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| | number = ML17037B964 | | | number = ML17037B964 |
| | issue date = 04/21/1975 | | | issue date = 04/21/1975 |
| | title = Nine Mile Point Generating Station, Units 1 and 2 - Request for Additional Information Related to the Design of the Containment of the Facility | | | title = Request for Additional Information Related to the Design of the Containment of the Facility |
| | author name = Stolz J F | | | author name = Stolz J |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = Rhode G R | | | addressee name = Rhode G |
| | addressee affiliation = Niagara Mohawk Power Corp | | | addressee affiliation = Niagara Mohawk Power Corp |
| | docket = 05000220, 05000410 | | | docket = 05000220, 05000410 |
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| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 8 | | | page count = 8 |
| | | project = |
| | | stage = RAI |
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| =Text= | | =Text= |
| {{#Wiki_filter:9Rocket1lo,50-410APR211975k'iagara)JohannpowerCorporation AY'XV:Nr.CeraldTi.Bho@eVicePresident | | {{#Wiki_filter:9 Rocket 1lo, 50-410 APR 21 1975 k'iagara )Johann power Corporation AY'XV: Nr. Cerald Ti. Bho@e Vice President Enpineerinp 3QO Erie boulevard Uest Syracuse', Petr York )3202 CentletEen: |
| -Enpineerinp 3QOErieboulevard UestSyracuse',
| | Pursuant to 5 50.54(f) of 10 CP" Part 50, tho l'IuClear Regulatory Cormiasien (DEC) staff requires that, certainEblisinfozr ation related to the'esign of the containment for your facility'e submitted promptly to L,BC for its reviev. |
| PetrYork)3202CentletEen:
| | .%isis requireE1ent results fgoa recent developr;ents associated with our on-going revieu area of Er,R plants with pressure supp'ression-typo contains.ento and the capability of the suppression pool retaininp structures to tolerate loads due to 'operation of th~ primary system pressure relief valves. |
| Pursuantto550.54(f)of10CP"Part50,thol'IuClear Regulatory Cormiasien (DEC)staffrequiresthat,certaininfozrationrelatedtothe'esign ofthecontainment foryourfacility'e submitted promptlytoL,BCforitsreviev..%isisrequireE1ent resultsfgoarecentdevelopr;ents associated withouron-goingrevieuareaofEr,Rplantswithpressuresupp'ression-typo contains.ento andthecapability ofthesuppression poolretaininp structures totolerateloadsdueto'operation ofth~primarysystempressurereliefvalves.Experience atseveraloperating; Eblisplantahasindicated thatloadsduetoreliefvalveact1$ationraynothavebeenfullyconsidered inthestructural desi~aofthesuppression chaw'ber.
| | Experience at several operating; planta has indicated that loads due to relief valve act1$ ation ray not have been fully considered in the structural desi~a of the suppression chaw'ber. Xn addition, the Ceneral Electric Company is no19 Pr'eparing to start a series of srM111-scale relief valve tests ckich vill be used to verify analytical predictions of these loads aa applicable to al $ classes of plants. |
| Xnaddition, theCeneralElectricCompanyisno19Pr'eparing tostartaseriesofsrM111-scale reliefvalvetestsckichvillbeusedtoverifyanalytical predictions oftheseloadsaaapplicable toal$classesofplants.Pooldynaoicloadsdu~toreliefvalve-operation areduetotwodistinctphenomena.
