|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20059J0261994-01-24024 January 1994
Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059H9941993-11-0808 November 1993
Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20128C9371993-01-14014 January 1993
Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20246E1531989-08-16016 August 1989
Summary of 890727 Meeting W/Util,Nus Corp,Conner & Wetterhahn,Bechtel,Bnl & State of PA in Rockville,Md Re Severe Accident Issues.Licensee Presented Info Re Comparison of Core Damage for Accident Classes in PRA
ML20247R6001989-05-15015 May 1989
Summary of ACRS Subcommittee on Limerick Unit 2 Meeting on 890425 in Philadelphia,Pa Re Application for Ol.Statement of Limerick Ecology Action Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20206E3591988-11-10010 November 1988
Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program
ML20205P3121988-10-26026 October 1988
Summary of Operating Reactors Events Meeting 88-42 on 881025 Re Reactor Scrams.Three Significant Events Identified for Input to NRC Performance Indicator Program.List of Attendees Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams 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
ML20206B0521987-04-0606 April 1987
Summary of 870115 Meeting W/Util in Bethesda,Md Re ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Classes 1,2 & 3 Piping Sections,Section Iii,Div 1. List of Attendees Encl
ML20205E7821987-03-25025 March 1987
Summary of 870323 Meeting W/Util & Bechtel in Bethesda,Md Re Proposal Made in Licensee 870113 Application Concerning Connection of Standby Gas Treatment Sys Svc to Refueling Floor Area.List of Attendees Encl
ML20214K1961986-11-21021 November 1986
Summary of 861107 Meeting W/Util,Ge & Bechtel in Bethesda,Md Re Use of ASME Code Case N-411 Concerning Alternative Damping Values for Seismic Analysis of Class 1-3 Piping.List of Attendees & Viewgraphs Encl
ML20214A1351986-11-13013 November 1986
Summary of 861001 Meeting W/Util in Bethesda,Md Re Schedules for Licensing Actions.Adequate Preparation of License Amend Applications Emphasized
ML20210R3741986-05-0808 May 1986
Summary of 860430 Meeting W/Util in Bethesda,Md to Discuss Processes to Be Used to Review Issues Raised in Remainder of OL Review for Facility
ML20126M4721985-06-0303 June 1985
Summary of 850524 Meeting W/Util,Conner & Wetterhahn & Limerick Ecology Action in Bethesda,Md to Discuss Unit 1 Readiness for Full Power Licensing
ML20128M2721984-10-26026 October 1984
Summary of ACRS Subcommitees on Limerick Units 1 & 2 & PRA 841020 Meeting in Los Angeles,Ca Re PRA & Application for OL
ML20128L7171984-10-23023 October 1984
Summary of Subcommittees on Limerick Units 1 & 2 & Reliability & Probabilistic Assessment 841009 Meeting in Washington,Dc Re SER & Eis.Viewgraphs Encl
ML20055B8291982-07-20020 July 1982
Trip Rept of 820608 Site Visit Re Status of Const
ML20062F2711982-07-0606 July 1982
Summary of 820514 Meeting W/Util in King of Prussia,Pa Re Revision 3 to Probabilistic Risk Assessment. Viewgraphs Encl
ML20148C1311979-12-20020 December 1979
Summary of Meeting W/Mark II Owners Group in Bethesda,Md Re Status of Several long-term Program Tasks in Advance of Final Documentation.Agenda,List of Attendees & Viewgraphs Encl
ML20213D0331979-08-22022 August 1979
Summary of 790717-18 Meeting W/Mark II Owners Group Re long-term Program Tasks
ML20213C8911979-03-14014 March 1979
Summary of 790213-14 Meeting W/Mark II Owners Group Re Lead Plant Acceptance Criteria & Intermediate Plant Program Tasks
ML20150C6821978-11-13013 November 1978
Agenda for 781128-30 ACRS Meeting in San Francisco of Fluid Hydraulic Dynamic Effects Subcomm Re Mark II LOCA & SRV Pool Dynamic Loads & Load Combinations
ML20214G8711978-01-11011 January 1978
Summary of 771202 Meeting W/Ge Re Rev 1 to NEDO-10466, Power Generation Control Complex Design Criteria & Safety Evaluation. List of Meeting Attendees Encl
ML20214G8691978-01-10010 January 1978
Summary of 770518-19 Meetings W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads Program
