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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20195J6351999-06-16016 June 1999 Forwards Addendum to Rev 30 of GGNS Physical Security Plan IAW 10CFR50.54(p).Addendum Is Submitted to Announce Relocation/Reconfiguration of Plant Central & Secondary Alarm Station Facilities.Rev Withheld,Per 10CFR73.21 ML20195G0281999-06-0909 June 1999 Submits Summary on Resolution of GL 96-06 Re Eighteen Penetrations Previously Identified as Being Potentially Susceptible to Overpressurization ML20207F5041999-06-0202 June 1999 Forwards Updated Medical Rept IAW License Condition 3 for DA Killingsworth License OP-20942-1.Without Encls ML20206P2981999-05-13013 May 1999 Forwards Responses to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Cancelling 990402 Submittal ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J0941999-05-0404 May 1999 Forwards Proprietary & Redacted ME-98-001-00,both Entitled, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators. Rept ME-98-002-00 Re Flexible Wedge Gate Valves,Encl.Proprietary Rept Withheld ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20206D8171999-04-29029 April 1999 Informs NRC of Results of Plant Improvement Considerations Identified in GGNS Ipe,As Requested in NRC . Licensee Found Efforts Have Minimized Extent of Radiological Release in Unlikely Event That Severe Accident Occurred ML20206D7281999-04-28028 April 1999 Forwards South Mississippi Electric Power Association 1998 Annual Rept, Per 10CFR50.71(b).Licensee Will Submit 1998 Annual Repts for System Energy Resources,Inc,Entergy Mississippi,Inc & EOI as Part of Entergy Corp Annual Rept ML20206C9551999-04-22022 April 1999 Forwards 1999 Biennial Emergency Preparedness Exercise Scenario. Without Encl ML20205M1311999-04-0202 April 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Info Was Discussed During Conference Call with NRC on 990126.Wyle Position Paper Encl.Subj Paper Withheld ML20205H5861999-04-0101 April 1999 Requests Relief from ASME B&PV Code,Section XI for Period of Time That Temporary non-code Repair Was in Effect,Per 10CFR50.55a(g)(5)(iii) ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) ML20205A6511999-03-25025 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-416/99-01 on 990201-05.Corrective Actions:Program Will Be Implemented to Ensure Accessible Areas with Radiation Levels Greater than 1000 Mrem/H ML20204E7391999-03-15015 March 1999 Forwards Objectives for June 1999 Emergency Preparedness Exercise for Plant.Without Encl ML20207H9291999-03-0404 March 1999 Submits Update to Original Certification of Grand Gulf Nuclear Station Simulation Facility IAW Requirements of 10CFR55.45(b)(5) ML20207E3081999-03-0303 March 1999 Informs That GGNS Severe Accident Mgt Implementation Was Completed on 981223.Effort Was Worthwhile & Station Ability to Respond & Mitigate Events That May Lead to Core Melt Has Been Enhanced ML20207E3221999-03-0303 March 1999 Notifies of Change in Status of Mj Ellis,License SOP-43846. Conditional License Requested to Accommodate Medical Condition.Revised NRC Form 396 with Supporting Medical Evidence Attached.Without Encls ML20207A8161999-02-24024 February 1999 Forwards 1998 Annual Operating Rept for Ggns,Unit 1. Listed Attachments Are Encl ML20207A9901999-02-24024 February 1999 Informs That Util Has No Candidates from GGNS to Nominate for Participation in Planned Gfes,Scheduled for 990407 ML20203A1551999-02-0101 February 1999 Forwards Grand Gulf Nuclear Station Fitness for Duty Program Performance six-month Rept for Reporting Period 980701-981231 ML20202G0791999-01-26026 January 1999 Informs That He Mcknight Has Been Permanently Reassigned from Position Requiring License to Perform Assigned Duties. License Is No Longer Needed,Effective 981231 ML20199K4151999-01-20020 January 1999 Forwards Proposed Addendum to Emergency Plan Changes Previously Submitted Via GNRO-98/00028 