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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study ML20137U2051997-04-14014 April 1997 Informs That Davis-Besse Nuclear Power Station Nuclear Assurance Dept Will Be Reorganized Into Two Separate Dept; DB Nuclear Assurance & DB Nuclear Support Svc,Effective, 970414 ML20136F9491997-03-13013 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Progress on Thermo-Lag Issue Resolution ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination ML20059H8361994-01-19019 January 1994 Notification of 940201 Meeting W/Util in Rockville,Md to Discuss Pending Davis-Besse Licensing Actions ML20057F1311993-10-0707 October 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Davis-Besse Implementation of Reg Guide 1.97 for Steam Generator Pressure Instruments ML20127N6121993-01-25025 January 1993 Notification of 920205 Meeting W/Util in Rockville,Md to Discuss Emergency Action Levels Proposed Rev,Submitted 930112 ML20127C0411993-01-0808 January 1993 Notification of 930112 Meeting W/B&W Owners Group in Clearwater Beach,Fl to Discuss Generic Program Plan for License Renewal Initiative ML20127F5461993-01-0707 January 1993 Notification of 930115 Meeting W/Util in Rockville,Md to Discuss Plant Containment Penetration Bellows Tests.Draft Agenda Encl ML20126F5541992-12-0808 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend to Change from Automatic to Manual Closure of Containment Purge & Exhaust Valves in Mode 6 ML20128C2071992-11-0606 November 1992 Notification of 921202 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance ML20127C4131992-07-24024 July 1992 Responds to 910322 Memo Requesting Assistance on Whether 10CFR50.59 Review Should Have Been Performed for Broken Pipe in Station Drainage & Discharge Sys Releasing low-level Radioactivity Onsite ML20059D2711990-08-0606 August 1990 Discusses Review of State of Oh & Local Radiological Emergency Response Plans.Determined That No Issues Identified During 890809-09 Exercise to Prevent Finding of Reasonable Assurance for Site ML20148T1891990-04-10010 April 1990 Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N8091989-08-30030 August 1989 Notification of 890907 Meeting W/Util in Rockville,Md to Discuss Exemption from App R to 10CFR50 for Specific Configuration of Pressurizer Instrumentation ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20244A4611989-06-0606 June 1989 Notification of 890615 Meeting W/Util & Westinghouse Owners Group in Rockville,Md to Discuss Reactor Vessel Support Embrittlement ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS 1999-03-26
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study ML20137U2051997-04-14014 April 1997 Informs That Davis-Besse Nuclear Power Station Nuclear Assurance Dept Will Be Reorganized Into Two Separate Dept; DB Nuclear Assurance & DB Nuclear Support Svc,Effective, 970414 ML20136F9491997-03-13013 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Progress on Thermo-Lag Issue Resolution ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination ML20059H8361994-01-19019 January 1994 Notification of 940201 Meeting W/Util in Rockville,Md to Discuss Pending Davis-Besse Licensing Actions ML20057F1311993-10-0707 October 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Davis-Besse Implementation of Reg Guide 1.97 for Steam Generator Pressure Instruments ML20127N6121993-01-25025 January 1993 Notification of 920205 Meeting W/Util in Rockville,Md to Discuss Emergency Action Levels Proposed Rev,Submitted 930112 ML20127C0411993-01-0808 January 1993 Notification of 930112 Meeting W/B&W Owners Group in Clearwater Beach,Fl to Discuss Generic Program Plan for License Renewal Initiative ML20127F5461993-01-0707 January 1993 Notification of 930115 Meeting W/Util in Rockville,Md to Discuss Plant Containment Penetration Bellows Tests.Draft Agenda Encl ML20126F5541992-12-0808 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend to Change from Automatic to Manual Closure of Containment Purge & Exhaust Valves in Mode 6 ML20128C2071992-11-0606 November 1992 Notification of 921202 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance ML20127C4131992-07-24024 July 1992 Responds to 910322 Memo Requesting Assistance on Whether 10CFR50.59 Review Should Have Been Performed