| | Pool dynaoic loads du~ to relief valve -operation are due to two distinct phenomena. Pizat$ pressure T1aves are generated within the suppression pool on first opening,$ r@11+f valves discharge high pressure air fol1owed ';hen, by el*eau into the pool eater. Those are, referred to as stear1 vent clearing loads. "econ4$ st,eaT3 quenching vibrations can accor pany e-tend d relief valve diacharpe into the pool if the water is at an elevated temperature. |
| Pizat$pressureT1avesaregenerated withinthesuppression pool';hen,onfirstopening,$ | | The, enclosure specifies the infortation pertaining to these effects, T'hich c''e vill require tt3 ceaplete our review of your,design vith regard to these phenomena. |
| r@11+fvalvesdischarge highpressureairfol1owedbyel*eauintothepooleater.Thoseare,referredtoasstear1ventclearingloads."econ4$st,eaT3quenching vibrations canaccorpanye-tenddreliefvalvediacharpe intothepoolifthewaterisatanelevatedtemperature. | | Youp response to this request for information should be filed within ninety days, of'he date of receipt of this letter. Xf you cannot r1eet gg Ut1s schedule 9 please Bdv1se ua Qlthln f1fteen days., |
| The,enclosure specifies theinfortation pertaining totheseeffects,T'hichc''evillrequirett3ceapleteourreviewofyour,design vithregardtothesephenomena. | | OFFICE% |
| Youpresponsetothisrequestforinformation shouldbefiledwithinninetydays,of'hedateofreceiptofthisletter.Xfyoucannotr1eetggUt1sschedule9pleaseBdv1seuaQlthlnf1fteendays.,OFFICE%SURNAMEI$
| | SURNAMEI$ |
| DATE+FormAEC-318(Rev.9-53)AECM02+*II.d.OOVddNNCNT JAINTINOOFTICd)1929~99,2$ | | DATE+ |
| $
| | Form AEC-318 (Rev. 9-53) AECM 02+ |
| 8C~~H 0NiagaraNohawkPowerCorporation Pleasecontactusifyoudesireadditional discus'sion orclarification oftheinformation requested.
| | * II.d. OOVddNNCNT JAINTINO OFTICd) 1929~99,2$ $ |
| Sincerely, OriginalSignedbgD.e.Id,4cogJohnP.Stolz,ChiefLightWaterReactorsBranch2-1DivisionofReactorLicensing | | |
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| | 0 Niagara Nohawk Power Corporation 2 Please contact us if you desire additional discus'sion or clarification of the information requested. |
| | Sincerely, Original Signed bg D.e .Id,4 cog John P. Stolz, Chief Light Water Reactors Branch 2-1 Division of Reactor Licensing |
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| ==Enclosure:== | | ==Enclosure:== |
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| 'equestforAdditional Information ThisrequestforGenericInformation wasapprovedbyGAOunderablanketClearance No.B-180225(R0072);thisclearance expiresJuly31,1977.cc:LeBoeuf,Iamb,Leiby&HacRaeATTN:Hr.Arvi'nE.Upton,Esq.1737NStreet,N.W.Washington D.C.20036J.BruceHacDonald, Esq.,DeputyCommissioner andCounselNewYoikStateDepartment ofCommerce99Washington AvenueAlbany,NewYork12210CarmineJ.Clemente, Esq.NewYorkStateAtomicEnergy'ouncil "Department ofCommerce99Washington AvenueAlbany,NewYork12210AnthonyZ.Roisman,Esq.'erlin,RoismanandKessler1712NStreet,N.IU.Washington, D.C.20036tbcc:EHissSuzanneWeber,78WestSenacaStreetOswego,NewYork13126Hr.RichardGoldsmith SyracuseUniversity CollegeofLawE.I.IUhiteHall,CampusSyracuse, NewYork13210J.R.Buchanan, ORNLThomasB.Abernathy, DTIEDISTRIBUTION: | | 'equest for Additional Information This request for Generic Information was approved by GAO under a blanket Clearance No. B-180225 (R0072); this clearance expires July 31, 1977. |
| NRCPDRLocalPDRBranchFileDocketFileR.KleckerF.IUilliams F.Schroeder V.MooreA.KennekeR.DeYoungELDIE(3)IU.kaneH.SmithACRS(14)TRBranchesLIUR2BC'sJ.NorrisL'LUR-1IrOFFICEDSURI4AMEQ bATEQ4$ILUFormAEC-318(Rev.9-53)AECM0240L:LIUR2-1J44ZJ7S*V,S,COVCRNIICN2 PRIN2INOOPFICCII52$~55~555 0Qi)I'',8~.'-~lj;gi'~g Hr""~wJ1/n' 0'''REUESTFORADDITIOlcKLi"OP~~fATIOal RELIEFVALVELOwJ)S1.Specifythenumberofsafetyreliefvalves,theirdesignflowrate,anddischarge linesize.Providealistingofoperating conditions underwhichthese:valves wouldbeoperatedeithermanuallyorauto-matically.
