Letter Sequence Other |
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MONTHYEARML20236L6531995-07-0707 July 1995
Responds to 950330 TIA 95-002 Requesting NRR Review Design & Licensing Basis for TS 3.2 Re Operability of CVCS at Plant Unit 2.Since Charging Pumps Do Not Perform Any ECCS Function Pumps Not Required to Be Powered from Normal & EP Sources
Project stage: Other
ML20236L9211995-07-14014 July 1995
Responds to 950330 TIA 95-002 Request for Technical Assistance in Evaluation of Licensee Position on TS Compliance & Operability of Chemical & Volume Control Sys for Plant,Unit 2.TAC Closed
Project stage: Other
1995-07-14
[Table View] |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20153B4531998-09-0404 September 1998
Notification of Cancellation of 980924 Meeting with TVA in Rockville,Md to Discuss Review of Best Estimate of LOCA Methodology at Plant,Unit 2
ML20236W8131998-08-0404 August 1998
Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72
IR 05000261/19963011997-01-24024 January 1997
Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 960816-24 for Rept 50-261/96-301
ML20128G5751996-10-0303 October 1996
Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations
ML20236X0131996-09-12012 September 1996
Informs That NRC Has Given Exemptions to 72.122(i) to Robinson,Calvert & Oconee.Basis Was That Due to Passive Design & Inherent Safety of NUHOMS-7P Cask,No Instrumentation Required for Dry Shielded Cannister
ML20134B7921996-06-24024 June 1996
Discusses Results of Audit Review of Changes to Siemens Large Break ECCS Evaluation Model
ML20236L9211995-07-14014 July 1995
Responds to 950330 TIA 95-002 Request for Technical Assistance in Evaluation of Licensee Position on TS Compliance & Operability of Chemical & Volume Control Sys for Plant,Unit 2.TAC Closed
ML20236L6531995-07-0707 July 1995
Responds to 950330 TIA 95-002 Requesting NRR Review Design & Licensing Basis for TS 3.2 Re Operability of CVCS at Plant Unit 2.Since Charging Pumps Do Not Perform Any ECCS Function Pumps Not Required to Be Powered from Normal & EP Sources
ML20149K1731994-12-13013 December 1994
Forwards Allegation Evaluation Rept of Allegation RII-93-A-0125 Re Harassment for Reporting Erosion/Corrosion Problems at CP&L Hb Robinson
ML20149K1661994-06-0101 June 1994
Informs That H Christensen Conducted Review of Investigation Matl for Allegation RII-93-A-0125.Listed Info May Need to Be Paneled
IR 05000261/19920131994-01-11011 January 1994
Discusses Alleged Discrimination for Reporting Erosion/ Corrosion Problems to NRC & Forwards Insp Repts 50-261/92-13 & 50-261/93-20 Excerpts
ML20057B2671993-09-17017 September 1993
Forwards Rept WCAP-11104, Evaluation of Surveillance Capsule & Reactor Cavity Dosimetry Form Hb Robinson Unit 2, Cycle 9, Dtd Feb 1987 to Be Placed in PDR & Central Files
ML20057B1491993-09-14014 September 1993
Forwards Documents on Proposed rules,10CFR2 & 72 Re Interim Storage of Spent Fuel in Independent Spent Fuel Storage Installation & site-specific License to Qualified Applicant
ML20057B1891993-09-14014 September 1993
Requests Commission Approval of Proposed Rulemaking to Eliminate Requirement of Prior Commission Approval for Specific License for ISFSI Under 10CFR2 & 72.Notice of Proposed Rulemaking & Addl Info Encl
ML20138D0041991-04-0303 April 1991
Submits Results of 10CFR50.59 Safety Review Audit During Wk of 900827.New 10CFR50.59 Review Procedure Consistently Implemented & Quality of Safety Review Significantly Improved Over Reviews Conducted Prior to New Procedure
ML20136A8371990-06-21021 June 1990
Informs That Preliminary Test Results Indicate That Counterfeit Relays Provided to Util by Spectronics of Mobile,Al,Would Not Function in Normal Operation.Remaining Testing & Disassembly Should Be Completed by 900622
ML20235S6271989-02-28028 February 1989
Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl
ML20196E8731988-02-18018 February 1988