ML20214G8451977-12-0202 December 1977
Summary of 770510 Meeting W/Mark II Owners Executive Committee Re Mark II Containment Dynamic Loads Program.List of Attendees & Viewgraphs Encl
ML20214G8351977-11-29029 November 1977
Summary of 770401 & 0707 Meetings W/Mark II Owners & GE Re Methods for Combining Dynamic Loads for Structural Design of Mark II Containment.List of Attendees & Viewgraphs Encl
ML20214G7951977-08-0202 August 1977
Summary of 770729 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Load Program
ML20214G7841977-06-23023 June 1977
Summary of 770615 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Loads.List of Attendees Encl
ML20214G7741977-06-0808 June 1977
Summary of 770526 Meeting W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads.List of Meeting Attendees Encl
ML20214G6951977-04-18018 April 1977
Summary of 770216-17 Meeting W/Mark II Owners,Ge & BNL Re Mark II Containment Pool Dynamic Load Support Program.List of Meeting Attendees & Viewgraphs Encl
ML20214G4271976-12-29029 December 1976
Summary of 761202 Meeting W/Mark II Owners & GE Re Mark II Containment Structural Design & Pool Dynamic Loads Supporting Program.Attendee List & Viewgraphs Encl
ML20214G4371976-12-0707 December 1976
Summary of 761027-28 Meetings W/Mark II Owners,Ge & BNL Re Pool Dynamic Loads Analytical Model & Test Program.Lists of Attendees & Viewgraphs Encl
ML20214G4501976-06-0808 June 1976
Summary of 760429 Meeting W/Ge,Mark II Owners & Respective Aes Re GE 751105 Design Basis Document NEDE-21061, Mark II Containment Dynamic Forcing Function Info Rept (Dffr)
ML20214G6031975-08-26026 August 1975
Summary of 750821 Meeting W/Mark II Owners,Sargent & Lundy, Bechtel,S&W & B&R in Bethesda,Md Re Load Factors & Load Combinations for Assessing Capability of Mark II Containments to Accommodate Safety/Relief Valve Loads
ML20214G7791975-07-0303 July 1975
Summary of 750630 Meeting W/Mark II Owners,Aes & GE in Bethesda,Md Re Role of Mark II Owners,Status of Const of Various Mark II Units & Program for Determining Mark II LOCA & Safety/Relief Valve Loads
1998-12-15
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20059J0261994-01-24024 January 1994
Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059H9941993-11-0808 November 1993
Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20128C9371993-01-14014 January 1993
Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20246E1531989-08-16016 August 1989
Summary of 890727 Meeting W/Util,Nus Corp,Conner & Wetterhahn,Bechtel,Bnl & State of PA in Rockville,Md Re Severe Accident Issues.Licensee Presented Info Re Comparison of Core Damage for Accident Classes in PRA
ML20247R6001989-05-15015 May 1989
Summary of ACRS Subcommittee on Limerick Unit 2 Meeting on 890425 in Philadelphia,Pa Re Application for Ol.Statement of Limerick Ecology Action Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20206E3591988-11-10010 November 1988
Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program
ML20205P3121988-10-26026 October 1988
Summary of Operating Reactors Events Meeting 88-42 on 881025 Re Reactor Scrams.Three Significant Events Identified for Input to NRC Performance Indicator Program.List of Attendees Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams 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
ML20206B0521987-04-0606 April 1987
Summary of 870115 Meeting W/Util in Bethesda,Md Re ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Classes 1,2 & 3 Piping Sections,Section Iii,Div 1. List of Attendees Encl
ML20205E7821987-03-25025 March 1987
Summary of 870323 Meeting W/Util & Bechtel in Bethesda,Md Re Proposal Made in Licensee 870113 Application Concerning Connection of Standby Gas Treatment Sys Svc to Refueling Floor Area.List of Attendees Encl
ML20214K1961986-11-21021 November 1986
Summary of 861107 Meeting W/Util,Ge & Bechtel in Bethesda,Md Re Use of ASME Code Case N-411 Concerning Alternative Damping Values for Seismic Analysis of Class 1-3 Piping.List of Attendees & Viewgraphs Encl
