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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20212J3501999-06-23023 June 1999 Forwards Draft Ltr for Use in Transmitting FERC Rept Re 981008 Audit to Licensee & Copy of FERC Insp Rept ,containing Color Photographs.Without Encls ML20196H9721999-06-23023 June 1999 Requests Attached Request for Addl Info Be Put Into NRC Public Document Room.Encl RAI e-mailed to W Sparkman of Southern Nuclear Operating Co on 990610 IA-96-023, Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier1999-06-18018 June 1999 Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier ML20205N7511999-04-13013 April 1999 Requests That Attached RAI Re TS 3/4.4.7.2e Be Placed in NRC Pdr.Informs That RAI Was Faxed to W Sparkman on 990413 & Will Be Used to Facilitate Discussions During Upcoming Telcon Between NRC & Snoc Staff ML20205M8681999-04-13013 April 1999 Requests That Encl Topics for Discussion Be Made Available in NRC Pdr.Items Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & SNC Staff ML20205J1401999-04-0505 April 1999 Notification of 990419 Meeting with Util to Discuss Licensee Justification of Certain TS Changes Need to Implement Improved Standard Ts.Meeting Was Held in Rockville,Md ML20205G5781999-04-0101 April 1999 Notification of 990416 Meeting with Snoc in Rockville,Md to Discuss Farley Npp,Unit 1 SG Operational Assessment ML20205C8771999-03-31031 March 1999 Requests That Encl questions,e-mailed to W Sparkman of Southern Nuclear Operating Co,Inc,Which Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & Util Be Made Available in NRC PDR IR 05000348/19983001999-03-0101 March 1999 Forwards NRC Operator Licensing Exam Repts 50-348/98-300 & 50-364/98-300 (Including Completed & Graded Tests) for Tests Administered on 980313 ML20207J4681999-03-0101 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980313 at Farley NPP ML20202E1621999-01-29029 January 1999 Requests That Encl RAI Be Made Available in NRC Pdr.Subj Document Neither Constitutes Formal Request for Info Nor Represent Formal NRC Position.Encl RAI Faxed on 990129 to W Sparkman of Snoc ML20198H5741998-12-22022 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss Licensee Justification of Certain TS Changes Needed to Implement Improved Standard TSs ML20197J0501998-12-14014 December 1998 Requests That Encl Memo & Attachments Associated with Task Interface Agreement (TIA 96-023) Fraley License Basis & Acceptability of Kaowool as Electrical Raceway Fire Barrier Be Placed in NRC PDR ML20196H1181998-12-0404 December 1998 Forwards Message Faxed to M Ajluni of Southern Nuclear Operating Co (SNC) on 981204,to Prepare SNC for Conference Call.Message Does Not Constitute Formal Request for Info or Represent Formal NRC Staff Position ML20196E2911998-12-0101 December 1998 Notification of 981215 Meeting with Util in Rockville,Md to Discuss Matters Re Kaowool Fire Barriers Installed at Plant ML20195B7721998-11-12012 November 1998 Forwards Message That Had Been Faxed to M Ajluni on 981112. Purpose of Message Was to Prepare Licensee Personnel for Conference Call Re SG Tube Insp Results for Farley NPP Unit 1 ML20196F7001998-11-0202 November 1998 Notification of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Maryland to Discuss Matters Re Current SG Tube Insps at Farley NPP Unit 1 ML20154L1171998-10-15015 October 1998 Notification of 981026 Meeting with Util in Rockville,Md to Discuss Westinghouse BE-LOCA Abbreviated Reanalysis for Plant,Units 1 & 2 New SG ML20154B0411998-09-29029 September 1998 Notification of 981014 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Justification of Certain TS Changes Needed to Implement Improved Std TSs ML20154B0681998-09-29029 September 1998 Notification of 981008 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Repair of SG Tubes ML20217B1371998-04-21021 April 1998 Forwards Three Documents Associated W/Farley Nuclear Plant, Units 1 & 2-licensing/design Basis for Tornado Missile Protection to Be Made Available in PDR