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| | issue date = 05/12/1988 | | | issue date = 05/12/1988 |
| | title = Forwards Nonproprietary Info Used from C-E Rept NPSD-151, C-E Safety Analysis Method for Calvert Cliffs,Units 1 & 2, Per SA Mcneil 880224 Ltr to Ja Tiernan Requesting Addl Info in Response to Generic Ltr 86-06 | | | title = Forwards Nonproprietary Info Used from C-E Rept NPSD-151, C-E Safety Analysis Method for Calvert Cliffs,Units 1 & 2, Per SA Mcneil 880224 Ltr to Ja Tiernan Requesting Addl Info in Response to Generic Ltr 86-06 |
| | author name = TIERNAN J A | | | author name = Tiernan J |
| | author affiliation = BALTIMORE GAS & ELECTRIC CO. | | | author affiliation = BALTIMORE GAS & ELECTRIC CO. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:( | | {{#Wiki_filter:* BALTIMORE GAS AND ELECTRIC CHARLES CENTER |
| * BALTIMORE GAS AND ELECTRIC | | * P. 0. BOX 1475 *BALTIMORE, MARYLAND 21203 JOSEPH A. TIERNAN VJCE PRESIDENT NUCLEAR ENERGY May 12, 1988 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk |
| * CHARLES CENTER
| |
| * P. 0. BOX 1475 *BALTIMORE, MARYLAND 21203 JOSEPH A. TIERNAN VJCE PRESIDENT NUCLEAR ENERGY U. S. Nuclear Regulatory Commission Washington, DC 20555 May 12, 1988 ATTENTION: | |
| Document Control Desk | |
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| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Response to Request for Additional Information | | Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Response to Request for Additional Information - Generic Letter 86-06 (TACS 49674 and 49675) |
| -Generic Letter 86-06 (TACS 49674 and 49675) | |
|
| |
|
| ==REFERENCES:== | | ==REFERENCES:== |
| (a) Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tiernan (BG&E), dated February 24, 1988, Request for Additional Information
| | (a) Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tiernan (BG&E), |
| -Generic Letter 86-06, "Implementation of TMI Action Item 11.K.3.5, Automatic Trip of Reactor Coolant Pumps" Gentlemen:
| | dated February 24, 1988, Request for Additional Information - |
| | Generic Letter 86-06, "Implementation of TMI Action Item 11.K.3.5, Automatic Trip of Reactor Coolant Pumps" Gentlemen: |
| As requested in Reference (a), we are providing the non-proprietary information used from the CE report, NPSD-151, "CE Safety Analysis Method for Calvert Cliffs Units 1 and 2." There is no non-proprietary version of the complete report available, therefore, we have extracted the non-proprietary portion of the trending tables that were used in our evaluation. | | As requested in Reference (a), we are providing the non-proprietary information used from the CE report, NPSD-151, "CE Safety Analysis Method for Calvert Cliffs Units 1 and 2." There is no non-proprietary version of the complete report available, therefore, we have extracted the non-proprietary portion of the trending tables that were used in our evaluation. |
| Should you have any questions on this matter, we will be pleased to discuss them with you. JA T /PSF /WPM/ dlm cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble, NRC 88os200335 PPDR ADOCK 05000317 DCD | | Should you have any questions on this matter, we will be pleased to discuss them with you. |
| *-TABLE 8-1 KEY INPUT P/\llAMETERS Atm TllE IR IMPACT ON TllE LOSS OF LOAD EVENT Par;meter Sense of Chanqe Power Level lligher \ . lligher RCS Pressure Lower Physical Impact 1.. /\ higher initial power level initiate the event from conditions closer to SAFDLs. i 2. /\higher power will maximize the power to pressurizer steam space ratio. A Tinlet will initiate*
| | JA T /PSF /WPM/ dlm cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble, NRC |
| the event from conditions closer to SAFOLs. 1. A lower initial pressure will initiate the event from conditions closer to SAFDLs. 2. A lower initial pressure delays the time of high pressurizer pressure trip and thus maximizes the.rate of pressure change at time of trip. -------*- | | ( |
| ... | | 88os200335 e:::os:t~ |
| .. *--*-------------*--*---**-*--. | | PPDR ADOCK 05000317 DCD |
| Impact on Analytical Results 1. No impact on transient results ex-cept that higher powers lower the initial ONBR and thus result in a lower transient minimum ONBR. l *2. /\ higher power to steam space ratio will maximize the peak pressure during the event. No impact on transient results except that a higher Tinlet lowers the initial DNBR and thus results in a *lower sient minimum ONBR. 1. No impact on minimum ONBR during the event since no credit is taken for the pressure increase.
