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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
[Table view] |
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6 BALTIMORE GAS AND ELECTRIC ,
1650 CALVERT CLIFFS PARKWAY . LUSBY, MARYLAND 20657-4702 ROBERT E DENTON VsCE PRE 51 DENT NUCLE AR ENERGY (4so)200-4455 July 29,1993 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Ccmtrol Desk i
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 ,
Installation of a Neutron Shield / Pool Seal at Calvert Cliffs Units 1 and 2 ,
REFERENCES:
(a) Topical Report CEN-367-A, " Leak Before Break Evaluation of l Primary Coolant Piping in Combustion Engineering Designed Nuclear Steam Supply Systems, February 1991 7
(b) Letter from Mr. J. E. Richardson (NRC) to Mr. E. C. Sterling l (CEOG), dated October 30, 1990, Acceptance for Referencing of !
Topical Report CEN-367,
- Leak-Before-Break Evaluation of Primary l Coolant Imop Piping in Combustion Engineering Designed Nuclear :
Steam Supply Systems" l
Baltimore Gas and Electric Company (BG&E) plans to install a permanent neutron shield / pool seal over the reactor vessel annulus in both Calvert Cliffs Units 1 and 2. We expect the new shield to ,
reduce BG&E's personnel radiation exposure rates long term by reducing the time and the number ;
of personnel required to install and remove the existing neutron shield and pool seal. We also expect to decrease our outage times by reducing the time it takes to establish a good seal and restore the reactor vessel annulus to its normal operating condition. The shield deJgn and installation requires a change to our compliance with General Design Criteria (GDC) 4. As required by GDC 4, we are submitting our leak-before-break analysis to allow us to exclude a rupture of the primary reactor i coolant piping from our design basis. This will allow us to close off the top of the reactor vessel annulus with the neutron shield / pool seal. A description of the permanent neutron shield / pool sealis provided in Attachment (1).
Reference (a) is a description of the leak-before-break analysis performed by Combustion Engineering for their nuclear steam supply systems. The report is applicable to Calvert Cliffs. This topical report has been approved for our use by the NRC (Reference b). We wish to reference the topical report in support of the neutron shield installation. A brief discussion of the applicability of the report to Calvert Cliffs is provided in Attachment (2). In addi' ion to the leak-before-break analysis, the report requires that we submit a description of our leakage detection system to ensure it has the necessary sensitivity. This information is provided in Attachment (3). , i 9308050096 930729 PDR n e. ~ .--
ADOCK 05000317
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Document Control Desk July 29,1993 Page 2 By this letter, we are informing the NRC that we intend to use CEN-367-A as 9 technical basis for
] applying leak-before-break to the primary coolant piping. In addition, we are providing a description of the leakage detection system at Calvert Cliffs. We request NRC concurrence that installation of a
)) ~
permanent neutron shield over our reactor vessel annulus is consistent with GDC 4. We anticipate installing the new neutron shield / pool seal in Unit I during the scheduled refueling outage in the opring 1994. Therefore, we request NRC concurrence by January 15, 1994. The new neutron shield / pool seal is scheduled to be installed in Unit 2 in the spring 1995 refueling outage.
L Should you have any questions regarding this matter, we will be pleased to discuss them with you.
i Very truly yours,
~.
A
[ C RED / PSF / psf! dim Attachments: (1) Permanent Neutron Shield / Pool Seal Description ,
(2) Leak-Before-Break Analysis (3) Description of Leakage Detection System l
l cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. IL Walter. PSC l
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l
'. : I ATTACIIMENT (1) j PERMANENT NEUTRON SIIIELD/ POOL SEAL DESCRIPTION 1
The bottom of the refueling pool surrounds the upper part of the reactor vessel in the vicinity of the )
reactor vessel head flange for both Calvert Cliffs Units 1 and 2. During operation, a gap exists '
between the reactor vessel and the refueling pool floor. This gap is partially covered by a neutron shield, which consists of water bags supported by a steel frame. The neutron shielding is arranged so that adequate ventilation is maintained in the reactor vessel cavity. The forced ventilation cools the concrete and instrumentation in the cavity. During refueling operations, it is necessary to remove i the existing neutron shielding and seal this gap to prevent entry of the refueling pool water into the reactor vessel cavity. The hardware used to close this gap is a removable circular seal ring made of stainless steel plate with rubber gaskets attached. After refueling is completed and the refueling pool is drained, the seal ring is removed and the neutron shield is re-installed.
in an effort to minimize personnel exposure and decrease the potential for leakage into the reactor vessel c:.vity, a permanent neutron shield / refueling pool seal ring will be installed. The attached sketch (Figure 1) shows the top view of the proposed permanent neutron shield and seal ring. The removable hatches in the seal ring provide a pathway for ventilation air, a pathway for containment spray water to reach the sump, and provide access to excore instrumentation.
