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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 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) 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 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 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 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 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) ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 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 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 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 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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 ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) 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 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 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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) ML20195B3751999-05-25025 May 1999 Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii) 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 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 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 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 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
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Routui V. DENtoN Baltimore Gas and Electric Company Mce President Calvert Cl@ Nuclear Power Plant NucIcar Energy 1650 Ccdvert CliVs Parkway (2nby. Maryland 2065 7 410 586-2200 Err. 4455 local 410 260-4455 Bal:imore l
l October 13,1094 1
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U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTiDN: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Use of NUREG-0800 Standard Review Plan Guidance in Evaluating the Need for Tomado-Generated Misrile Barriers Baltimore Gas and Electric Company hereby proposes a change to the methodology used to evaluate the need for tornado missile protection for Calvert Cliffs Nuclear Power Plant (CCNPP), Units I and 2. The proposed methodology change will allow the use of Probabilistic Risk Assessment (PRA) techniques, consistent with NUREG-0800, Standard Review Plan (SRP), to evaluate the need for structural barriers to protect against tomado-generated missiles. NRC approval of this proposed change is requested.
DESCRIPTION OF Cil ANGE The Updated Final Safety Analysis Report (UFSAR) will be changed to allow the use of PRA techniques in evaluating the need for tornado-generated missile barriers. Probability of exposures in excess of 10 CFR Part 100 guidelines ofless than 104 per year per unit due to postulated tornado-generated missile strikes will be used as a conservative threshold for evaluating our compliance with draft General Design l Criteria (GDC) 2. Existing plant conditions, as well as future changes to the facility, may be evaluated using this revised methodology, and determined acceptable if the total probability of exposures in excess of 10 CFR Part 100 guidelines due to postulated tornado-generated missile strikes is less than 104 per year per unit. The UFSAR will be updated on the normal cycle with a list of affected plant areas which are not designed, fabricated or erected to withstand the additional forces imposed by tornado-generated missile strikes. The list will be a subset of those systems, structures and components (SSCs) identified as
" essential" in response to GDC 2. The total probability from all listed SSCs will be rnaintained below the 104 per year per uuit threshold. The only known SSCs for inclusion in the next update will be the existing Emergerry Diesel Generator (EDG) engines' intake air filter, exhaust piping and mufflers.
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Document Control Desk October 13,1994 Page 2 BACKGROUND As stated in our Final Safety Evaluation Report submittal (1971), the plant design and construction proceeded based upon the intent of the 1967 draft GDC. Draft GDC 2 states, "Those systems and components of reactor facilities which are essential to the prevention of accidents which could affect the public health and satty or to mitigation of their consequences shall be designed, fabricated, and erected to performance standards that will enable the facility to withstand, without loss of the capability to protect the public, the additional forces that might be imposed by natural phenomena such as carthquakes, tornadoes, flooding conditions, winds, ice, and other local site effects. The design bases so established shall reflect: (a) appropriate consideration of the most severe of these natural phenomena that have been recorded for the site and surrounding area, and (b) an appropriate margin for nithstanding forces greater than those recorded to reflect uncertainties about the historical data and their suitability as a basis for design."
The Calvert Cliffs Final Safety Analysis Report, Appendix 1 A, provided a list of SSCs essential to incident prevention and mitigation ofincident consequences. The list of essential systems includes " electrical power sources."
The original CCNPP licensing basis assumed a tornado-generated missile strike to exposed essential components. Accordingly, barriers to protect certain critical components against these postulated missiles l
were designed and constmeted. While conducting a review in support of construction efforts associated with our new EDGs, we identified components of equipment subsystems required to mitigate the consequences of accidents which are not protected from tornado-generated n-issiles. The specific components identified are the existing EDG engines' intake air filter and exhaust piping and muflier. He .
unprotected components are located on the roof of the seismic Class I Auxiliary Building.