for Broken Pipe in Station Drainage & Discharge Sys Releasing low-level Radioactivity Onsite ML20059D2711990-08-0606 August 1990 Discusses Review of State of Oh & Local Radiological Emergency Response Plans.Determined That No Issues Identified During 890809-09 Exercise to Prevent Finding of Reasonable Assurance for Site ML20148T1891990-04-10010 April 1990 Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N8091989-08-30030 August 1989 Notification of 890907 Meeting W/Util in Rockville,Md to Discuss Exemption from App R to 10CFR50 for Specific Configuration of Pressurizer Instrumentation ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20244A4611989-06-0606 June 1989 Notification of 890615 Meeting W/Util & Westinghouse Owners Group in Rockville,Md to Discuss Reactor Vessel Support Embrittlement ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl 1999-03-26
[Table view] |
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i MEMORANDUM FOR:
D. Eisenhut, Director Division of Licensing l
FROM:
C. E. Norelius, Director, Division of Engineering and Technical Programs
SUBJECT:
INSERVICE TEST PROGRAMS - FULL STROKE EXERCISING OF NORMALLY CLOSED SWING OR TILTING DISK CHECK VALVES Licensees conducting inservice testing of valves in accordance with !
10 CFR 50.558, and applying the ASME Code,Section XI, edition and' addenda combinations allowed by 10 CFR 50.55a(6)(2)(1) are required to full stroke exercise normally closed check valves whose safety function is to permit flow upon reversal of differential pressure j (e.g. check in ECCS injection line). The ASME Code requires that, f for swing or tilting disk check valves, if the test is made by use of fluid flow through the valve (as opposed to using a mechanical exercisor), the pressure dif ferential for equivalent flow shall be no greater than that observed during the preoperational test.
During a recent inspection of Toledo Edison Company's Davis Besse Nuclear Power Plant, Mr. K. Connaughton of this of fice determined that flow through the check valves was the only parameter used.to .
satisfy the full stroke exercising requirements referenced above.
This practice is not uncommon among licensees. Acceptance" criterion vary. Some licensees may specify " design flow" while'others use l
" minimum flow for check valve lift" or merely " observe flow." Under design conditions, observation of design flow may be adequate to demonstrate that a valve is capable of fulfilling its safety function.
Corrections to measured flow for off-design conditions (e.g. check in ECCS injection line being tested in the Refueling Mode) must be made in order to provide a similar demonstration. The observation of
" minimum flow for check valve lift" (presumably established for a particular model of valve when new) or some arbitrary flow does not, in our opinion, provide any information as to the condition of the valve unless, of course, the valve has failed in some manner as to deny practically any flow.
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D. Eicanhut We are not aware of any licensees having submitted written requests for relief from this particular requirement. While we realize that preopera-tional test data on differential pressure across individual valves at reference flows is all but nonexistent, we feel that the use of differ-ential pressure as the test parameter may have greater technical merit than current practice. Please inform us of the staff's positions on:
- 1) the applicability and enforceability of the requirement considering:
the lack of preoperational test data and; the absence of requests for relief from this requirement.
- 2) whether or not licensees should be required (as an alternative to the test method and acceptance criterion described in the ASME Code) to:
demonstrate that under design conditions, the valves will permit design flows and are therefore capable of performing their intended function or; establish, by test and measurement, appropriate baseline differential pressures at reference flows which can be used in place of nonexistent preoperational test data.
On May 17, 1982, W. D. Shafer and K. Connaughton of this office discussed these matters, via telephone, with J. Page of your staff (MEB). Your efforts in resolving these concerns are greatly appreciated.