ML20214A1351986-11-13013 November 1986
Summary of 861001 Meeting W/Util in Bethesda,Md Re Schedules for Licensing Actions.Adequate Preparation of License Amend Applications Emphasized
ML20210R3741986-05-0808 May 1986
Summary of 860430 Meeting W/Util in Bethesda,Md to Discuss Processes to Be Used to Review Issues Raised in Remainder of OL Review for Facility
ML20126M4721985-06-0303 June 1985
Summary of 850524 Meeting W/Util,Conner & Wetterhahn & Limerick Ecology Action in Bethesda,Md to Discuss Unit 1 Readiness for Full Power Licensing
ML20128M2721984-10-26026 October 1984
Summary of ACRS Subcommitees on Limerick Units 1 & 2 & PRA 841020 Meeting in Los Angeles,Ca Re PRA & Application for OL
ML20128L7171984-10-23023 October 1984
Summary of Subcommittees on Limerick Units 1 & 2 & Reliability & Probabilistic Assessment 841009 Meeting in Washington,Dc Re SER & Eis.Viewgraphs Encl
ML20062F2711982-07-0606 July 1982
Summary of 820514 Meeting W/Util in King of Prussia,Pa Re Revision 3 to Probabilistic Risk Assessment. Viewgraphs Encl
ML20148C1311979-12-20020 December 1979
Summary of Meeting W/Mark II Owners Group in Bethesda,Md Re Status of Several long-term Program Tasks in Advance of Final Documentation.Agenda,List of Attendees & Viewgraphs Encl
ML20213D0331979-08-22022 August 1979
Summary of 790717-18 Meeting W/Mark II Owners Group Re long-term Program Tasks
ML20213C8911979-03-14014 March 1979
Summary of 790213-14 Meeting W/Mark II Owners Group Re Lead Plant Acceptance Criteria & Intermediate Plant Program Tasks
ML20214G8711978-01-11011 January 1978
Summary of 771202 Meeting W/Ge Re Rev 1 to NEDO-10466, Power Generation Control Complex Design Criteria & Safety Evaluation. List of Meeting Attendees Encl
ML20214G8691978-01-10010 January 1978
Summary of 770518-19 Meetings W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads Program
ML20214G8451977-12-0202 December 1977
Summary of 770510 Meeting W/Mark II Owners Executive Committee Re Mark II Containment Dynamic Loads Program.List of Attendees & Viewgraphs Encl
ML20214G8351977-11-29029 November 1977
Summary of 770401 & 0707 Meetings W/Mark II Owners & GE Re Methods for Combining Dynamic Loads for Structural Design of Mark II Containment.List of Attendees & Viewgraphs Encl
ML20214G7951977-08-0202 August 1977
Summary of 770729 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Load Program
ML20214G7841977-06-23023 June 1977
Summary of 770615 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Loads.List of Attendees Encl
ML20214G7741977-06-0808 June 1977
Summary of 770526 Meeting W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads.List of Meeting Attendees Encl
ML20214G6951977-04-18018 April 1977
Summary of 770216-17 Meeting W/Mark II Owners,Ge & BNL Re Mark II Containment Pool Dynamic Load Support Program.List of Meeting Attendees & Viewgraphs Encl
ML20214G4271976-12-29029 December 1976
Summary of 761202 Meeting W/Mark II Owners & GE Re Mark II Containment Structural Design & Pool Dynamic Loads Supporting Program.Attendee List & Viewgraphs Encl
ML20214G4371976-12-0707 December 1976
Summary of 761027-28 Meetings W/Mark II Owners,Ge & BNL Re Pool Dynamic Loads Analytical Model & Test Program.Lists of Attendees & Viewgraphs Encl
ML20214G4501976-06-0808 June 1976
Summary of 760429 Meeting W/Ge,Mark II Owners & Respective Aes Re GE 751105 Design Basis Document NEDE-21061, Mark II Containment Dynamic Forcing Function Info Rept (Dffr)
ML20214G6031975-08-26026 August 1975
Summary of 750821 Meeting W/Mark II Owners,Sargent & Lundy, Bechtel,S&W & B&R in Bethesda,Md Re Load Factors & Load Combinations for Assessing Capability of Mark II Containments to Accommodate Safety/Relief Valve Loads
ML20214G7791975-07-0303 July 1975
Summary of 750630 Meeting W/Mark II Owners,Aes & GE in Bethesda,Md Re Role of Mark II Owners,Status of Const of Various Mark II Units & Program for Determining Mark II LOCA & Safety/Relief Valve Loads
1998-12-15
[Table view] |
Text
_ _ __ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ - _ ._ _ _ _ _ _ _ _ _ - _ _ - .