| | cc: LeBoeuf, Iamb, Leiby & HacRae Carmine J. Clemente, Esq. |
| : Describe, withtheaiddischarge lineto,andorientation ofdrawings, theroutingofthein,thesuopression pool,andthedesignofthedischarge lineexit.2.Providetheloadspecification forthesuppression chaberstructure toaccommodate adtuation ofoneormoresafetyreliefvalves.I3.Providethedesignloadcapability forthesuppression chamberstructure.
| | ATTN: Hr. Arvi'n E. Upton, Esq. New York State Atomic 1737 N Street, N.W. Energy'ouncil Washington D. C. 20036 " Department of Commerce 99 Washington Avenue J. Bruce HacDonald, Esq., Deputy Albany, New York 12210 Commissioner and Counsel New Yoik State Department of Anthony Z. Roisman, Esq. |
| 4.Providejustification fortheloadspecification givenin(2)abovebytheuseofappropriate experi-ental dataandanalysis. | | Commerce Roisman and Kessler |
| IftheGeneralElectric(GE)Companyisresponsible forspecifying theseloads,astatement tothateffectissufficient.'.
| | 'erlin, 99 Washington Avenue 1712 N Street, N.IU. |
| : Identify, withtheaidofdrawings, anycomponents orstructures inthesuppression poolregion,otherthantheboundingwallsofthesuppression chamber,andthelocationofsuchcomponents relativetothereliefvalvedischarge lineexits.Discussthestructural capability ofthesecomponents toaccommodate loadsduetoreliefvalveactuation.
| | Albany, New York 12210 Washington, D. C. 20036 E |
| 6.Estimatethemaximumnumberofsingleandmultiplereliefvalveopeningsoverthelifeofyourplant. | | Hiss Suzanne Weber |
| | ,78 West Senaca Street DISTRIBUTION: |
| | Oswego, New York 13126 NRC PDR ACRS (14) |
| | Local PDR TR Branches Hr. Richard Goldsmith Branch File LIUR 2 BC's Syracuse University Docket File J. Norris College of Law R. Klecker E. I. IUhite Hall, Campus F. IUilliams Syracuse, New York 13210 F. Schroeder V. Moore A. Kenneke R. DeYoung ELD t IE (3) bcc: J. R. Buchanan, ORNL IU. kane Thomas B. A bernathy, DTIE H. Smith OFF ICED L'L UR -1 L: LIUR 2-1 SURI4AMEQ Ir J bATEQ 4$ILU 44ZJ7S Form AEC-318 (Rev. 9-53) AECM 0240 *V,S, COVCRNIICN2 PRIN2INO OPFICCI I52$ ~55 ~ 555 |
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| | RE UEST FOR ADDITIO lcK Li "OP~~fATIOal RELIEF VALVE LOwJ)S |
| | : 1. Specify the number of safety relief valves, their design flow rate, and discharge line size. Provide a listing of operating conditions under which these:valves would be operated either manually or auto-matically. Describe, with the aid of drawings, the routing o f the discharge line to, and orientation in, the suopression pool, and the design of the discharge line exit. |
| | : 2. Provide the load specification for the suppression cha ber structure to accommodate adtuation of one or more safety relief valves. |
| | I |
| | : 3. Provide the design load capability for the suppression chamber structure. |
| | : 4. Provide justification for the load specification given in (2) above by the use of appropriate experi-ental data and analysis. If the General Electric (GE) Company is responsible for specifying these loads, a statement to that effect is sufficient.'. |
| | Identify, with the aid of drawings, any components or structures in the suppression pool region, other than the bounding walls of the suppression chamber, and the location of such components relative to the relief valve discharge line exits. Discuss the structural capability of these components to accommodate loads due to relief valve actuation. |
| | : 6. Estimate the maximum number of single and multiple relief valve openings over the life of your plant. |
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| | : 7. identify the maximum temperature limits of the suppression pool with the reactor at power. This temperature limit should include I |
| | provisions for the testing requirements of relief valves. |
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| | : 8. Specify the operator actions that are planned when specified temperature limits are exceeded. |