| | |
| : 2. Lower initial pressure delays time of trip. This the rate of change of pressure at time of trip and in higher peak RCS
| | TABLE 8-1 KEY INPUT P/\llAMETERS Atm TllE IR IMPACT ON TllE LOSS OF LOAD EVENT Par;meter Sense of Chanqe Physical Impact Impact on Analytical Results Power Level lligher 1.. /\ higher initial power 1. No impact on transient results ex-level ~1ill initiate the cept that higher powers lower the initial ONBR and thus result in |
| -co I \.0 Par;*r.1eter
| | \ |
| ------:1 MTC Doppler Coefficient Sense of Change More Positive (i.e., BOC) Less Negative (i.e., BOC)
| | event from conditions closer to SAFDLs. a lower transient minimum ONBR. |
| I TABLE B-1 (continued)
| | . i l |
| Phys1cal Impact A more positive MTC in tion with increasing coolant tempera tu res wi 11 add greater positive reactivity.
| | /\higher power will maximize *2. /\ higher power to steam space 2. |
| This creases the core power, heat flux, coolant system pressure and temperatures. | | the power to pressurizer ratio will maximize the peak steam space ratio. pressure during the event. |
| A less negative Doppler coe'fficient in combination with increasing fuel temperatures, adds less negative reactivity ThiS maximizes the increase in power, heat flux, coolant Ii temperature and pressure. | | lligher A bighe~ Tinlet will initiate* No impact on transient results except the event from conditions that a higher Tinlet lowers the initial co closer to SAFOLs. DNBR and thus results in a *lower tran- I |
| Allows the heat flux to follow the power more closely. Also, ilicreases the rate at \'1hich the heat generated within the fuel gets into the coolant and by increases the coolant tempera lures and pressure. | | \.0 sient minimum ONBR. |
| Impact on Analyt1cal Results 1. Increasing core average heat flux and coolant temperature result in lower. transient orrnn values. 2. Maximizes the peak RCS pressure during the event. 1. 2. Results in higher core heat flux and coolant temperatures and thus minimizes the transient DNBR. Maximizes the peak RCS pressure.
| | RCS Pressure Lower 1. A lower initial pressure 1. No impact on minimum ONBR during will initiate the event the event since no credit is taken from conditions closer for the pressure increase. |
| : 1. Results in higher core average heat flux and coo 1 ant tempera tu res and thus minimizes the transient ONBR. 2. Maximizes the peak RCS pressure. I ...... 0 i | | to SAFDLs. |
| ' '* Parm1eter Initial Steam Generator Pressure Axial Power Distribution Sense of Chanqe Lower . . Top Peaked Positive neactivity Insertion Curve (i.e.1 ASI) Pressurizer Pressure Control System Inoperable (i.e., no sprays or PROVs) T/\OLE 8-1 (continued}
| | : 2. A lower initial pressure 2. Lower initial pressure delays delays the time of high time of trip. This maxi~izes pressurizer pressure trip the rate of change of pressure and thus maximizes the.rate at time of trip and t~~s res~]ts of pressure change at time in higher peak RCS pressures~ |
| Physical Impact A lower initial steam generator pressure delays the time when main steam safety valves open. The delay in opening the MSSVs increases the heatup of both the primary and secondary systems. A top peaked shape results in higher enthalpy rise in the hot channel. Scram reactivity insertion associated with a positive ASI 1 minimizes the scram reactivity inserted after a reactor trip. This rni zes the power, heat flux, coolant temperature and pressure overshoot. | | of trip. |
| More pronounced transient | | -------*- *---~...=*=~-=*"~--*-=-*=**-~~--~ .. *--*-------------*--*---**-*--. |
| * | | |
| * variations in primary pressure. | | i TABLE B-1 (continued) |
| Impact on Analytical Results Maximizes the peak RCS pressure.
| | Par;*r.1eter Sense of Change Phys1cal Impact Impact on Analyt1cal Results MTC More Positive A more positive MTC in combina- 1. Increasing core average heat flux (i.e., BOC) tion with increasing coolant and coolant temperature result in tempera tu res wi 11 add greater lower. transient orrnn values. |
| Minimizes transient DNBR. l. Maximizes core average heat flux, and coolant temperatures.
| | positive reactivity. This in-creases the core power, heat 2. Maximizes the peak RCS pressure flux, coolant system pressure during the event. |
| * Minimizes the transient DNBR. 2. Maximizes RCS pressure.