for NRC Review & Approval as Required by 10CFR50.54(q) & 50.4 ML20199K6771999-01-14014 January 1999 Provides Notification of Planned ERDS Software Change Scheduled to Take Place on 990215 ML20199D8811999-01-11011 January 1999 Submits Response to SE JOG Program on Periodic Verification of motor-operated Valves,In Response to GL 96-05 ML20199D9521999-01-0808 January 1999 Informs That CE Cresap,License SOP-4220-4,has Been Permanently Reassigned from Position Requiring License & No Longer Has Need for License,Per 10CFR50.74 ML20199A6081999-01-0606 January 1999 Submits List of Plant Info Brochures Disseminated Annually to Public & List of Updated State &/Or Local Emergency Plan Info,Per NRC Administrative Ltr 94-07, Distribution of Site-Specific & State Emergency Planning Info ML20202B7531998-12-21021 December 1998 Submits Ltr Confirming Discussion with J Tapia,Documenting Extension for Response to NOV 50-416/98-13.Util Response Will Be Submitted by 990212 1999-09-08
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g=g Entergy F"'"a *"auaaa 'ac-Operations v April 10, 1991 U.S. Nuclear Regulatory Comminnion Mail Station P1-137 Washington, D.C. 20555 Attention: Document Control Desk Sl'IU TCT : Grand Gul f Nuc ient Stntinn Unit 1 Docket No. 50-416 License No NPP-29 Summary of Calculat ions Rega rding Precipit at ion in t he ShCS Discharge Piping (Revision 1)
GNRG: 91/00061 Gentlemnn:
On Pobruary 12, 1991 f.ntergy Operations, Inc., Grand Gulf Nuclent Station (GGNS) mot with members of the NRC Staf f to discuss the results of calculations performed by GGNS nt the request of the Staf f to confirm that excesniin sodium pent aborate solut ion precipitat ion in t he Standby Liquid Control System (SI.CS) discharge piping does not occur. As a follow-up to that moet ing, the Staf f requested that GGNS submit a summary descript lou of t he calculnt f onal methodology and result s. That summnry was submitted on March 4, 1991.
Subsnquently, as discussed with your Staf f, an er ror was discovered in the calculations. We have . initiated appropriate quality deficiency actionn to address the nrror. While the error did not af fect our conclusions it did require us to modify somewhat our methoslology.
Thereforo, we are resubmitt.ing a summary description of the calculat ional inthodology and results.
i G9102264/SNI.ICPhR - 1 j- [;[
{ (g
- 9104180235 910410 PDR P
ADOCK 05000416 \
_ _ _ _ _ _ _ _ _ _ P D L _ ____ ___ ___ ____ -_------ ----
. April 10, 1991 GNRO-91/00061 Page 2 of 3 We would appreciate your timely review and closure of this issue.
Yours truly, csO CCarx-21.
WTC/I'RS/ m t e attachment: Standby 1.iquid Cont rol System Calculation Summar y (Revision 1) c r. ' Mr. D. C. Ilint a (w/n)
Mr. J. Mathis (w/n)
M r . R . 14 McGehee (w/a)
Mr. N. S. Reynolds (w/n)
Mt. 11. L. Thomas (w/o)
Mr. T. W. Titus (w/n)
Mr. Stewart D.17.bnet er (w/n)
Regional Administrator U.S. Nuclear Regulatory Commission Region 11 101 Marietta St., N.W., Sutto 2900 Atlanta, Georgia 30323 Mr. I., L. Kintner. Project Manager (w/a)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 11D21 Washington, D.C. 20555 G9102264/SNh1CI'I.R - 2
Attachment to GNRO ' ',1 4
)
1 l
1 STANDBY LIQUID CONTR01. SYSTEM CALCUI.ATION
SUMMARY
(REY.ISION 1) ,
t i
L t
i 09102264/SNLICFLR - 4
, *r--- r, n .- ._ -.%-,__ _ _ _ ~.. ..w. ....rv......,__-.-_.,-.--m -,..--.-.....-_..m_ -
s,.. . . . -. - - . ,,,,%,.. < - , .. . - , -
Attachment to CNRO 91/00061 STANDDY LIQUID CONTROL SYSTCH CALCULATION
SUMMARY
I. .Qalculationjurpose The current GONS Technical Speciffentions (TS) allow the solution in the Standby 1.1 quid Control System (SLCS) to have n sodium pontaborate concentration of 28.5 weight percent (w/c) when at n solut ion t emperat ure of 130*F. The issue of whether such a solution is enpable of being injected into the renctor vessel without excessive nodium pentnborate precipitation occurring has been raised by the NRC.