ML20217H4431998-04-0101 April 1998 Forwards Message Faxed on 980401 to M Ajluni of Southern Nuclear Operating Co,Inc (Snc).Purpose of Message Was to Prepare SNC Personnel for Conference Call & Does Not Consitute Formal Request for Info ML20217B1811997-12-18018 December 1997 Discusses Design Insp of Farley Units 1 & 2,for Jan-March of 1997,identified Tornado Missile Protection Issue Re Exhaust Piping & Silencers for EDG for Both Units (Including Station Blackout DG) ML20198S9281997-10-31031 October 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Plans & Schedule for SG Replacement ML20217B1961997-10-15015 October 1997 Discusses Review of Farley Nuclear Plant,Units 1 & 2 Licensing & Design Basis for Protection Against Tornado Missiles at Farley in Accordance w/970402 Memo from RM Gallo ML20217D9721997-09-30030 September 1997 Notification of 971022 Meeting W/Licensee in Rockville,Md to Discuss Licensee Initiatives That Focus on Planned Licensing Actions for FNP & Corrective Measures Related to Problems Considered by Licensee Mgt to Warrant Special Attention ML20216G2151997-09-0505 September 1997 Notification of 970916 Meeting W/Snoc in Rockville,Md to Discuss Improved Standard Technical Specification Conversion Application & Schedule for Submittal ML20236N3231997-08-21021 August 1997 Forwards SER in Response to Licensee 970522 Requested Interpretation of TS 4.8.1.1.2.e for Two Shared EDGs ML20148J8131997-06-16016 June 1997 Notifies of 970701 Meeting W/Util in Rockville,Md to Discuss Util Initiatives That Focus on Planned Licensing Actions for Plant & Corrective Measures Re Problems Considered by Util Mgt ML20141B0131997-06-16016 June 1997 Notification of 970701 Meeting W/Southern Nuclear Operating Co in Rockville,Md to Discuss SNC Initiatives That Focus on Planned Licensing Action for FNP & Corrective Measures. Meeting Cancelled ML20217B2111997-04-0202 April 1997 Informs That During Insp of Farley Units 1 & 2 in Jan-March 1997,NRR Led Insp Team Identified Tornado Missile Protection Issue W/Exhaust Silencers for DG for Both Units ML20236M9961997-03-27027 March 1997 Forwards Response to Questions Re Ventilation Specs for Farley ML20137C2501997-03-20020 March 1997 Forwards Message to M Ajluni of Southern Nuclear Operating Re Preparing Licensee Personnel for Conference Call ML20236M9661997-02-12012 February 1997 Discusses from Southern Nuclear Operating Co Requesting NRC Review Interpretation of Application of TS 3/4.9.13 at Farley Nuclear Plant,Units 1 & 2 During Modes 5 or 6,or When Defueled ML20134B3421997-01-27027 January 1997 Notification of 970205 Meeting W/Listed Attendees in Rockville,Md to Discuss Util Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair Method in Repair of SG ML20197J0751996-11-26026 November 1996 Requests Technical Assistance in Evaluation of Issues Identified During Routine Insp at Plant.Insp Rept Summary with Justification Encl ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML17164A5301995-01-17017 January 1995 Forwards Attached Documents Re Postulated Loss of Sfpc Events at Plant,Units 1 & 2 ML17164A4761994-12-23023 December 1994 Forwards Documents for NRC Staff Re Ongoing Review of Spent Fuel Pool Cooling Design Issues at Plant ML20149E9221994-02-18018 February 1994 Responds to 930215 Request from J Strosnider Re Documentation of Concerns Re Plant Two Volt IPC Proposal & Resolution of Public Comments Concerning Voltage Based Repair Criteria NUREG-1231, Forwards Documents Referenced in Suppl 16 to NUREG-09331993-11-29029 November 1993 Forwards Documents Referenced in Suppl 16 to NUREG-0933 ML20058J7101993-11-18018 November 1993 Notification of Significant Licensee Meeting W/Util on on 931123 to Discuss Plant SALP Board Assessment for Period of 930531-0925 IR 05000364/19930261993-11-10010 November 1993 Notification of Significant Licensee Meeting W/Util on 931117 in Atlanta,Ga to Discuss Violation 50-364/93-26-01 Re Personnel Error Resulting in Losses of Configuration Control During Performance of Maint & Testing Activities