|
---|
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
1
[AS,at: o UNITEJ STATES y n NUCLEAR REGULATORY COMMISSION REGloN il 3 Ij
e ATLANTA. GEORGI A 30323
- ME 3 01985 MEMORANDUM FOR: Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response, IE FROM:
Paul R. Bemis Director Division of Reactor Safety
SUBJECT:
INTERPRETATIONS OF 10 CFR 50.59 AND 10 CFR 50.72 Recently, two separate equipment problems at the Robinson facility have raised questions concerning the NRC approval portion of 10 CFR 50.59 and the reporting requirements of 10 CFR 50.72. Although both problems were in separate unrelated b,eing outside their " design basis". systems, they share a commonality in that In the first equipment problem, the logic controlling Main Steam Isolation Valve (MSIV) should closure,the an Itce isolation Safety signal be Features generated (ESF) trains. from either one of the two redundant Engineering (Detatis discussed in inspection report 261/84-53 and LER 85-002.) The updated Final Safety Analysis Report (FSAR) provides a description and analysis for the Steam System Piping Failure Accident. As stated in the FSAR, the MSIV valve arrangement is expected "to prevent the blowdown of close."than one steam generator for any break location, even if one valve fails to more As originally constructed, the MSIV logic did not provide this protection "B" for all steam line breaks in the event of a single failure in the ESF logic train.
A break in the piping downstream of the main steam check valves and the failure of a single active component in the ESF "B" train would result in the blowdown of both the "B" and "C" steam generators.
In the second case, a licensee review of safety-related loads on two 480 VAC Motor Control Centers (MCCs) revealed that several of the loads had oversized overcurrent trip devices, in that an instantaneous trip of one of there devices would also cause the MCC feeder breaker to trip, resulting in loss of power to all the loads on the MCC. (Details discussed in inspection report 261/85-08 and LER 85-008.) A further review revealed that a design drawing documented the installed devices to be the correct size.
10 CFR 50.2 defines " Design Basis" to be information which identifies the specific functions to be performed by a structure, system, or component of a factitty, and the specific values or ranges of values chosen for controlling parameters as reference bounds for design.
derived from generally accepted " state of the art"These values may be (1) restraints functional goals, or 2) requirements derived from practices for achieving analysis (based on calculations and/or expe(riments) of the effects of a postulated foraccident which a structure, system, or component must meet its functional goals.
me F edrickson -
H Edward L. Jordan ,
2 .
MAY 3 01985 10CFR50.72(b 1)(it)(B) requires that the licensee notify the NRC within one hourbeing plant of any eve)n(t in a condition thator condition during operation that re is outside the design basis of the plant.
Clearly, basis the MSIV problem was outside the equipment design basis and the accident and thus, resulted in "the nuclear power plant being in a
. condition that is outside the design basis of the plant." In comparison to the basis and thus by extrapolation, was also outside the "
plant."
The difference is that while the MSIV problem was beyond the design i basis accident, the FSAR. the trip device was not, in that loss.cf one MCC is analyzed in The trip device difference raises an interpretation concerning the wording of 10 CFR 50.72.
In that the 10 CFR 50.72(b) question (1)(11 requirements state "outside the design basis of the plant" and not "outside the design basis accident," the most conservative position is that any equipment condition that places that item cutside its design basis is reportable, irrespective of the effect on the design basis accident. The Region II position ' '
is that and that" design basis of the plant" refers to the design basis accident analysis individual items being beyond their design basis 3 10 CFR 50.2 does not necessarily require reporting under 10 CFR 50.72.as defined in i L
Similar to of question theapplicability 10 CFR 50.72 criteria. question, the wording of 10 CFR 50.59 also raises a t Experiments," enables the holder of a10 CFR 50.59, titled " Changes, Tests and license authorizing operation of a utilization facility to make changes in the facility "as described" in the FSAR without prior NRC approval, provided several specific conditions are met.
Although the MSIV and MCC systems are " described" in the FSAR, the as-built and thus each system was not "as described"With in the FSAR. condit changes to systems tation is "that described" in the FSAR, but not "as described", the literal interpre- .
licensees must receive NRC approval prior to making these In mod fact, withexists question equipment outside with the equipment its design as-built. basis, a potential unreviewed safety The Region 11 position is that if a ,
i modification will correct the discrepancy so that the system becomes ' "as described" in the FSAR, th'en 10 CFR 50.59 applies and evaluation of the modif t-cation in accordance with 10 CFR 50.59 should be conducted by the licensee.
Region II requests that you review these generic questions as they relate to the intentthat from of 10 CFR 50.5g proposed and 10 by Region II. CFR 50.72 and inform us if the NRC position differs t A
! Paul R. Bemis
- M r
l
- i l
f I ;
t I
---,-.---------..,___.-e-- - _ . _ _ _ - - - - - - . . -