p uom w l 3
n UNITED STATES
/ 3 i NUCLEAR REGULATORY COMMISSION o I WAsHINoToN, D C. 206M
%'.... */ January 14, 1993 Docket Nos. 50-352 and 50-353 LICENSEE: Philadelphia Electric Company FACillTY: Limerick Generating Station, Units 1 and 2
SUBJECT:
SHUTDOWN MARGIN DETERMINATION On November 10, 1992, a meeting was held at One White Flint North with representatives of the Philadelphia Electric Company (PEco) to discuss two issues affecting activities performed during the Limerick Generating Station (LGS) refueling outages. A list of attendees is enclosed (Enclosure 1). .The agenda for the meeting is presented in Enclosure 2. The slides used by the licensee are presented in Enclosure 3. The issues focus on PEco's performance of control rod withdrawal for operability testing during the reactor vessel hydrostatictestinginOPERATIONALCONDITION(OPCON)4,ColdShutdown. The first issue concerns the means by which Technical Specification (TS) Limitir,g Condition for Operation (LCO) 3.1.1, " Shutdown Margin" is satisfied. The second issue concerns the position of the Reactor Protection System (RPS) shorting links, described by Note "c" in TS Table 3.3.1-1, " Reactor Protection System Instrumentation." Section 3.1.1 of the Limerick TSs requires that "the SHUTDOWN MARGIN shall be equal to or greater than:
- a. 0.38% Ak/k with the highest worth rod analytically determined., or
- b. 0.28% Ak/k with the highest worth rod determined by test."
Section 4.1.1 states that "The SHUTDOWN MARGIN shall be determined to be equal to or greater than specified at any time during the fuel cycle:
- a. By measurement, prior to or during the first startup after each refueling.
Table 3.3.1-1 of the Limerick TSs lists the reactor protection system instrumentation channels that must be operable. Note "c" to this Table states:
"(c) The " shorting links
- shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn
Control rod scram time testing is normally performed during Operational hydro, following fuel loading and installation of the reactor vessel head. Control rod scram timing requires each individual control rod to be fully withdrawn 290070 m <m c, m--., , , .
9302040209 930114 PDR ADOCK 05000352 gli P PDR U.,
d
. and scrammed into the reactor. During the first two refueling outages of Unit 1, during performance of the Operational hydro, single rod scram timing and control rod stroke timing were performed by taking the reactor mode switch to REFUEL, thereby activating the one-rod-out interlock. This action ensures that only one control rod can be withdrawn at a time. There are a number of other requirements that must also be met; for example, the Standby Liquid Control system must be operable and available to inject sodium pentaborate in the event of inadvertent criticality.
During the review of the Unit 2 startup test procedures prior to issuance of the fuel load license in June 1989, an NRC inspector raised the question as to whether scram time testi- *hould be conducted during the vessel hydrostatic in operational condition sp Con) 4, instead of during plant startup, since the sour a range monitors (SRM) are not in the RPS logic circuit. In addition, the inspector questioned if the requirement of TS 3.9.2 for demonstrating adequate shutdown margin (SDM) could be met through an analysis, inasmuch as TS 4.1.1 mentions that the SOM should be determined by measurement. (See Inspection Reports 50-352/89-12 and 50-3E3/89-19 and Section 5.0 of Inspection Reports 50-352/89-15 and 50-353/89-24). The issue was resolved at the time (prior to Unit 2 initial fuel load) by the licensee revising Startup Test Procedure (STP) - 5.6, " Rated Reactor Pressure Scram Testing" to remove the shorting links during the entire test period when control rods are withdrawn. This provides SRM and non-coincident Ni scrams in the case of inadvertent criticality.