Forwards Rev to Guidance for Trial NRC Requalification Exams,Per Lessons Learned from Requalification Exams Administered in Dec 1987.Final Version Will Be Incorporated Into Examiner Stds When Trial Program Complete
ML20214L5831987-05-21021 May 1987
Summarizes 870519 Operating Reactors Events Meeting 87-15 to Brief Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870512 Meeting.Events Discussed & Significant Elements of Events Encl
ML20214H1251986-07-30030 July 1986
Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltr 85-09 & Generic Ltr 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee
ML20199F5781986-03-19019 March 1986
Requests Fire Protection SERs for CP&L & Northeast Utils Plants
ML20133F8921985-10-0202 October 1985
Notification of 851011 Meeting W/Exxon Nuclear Co,Inc in Bethesda,Md to Discuss Recent Exxon Activities Toward Resolving Safety Analysis Issues
ML20127F3061985-06-18018 June 1985
Forwards Tabular Summary of Key Results from Regional Survey of plant-specific Info Re Potential for Uncontrolled Radiation Exposures in PWR Cavities,Per Jg Partlow 850315 Request.No Further Generic Action Needed
ML20209E5411985-05-30030 May 1985
Requests Interpretation of 10CFR50.59 & 50.72 Re Facility safety-related Components Outside Design Basis
ML20126L2271981-05-0101 May 1981
Forwards Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Vessels
ML20153H1771981-02-19019 February 1981
Discusses Selection of Severity Level IV for 810114 Loss of Heat Tracing at Robinson 2.Mitigating Circumstances Listed
ML20235E9251972-12-21021 December 1972
Forwards to Applicants Re Consequences of Postulated Pipe Failures Outside Containment Structure
ML20125B4121972-07-11011 July 1972
Lists Facility Licensees Due to Be Billed for Annual Fees for Months of Jul,Aug & Sept 1972
ML20235N5961971-03-25025 March 1971
Discusses AEC Plans to Apply New Position Re Means for Providing Control of Combustible Gas Concentrations Following Design Basis LOCA in Water Cooled Nuclear Power Plants,Per Regulatory Info Meeting 422 on 700904
1998-09-04
[Table view]
Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20153B4531998-09-0404 September 1998
Notification of Cancellation of 980924 Meeting with TVA in Rockville,Md to Discuss Review of Best Estimate of LOCA Methodology at Plant,Unit 2
ML20236W8131998-08-0404 August 1998
Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72
IR 05000261/19963011997-01-24024 January 1997
Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 960816-24 for Rept 50-261/96-301
ML20128G5751996-10-0303 October 1996
Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations
ML20236X0131996-09-12012 September 1996
Informs That NRC Has Given Exemptions to 72.122(i) to Robinson,Calvert & Oconee.Basis Was That Due to Passive Design & Inherent Safety of NUHOMS-7P Cask,No Instrumentation Required for Dry Shielded Cannister
ML20134B7921996-06-24024 June 1996
Discusses Results of Audit Review of Changes to Siemens Large Break ECCS Evaluation Model
ML20236L9211995-07-14014 July 1995
Responds to 950330 TIA 95-002 Request for Technical Assistance in Evaluation of Licensee Position on TS Compliance & Operability of Chemical & Volume Control Sys for Plant,Unit 2.TAC Closed
ML20236L6531995-07-0707 July 1995
Responds to 950330 TIA 95-002 Requesting NRR Review Design & Licensing Basis for TS 3.2 Re Operability of CVCS at Plant Unit 2.Since Charging Pumps Do Not Perform Any ECCS Function Pumps Not Required to Be Powered from Normal & EP Sources
ML20149K1731994-12-13013 December 1994
Forwards Allegation Evaluation Rept of Allegation RII-93-A-0125 Re Harassment for Reporting Erosion/Corrosion Problems at CP&L Hb Robinson
ML20149K1661994-06-0101 June 1994
Informs That H Christensen Conducted Review of Investigation Matl for Allegation RII-93-A-0125.Listed Info May Need to Be Paneled
IR 05000261/19920131994-01-11011 January 1994