ML20057C3131993-09-15015 September 1993 Notification of Significant Licensee Meeting W/Util on 931013 to Discuss SALP Performance of Facility During Period 920531-0925 ML20056E4221993-08-0606 August 1993 Requests Written Inputs on Performance of Farley Facilities During Completed SALP Cycle 11 During Period 920531-930925 Using Encl Feeder Forms.Salp Board Meeting for Farley Scheduled for 931013 ML20046D0061993-08-0202 August 1993 Notification of Significant Licensee Meeting 93-99 on 930831 in Monroeville,Pa to Discuss Status of Decommissioning of Former B&W Nuclear Fuel Fabrication Facility in Apollo & Operations at Parks Township Site ML20046B1751993-07-15015 July 1993 Requests That Encl Documents Received from Thermal Ceramics, Inc Be Placed in PDR & Copies Distributed to Listed Individuals ML20044B7801993-02-12012 February 1993 Notification of Cancellation of 930304 Meeting W/Util in Rockville,Md to Discuss Emergency Response Facility Staffing Time 1999-06-23
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20212J3501999-06-23023 June 1999 Forwards Draft Ltr for Use in Transmitting FERC Rept Re 981008 Audit to Licensee & Copy of FERC Insp Rept ,containing Color Photographs.Without Encls ML20196H9721999-06-23023 June 1999 Requests Attached Request for Addl Info Be Put Into NRC Public Document Room.Encl RAI e-mailed to W Sparkman of Southern Nuclear Operating Co on 990610 IA-96-023, Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier1999-06-18018 June 1999 Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier ML20205N7511999-04-13013 April 1999 Requests That Attached RAI Re TS 3/4.4.7.2e Be Placed in NRC Pdr.Informs That RAI Was Faxed to W Sparkman on 990413 & Will Be Used to Facilitate Discussions During Upcoming Telcon Between NRC & Snoc Staff ML20205M8681999-04-13013 April 1999 Requests That Encl Topics for Discussion Be Made Available in NRC Pdr.Items Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & SNC Staff ML20205J1401999-04-0505 April 1999 Notification of 990419 Meeting with Util to Discuss Licensee Justification of Certain TS Changes Need to Implement Improved Standard Ts.Meeting Was Held in Rockville,Md ML20205G5781999-04-0101 April 1999 Notification of 990416 Meeting with Snoc in Rockville,Md to Discuss Farley Npp,Unit 1 SG Operational Assessment ML20205C8771999-03-31031 March 1999 Requests That Encl questions,e-mailed to W Sparkman of Southern Nuclear Operating Co,Inc,Which Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & Util Be Made Available in NRC PDR IR 05000348/19983001999-03-0101 March 1999 Forwards NRC Operator Licensing Exam Repts 50-348/98-300 & 50-364/98-300 (Including Completed & Graded Tests) for Tests Administered on 980313 ML20207J4681999-03-0101 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980313 at Farley NPP ML20202E1621999-01-29029 January 1999 Requests That Encl RAI Be Made Available in NRC Pdr.Subj Document Neither Constitutes Formal Request for Info Nor Represent Formal NRC Position.Encl RAI Faxed on 990129 to W Sparkman of Snoc ML20198H5741998-12-22022 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss Licensee Justification of Certain TS Changes Needed to Implement Improved Standard TSs ML20197J0501998-12-14014 December 1998 Requests That Encl Memo & Attachments Associated with Task Interface Agreement (TIA 96-023) Fraley License Basis & Acceptability of Kaowool as Electrical Raceway Fire Barrier Be Placed in NRC PDR ML20196H1181998-12-0404 December 1998 Forwards Message Faxed to M Ajluni of Southern Nuclear Operating Co (SNC) on 981204,to Prepare SNC for Conference Call.Message Does Not Constitute Formal Request for Info or Represent Formal NRC Staff Position ML20196E2911998-12-0101 December 1998 Notification of 981215 Meeting with Util in Rockville,Md to Discuss Matters Re Kaowool Fire Barriers Installed at Plant ML20195B7721998-11-12012 November 1998 Forwards Message That Had Been Faxed to M Ajluni on 981112. Purpose of Message Was to Prepare Licensee Personnel for Conference Call Re SG Tube