To assist in resolving this innue, a calculation was performed to determine how the temperature of the SLCS process flow (start Ing from the SLCS pump discharge) changes due to ambient tempetnture condit ions (in the vicinity of the SLCS discharge piping) when being inject ed into the s enctor vessel. The resulting sodium pentaborate precipitation in calculated and totalled. Figure I contains a schemntic of the St.CS piping layout.
The calculation consisted of two parts:
- 1) Calculation of the St.CS process flow temperature change under steady stato conditions (i.e., SICS discharge piping warmed to SLCF process flow temperature).
- 2) Cniculat ion of the SLCS process flow temperature immediately af ter SLCS initiation (i.e. , SLCS discharge piping in t he containment is initially at 70'F and the drywell portion of piping is initially at 110'F) until process flow temperature exceeds anturation temperature of the SLCS solution.
The results of the calculation n' used to demonstrate analyt ically that excessive precipitation does not occur.
II. _ Scoping _Qa_lcula t.f on Before reviewing the cniculations discussed above, it is instructive to take n look at a simple (and highly conservat(ve) calculation which should serve to place an upper bound on the amount of precipitation which could occur in the GGNS SLCS design.
While we do not credit this calculation in resolving the question posed by Lle 3 NRC, it is nonetheless useful in placing the precipitat.lon issue in perspectivo and serving as a check on calculation results.
The scoping eniculation assumes that the SLCS discharge piping (including drywell piping) is init.inlly at 70'F. The SLCS solution is discharged at 130'r and 28.5 w/o sodium pentaborate.
09102264/SNLICFLR - 5 i.
Attachment to GNRO-91/00061 I
We nasume that the dischargo piping must be heated uniformly to approximately 130'r (the steady state temperature reached during St.CS injection). Until the piping reaches 130'r all 81.05 solution )
passing through the piping is assumed to transfer heat. to the
-piping represented by n final solution temperature of 70*P (1.c. , 4 cach lbm of St.CS solution cools down f rom 130'r to 70'P regardless I of the actual piping temperature). The total precipitato is then l calculated based on a SLCS solution temperature of 70'F. I First , we calculate the total amount of heat necessary to raise the St.CS dischatge piping f rom 70'r to 130'F.
The ShCS dischargo piping mast I ist pjameter Leng(h hbmLft Total 2" 4.68' 5.02 23.49 1.5" 166.09' 3.63 602.91 T' 3.25' 10.25 _3h31 659.71 lbm The necessary heat transfer ist i
- Q = Mc A7 P l i- where H- a mass of dischargo piping (Ibm) c = stainless steel specific heat'(DTU/lbm'r) '
AT
- finnt - initial pipe temperature ('F)
-* ;(659.71 lbm) (O.12 DTU/1bm*P) (130 - 70'F) ,
= 4750 DTU e
I The HPCS dischargo piping is 1genrod due to the low piping surface contact arca to volume ratio for the ShCS solution and the.
i- resultant low hont transfer.
i 09102264/SNhlCPLR - 6
Attachment to CNRO-91/00061 The heat lost per lbm of SLCS solution is given by:
Q/M = cp AT j
where: H = 1 lbm of SLCS solution c = SLCS solution spec] fic heat (bTV/lbm*F)
- AT = Initial - final SLCS solution temperaturo ('F)
=
(0.82488 DTU/lbm*F) (130 - 70*F) 1 a 49.49 BTU /lbm '
l Therefore, t % amount of SLCS solution required to raisn the 1 discharge pli eig temperature to 130'T is t i 1
4750 HTU/49.49 BTU /lbm = 96 lbm At 70*F the sodium pontaborato solution concentration has been roduend to 16 w/o comparnd to the initial concentration of
- 28.5 w/o. Thn total amount of precipitation 1s t
=
Hp (28.S w/o - 16 w/o) (96 lbm)/100
= 12.0 lbm As will be discussed in more detail lator, this is clearly a negligible quantity of precipitation.