PEco presented information describing its justification for maintaining the RPS shorting links installed during refueling outage evolutions at times other than when the TS explicitly requires the RPS shorting links to be removed (e.g., 15 Section 3.10.3, " Shutdown Margin Demonstrations"). Removing the RPS shorting links results in the RPS trip logic for nuclear instrumentation being -
one-out-of-one; i.e., a single non-coincident signal will result in a reactor trip. Removal of the coincident function in the RPS logic will increase the-probability of inadvertent reactor SCRAM due to RPS instrument spiking caused by random signals er workers coming in contact with under-vessel instrument cables. While not a safety issue alone, if the reactor SCRAM signal occurs while all control rods are inserted, the unmitigated pressure transient (i.e.,
the pre:sure differential between the pressurized hydraulic control units and the depressurized reactor vessel) challenges the integrity of the Control Rod -
Drive (CRD) seals and drive mechanisms. In addition, since all SCRAM occurrences must be investigated before plant operations can continue (i.e.,
in this case, refueling operations) inadvertent SCRAMS can cause an increase in the refueling outage length. Furthermore, with the RPS shorting links o -installed, multiple (i.e., redundant) nuclear instruments monitor the i reactivity in each reactor core region, thereby protecting against reactor criticality events. Accordingly, the Intermediate Range Monitors (IRMs) on l range I will cause a reactor SCRAM prior to the time the SRM rod block L
i i
setpoint (i.e., 100,000 cps) is achieved. Note that these events occur prior to the SCRAM that would be initiated by the SRMs (i.e., at 200,000 cps) if the shorting links are removed and furthermore, no setpoint for an SRM high neutron flux level scram is specified in the Technical Specifications. Also, no credit is taken for an SRM initiated reactor SCRAM in the accident or transient analysis in the Updated Final Safety Analysis Report.
The NRC staff advised PEco that the analytically calculated Shutdown Margin can be used to satisfy TS Limiting Condition of Operation (LCO) 3.1.1 during such evolutions as scram time testing of one control rod at a time durinq hydrostatic testing in OPCON 4, cold shutdown. The first rod to be pullsd should be the highest worth rod as determined by the analytical determination.
The shorting links do not need to be removed. The-one-rod-out interlock shall be activated to prohibit withdrawal of more than one control rod at a time.
The shutdown margin must, however, be actually determined by measurement in OPCON 2 Startup to satisfy TS Surveillance Requirement 4.1.1. No changes to the present TSs are necessary to permit stroke and scram testing of the control rods during hydrostatic testing. Original signed by Richard J. Clar , r'ojfcNanager Project Directorate I-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
- 2. Meeting Agenda
- 3. Licensee's slides cc w/ enclosures:
See next page l DISTRIBUTION 2 Docket file. LScholl NRC'& Local PDRs CDoutt PDI-2 Reading CShulten TMurley/FMiraglia HRichings !
JPartlow ACRS(10)
SVarga VMcCree JCalvo EWenzinger, RGN-1 CMiller CAnderson, RGN-I RClark CGrimes M0'Brien FRinaldi OGC EJordan ;
- Previously Concurred OfflCE POUd/CQ PDI-MPH PDl4/AM PDI-2/A SRXB*a49 SR)(0,f NAME ik0 h$e'n M :rb ditM8t* CidQ[
HRich'ingh bes -
DATE / h93 o///2/93 / /hy./93 //h93 01/04/93 / /pd93' -
0FFICIAL RECORD COPY /
DOCUMENT NAME: Lill-10. HTS-
setpoint (i.e., 100,000 cps) is achieved. Note that these events occur prior to the SCRAM that would be initiated by the SRMs (i.e., at 200,000 cps) if the shorting links are removed and furthermore, no setpoint for an SRM high neutron flux level scram is specified in the Technical Specifications. Also, no credit is taken for an SRM initiated reactor SCRAM in the accident or transient analysis in the Updated Final Safety Analysis Report.
The NRC staff advised PECo that the analytically calculated Shutdown Margin can be used to satisfy TS Limiting Condition of Operation (LCO) 3.1.1 during such evolutions as scram time testing of ona control rod at a time during hydrostatic testing in OPCON 4, cold shutdown. The first rod to be pulled should be the highest worth rod as determined by the analytical determination.