Our EDGs are defined as systems which mitigate the consequences of an accident. The Calvert Cliffs site currently has three EDGs. Normally, No.1I EDG is dedicated to Unit 1, No. 21 EDG is dedicated to :
Unit 2, and No.12 EDG is able to swing to either Unit. Each EDG is enclosed in a separate room in the Auxiliary Building. He Auxiliary Building is a Class I structure, one of whose functions is to protect the EDGs and their support systems from severe weather effects. The only EDG components which are exposed to outside weather effects are the engine intake air filter and exhaust piping and mutiler. They extend through the roof of the Auxiliary Building. The top of the intake air filter is approximately 9' above the roof elevation, while the exhaust piping extends to an elevation of approximately 26' above the roof elevation. Most of the intake air filter and a portion of the exhaust piping, including the entire muf!1er, is located behind a 7'-6" high parapet wall along the west side of the roof; however, this parapet does not provide complete protection from all postulated tornado missiles.
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Document Control Desk October 13,1994 Page 3 TECllNICAL JUSTIFICATION A PRA was conducted to determine the risks associated with postulated tornado-generated missile strikes on exposed EDG engine air intake and exhaust piping and components. The PRA determined that the probability of potential exposures in excess of 10 CFR Part 100 guidelines occurring as a result of tornado-generated missile strikes on the subject components is approximately 10-8 per year (Attachment 1).
The PRA results were evaluated in light of SRP Section 3.5.1.4, Missiles Generated by Natural Phenomena, using the acceptance criteria specified in SRP Section 2.2.3, Evaluation of Potential Accidents. Table 1 provides a comparison of the SRP and the proposed licensing basis for CCNPP.
Table 1 SRP and CCNPP Proposed Licensing Basis Acceptance Criteria Comparison SRP Section 3.5.1.4, Revision 2, The methodology ofidentification of appropriate Missiles Generated by Natural Phenomena design basis missiles generated by natural phenomena shall be consistent with the acceptance criteria defined for the evaluation of potential accidents from external sources in SRP Section 2.2.3.
SRP Section 2.2.3, Revision 2, The expected rate of occurrence of potential Evaluation of Potential Accidents exposures in excess of 10 CFR Part 100 guidelines of approximately 104per year is acceptable if, when combined with reasonable qualitative arguments, the realistic probability can be shown ;
to be lower.
CCNPP Unit Nos.1 & 2 Tomado-generated missile protection is not Proposed Licensing Basis reo,uired for systems designed to meet the perfonnance standards of dran GDC 2 if the resultant aggregate probability of exposures in excess of 10 CFR Part 100 guidelines is less than 104 per year.
Document Control Desk October 13,1994 Page 4 NUREG-0800, SRP Section 3.5.1.4, Revision 2, and Section 2.2.3, Revision 2 provides a conservatively as:eptable threshold for safety due to damage caused by postulated missile strikes. We have chosen to implement the acceptance criteria of these SRP sections to evaluate the necessity of providing tornado t
missile protection for systems designed to meet the performance standards of draft GDC 2. The attached PRA evaluation for the EDG air intake and exhaust components identifies conservative assumptions which indicate that the actual probability is substantially lower.
The acceptance threshold of 10 4 per year for exposures in excess of 10 CFR Part 100 guidelines due to a I postulated missile strike is negligible when compared to the overall probability for core damage for CCNPP Units I and 2. The magnitude of the acceptance criteria is so small that this methodology change will not involve an increase in the probability or consequences of an accident or malfunction of equipment.
Therefore, this methodology change does not adversely impact plant safety. This methodology is consistent with the work being performed for the Individual Plant Examination of External Events.
SCIIEDULE 1
This methodology change is requested to be approved and issued by March 15, 1995. Ilowever, issuance of this change is not currently identified as having an impact on outage completion or continued plant operation.
Should you have any questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, I
RED /NII/ dim
Attachment:
Probabilistic Risk Assessment Evaluation of Tornado-Generated Missile Impact on the Calvert Cliffs Nuclear Power Plant Emergency Diesel Generator Engine Air Intake and Exhaust cc: D. A. Brune, Esquire J. E. Silberg, Esquire M. J. Case, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R.1. McLean, DNR J. II. Walter, PSC i
.