Before the refueling pool is flooded, hatches will be installed on each of the access holes. The covers contain a seal that will prevent leakage from the canal to t. reactor cavity. After the refueling pool is dromed, some of these hatches will be removed to provide a ventilation pathway during plant operatimns. The hatches are located so that access to the reactor cavity and reactor vessel nozzles is maintained for inspection purposes. Excore nuclear instrumentation can also be accessed through open hatches.
Under the permanent pool seal, neutron shield material will be installed. The shield ring consists of borated concrete, enclosed in a carbon steel assembly. This shield will ensure that neutron radiation leve' emain low in the containment. Figure 2 shows the proposed arrangement of the neutron sh' eld urer the pool seal.
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. ATTACINENT (2)
LEAK-BEFORE-BREAK ANALYSIS In October 1990, the N: J completed a review of Topical Report CEN-367-A, " Leak Before Break Evaluation of Primary Coolant Loop Piping in Combustion Engineering Designed Steam Supply Systems." This topical report forms the basis for ensuring that tl e probability of a pipe rupture in the primary system is sufficiently low that it no longer has to be considered in the design basis. This concept is allowed by General Design Criteria (GDC) 4.
The resised GDC 4 is based on the development of advanced fracture mechanics technology using i the leak-before-break concept. On October 27,1987, a final rule was published, amending GDC 4 of i Appendix A to 10 CFR 50. The revised GDC 4 allows the use of analyses to climinate from the design basis the dynamic effects of postulated pipe ruptures in the high energy piping. The new technology reflects an engineering advance which allows simultaneously an increase in safety, reduced worker radiation exposure, and lower maintenance costs. Implementation permits the ,
installation of a permanent neutron shield / pool seal. Although functional and performance !
requirements for containments, emergency cor; cooling systems, and emironmental qualification of i equipment remain unchanged, local dynamic sffccts uniquely associated with postulated ruptures in piping which qualified for leak-before-break may be excluded from the design basis. The acceptable technical procedures and criteria are defined in NUREG-1061, Volume 3. t Using the criteria given in NUREG-1061, the Combustion Engineering Owners Group (CEOG) !'
analyzed the primary coolant piping for Combustion Engineering plants and presented their results in Topical Report CEN-367-A. The report covers the primary coolant piping for Calvert Cliffs Units 1 and 2. The NRC reviewed and approved the report in a Safety Evaluation Report dated :
October 30,1990. The NRC Staff found that the CEOG plants (which includes Calvert Cliffs) are in compliance with GDC 4, with a limitation. The NRC Staff did not review CEOG plants' leak detection systems for conformance to Regulatory Guide 1.45. Therefore, we ace submitting a description of our conformance with Regulatory Guide 1.45 in Attachment 3.
The CEOG Topical Report specifically included Calvert Cliffs' primary coolant piping, with the exception of the pressurizer surge line, in the scope of the analysis. We have reviewed the primary i coolant piping layout in our plant to ensure there are no additional lines which should have been included in the analysis. We have found no additionallines. Therefore, the conclusion of the CEOG Topical Report applies to Calvert Cliffs without modification.
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ATTACilMENT (3) i DESCRIPTION OF LEAKAGE DFTECTION SYSTEM 1
ne leakage detection system for the Reactor Coolant System is described in detail in Section 4.3 of our Updated Final Safety Analysis Report. This system complies with the guidance given in 4 Regulatory Guide 1.45 (May 1973) as described below.
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- 1. Requirement Leakage to the primary reactor containment from identified sources should be collected or otherwise isolated so that:
> the flow rates are monitored separately from unidentified leakage, and
> the total Ib' rate can be established and monitored.
Method of Compth.m i r
Identified leakage is defined as any leakage into a closed system, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank. Other sources of identified leakage includ. leakage into the containment atmosphere from sources that are both specifically known either not to interfere with the operation of the leakage detection systems or not to be pressure boundary leakage. Additionally, reactor coolant leakage through a steam generator to the secondary system is considered identified leakage.
Section 4.3.2.2 of the UFSAR describes the instrumentation available to determine the k> cation of identified leakuge. Methods exist for identifying leakage from the relief and ,
safety valves, the reactor vessel head closure seal, the reactor coolant pump seals, the steam generator tubes or tubesheets, and any miscellaneous Reactor Coolant System valve stem i leakage. ;
- 2. Requirement leakage to the primary reactor containment from unidentified sources should be collected and the flow rate monitored with an accuracy of one gallon per minute (gpm) or better.
Method of Compliance .