Insp Results for Farley NPP Unit 1 ML20196F7001998-11-0202 November 1998 Notification of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Maryland to Discuss Matters Re Current SG Tube Insps at Farley NPP Unit 1 ML20154L1171998-10-15015 October 1998 Notification of 981026 Meeting with Util in Rockville,Md to Discuss Westinghouse BE-LOCA Abbreviated Reanalysis for Plant,Units 1 & 2 New SG ML20154B0411998-09-29029 September 1998 Notification of 981014 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Justification of Certain TS Changes Needed to Implement Improved Std TSs ML20154B0681998-09-29029 September 1998 Notification of 981008 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Repair of SG Tubes ML20217B1371998-04-21021 April 1998 Forwards Three Documents Associated W/Farley Nuclear Plant, Units 1 & 2-licensing/design Basis for Tornado Missile Protection to Be Made Available in PDR ML20217H4431998-04-0101 April 1998 Forwards Message Faxed on 980401 to M Ajluni of Southern Nuclear Operating Co,Inc (Snc).Purpose of Message Was to Prepare SNC Personnel for Conference Call & Does Not Consitute Formal Request for Info ML20217B1811997-12-18018 December 1997 Discusses Design Insp of Farley Units 1 & 2,for Jan-March of 1997,identified Tornado Missile Protection Issue Re Exhaust Piping & Silencers for EDG for Both Units (Including Station Blackout DG) ML20198S9281997-10-31031 October 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Plans & Schedule for SG Replacement ML20217B1961997-10-15015 October 1997 Discusses Review of Farley Nuclear Plant,Units 1 & 2 Licensing & Design Basis for Protection Against Tornado Missiles at Farley in Accordance w/970402 Memo from RM Gallo ML20217D9721997-09-30030 September 1997 Notification of 971022 Meeting W/Licensee in Rockville,Md to Discuss Licensee Initiatives That Focus on Planned Licensing Actions for FNP & Corrective Measures Related to Problems Considered by Licensee Mgt to Warrant Special Attention ML20216G2151997-09-0505 September 1997 Notification of 970916 Meeting W/Snoc in Rockville,Md to Discuss Improved Standard Technical Specification Conversion Application & Schedule for Submittal ML20236N3231997-08-21021 August 1997 Forwards SER in Response to Licensee 970522 Requested Interpretation of TS 4.8.1.1.2.e for Two Shared EDGs ML20148J8131997-06-16016 June 1997 Notifies of 970701 Meeting W/Util in Rockville,Md to Discuss Util Initiatives That Focus on Planned Licensing Actions for Plant & Corrective Measures Re Problems Considered by Util Mgt ML20141B0131997-06-16016 June 1997 Notification of 970701 Meeting W/Southern Nuclear Operating Co in Rockville,Md to Discuss SNC Initiatives That Focus on Planned Licensing Action for FNP & Corrective Measures. Meeting Cancelled ML20217B2111997-04-0202 April 1997 Informs That During Insp of Farley Units 1 & 2 in Jan-March 1997,NRR Led Insp Team Identified Tornado Missile Protection Issue W/Exhaust Silencers for DG for Both Units ML20236M9961997-03-27027 March 1997 Forwards Response to Questions Re Ventilation Specs for Farley ML20137C2501997-03-20020 March 1997 Forwards Message to M Ajluni of Southern Nuclear Operating Re Preparing Licensee Personnel for Conference Call ML20236M9661997-02-12012 February 1997 Discusses from Southern Nuclear Operating Co Requesting NRC Review Interpretation of Application of TS 3/4.9.13 at Farley Nuclear Plant,Units 1 & 2 During Modes 5 or 6,or When Defueled ML20134B3421997-01-27027 January 1997 Notification of 970205 Meeting W/Listed Attendees in Rockville,Md to Discuss Util Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair Method in Repair of SG ML20197J0751996-11-26026 November 1996 Requests Technical Assistance in Evaluation of Issues Identified During Routine Insp at Plant.Insp Rept Summary with Justification Encl ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML17164A5301995-01-17017 January 1995 Forwards Attached Documents Re Postulated Loss of Sfpc Events at Plant,Units 1 & 2 ML17164A4761994-12-23023 December 1994 