The shorting links do not need to be remov?d. The one-rod-out interlock shall be activated to prohibit withdrawal of more than one control rod at a time.
The shutdown margin must, however, be actually determined by measurement in OPCON 2 Startup to satisfy TS Surveillance Requirement 4.1.1. No changes to the present TSs are necessary to permit stroke and scram testing of the control rods during hydrostatic testing.
hard-thlark, Project Manager roject Directorate I-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
- 2. Meeting Agenda
- 3. Licensee's slides cc w/ enclosures:
See next page
_y
t 4
4
[ Philadelphia Electric Company Limerick Generating Station, Units 1 & 2 cc:
J. W. Durham, Sr., Esquire Mr. William P. Dornsife, Director Sr. V.P. & General Counsel Bureau of Radiation Protection Philadelahia Electric Company PA Dept. of Environmental Resources ,
2301 Marcet Street P. O. Box 2063 Philadelphia, Pennsylvania 19101 Harrisburg, Pennsylvania 17120 Mr. Rod Krich 52A-5 Mr. James A. Muntz Philadelphia Electric Company Superintendent-Technical 955 Chesterbrook Boulevard Limerick Generating Station Wayne, Pennsylvania 19007-5691 P. 0. Box A Sanatoga, Pennsylvania 19464 Mr. David R. Helwig, Vice President Limerick Generating Station Mr. Gil J. Madsen Post Office Box A Regulatory Engineer Sanatoga, Pennsylvania 19464 Limerick Generating Station P. O. Box A Hr. John Doering Sanatoga, Pennsylvania 19464 Plant Manager Limerick Generating Station Library P.O. Box A US Nuclear Regulatory Commission Sanatoga, Pennsylvania 19464 Region 1 475 Allendale Road Regional Administrator King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission Region I Mr. George A. Hunger 475 Allendale Road Project Manager King of Prussia, PA 19406 Limarick Ge.1erating Station P. O. Box A Mr. Thomas Kenny Sanatoga, Pennsylvania 19464 Senior Resident inspector .
US Nuclear Regulatory Commission Mr.' Larry Hopkins P. O. Box 596 Superintendent-0perations ,
Pottstown, Pennsylvania 19464 Limerick Generating Station P. O. Box A Mr. Di:hard W. Dubiel Sanatoga, Pennsylvania 19464 Superihtendent - Services Limerick Generating Station Mr. George J. Beck P.O. Box A Manage. Licensing, MC 52A-5 Sanatoga, Pennsylvania 19464 Philadelphia Electric Company Nuclear Group Headquarters Correspondence-Cnntrol Desk P.O. Box No. 195 Wayne, Pennsylvania 19087-0195 l
l l
L l
l' -, - - -
ENCLOSURE 1 L11L Of ATIENDEES MEETING WlE _ff,(g ON $HUIDOWN MARGH tiOVEMBER 10. J112 tLE DEEM 11AH0!1 R. Clark 11RC/NRA L. 5:ho11 NRC/ Resident inspector C. Doutt NRC/NRR C. Schuit(n NRC/NRR H. Richings NRC/NRR 0 tief f PECo R. Krich PECo C. Bornand PEco J. Podlesney PEco H. Eyre PECo i
a M
% i
- n. . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . . _ _ _ _ _ _ .
DJCLOSURE 2 Meeting Agenda llovember 10, 1992 Philadelphia Electric Company Limerick Generating Station and office of Nueionr Reactor and Regulations TOPIC: Shutdown Margin McAr9rJauent and Control of Rod Withdrawal Daring a Refueling Outage PURPOSE: ro present interpretation of Toch Specs To reach common understanding To identify necessary action DISCUSSIO!1:
I Introduction of Dackground Rod Krich, Licensing II 3equence of Outage Activitics John Podlesney, Limerick Reactor Engineering III SDM Demonstration by Analysis Christine Dornand, for Tech Spec 3.1.1 Fuel Management IV Summary of Tech Spec David Meff, Limerick Interpretation Licensing V Questions and Discussion VI Conclusion and Summary of Action Items
DELOSURE 3
.I LIMERICK GENERATING STATION l
l i
! REFUELING SEQUENCES
. . , , . , , . _ . . , . . . , . . . . . . . . - . ~ . - . . . . , . , , . . - . . . , , - - _ . . . , . - . - . , . _ _ . . _ . . . _ - . . - . , . _ . . . ~ , , . . , , . . . . . , - . . . - . , .