| | and temperatures. |
| Maximizes peak RCS pressure. . \ 0 0 * ---}}
| | Doppler Less Negative A less negative Doppler 1. Results in higher core heat flux Coefficient (i.e., BOC) coe'fficient in combination and coolant temperatures and thus with increasing fuel minimizes the transient DNBR. ~ |
| | temperatures, adds less I negative reactivity 2. Maximizes the peak RCS pressure. 0 ThiS maximizes the increase in power, heat flux, coolant temperature and pressure. |
| | Ii Mi~her Allows the heat flux to follow 1. Results in higher core average the power more closely. Also, heat flux and coo 1ant tempera tu res ilicreases the rate at \'1hich the and thus minimizes the transient heat generated within the fuel ONBR. |
| | gets into the coolant and there-by increases the coolant 2. Maximizes the peak RCS pressure. |
| | tempera lures and l~CS pressure. |
| | :1 I |
| | |
| | 0 |
| | \ |
| | 0 |
| | * T/\OLE 8-1 (continued} |
| | Parm1eter Sense of Chanqe Physical Impact Impact on Analytical Results Initial Steam Lower A lower initial steam Maximizes the peak RCS pressure. |
| | Generator . generator pressure delays Pressure the time when main steam safety |
| | . valves open. The delay in opening the MSSVs increases the heatup of both the primary and secondary systems. |
| | Axial Power Top Peaked A top peaked shape results in Minimizes transient DNBR. |
| | Distribution higher enthalpy rise in the hot channel. |
| | Sera~ Positive Scram reactivity insertion l. Maximizes core average heat flux, neactivity associated with a positive and coolant temperatures. |
| | * Insertion ASI 1 minimizes the scram Minimizes the transient DNBR. |
| | Curve (i.e. 1 reactivity inserted after ASI) a reactor trip. This maxi- 2. Maximizes RCS pressure. |
| | rni zes the power, heat flux, coolant temperature and pressure overshoot. |
| | Pressurizer Inoperable (i.e., More pronounced transient * |
| | * Maximizes peak RCS pressure. |
| | Pressure no sprays or PROVs) variations in primary Control pressure. |
| | System}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999
Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition
ML20217M9991999-10-22022 October 1999
Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2
ML20217M1721999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20212M2631999-10-0404 October 1999
Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant
ML20216J8671999-10-0101 October 1999
Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements
ML20212J7811999-09-30030 September 1999
Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future
ML20212J5611999-09-29029 September 1999
Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl
ML20216H7831999-09-28028 September 1999
Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application
ML20212D5361999-09-20020 September 1999
Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon
ML20212C1861999-09-15015 September 1999
Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp
ML20212A2001999-09-0808 September 1999
Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations
ML20211N8971999-09-0707 September 1999
Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants
ML20211H9841999-08-31031 August 1999
Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
ML20211K3091999-08-27027 August 1999
Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025
ML20211J1611999-08-17017 August 1999
Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement
ML20210V1181999-08-17017 August 1999
Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96
ML20210T5061999-08-16016 August 1999
Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5
ML20210U2761999-08-13013 August 1999
Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements
ML20210S8131999-08-12012 August 1999
Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506
ML20210S8101999-08-12012 August 1999
Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl
ML20210S7901999-08-12012 August 1999
Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d)
ML20210Q1941999-08-11011 August 1999
Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
ML20210N5881999-08-0606 August 1999
Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements
ML20210N1291999-08-0505 August 1999
Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr
ML20210N5491999-08-0505 August 1999
Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application
ML20210N5471999-08-0505 August 1999
Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License
ML20210N9291999-08-0404 August 1999
Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1)
ML20210J0741999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks
ML20211B5381999-07-30030 July 1999
Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC
ML20211C0951999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714
ML20211C3251999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714
ML20210E4941999-07-23023 July 1999
Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan
ML20210D0911999-07-22022 July 1999
Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc
ML20210C5011999-07-21021 July 1999
Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested
ML20210C2681999-07-20020 July 1999
Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e)
ML20210A5021999-07-20020 July 1999
Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment
ML20211N9101999-07-20020 July 1999
Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant
ML20210C8461999-07-19019 July 1999
Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested
ML20209J5171999-07-16016 July 1999
Forwards Comments from Accuracy Review of License Renewal Application SER
ML20210B7651999-07-15015 July 1999
Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl
ML20209G2081999-07-13013 July 1999
Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted
ML20210A6311999-07-0606 July 1999
Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2
ML20209C1391999-07-0202 July 1999
Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future
ML20210D1531999-06-30030 June 1999
Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations
ML20209B5781999-06-29029 June 1999
Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML20210D1741999-06-24024 June 1999
Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info
ML20211H8431999-06-23023 June 1999
Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl
ML20196C6831999-06-21021 June 1999
Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701
ML20196C4291999-06-21021 June 1999
Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes
ML20195J8271999-06-16016 June 1999
Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217M9991999-10-22022 October 1999
Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2
ML20216J8671999-10-0101 October 1999
Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements
ML20216H7831999-09-28028 September 1999
Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application
ML20212D5361999-09-20020 September 1999
Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon
ML20212C1861999-09-15015 September 1999
Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp
ML20211H9841999-08-31031 August 1999
Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
ML20210V1181999-08-17017 August 1999
Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96
ML20210T5061999-08-16016 August 1999
Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5
ML20210U2761999-08-13013 August 1999
Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements
ML20210S8101999-08-12012 August 1999
Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl
ML20210S8131999-08-12012 August 1999
Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506
ML20210S7901999-08-12012 August 1999
Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d)
ML20210N5881999-08-0606 August 1999
Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements
ML20210N5491999-08-0505 August 1999
Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application
ML20210N5471999-08-0505 August 1999
Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License
ML20210N9291999-08-0404 August 1999
Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1)
ML20210E4941999-07-23023 July 1999
Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan
ML20210C5011999-07-21021 July 1999
Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested
ML20210C2681999-07-20020 July 1999
Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e)
ML20211N9101999-07-20020 July 1999
Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant
ML20210C8461999-07-19019 July 1999
Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested
ML20209J5171999-07-16016 July 1999
Forwards Comments from Accuracy Review of License Renewal Application SER
ML20209C1391999-07-0202 July 1999
Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future
ML20210D1531999-06-30030 June 1999
Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations
ML20209B5781999-06-29029 June 1999
Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML20210D1741999-06-24024 June 1999
Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info
ML20196C4291999-06-21021 June 1999
Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes
ML20195J6591999-06-16016 June 1999
Submits Proposed Alternative to Requirements of 10CFR50.55a(g)(4) (Automatic Compliance with Latest Approved Edition of ASME Code Every 120 Months).Proposal Will Apply Third ten-year ISI Interval,Scheduled to Begin 990701