./
/
C..E. Norelius, Director Division of Engineering and Technical Programs l
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JAli1 ? Igm SEiiiiingglBrRO Dziemann, DaFS -
LBf2 Reading BSheron, DSI EHylton DWessman, DL ABournia -
ASchwencer : i TMNovak DGElsenhut Tippolito. ORAB HEMORAWOUM FOR: Richard Spessard, Director 01 vision of Engineerinn & "
Technical Programs Region III NRC -
FRON: Darrell G. Eisenhut, Director :
Division of Licensing, NRR :
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l
SUBJECT:
STOPWATCHES CAL 1 BRAT 10H AND ASME REQUIREMENTS OH 'l TRANSIENTS ANALYSES i-In your letter of Septenber 7,1982, you requested NRR assistance to evaluate the I use of uncalibrated timing devices in safety-related applications and to clarify [
aQ apparent inconsistency between transient analyses and ASME reoutrements regarding f:
valve closure times which are defined in the Technical Specifications. Our Reactor i:
Systems Branch evaluated the main steam ifolation valves (MS!Y) closure, and its i '
impact on minimum critical power ratio (HCPR) as determined in the FSAR analyses.
Our Procedure and Test Review Branch provided the requirements for the stopwatches.
This review was performed pursuant to TIA 82-58.
?
The ASME code allows rounding of measured closure times for MSIV's to the nearest 1.0 second or the use of a timing device with an occuracy of 1.0 second. This makes it possible for a ceasured closing time of 2.0 seconds to appear as 3.0 seconds which would satisfy the allowable technical specification value and the FSAR analyses. l
~
We evaluated the impact of a 2.0 second closure time versus a 4.0 second closure time on vessel pressure and EPR for the MS!V closure event. In the analysis, an 9 MSIV positten switch scram was assumed for the effect en MCPR and a high flux scram was assumed for the assessment of the effect on overpressure protection.
The results of these analyses indicate that for closure times of 2.0 seconds or j greater, the impact on MCPR and vessel pressure is insignificant and will not li challenge safety limits. For the limiting cases, vessel done pressure was calcu- 1 lated to increase 170 pst and the MCPR was calculated to be four percent of the il initial NCPR valve. For a typical boiling water reactor operating at 1100 psig y and an initial MCPR of 1.24, this results in a eak vessel pressure (bottom nf I
Dressure) of less than 1300 psig and a HCPR OF .19. The respective safety Ilmits aret pressure must he less than 1375 plig and HCPR must he ortater than )\)" k'I N 1.06 On this basis, we conclude that the interpretation of the ASME code which allow as ev:b as 1.0 second errnr in elv closure time is of no safety cr,ncern (h for plants with a technical specification mintmm allowable "$1Y closure time of ;"f *}l [ d' 3.0 inconds or orester. q ,# [
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Richard Spessard Vith respect to the use of stopwatches for measur. ment of tirie intervals for validating operability of safety-related equipment, this method is acceptable where it can be shown that this method of measurement provides the reouired accuracy. Therefore, the results of the above analyses indicates that a 1.0 second total deviation on MSIV closure time is acceptable. The stopwatches mst be calibrated and controlled as required by 10 CFR Part 50, Appendix B, Article X11, and the the required accuracy is detemined from the technical specification bases. ANSI /ANS-58.4-1979, "American National Standard Criteria for Technical Specifications for Nuclear Power Plants," paragraoh 5.1.(6) states:
" Errors, frw instrumentation or other sources, assumed in the development of the technical specification limits shall be dis-cussed in the bases to provide a clear relationship between the technical specification and the safe +y analysis values."
Our technical specification basis does not provide a discussion of measurement error, and the limit does not include an allowance for measurement error. it is necessary to include a measurement error allowance in the surveillance test acceptance criteria.
For the operator error component of the error associated with the use of stop-watches, we consider 700 milliseconds to be an acceptable assumption.
We trust that the information provided is responsive to your concern, and 19 WRR responsibilities under TI A Ho, R?-58 have been comoleted.
Ori ginal signed t'y :
Darrell G. Eisenhut, Director Division of t.icensino Of fice of Huc1rar Reactor E* qui stion cc: 9. Starottu.ki. 0-1 J. 01shinski, 0-!!
J. c.agliardo, P-1V J . Crews , 0-V e
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