II1. GoneM1.Assump_t1ons Alt. hough the scoping calculation result may be conclusivo, tien and temperature dependent calculations were parlormed.
The following are the major assumptions used in both the steady stato and transient: parts of the calculation:
- 1) The temperature of the SLCS sodium pentaborato solution (process flow) is assumed to bo 130'F at the SLCS pump dischargo.
- 2) The SLCS flow rato for two pumps is assumed to ho 82.4 gpm.
- 3) No credit is taken for insulation on the SLCS discharge piping.
- 4) The ambient temperaturo in the containment is assumed to bo 70*F (i.e., the SLCS discharge piping in the containment is initially at 70'F).
- 5) The ambinnt temperature in the drywell is assumed to be 110'F (i.e. , the SLCS dischargo piping in the drywell is initially at 110'F).
G9102264/SNLICFLR =7
Attachment to GNRO-91/00061
- 6) The initial bodium pentaborate concentration of the process flow is assumed to be 28.5 w/o.
- 7) The amount of sodium pentaborate precipitation is assumed to vary linearly between ll4'r (28.5 w/o) and 70'F (16 w/o). In other words, a lbm of SLCS solution that is cooled to 70'F will precipitate 0.125 lbs. (0.285 lbs. - 0.16 lbs.) of sodium pentaborate.
- 8) No credit is taken for redissolving precipitate as the SLCS solutton temperature increases in the drywell.
IV. Steady _ Stat.o Condi. tion Calculation.Hethodology The process flow temperature change due to ambient temperatures was calculated by first determining the total heat transfer rate by free convection and radiation. Then dividing the total heat trannfer rate by the process fluid mass flow rate to obtain the enthalpy change per pound mass (thm). The temperature change is then calculated by dividing the enthalpy change by the specific heat of the SLCS sclution. These calculations were performed separately for each of ten pipe sections of the system piping model.
V. SteadLState Calc.ulat_fon_Results Once the piping reaches steady state tempointures, the total temperature drop from when the solution leaves the pump discharge until it reaches the reactor vessel is only 0.22'F. Therefore, the temperature losses to the ambient are very small and do not cause any excessive sodium pentaborate precipitation to occur since the resulting final solution temperature (129.78'F) remains above the saturation temperature (ll4*F).
VI. Transient _ Condition _ Cal _culation_Hethodology While the drywell piping temperature was assumed to be initially at 110'F, it was necessary to account for the cooling ef fects of the 70*F domineralized water in the containment portion of the SLCS piping. Using methodology similar to that discussed below (but incorporating the physical properties of water), an initial drywell piping t emperature profile was calculated, prior to modeling the injection of SLCS solutlon.
The transient calculation for injecting SLCS solution modeled the SLCS piping from the SLCS pump dischargo to the reactor vessel in variable length increments. F,ach increment contained 0.8685 lbm of SLCS solution, which corresponds to a one foot increment in 1.5 inch diameter piping. The calculation also verified that the SLCS flow was turbulent at all locations in the discharge piping so as to assure that no thermal stratification occurred.
G9102264/SNLICFLR - 3
1-Attachment to GN5t0-91/00061 y .
1 .
The first. step was to calculato the transit time through the pipo increment. The SLCS flow rato used was 82.4 gpm for the common dischargo. piping and 41.2 spm in the piping which is apstream of the point where the dischargo piping from each SLCS puap meets.
4 Dividing the SLCS flow rato by the cross sectional aren far the appropriato pipe internal diameter gave the SLCS solution velocity through the piping. Dividing the increment's piping length by the
,_ solution velocity gave the transit time for that pipe inctement.