- LIMERICK ~ REFUELING PRESENT OFF LOADlRELOAD
> OFF LOAD CORE Msds' 5
> PERFORM HCU/CRDICRB MAINTENANCE
> DYNAMIC VENT ALL MAINTENANCE LOCATIONS
> VERIFY ALL CONTROL RODS ARE FULLY INSERTED
> RELOAD CORE
> VERIFY CORE LOADING
> NOTE: THE NEXT FOUR STEPS HAVE BEEN REQUIRED SINCE LGS 2 INITIAL CORE LOADING.
> 1. REMOVE SHORTING LINKS
> 2. SCRAM CONTROL RODS FOR
> 4. INSTALL SHORTING LINKS
> START OPS HYDRO
> STROKE / SCRAM CONTROL RODS DURING OPS HYDRO .
> PERFORM SHUTDOWN MARGIN MEASUREMENT DURING START UP dpcon 2
. = - _ - .-
- LIMERICK REFUELING
- PROPOSED OFF LOAD / RELOAD .- -
l .
> OFF LOAD CORE
> PERFORM HCU/CRD/CRB MAINTENANCE _
4
> DYNAMIC VENT ALL MAINTENANCE LOCATIONS
> VERIFY ALL CONTROL RODS ARE FULLY INSERTED
> RELOAD CORE
> VERIFY CORE LOADING
> START OPS HYDRO
> STROKE / SCRAM CONTROL RODS DURING OPS HYDRO
> DECLARE CONTROL RODS OPERABLE
> PERFORM SHUTDOWN MARGIN MEASUREMENT DURING START UP I
l
, n n - ,-,n... - - - - , ,-, - . ., n,- ,, , .- ,,,
- LIMERICK REFUELING PROPOSED FUEL SHUFFLE _
> SHUFFLE FUEL TO MAINTENANCE CONFIGURATION
> WITHDRAW CONTROL RODS REQUIRING MAINTENANCE
> PERFORM HCU/CRD/CRB MAINTENANCE
> DYNAMIC VENT ALL MAINTENANCE LOCATIONS
> VERIFY ALL CONTROL RODS ARE FULLY INSERTED
> SHUFFLE FUEL TO FINAL LOADING
> VERIFY CORE LOADING
> START OPS HYDRO
> STROKEISCRAM CONTROL RODS DURING OPS HYDRO
> DECLARE CONTROL RODS OPERABLE
> PERFORM SHUTDOWN MARGIN MEASUREMENT DURING START UP
0 i 1
Analysis satisfies requirement of LCO 3.1.1 to permit control rod operability testing ,
during OPCON 4. '
BASES:
9 Use NRC-approved methods. 1 i
9 Apply NRC-approved design mhrgin. /gs---
&,,,,, arp,/s at yJ . S- e.<< n as, sa<1ng & {
/.rg 4
9 Analysis is complete prior to core loading. 1 l
4 9 Tests orlor to startup do NOT quantify CSDM.
- %,,,J; 4,,y s / a a is & a sc. w a/
9 Single rod withdrawalis more conservative than multiple rod withdrawal.
O Licens'ed operators monitor nuclear during all control rod withdrawal, monitoring :
power changes.
9 Consi,*ent with Improved Tech Specs.
p,u/,,u ca<, .udr.sf sco .
l RPS SHORTING LINKS NOT REQUIRED TO BE REMOVED BASES:
- Tech Spec Table 1.2 does not require removal.
m Mde Y
- IRMs on Range 1 will SCRAM prior to SRM 100,000 cps.
4 Multiple instruments monitoring each region.
9 No credit given for SRM SCRAM in accident / transient analyses.
9 No RPS setpoint for SRM hllevel SCRAM.
- inadvertent SCRAM more likely.
Detrimental to equipment increased outage time, for cause lovestigation.
- - _ _ .