Forwards Documents for NRC Staff Re Ongoing Review of Spent Fuel Pool Cooling Design Issues at Plant ML20149E9221994-02-18018 February 1994 Responds to 930215 Request from J Strosnider Re Documentation of Concerns Re Plant Two Volt IPC Proposal & Resolution of Public Comments Concerning Voltage Based Repair Criteria NUREG-1231, Forwards Documents Referenced in Suppl 16 to NUREG-09331993-11-29029 November 1993 Forwards Documents Referenced in Suppl 16 to NUREG-0933 ML20058J7101993-11-18018 November 1993 Notification of Significant Licensee Meeting W/Util on on 931123 to Discuss Plant SALP Board Assessment for Period of 930531-0925 IR 05000364/19930261993-11-10010 November 1993 Notification of Significant Licensee Meeting W/Util on 931117 in Atlanta,Ga to Discuss Violation 50-364/93-26-01 Re Personnel Error Resulting in Losses of Configuration Control During Performance of Maint & Testing Activities ML20057C3131993-09-15015 September 1993 Notification of Significant Licensee Meeting W/Util on 931013 to Discuss SALP Performance of Facility During Period 920531-0925 ML20056E4221993-08-0606 August 1993 Requests Written Inputs on Performance of Farley Facilities During Completed SALP Cycle 11 During Period 920531-930925 Using Encl Feeder Forms.Salp Board Meeting for Farley Scheduled for 931013 ML20046D0061993-08-0202 August 1993 Notification of Significant Licensee Meeting 93-99 on 930831 in Monroeville,Pa to Discuss Status of Decommissioning of Former B&W Nuclear Fuel Fabrication Facility in Apollo & Operations at Parks Township Site ML20046B1751993-07-15015 July 1993 Requests That Encl Documents Received from Thermal Ceramics, Inc Be Placed in PDR & Copies Distributed to Listed Individuals ML20044B7801993-02-12012 February 1993 Notification of Cancellation of 930304 Meeting W/Util in Rockville,Md to Discuss Emergency Response Facility Staffing Time 1999-06-23
[Table view] |
Text
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December 4,_1998 e
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MEMORANDUM TO: Docket File a
FROM:
' Jacob L Zimmerman, Project Manager Original signed by:
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Project Directorate 11-2 Division of Reactor Projects - t/II -
Office of Nuclear Reactor Regulation '
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1
SUBJECT:
FARLEY UNITS 1 AND 2 '- PLACEMENT OF A DOCUMENT IN THE PUBLIC DOCUMENT ROOM i
(
The attached message was faxed today to Mark Ajiuni of the Southem Nuclear l
l..
Operating Company, Inc. (SNC). The sole purpose of the message is to prepare SNC personnel for a conference call. The message itseK does not constitute a formal request for 4
i I
information or represent a formal NRC staff position.
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Docket Nos. 50-348 and 50-364 i
Attachment:
As stated l
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Distribution' I
Docket File i
PDil-2 RF i
^
PUBLIC H. Berkow i
G. Hsii i
To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure i
"E" = Copf with y tachment/ enclosure "N" = No copy]
OFFICE PM:Ff6152 l
LA:PDlif2!)
D:PDil-2;//jl l
l NAME JZi$in# man:cn LBerry \\'d /
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DATE fuj 798 l'L l' 798
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PDR ADOCK 05000348 fj(\\
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t WASHINGTON, D.C. 30666-4001
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December 4, 1998 i
4 MEMORANDUM TO: Docket File
/
- ~
FROM:
Jacob 1. Zimmerman, Project Manager d,
Project Directorate Il-2 4
Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
SUBJECT:
FARLEY UNITS 1 AND 2 - PLACEMENT OF A DOCUMENT IN THE i
PUBLIC DOCUMENT ROOM The attached message was faxed today to Mark Ajluni of the Southem Nuclear Operating Company, Inc. (SNC). The sole purpose of the message is to prepare SNC personnel for a conference call. The message itself does not constitute a formal request for information or represent a formal NRC staff position.
