accepted by the staff.
The licensee does not believe the problem with the one swit..; above is generic to the remaining seven switches. The licensee is now planning to install the new valves on the remaining switches as surveillance is required on these switches by the Technical Specifications and return all the switches to service using the modified C-test as described above.
The licensee stated that the switch manufacturer will be at the station site to inspect the inoperable switch to help determine the mode of failure. The results of this inspection will be shared with NRC and may change its position on not doing the surveillance immediately on the remaining seven switches. The licensee stated that it is not planning to proposed a change to the Technical Specification to make the valve modifications to the remaining switches.
VALVE PIPING r,-
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rm.
1I SWITCH jfD(SALVES INSTALLED e
~
. s SIMPLIFIED SCHEMATIC 0F THE LOW AND LOW-LOW REACTOR WATER LEVEL INSTRUMENTATION CHANNEL SWITCHES t l t
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l . .
, .. . .~ - . ..- . . . . .- . - . . - _ .
1
- I i
9 i
For the second part of the meeting, the licensee handed out a chart which is Attachment 2. The September 1985, December 1985 and September 1986 dates in
- the chart reflect 1) before .the low and low-low reactor water level instrument- ;
! ation was modified, 2) after the modifications were completed in the Cycle 10M .
outage and 3) after the new modifications to be discussed here are completed i
in the Cycle 11R outage. The staff issued its evaluation of the modification i of the low and low-low reactor water level instrumentation in-the SE attached i to Amendment No. 91 dated November 19, 1985.
, The chart also contains references to the low-low-low reactor water level,
, high drywell pressure and main steam high flow instrumentation. These ,
instrumentation were not involved in Amendment Nos. 91 and 95.
The licensee discussed the modifications which will provide a channel check for the low and low-low reactor water level instrumentation:
low - install Rosemount transmitters for the four existing RE-05 switches low-low - install permanent differential pressure gauges across the four switches.
These modifications will require rearranging the instrument racks. The licensee stated it is considering doing the modilications with the fuel out of the reactor vessel.
The staff requested the surveillance done to verify communication with the
. reactor vessel for the low-low-low reactor water level instrumentation channels before a channel is returned to service. The staff asked if there j were instrumentation that could backup'the high drywell pressure and main steam high flow instrumentation both of which the licensee may proposed to I delete the daily channel check? The staff stated that in accordance with
- 10 CFR 50.59 any modification which will result in a. change to the Technical ;
Specifications must be submitted to. the staff for its review and approval.
] The staff stated that the licensee does not need to propose a change to Technical Specifications to return the channel check for the low and low-low l reactor water level instrumentation channels to daily. - The channel check for this instrumentation in Amendment No. 95 will automatically revert to a daily channel check at the restart from the Cycle 11R outage. The staff also stated that doing these modifications to these instrumentation without
- fuel in the reactor vessel should not be an unreviewed safety question.
At the end of the meeting, the licensee and the staff discussed the licensee's i proposed change to the Technical Specifications in its letter dated October 11,.
i 1985, for the reactor vessel isolation when the low-low reactor water level i instrumentation is inoperable in the reactor shutdown mode. The licensee i stated that it has decided to submit a new proposed change for reactor
- vessel isolation by April 30, 1986. The other change submitted-in the 4
October 11, 1985, letter resulted in Amendment No. 95 dated November 30, 1985.
l l
l
In summary, the following was agreed to in the meeting:
- 1. The licensee will provide the surveillance that verifies comunication with the reactor vessel for the low-low-low reactor water level instrumentation channels before a channel is returned to service.
- 2. If there is backup instrumentation for the high drywell pressure and main steam high flow instrumentation, deleting the channel check is acceptable to the staff.
- 3. The licensee will infom the NRR Project Manager of the results of the manufacture's inspection of the inoperable switch.
The staff stated that the modifications discussed in the meeting for the low and low-low reactor water level instrumentation in the Cycle 11R outage should be done while the fuel is out of the reactor vessel.
hhBWRk Project
& h., Project Manager idack F. Donohew, Directorate #1 Division of BWR Licensing Attachments:
- 1. List of Attendees
- 2. Licensee's handout cc: R. Bernero R. Houston G. Lainas W. Hodges L. Phillips M. Scrinivasan DISTRIBUTION Docket EJordan NRC PDR BGrimes :
Local PDR JPartlow .)
PD#1 Reading JDonohew i 0 ELD CJamerson l OC File JZwolinski i ACRS(10) 1 DBL DBL:PD#1 JD5 jg JZwolinski 86 t /p /86 7
Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station cc:
G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W. Post Office Box 445 Washington, D.C. 20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 D. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 P. B. Fiedler Vice President & Director Oyster Creek Nuclear Generating Station Post Office box 388 Forked River, New Jersey 08731
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ATTACHMENT 1 i
j MEETING WITH GPU NUCLEAR CORPORATION (GPUN) 4 January 23, 1986 r
NAME ORGANIZATION J. Donohew NRC/NRR/ DBL l M. Laggart GPUN d
A. Agarwal GPUN-i T. Hoatson GPUN 1 J. Rogers GPUN i
j R. Stevens NRC/NRR/ DBL i G. Holahan NRC/NRR/ORAS l R. Scholl, Jr. NRC/NRR/0 RAS W. Hodges NRC/NRR/ DBL 1
l
]
, 1 l
1 J
I l
E AFFECTED TECHNICAL SPECIFICATION INSTRUMENTS 3
- l l l l 1 1 l SEPTEMBER 1985 l DECEMBER 1985 l SEPTEMBER 1986 l
- l -
l l- 1 I l l l l Daily ,
l Daily l l Daily l l Inst. Channel l Type i Dian. Ck. l Type I Chan. Ck. I Type l Chan. Ck. 1 I i l .
l l La Rx Water Level l Yarway l 1/d l SOR ', l RE21A (1) l Rosemount/ Fox l 1/d l'
- l i Indicating I Non-Ind RE21G XMTR/ Analog Trip l l l l l 1 l Lc-Lo Rx Water Level l Yarway 1/d l SOR , RE21A (1) SOR 1/d l l Indicating Non-Ind RE218- W/Ind. Gauges l l l l Ls-Lo-Lo Rx. Water l Barton l N/A l Barton l N/A' SOR (2) l N/A l Non-Indicating
-l Level i Indicating ll Indicating l l
- l l 1 1 I I i !
,1 Hi DW Press (Core l Barton l 1/d l Barton 1/d l SOR l N/A (3) l ll Cos11ng) Indicating Indicating Non-Indicating l
.I ,
1 Main Steam Hi Flow I Barton i 1/d l Barton l 1/d l SOR (4) l N/A (3) l l Indicating l l Indicating l l Non-Indicating I l
.(1) Ttchnical Specification Change Request'#141.
-(2) One Barton Lo-Lo-Lo indicator per header to remain.
(3) Will require Technical Specification change.
(4) One Barton' flow indicator per header to remain.
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