The second stop was to calculate the area that the sluf, of SLCS solution had in contact with the pipe wall for the appropriato )
diameter of dischargo piping. l EThe third step was to calculate the heat transfer rate por it' of cont.act area for cach increment of piping. The calculation for the ]
heat transfer rate was performed using a computer program. The j heat transfer rate was calculated for each inctement of piping.
4 The enthalpy change was then calculated as a product of the heat transfer rato and the transit timo divided by the slug mass (0.8685 lbm). The temperature change of t.he SLCS solution was calculatea by dividing the enthalpy chango by the specific heat of
- the SLCS solution. The temperature change of the piping was similarly calculatod by dividing the amount of heat t ransferred (D
- transit time) by the product of the mass of stool for the pipe section and the piping specific heat (it
Finally, the amount of precipitation (if'any) for each slug of SLCS solution was calculated. _ precipitation was assumed to occur if tho solution temperature was loss than ll4*F (the saturation temperature for 28.5 w/o sodium pontaborate solution) and was 1 -calculated separately for the containment and drywell piping.
The preceding steps woro performed separately for each slug of SLCS solution until SLCS solution temperature exceeded Il4*F at the RpV Mnjection point.
An additional calculation was performed to determino the period of timo during which sodium pentaborato precipitation was possible -
in other words, the amount of timo required to heat up SLCS piping sufficiently that SLCS solution is injected into the RpV at a temperature greater than ll4'F. The transient calculation was terminated when the SLCS solution temperature exceeded ll4*F at the RpV. Thorofore, the timo required to pump the solution mass calculated for the transient case, added'to the transit time for nach piping section, datormines the duration of the precipitation transient.
G9102264/SNLICFLR - 9 -
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-. - .w , . - -. - ~ _ - - . - _ , , , - , _ , ., -,m-v-,,~, - ,<r.,,,-rc..n., y.w,,,-aw- ,--r--r-c .c .r r
j '
Attachment to GNRO 91/00061 1- .
4
)
, VII. S a_mp.l.e _T r a n.s i en t, Ca l cu l a t ion i
A samplo calculation demonstrating the above described methods for the first slug of SLCS solution in the last full 1 foot section of common 1-1/2" diameter piping in the drywell follows:
The transit time for this 1 foot increment: ,
T D
= increment length / fluid velocity l
= 1 ft / 14.96 fps = 0.066645 seconds At this location the calculated initini St.CS solution temperature (t is 74.69'F, the pipo temperature-(t ) is 77.161'F, thn SLCS soI)ution velocity ja 14.96 f t/sec, and the internal pipe diameter in 1-1/2". The heat transfer coefficiout 18 given by (Source -
liark 'n St andard llandbook for Mechanjcal 1:nginocre, 8th ed. , page 4-64, equation 6c):
h, = 160*( 14 0. 012 t,)V,' * * / ( D,)' ' 8 Where: h =
mean value of h for entiro surface (BTV/br f tF) tg = film temperature = (t,i t )/2 (*F) t,a pipe wall temperaturo t, = SLCS solution temperature V, e average fluid velocity (ft/sec)
D, = insido pipn diameter (inches)
= 160 * (140.012
= 2455.45 BTU /hr ft**F The heat transfer rate at this location is thereforn:
Q=b m* A a* AT where: hy = mean flim coef ficient (BTU /hr f t 'F) 8 A, = surface contact area (f t*)
AT = St.CS solution temperature - pipo temperature (*F)
= 2455.45 BTU /hr ft**F
= -2382.7 BTU /hr = -0.66186 BTV/sec G9102264/SNLICFhR - 10
Attachment to GNRO-91/00061 The enthnipy change per Ibm of St.CS solution while traversing thir. P ipe increment:
AH = h*T oin /H D s where h=hent transfer rate at this location (BTU /sec)
T ,,g = lticroitent trnnait timn (soc)
H, " mnss of solut.lon in this increment (1bm)
= -0.6618611TU/sec
= -0.051 BTU /lbm The teirporature chnrige across this increment:
AT = All / c P
where: All = enthalpy change (BTU / lbm) c = SLCS solut ion speci f ic hent ( BTU / lbm'F)
= -0.051 IlTU/lbm/0.82488 BTU /lbm*F = -0.06183*F Therefore, the SLCS hlug temperature upon exiting this increment 1s:
74.69 F - (-0.06183)0F = 74.75ar The mass of sodlum pentnborate precipitated from this slug in the SLCS piping:
M = AC
- M, wheret AC = (28.5 w/o - saturation w/o at this slugs lowest solution tempernture)/100 H, = mass of solution in this increment (lbm)
= (28.5 w/o - 17.05 w/o)
= 0.09944 lbm Finnily. the change in piping temperature is:
AT=(h*T tiin L / tM*L*c)p G9102264/SNLICFI,R - 11
l Attachment to GNRO-91/00061 !