Docket Nos. 50-348 and 50-364
Attachment:
As stated
a REQUEST FOR ADDITIONAL INFORMATION WCAP-14750 RCS FLOW VERIFICATION USING ELBOW TAPS AT WESTINGHOUSE 3-LOOP PWRS (TAC NOs. M97325 and M97326) 1.
Section 4.2, Elbow Tap Flow Measurement Procedure, defines the baseline elbow tap flow coefficient (B), and future cycle elbow tap flow coefficient (K) as the elbow tap AP (inches water) multiplied by the cold leg water specific volume (v).
(a)
The use of the terminology " flow coefficient" to define the AP measurement values is confusing because the elbow tap " flow coefficient" normally refers to the constant (C) in the elbow tap equation Q = C (AP)% whereas AP is a variable as a function of flow rate. Why not use an attemate terminology, other than " flow coefficient," for "AP x v?"
(b)
Discuss the reasons for not directly using the equation Q = C (AP)% or measuring f
reactor coolant system (RCS) flow rate with elbow tap meters, where the flow coefficient, C, should have a constant value for an elbow tap installation, and the elbow tap AP readings would be proportional to the square of the cold leg flow rates, independent of the plant hydraulic changes such as pump impeller smoothing, steam generator tube plugging, and fuel design change.
(c)
The definition in Equations 1 and 2 that B (or K) = AP x v (where AP is in inches H 0, 2
and B and K are in inches H O
- ft /lb) is not consistent with the basic elbow tap flow 2
2 equation volumetric flow rate Q = C x (AP)M.
Explain why B and K are defined as they are. Please examine Equations 1 and 2 for whether B and K are defined correctly.
2.
In the elbow tap flow measurement procedure in Section 4.2, the future cycle RCS flow rate will be calculated from the baseline calorimetric-measured RCS flow multiplied by the " ratio of future cycle flow," R, which is defined in Equation 3 to be the square root of the ratio of the average AP (times specific volume) of all elbow tap from the future cycle to that of the baseline cycle, i.e. (K/B)M.
(a)
Because of the variations in the elbow tap flow coefficients (note that the flow coefficient here is C in the basic elbow tap equation, not B or K as defined in Equations 1 and 2 of your report) and the APs for different elbow taps in the cold legs, what is the mathematical basis for the use of the average AP of all elbow taps in defining the ratio of future cycle flow, R? Provide the mathematical derivation to show correctness of "R," *B," and *K" as defined in Section 4.2 using the average APs.
(b)
As the flow coefficient (C) for each elbow tap should remain constant, the volumetric flow ratio should be equal to the square root of the AP ratio between two cycles, which should be anticipated to be the same for all elbow taps. Would it be more appropriate, mathematically, to use the average value of the flow ratios (i.e., square root of AP ratios) between the future cycle and the baseline cycle of all elbow taps to define the
" ratio of future cycle flow," R7 If not, why not?
I
=
2 (c)
FSAR Section 4.4.1.1 indicates there is to be at least a 95 percent probability at a 95 percent confidence level that departure from nuclear boiling (DNB) will not occur on 4
the limiting fuel rods during normal operation and anticipated operational occurrences.
Technical Specification 3.4.1 requi.res measurement of the DNB parameter of total RCS flow rate.
To provide a 95/95 probability / confidence of the value of R, would it be more appropriate to adjust the " future cycle flow ratio," R, by taking into to account the uncertainty distribution of the AP ratios among the elbow taps as in the equation below? If not, why not?
R=R - K(95,95,N) o m
- where, R
= I R,/N m
R, = (AP, / AP )P, I = 1,2,....N (Note that APs are in inch of water. If APs are in psi, then it will be multiplied by the specific volume of water)
N = total number of elbow taps = 3 x number of cold legs o = standard deviation of R,s K(95,95,N) = factor for one-sided tolerance limit for 95% probability at 95% confidence level for a sample size of N.