ML20207F0201999-06-0101 June 1999
Forwards Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2, for NRC Review.Plan Satisfies Commitment Contained in Licensee to NRC
05000317/LER-1999-002, Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b)1999-05-28028 May 1999
Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b)
ML20195B2521999-05-25025 May 1999
Submits Response to RAI Re LAR for Tube Repair Using Leak Limiting Alloy 800 Sleeves for Ccnpp,Units 1 & 2.Test Repts Encl
ML20195B3751999-05-25025 May 1999
Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii)
ML20195B2271999-05-24024 May 1999
Forwards Certified Copy of Nuclear Liability Policy NF-216, Endorsement 128
ML20206U3051999-05-19019 May 1999
Submits Written Rept as Required follow-up to Verbal Rept Given to NRC Regional Administrator on 990419 of SG Tube Insps Conducted,Cause of Tube Degradation & Corrective Measures Taken as Result of Insp Findings
ML20206U8281999-05-18018 May 1999
Forwards Missing Pages C-30,C-31,C-114 & C-115 from 990319 Response to NRC RAI, Wind Tunnel Modeling of Calvert Cliffs NPP Cpp Project 94-1040. Complete Copy of 1985 Rept, Wind Flows & Dispersion Conditions of Calvert Cliffs, Encl
ML20212G9751999-05-12012 May 1999
Forwards Draft write-up Re OI 16 for F Grubelich to Consider
ML20206K6921999-05-10010 May 1999
Forwards Certified Copy of Listed Nuclear Liability Policy Endorsements,In Compliance with 10CFR140.15(e).Without Encl
ML20206K1711999-05-0707 May 1999
Informs That on 990430 Util Filed Encl Articles of Share Exchange with Maryland Dept of Assessments & Taxation to Form Holding Company,Constellation Energy Group,Inc (Ceg). CEG Is Parent Company of Bg&E
ML20206C7521999-04-29029 April 1999
Provides Rept of Number of Tubes Plugged in Calvert Cliffs Unit 2 SGs During Recently Completed Isi,As Required by Calvert Cliffs Unit 1,TS 5.6.9.a
ML20206C7271999-04-28028 April 1999
Forwards Occupational Radiation Exposure Repts for 1998, as Required by Units 1 & 2 Tech Specs 5.6.1 & 6.1 of Isfsi. Repts Contain Tabulation of Number of Station,Util & Other Personnel Receiving Exposures Greater than 100 Mrem
ML20212G9891999-04-28028 April 1999
Forwards Current Draft Response to Ci 3.3.2.2-1 to Be Used as Example for OI Vs License Condition Vs Commitment Situation
ML20206C7211999-04-27027 April 1999
Forwards Addl Info Which Is Being Made Available in Encl Licensed Operators Fitness for Duty Questionnaire.Encl Specifics of Personal Info Are Withheld,Per 10CFR2.790
ML20212G9851999-04-26026 April 1999
Provides Proposed Response to OI 4.1.3-1 for B Elliott to Consider
ML20206U6691999-04-26026 April 1999
Advises That Documents Re Operation of Calvert Cliffs Nuclear Power Plant Should Be Addressed to Listed Natl Marine Fisheries Svc Office
ML20205F8851999-04-0202 April 1999
Provides First Annual Amend to Bg&E License Renewal Application for Ccnpp,Units 1 & 2,as Required by 10CFR54
ML20205J0691999-04-0202 April 1999
Forwards Response to NRC 990129 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs
ML20205G2971999-04-0101 April 1999
Requests That NRC Complete Review of Rev 0 to CENPD-396-P, Common Qualified Platform TR & Rev 0 to CE-CES-195-P, Software Program Manual for 'Common Q' Sys, by 990930
ML20205D7471999-03-30030 March 1999
Forwards Biennial Rept on Status of Decommissioning Funding, IAW 10CFR50.75(f)(1)
ML20207G4391999-03-30030 March 1999
Responds to from Cl Miller,Requesting Assistance of FEMA in Addressing Concerns Received by NRC Involving Offsite Emergency Preparedness at Plant NPP
ML20205C4091999-03-26026 March 1999
Submits Info Related to Scope,Risk Mgt & Summary of Risk for Performing Preventive Maintenance on P-13000-2 Unit Transformer Re License Amend 205
1999-09-28
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20064A7471990-09-18018 September 1990
Discusses Response to Generic Ltr 88-17, Loss of Dhr. Development of Appropriate Tech Spec Changes for Reducing Cooling Flow Rate in Process.Changes Will Provide Increased Margin to Vortexing Conditions
ML20059K1951990-09-18018 September 1990
Clarifies Auxiliary Feedwater Sys Commitments Concerning Ability of Sys to Prevent Total Loss of Feedwater Following Various Pipe Breaks & Component Failures
ML20059H2811990-09-0707 September 1990
Forwards Rev 4 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Rev Creates Std Format for Action Plans Which States Scope, Deliverables & Overall Objectives of Action Plan
ML20059F4761990-09-0707 September 1990
Forwards Rev 5 to Security Training & Qualification Plan.Rev Withheld
ML20059H4241990-09-0707 September 1990
Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900905
05000317/LER-1989-023, Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture1990-08-24024 August 1990
Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture
ML20059B7481990-08-21021 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990
ML20058Q2211990-08-14014 August 1990
Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900807.Synopsis of Activities Since Last Update & Updated List of Key Action Plan Info Also Encl
ML20058L8811990-08-0101 August 1990
Withdraws License Amend Request Changing Tech Spec Pages 3/4 25a & 25b, RCS Pressure-Temp Limitations. Change Would Have Revised Min Reactor Vessel Flange bolt-up Temp from 70 F to 90 F
ML20058L7271990-08-0101 August 1990
Forwards Plant Performance Improvement Plan Implementation Program Schedule Status as of 900724
ML20058L2151990-07-27027 July 1990
Responds to NRC Re Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80.Corrective Action: Evaluation of Battery Charger Determined That Provisions Adequately Verify Requirements of Tech Spec 4.8.2.3.2
ML20055H9241990-07-26026 July 1990
Forwards Decommissioning Plan for Calvert Cliffs Isfsi
ML20055G9981990-07-20020 July 1990
Responds to NRC Re Generic Implications & Resolution of Control Element Assembly Failure at Plant on 900607.New Control Element Assemblies Ordered.Addl Response Will Be Submitted at Least 60 Days Prior to Restart
ML20044B0401990-07-13013 July 1990
Forwards Rev 3 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Brief Summary of Changes Listed
ML20055E0801990-07-0303 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08.Corrective Actions:Instruction CCI-309B Re Control of Locked Valve Revised to Clarify Required Documentation and Verification of Locked Valves
ML19298E2271990-06-29029 June 1990
Confirms That Work Intended to Resolve Unresolved Items & Incorporate Improvement Suggestions Completed,Per Insp Repts 50-317/90-04 & 50-318/90-04
ML20055D0311990-06-25025 June 1990
Submits Corrections to Commitments Re Hydrogen Analyzer Sys. Under Worst Case Condition,Hydrogen Recombiners Would Be Started Prior to Hydrogen Concentration Inside Containment Reaching 3.0% Hydrogen
ML20043G1771990-06-12012 June 1990
Forwards Monthly Operating Repts for May 1990 for Calvert Cliffs Nuclear Power Plant Units 1 & 2 & Revised Operating Rept for Apr 1990 for Calvert Cliffs Unit 1
ML20043G5931990-06-0808 June 1990
Requests one-time Exemption from Requirement of 10CFR50.71(e) to Allow 3-month Extension to Schedule for Submitting 1990 Rev to Updated Fsar,Per NRC 1989 QA Audit & Insp Repts 50-317/89-27 & 50-318/89-28 Noting Weaknesses
ML20043F7101990-06-0606 June 1990
Suppls 900330 Response to Station Blackout Rule (10CFR50.63).Two Addl Class 1E Diesel Generators Added to Reduce Required Coping Duration.Required Coping Duration Is 4 H for One Unit
ML20043D7281990-06-0404 June 1990
Responds to NRC 900404 Ltr Re Weaknessess Noted in Maint Team Insp Repts 50-317/90-80 & 50-318/90-80.Efforts to Clean,Insulate & Paint Plant Areas to Improve Cleanliness Being Undertaken
ML20043C9051990-05-31031 May 1990
Notifies of Relocation of Ofcs,Effective 900604.New Addresses & Telephone Numbers Listed
ML20043C5971990-05-29029 May 1990
Forwards Startup Review Board Self-Assessment Rept:Apr 1990 Unit 1 Startup. Based on Assessment,Mgt Efforts Taken Through Performance Improvement Plan Appears Substantially on Track
ML20043B9341990-05-25025 May 1990
Advises of Licensee Progress to Date Re Unresolved Item Noted in Inps Repts 50-317/90-04 & 50-318/90-04 & Identify Slippage Past 900601 Target Date.Completion Date Extended to 900701
ML20043B4691990-05-21021 May 1990
Reaffirms Licensee Intention to Submit Rept Re Deletion of Tech Spec 3/4.6.1.8, Containment Sys - Containment Vent Sys, Upon Receiving Notification That Vent Valves 1(2)-MOV-6900 & 1(2)-MOV-6901 Established
ML20043A3381990-05-15015 May 1990
Responds to NRC 900409 Ltr Re Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Corrective Actions:Detailed & Specific Directions for Radiography Will Be Incorporated in Radiography Procedures within NDE Program
ML20043A3321990-05-14014 May 1990
Responds to SALP Rept Dtd 900404 Covering Util Performance During 1989.Feedback Mechanisms Established to Improve Training & 10CFR50.59 Screening Procedure & Training Revised
ML20042G3751990-05-10010 May 1990
Forwards Changes 1-3 to Rev 0 to Program Plan for Second Insp Interval for Calvert Cliffs Nuclear Plant,Units 1 & 2. Plan Revised to Include Volumetric & Surface Exams of Class 2 Piping Welds in Containment Spray & Shutdown Cooling Sys
ML20042G6141990-05-0505 May 1990
Requests Regional Temporary Waiver of Compliance to Provide Relief from Provision of Limiting Condition for Operation of Tech Spec 3.4.10.1, Structural Integrity of ASME Code Class 1,2 & 3 Sys.