where: All = heat t ransferred by the SLCS alog (BTV)
M = piping mass (Ibm /ft)
L = length of this increment ( f t) i e = stainless steel specific hent (llTV/lbm*F) j
= (-0.66186 liTU/sec
- 0.066645 sec)/(3.63 lbm/ft
= -0.1016'F And, the piping temperature after the SLCS slug exits this increment is:
77.161'r + (-0.1016'F) = 77.059'r All of the values calculated above approximato the values calculated by the computer program algorithm.
VIII. Tpnsfont_Ca}culation_Rosults The total amount of sodium pentaborate precipitation was calculated to be 6.993 lbm.
The duration of the precipitation transient was calculated to be 79.4 seconds. After this time, the SLCS solution temperature at the RpV . injection point remains above ll4*F.
IX. Sa f e ty_S i gn.i f.$ c an c e_o ff r o c.i p i.t a t ion SLCS injection is designed to meet a 3% shutdown requirement and includes a 25% margin to allow for uncertainties such as imperfect mixing in the core, leakage, etc. A minimum of 5800 lbm of scxtium pentaborato is necessary to fulfill this requirement. The 6.993 lbm of sodium pontaborate which may precipitato during injection represents only 0.001% of the minimum sodium pentaborate wolght - a negligible amount compared to the 25% margin.
Since lit tle published information exists on the precipitation of scxilum pentaborate, OGNS conducted a controlled laboratory experiment to observe and record the behavior of an approximato 28.5 w/o sodium pentaborato solution when cooled below its saturation temForature of Il4*F. Ilrlofly, a solution of 28.3 w/o sodium pontaborate was prepared and heated to 130 F. The heat source was removed and the solution cooled to room temperature (approximately 77'F). The solution was constantly stirred at rates well below those necessary to reach turbulent flow conditions.
09102264/SNLICFLR - 12
At t achinent to GNRO-91/00061 Various observations were made:
- Visible precipitntion did not occur until approximntely 100'r wheti cooling down e At room temperature the mixture exhibited a cloudy, " milky" tippenrnnce with fine particles of precipitato suspended throughout
- Upon discontinuing agitat ion, a smnll nrnount of precipitate settled in a thin layer on the bottom of the finsk - no plating of precipitate was observed on the finsk walls or bottom surface e Upon rehenting, the precipitate rindily redissolved prior to reachitig its saturation temperature Ensed on these observations, the smn11 amount of enIculated precipitate would not inhibit ShCS injectfon. The precipitate which forms is very fine niid remains in suspension unless flow in stagnant. p!nto-out. does not occur to any obserynhle extent .
Therefore, the precipitate would be injected into the RpV and redissolve upon mixing.
X. Conclus.lo_n The results of this calculat. ion confirm that excessive precipitation of sodlum pentaborate in the dischargo piping will not. occur for the conditions annlyzed. The minor precipitation which may occur would have no offont on the St.CS safety function.
09102264/SNh1CFI,R - 13
SLCS PlPING _AYOUT .
RPV i I
i :
F SLCS i 2" s 1.5" PUMP A J I 2' 19'lt I ( '
' 14" 1.5" 1.5" o 3" 12' f;
~ ,
62' 71' 3' i !
- t. ?
' j SLCS 2" % 1.5" j e U :
PUMP B J! 2' 14' : ,
i
- i r HPCS DISCHARGE P!PE CONTA!NMENT DRW/ ELL
- NOT DRAWN TO SCALE Figure 1
-