K(95,95,9) = 3.031 (d) Attematively, provide (1) statistical calculations that show that the 95/95 probability and confidence level can be met for RCS flow rate using your proposed measurement method utilizing the elbow tap flow meters, or (2) a justification for measures used to achieve an acceptable accuracy that bounds the 95/95 criteria such as by use of margins, conservative data, etc.
3.
The best-estimate flow confirmation procedure described in Section 4.2 sets the upper bound of the future cycle RCS flow in accordance with Equation 6 by comparing the measured flow ratio to the flow ratio of best-estimate hydraulic calculations, which is indicated in Section 5.1 to have been developed and confirmed by numerous component flow resistance tests and analyses to be accurate to plus or minus 2 percent. The multiplier in Equation 6 is said to be an allowance for elbow tap flow measurement repeatability. It is indicated that since the elbow tap flow measurement uncertainty includes this repeatability allowance, the measured flow ratio can be 0.4 percent higher than the estimated flow ratio and still define a conservative flow.
Section 4.1 discusses the elbow tap flow measurement repeatability with comparisons at the Prairie Island plant to the measurements of leading edge flow meter (LEFM), which is shown (in Section 5.2) to have an accuracy of plus or minus 0.67 percent established by a calibration test at the Alden Laboratories. An average difference of less than 0.3 percent is shown in Table 4-1 between the elbow tap meter and the LEFM measurements on the RCS loop flows at full power and the flow ratios with one-and two-pump operations.
l
s 3
(a) Provide the definition of the terms " repeatability,"
- accuracy," and " uncertainty" as applied to the indicated RCS flow rate obtained by the elbow tap flow meters.
(b) Provide the elbow tap measurement repeatability value, and describe how it is related to the data provided in Table 4-1, and explain how the elbow tap flow measurement uncertainty described in Appendix A of the report includes the repeatability allowance.
(c) Describe or reference the best-estimate hydraulic calculation methodology used by Farley and other 3-loop plants, and describe how the plus or minas 2 percent accuracy of the hydraulic calculation is obtained and will be assured in the future hydraulic calculations.
(d) The comparisons provided in Figures 6-1 and 6-2 of the RCS flows from the calorimetric measurements, elbow taps measurements, and best-estimate hydraulic calculations, show a difference of less than 0.5 percent between the elbow tap flow meter measured flow rates and the hydraulic calculation RCS flow rates. Explain how the use of Equation 6 defines a conservative flow, considering the hydraulic calculation accuracy, the elbow tap flow measurement repeatability and uncertainty.
4.
Tables 6-1 and 6-2 provide calorimetric flow rates of all three loops for various cycles and baseline flow rates for Farley Units 1 and 2, respectively. The baseline flow rates for both units, which are shown to be the average of the loop flow rates of earlier cycles (before the transition to low leakage fuel core loading patterns) with hydraulic corrections and roundoff, are shown to be higher than any individual value from the three early cycles from which the baseline flow rates are obtained.
(a) With pump impeller smoothing, which was indicated by the Prairie Island LEFM data to cause a reduction of the RCS flow by 0.6 to 0.8 percent, and why are the baseline RCS flow rates higher than the first cycle flow rate? Provide the calculations to show how these baseline value flow rates are obtained and why they are higher than any individual value.
(b) in addition to the reasons provided in Sections 6.1 and 6.2 for excluding data of several cycles from Tables 6-1 and 6-2 for Farley 1 and 2, respectively, provide the criteria and bases for the criteria that are used for Farley and will be used for other 3-loop plants such as V. C. Summer, Turkey Point 3 and 4, for excluding data from being used in deriving the baseline flow.
5.
Tables A-4 and A-5, respectively, provide the cold leg elbow tap flow uncertainty for the process computer and low flow reactor trip. Are the instrumentation uncertainty values sufficient to bound the uncertainties of the elbow tap measurement instrument, including the larger drift effects, caused by the absence of current normalization of elbow tap measurement against the precision heat balance measurement at the beginning of each cycle? Provide corrected uncertainty values, if necessary, and the basis for the uncertainty values.