ML20042F5771990-05-0404 May 1990
Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-317/90-80 & 50-318/90-80.Corrective Actions:Surveillance Test Procedure M-538-1 Revised to Include Verification of Alarm Function & Alarm Testing Reviewed
ML20042G4581990-05-0404 May 1990
Responds to Request for Addl Info Concerning Tech Spec Amend Re Emergency Diesel Generators.Preventive Maint Procedures Prepared on 900411 & Final Approval Will Be Completed After Issuance of Amend
ML20042E8271990-04-30030 April 1990
Forwards Rev 2 to Calvert Cliffs Performance Improvement Plan Implementation Program. Accountability Improvements, Engineering Planning & Sys Circles Action Plans Completed. New Sections to Rev Listed
ML20042F0101990-04-30030 April 1990
Forwards Update of Tables 1C,2A,2B,3A & Page 7 of Semiannual Effluent Release Rept for Second Half of 1989 & Table 3A for Second Half of 1988 & First Half of 1989.Update Includes Strontium Results for Fourth Quarter for Gaseous Releases
ML20042F0391990-04-19019 April 1990
Submits Initial Response to SALP Rept Dtd 900404.Licensee Devoted Substantial Senior Mgt Attention & Resources to Improving Facility Performance & Committed to Continue Efforts to Attain High Stds of Safety & Quality
ML20012F5511990-04-0606 April 1990
Responds to NRC 900306 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Corrective Actions:Operating Procedures Changed to Prohibit Testing of ECCS When in Solid Water Condition
ML20012F2991990-04-0404 April 1990
Revises Scheduled Completion Date for Implementation of Computerized Trending of Surveillance Test Data,In Response to Special Team Insp Repts 50-317/89-200 & 50-318/89-200 from 900601 to 901228
ML20042D8101990-03-30030 March 1990
Forwards Supplemental Info,Clarifying Util 890414 Response to Station Blackout Rule Noting That Util Followed NUMAR-87-00 Methodology
ML20012F0211990-03-29029 March 1990
Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-317/89-25.Corrective Actions:Plugging Error Identified & Correct Tube Plugged & Corrective Action Procedures Revised
ML20012D3111990-03-19019 March 1990
Provides Followup Response to Violation Noted in Insp Repts 50-317/89-24 & 50-318/89-24.Corrective Actions:Radiation Safety Technicians Responsible for Safety Procedures Trained in Jan 1990 & Radwaste Scaling Factors Approved on 900201
ML20012D1871990-03-16016 March 1990
Discusses Readiness for Restart of Facility
ML20012B9221990-03-0909 March 1990
Responds to NRC 900207 Ltr Re Violations Noted in Insp Repts 50-317/89-27 & 50-318/89-28.Corrective Actions:Demineralized Water & Chemicals Added to Steam Generators to Restore Chemical Concentrations to Required Specs
ML20012B9121990-03-0909 March 1990
Withdraws 891113 Request for Relief from ASME Code Section XI Requirements
ML20012B6111990-03-0707 March 1990
Responds to NRC 900229 Ltr Re Violations Noted in Readiness Assessment Team Insp Rept 50-317/89-81.Corrective Actions: Memo Issued re-emphasizing Importance of Mgt Controls & General Supervisor Counselled
ML20012D7271990-03-0505 March 1990
Responds to Violations Noted in Insp Repts 50-317/90-03 & 50-318/90-03 on 900108-12.Corrective Actions:Medical Svcs Tested All Members of Nuclear Security Force for Glaucoma & field-of-vision Requirements
ML20011F4251990-03-0101 March 1990
Forwards Page 4-9 of Rev 25 to Security Plan,Originally Submitted on 900228.Encl Withheld (Ref 10CFR73.21)
ML20011F4491990-02-28028 February 1990
Forwards 1989 Steam Generator Insp Results Rept.Rept Includes Number & Extent of Tubes Examined,Imperfections Noted & Identity of Tubes Plugged.No Steam Generator Tube Exams Conducted on Unit 1 During 1989
ML20012A1481990-02-28028 February 1990
Forwards Rev 25 to Security Plan & Details of Changes Made by Rev.Encls Withheld (Ref 10CFR73.21)
ML20012A1531990-02-28028 February 1990
Forwards Rev 11 to Safeguards Contingency Plan & Details of Changes Made by Rev.Encls Withheld (Ref 10CFR73.21)
ML20011F4141990-02-27027 February 1990
Forwards Rev 2 to, Evacuation Time Estimates within Plume Exposure Pathway EPZ for Calvert Cliffs Nuclear Power Plant. Evacuation Time Estimates Updated to Reflect Population & Road Network Changes Since 1981
ML20012A2331990-02-26026 February 1990
Advises That Erosion/Corrosion Program Controlling Implementing Procedure 5.05, Secondary Sys Piping Erosion/ Corrosion Insp Program, Fully Implemented on 891229
1990-09-07
[Table view] |
Text
- BALTIMORE GAS AND ELECTRIC CHARLES CENTER
- P. 0. BOX 1475 *BALTIMORE, MARYLAND 21203 JOSEPH A. TIERNAN VJCE PRESIDENT NUCLEAR ENERGY May 12, 1988 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Response to Request for Additional Information - Generic Letter 86-06 (TACS 49674 and 49675)
REFERENCES:
(a) Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tiernan (BG&E),
dated February 24, 1988, Request for Additional Information -
Generic Letter 86-06, "Implementation of TMI Action Item 11.K.3.5, Automatic Trip of Reactor Coolant Pumps" Gentlemen:
As requested in Reference (a), we are providing the non-proprietary information used from the CE report, NPSD-151, "CE Safety Analysis Method for Calvert Cliffs Units 1 and 2." There is no non-proprietary version of the complete report available, therefore, we have extracted the non-proprietary portion of the trending tables that were used in our evaluation.