Discusses Alleged Discrimination for Reporting Erosion/ Corrosion Problems to NRC & Forwards Insp Repts 50-261/92-13 & 50-261/93-20 Excerpts
ML20057B2671993-09-17017 September 1993
Forwards Rept WCAP-11104, Evaluation of Surveillance Capsule & Reactor Cavity Dosimetry Form Hb Robinson Unit 2, Cycle 9, Dtd Feb 1987 to Be Placed in PDR & Central Files
ML20057B1491993-09-14014 September 1993
Forwards Documents on Proposed rules,10CFR2 & 72 Re Interim Storage of Spent Fuel in Independent Spent Fuel Storage Installation & site-specific License to Qualified Applicant
ML20057B1891993-09-14014 September 1993
Requests Commission Approval of Proposed Rulemaking to Eliminate Requirement of Prior Commission Approval for Specific License for ISFSI Under 10CFR2 & 72.Notice of Proposed Rulemaking & Addl Info Encl
ML20138D0041991-04-0303 April 1991
Submits Results of 10CFR50.59 Safety Review Audit During Wk of 900827.New 10CFR50.59 Review Procedure Consistently Implemented & Quality of Safety Review Significantly Improved Over Reviews Conducted Prior to New Procedure
ML20136A8371990-06-21021 June 1990
Informs That Preliminary Test Results Indicate That Counterfeit Relays Provided to Util by Spectronics of Mobile,Al,Would Not Function in Normal Operation.Remaining Testing & Disassembly Should Be Completed by 900622
ML20235S6271989-02-28028 February 1989
Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl
NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989
Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants
ML20196E8731988-02-18018 February 1988
Forwards Rev to Guidance for Trial NRC Requalification Exams,Per Lessons Learned from Requalification Exams Administered in Dec 1987.Final Version Will Be Incorporated Into Examiner Stds When Trial Program Complete
ML20214L5831987-05-21021 May 1987
Summarizes 870519 Operating Reactors Events Meeting 87-15 to Brief Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870512 Meeting.Events Discussed & Significant Elements of Events Encl
ML20214H1251986-07-30030 July 1986
Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltr 85-09 & Generic Ltr 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee
ML20199F5781986-03-19019 March 1986
Requests Fire Protection SERs for CP&L & Northeast Utils Plants
ML20133F8921985-10-0202 October 1985
Notification of 851011 Meeting W/Exxon Nuclear Co,Inc in Bethesda,Md to Discuss Recent Exxon Activities Toward Resolving Safety Analysis Issues
ML20127F3061985-06-18018 June 1985
Forwards Tabular Summary of Key Results from Regional Survey of plant-specific Info Re Potential for Uncontrolled Radiation Exposures in PWR Cavities,Per Jg Partlow 850315 Request.No Further Generic Action Needed
ML20209E5411985-05-30030 May 1985
Requests Interpretation of 10CFR50.59 & 50.72 Re Facility safety-related Components Outside Design Basis
ML20126L2271981-05-0101 May 1981
Forwards Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Vessels
ML20153H1771981-02-19019 February 1981
Discusses Selection of Severity Level IV for 810114 Loss of Heat Tracing at Robinson 2.Mitigating Circumstances Listed
ML20235E9251972-12-21021 December 1972
Forwards to Applicants Re Consequences of Postulated Pipe Failures Outside Containment Structure
ML20125B4121972-07-11011 July 1972
Lists Facility Licensees Due to Be Billed for Annual Fees for Months of Jul,Aug & Sept 1972
ML20235N5961971-03-25025 March 1971
Discusses AEC Plans to Apply New Position Re Means for Providing Control of Combustible Gas Concentrations Following Design Basis LOCA in Water Cooled Nuclear Power Plants,Per Regulatory Info Meeting 422 on 700904
1998-09-04
[Table view] |
Text
___ ___
. ATTACm!DT n
- "'4 4g a* *t UNITED STATES i
j NUCLEAR REGULATORY COMMISSION WASHINGTON. 0.C. 30eeHoot J
k * . .l . ,/ July 7, 1995 l
MEMORANDUM TO: David B. Matthews, Project Director Project Directorate !!-l Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation .
FROM: Jose A. Calvo, Chief Electrical Engineering Branch * ' (* '
Division of Engineering Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR TECHNICAL ASSISTANCE - EVALUATION OF H. B. ROBINSON UNIT 2 POSITION PERTAINING TO TECHNICAL SPECIFICATION COMPLIANCE AND OPERABILITY OF CHEMICAL AND VOLUME CONTROL SYSTEM (TAC NO. M92012)
In Task Interface Agreement 95-002 sent to J. A. Zwolinskt on March 30, 1995 E. W. Herschoff (Region 11) requested that NRR review the design and licensing basis for the chemical and volume control system (CVCS) charging pumps and interpret Technical Specification (TS) 3.2 regarding the operability of the CVCS at H. B. Robinson Steam Electric Plant Unit 2 (HBR2).
TS 3.2.2 requires, in part, that the reactor not be made critical unless two charging pumps are operable. Operability (i.e., of the CVCS charging pumps) is defined in TS Definition 1.3 as follows:
A system, subsystem, train, component or device shall be operable or have operability when it is capable of performing its spectfled function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emeroency electrical power sources, cooling or seal water, lubrication or other auxtllary equipment that are required for the system, subsystem, train, component or device to perform its specified function (s) are also capable of performing their related support function (s).
Of the three positive displacement charging pumps (A, B, and C) installed at HBR2 for the CVCS function, only two (B and C) have normal (offsite power) and emergency (emergency diesel generators) electrical power sources; the A charging pump is powered from only the normal electrical power source.
CONTACT: P. Kang. EELB/DE 415-2779 9807130112 980624 ER -155 PDR
~
. . o
, David B. Matthews The licensee has been regularly removing either 8 or C charging pumps from service for routine maintenance / surveillance and has been regarding the A charging pump as a fully operable replacement for either the 8 or C pump removed from service. Because the resident inspector believed that the Itcensee's A pump replacement activity violated the TS, he asked the licenses to explain its position.
In response to the inspector's concern, the licensee reviewed the original CVCS design and found that the CVCS charging pumps at HBR2 are neither designed to perform any emergency core cooling system (ECCS) functions nor given any credit in the accident analyses. Although two power sources (normal and emergency) happen to be available for two of the three charging pumps, they are designed to be run by the normal power source only. One charging pump is adequate for normal CVCS makeup function of the reactor coolant system, and the use of any two pumps (i.e., considering a single failure) of the three charging pumps meets TS 3.2.2 for making the reactor critical. The Itcensee took a position that this was consistent with its original CVCS design and its current Ilcensing basis, thus satisfying TS 3.2 for CVCS operability at HBR2.
To ascertain the validity of the Itcensee's position, Region !! requested that NRR interpret TS 3.2 regarding CVCS operability.
The staff reviewed the Westinghouse plant design and licensing basis for its charging pump. It found that one of the design function of the CVCS is to maintain the proper water inventory in the reactor coolant system. Because of this function, a small-break loss-of-coolant accident can be accommodated by the charging pumps. In fact, In Westinghouse design two of the three charging pumps in ing plants are designed to serve as high head injection pumps during accident conditions. For those plants at which the ECCS function is performed, two of the three CVCS charging pumps are required to be on the safety buses that are powered from both normal and emergency power sources, while the third pump is powered from only the normal power source.
The staff reviewed the licensing and design basis for HBR2's ECCS and CVCS regarding the use of the charging pumps in the updated final safety analysis report (FSAR). It also reviewed the accident analyses in Chapter 15 of the updated FSAR for the plant systems and components required for pitigating accidents. During this review, the staff found that the ECCS function at HBR2 ts performed by three passive cold leg accumulators, three safety injection (high head) pumps, and two residual heat removal (low head) pumps. Thus, the CVCS charging pumps are neither used for~ accident mitigation nor given any +
credit in the accident analysis for HBR2.
Based on the above, the staff concludes that since the charging pumps at HBR2 do not perform any ECCS function, they are not required to be powered from normal as well as emergency power sources. Therefore, only normal power is
! sufficient for these pumps to meet their operability requirements.
(
- David B. Matthews l On June 3, 1995, the licensee submitted a TS amendment to clarify HBR2 TS 3.2 regarding the charging pumps and their operability.
l Docket No.: 50-261 l
l I
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