Unidentified leakage is any leakage which cannot be classified as identified leakage as I defined above. leakage from the Reactor Ccalant System to the containment is collected in i the containment sump. The sump level is alarmed and the sump is drained when the wate j reaches a pre-set level. The frequency of draining the sump determines the leakage flow i rate. This m-thod has an accuracy of determining leakage of one gpm in less than one hour.
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ATTACllMENT (3)
DESCRIPTION OF LEAKAGE DFT. ECTION SYSTEM
- 3. Requirement At least three separate detection methods should be employed and two of these methods should be: (1) sump level and flow monitoring and; (2) airborne particulate radioactivity I monitoring. The third method may be selected from the following:
> monitoring of condensate flow rate from air coolers ,
e monitoring of airborne gaseous radioactivity.
Ilumidity, temperature, or pressure monitoring of the containment atmosphere should be considered as alarms or indirect indication of leakage to the containment.
Method of Compliance ,
We have three methods of leakage detection. Two of them are the required methods of monitoring the sump level and airborne particulate radioactivity. The third method we chose was to monitor airborne gaseous radioactivity. In addition, Section 4.3 of the UFSAR contains a discussion of the sensitivity of changes in containment humidity, temperature and pressure to the leakage size.
- 4. Requirement l Provisions should oc made to monitor systems connected to the reactor coolant pressure boundary (RCPB) for signs of intersystem leakage. Methods should include radioactivity monitoring and indicators to show abnormal water levels or flows in the affected areas.
'r Method of Comoliance The following systems are connected to the Reactor Coolant System: ;
Chemical and Volume Control System - Leaks in the Reactor Coolant System may be detected while the plant is at power by performing an inventory balance calculation using parameters such as pressurizer level, volume control tank level, le:down flow, reactor coolant drain tank level, coolant temperature and charging flow rate. Process radiation monitors are i provided to continuously measure the activity of the reactor coolant.
Reactor Coolant Loop Drains. Ouench Tank Drains. Flance Leakace Detector Drains -
These drains are inside containment and drain to the containment sump. Both radiation and !
level monitors are provided for the containment as described in (3).
Reactor Coolant Pumn Seal Leakage - A controlled bleedoff flow through the pump seals is j maintained to cool the seals and to equalize th:: pressure drop across each seal. The !
controlled bleedoff is collected and processed by the Chemical and Volume Control System.
Any leakage past the vapor seal, the last mechanical seal is collected in the containment sump. A level alarm is provided for the sump. )
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ATTACIIMENT (3)
DESCRIPTION OF LEAKAGE DETECTION SYSTEM i
- 5. Reunirement The sensitivity and response time of each leakage detection system employed for unidentified ;
leakage should be adequate to detect a leakage rate, or its equivalent, of one gpm in less than one hour.
Method of Compliance The frequency of monitoring the leakage detection systems is given in Technical Specification 4.4.6.2. The sensitivity of the monitoring systems is dependent on a large number of factors, such as leak location, fuel burnup, etc. The sensitivity of the systems is ,
discussed in Section 4.3.2.3 of the UFSAR.
- 6. Requirement r
The leakage detection systems should be capable of performing their function following seismic events that do not require plant shutdown. The airborne radioactivity monitoring ,
system should remain functional when subjected to the safe shutdown earthquake.
I Method of Compliance ,
The leakage detection systems described in the response to (3) above, are seismically (
qualified. Therefore, they will perform their function following a safe shutdown earthquake. ;
- 7. Requireme_nt Indicators and alarms n.r each leakage detection system should be provided in the main !
control room. Procedures for converting various indications to a common leakage equivalent should be available to the operators. The calibration of the indicators should account for needed independent variables.
L Method of Compliance Alarms for each method of leak detection are provided in the main control room. Reactor Coolant System leakage is evaluated by the operators using Surveillance Test Procedure 0-27. This surveillance test procedure is an inventory balance method ofleakage ,
detection. The containment sump level alarm system channels are calibrated every 18 !
months, and the containment gaseous and particulate monitoring system channels are [
calibrated every 24 months in accordance with Technical Specification 4.4.6.1. The !
calibration accounts for the necessary independent variables. :
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. ATTACIIMENT (3)
DESCRIPTION OF LEAKAGE DETECTION SYSTEM )
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- 8. Requirement The leakage detection systems should be equipped with provisions to readily permit testing ;
for operability and calibration during plant operation. ;
Method of Compliance !
The three systems identified in the response to (3), above, are designed to permit channel checks and channel functional tests to be performed while the plant is at power. >
- 9. Requirement The technical specifications should include the limiting conditions for identified and unidentified leakage and address the availability if vario:ut types of instruments to assure adequate coverage at all times. t Method of Compliance Technical Specification 3.4.6.2 provides the limiting conditions for identified and unidentified reactor coolant leakage. Technical Specification 3.4.6.1 addresses the availability of the leakage detection systems and provides for grab samples if a system is out of service. ;
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