Should you have any questions on this matter, we will be pleased to discuss them with you.
JA T /PSF /WPM/ dlm cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble, NRC
(
88os200335 e:::os:t~
PPDR ADOCK 05000317 DCD
TABLE 8-1 KEY INPUT P/\llAMETERS Atm TllE IR IMPACT ON TllE LOSS OF LOAD EVENT Par;meter Sense of Chanqe Physical Impact Impact on Analytical Results Power Level lligher 1.. /\ higher initial power 1. No impact on transient results ex-level ~1ill initiate the cept that higher powers lower the initial ONBR and thus result in
\
event from conditions closer to SAFDLs. a lower transient minimum ONBR.
. i l
/\higher power will maximize *2. /\ higher power to steam space 2.
the power to pressurizer ratio will maximize the peak steam space ratio. pressure during the event.
lligher A bighe~ Tinlet will initiate* No impact on transient results except the event from conditions that a higher Tinlet lowers the initial co closer to SAFOLs. DNBR and thus results in a *lower tran- I
\.0 sient minimum ONBR.
RCS Pressure Lower 1. A lower initial pressure 1. No impact on minimum ONBR during will initiate the event the event since no credit is taken from conditions closer for the pressure increase.
to SAFDLs.
- 2. A lower initial pressure 2. Lower initial pressure delays delays the time of high time of trip. This maxi~izes pressurizer pressure trip the rate of change of pressure and thus maximizes the.rate at time of trip and t~~s res~]ts of pressure change at time in higher peak RCS pressures~
of trip.
*- *---~...=*=~-=*"~--*-=-*=**-~~--~ .. *--*-------------*--*---**-*--.
i TABLE B-1 (continued)
Par;*r.1eter Sense of Change Phys1cal Impact Impact on Analyt1cal Results MTC More Positive A more positive MTC in combina- 1. Increasing core average heat flux (i.e., BOC) tion with increasing coolant and coolant temperature result in tempera tu res wi 11 add greater lower. transient orrnn values.
positive reactivity. This in-creases the core power, heat 2. Maximizes the peak RCS pressure flux, coolant system pressure during the event.
and temperatures.
Doppler Less Negative A less negative Doppler 1. Results in higher core heat flux Coefficient (i.e., BOC) coe'fficient in combination and coolant temperatures and thus with increasing fuel minimizes the transient DNBR. ~
temperatures, adds less I negative reactivity 2. Maximizes the peak RCS pressure. 0 ThiS maximizes the increase in power, heat flux, coolant temperature and pressure.
Ii Mi~her Allows the heat flux to follow 1. Results in higher core average the power more closely. Also, heat flux and coo 1ant tempera tu res ilicreases the rate at \'1hich the and thus minimizes the transient heat generated within the fuel ONBR.
gets into the coolant and there-by increases the coolant 2. Maximizes the peak RCS pressure.
tempera lures and l~CS pressure.
- 1 I
0
\
0
Parm1eter Sense of Chanqe Physical Impact Impact on Analytical Results Initial Steam Lower A lower initial steam Maximizes the peak RCS pressure.
Generator . generator pressure delays Pressure the time when main steam safety
. valves open. The delay in opening the MSSVs increases the heatup of both the primary and secondary systems.
Axial Power Top Peaked A top peaked shape results in Minimizes transient DNBR.
Distribution higher enthalpy rise in the hot channel.
Sera~ Positive Scram reactivity insertion l. Maximizes core average heat flux, neactivity associated with a positive and coolant temperatures.
Curve (i.e. 1 reactivity inserted after ASI) a reactor trip. This maxi- 2. Maximizes RCS pressure.
rni zes the power, heat flux, coolant temperature and pressure overshoot.
Pressurizer Inoperable (i.e., More pronounced transient *
- Maximizes peak RCS pressure.
Pressure no sprays or PROVs) variations in primary Control pressure.
System