| | : 9. Present the temperature transient of the suppression pool starting from the specified limits in (1) for the following transients: |
| | (a) main steam line isolation; (b) 'emi-automtic blowdown;. and, (c) stuck open relief valve.. |
| | For purposes of this analysis, the minimum water level should be assumed in the suppression pool. |
| | : 10. The temperature instrumentation that will be installed in the pool and the sampling or averaging technique that will be applied to arrive at a definitive pool temperature. |
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| ~/+40-2-7.identifythemaximumtemperature limitsofthesuppression poolwiththereactoratpower.Thistemperature limitshouldincludeIprovisions forthetestingrequirements ofreliefvalves./8.Specifytheoperatoractionsthatareplannedwhenspecified temperature limitsareexceeded.
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| 9.Presentthetemperature transient ofthesuppression poolstartingfromthespecified limitsin(1)forthefollowing transients:
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| (a)mainsteamlineisolation; (b)'emi-automtic blowdown;.
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| and,(c)stuckopenreliefvalve..Forpurposesofthisanalysis, theminimumwaterlevelshouldbeassumedinthesuppression pool.10.Thetemperature instrumentation thatwillbeinstalled inthepoolandthesamplingoraveraging technique thatwillbeappliedtoarriveatadefinitive pooltemperature.
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24312A1662024-11-0707 November 2024 Request for Additional Information (11/7/2024 E-mail) - LAR to Revise TSs to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3 ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC – Fleet Request – License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - 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Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - 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9 Rocket 1lo, 50-410 APR 21 1975 k'iagara )Johann power Corporation AY'XV: Nr. Cerald Ti. Bho@e Vice President Enpineerinp 3QO Erie boulevard Uest Syracuse', Petr York )3202 CentletEen:
Pursuant to 5 50.54(f) of 10 CP" Part 50, tho l'IuClear Regulatory Cormiasien (DEC) staff requires that, certainEblisinfozr ation related to the'esign of the containment for your facility'e submitted promptly to L,BC for its reviev.
.%isis requireE1ent results fgoa recent developr;ents associated with our on-going revieu area of Er,R plants with pressure supp'ression-typo contains.ento and the capability of the suppression pool retaininp structures to tolerate loads due to 'operation of th~ primary system pressure relief valves.
Experience at several operating; planta has indicated that loads due to relief valve act1$ ation ray not have been fully considered in the structural desi~a of the suppression chaw'ber. Xn addition, the Ceneral Electric Company is no19 Pr'eparing to start a series of srM111-scale relief valve tests ckich vill be used to verify analytical predictions of these loads aa applicable to al $ classes of plants.
Pool dynaoic loads du~ to relief valve -operation are due to two distinct phenomena. Pizat$ pressure T1aves are generated within the suppression pool on first opening,$ r@11+f valves discharge high pressure air fol1owed ';hen, by el*eau into the pool eater. Those are, referred to as stear1 vent clearing loads. "econ4$ st,eaT3 quenching vibrations can accor pany e-tend d relief valve diacharpe into the pool if the water is at an elevated temperature.
The, enclosure specifies the infortation pertaining to these effects, T'hich ce vill require tt3 ceaplete our review of your,design vith regard to these phenomena.
Youp response to this request for information should be filed within ninety days, of'he date of receipt of this letter. Xf you cannot r1eet gg Ut1s schedule 9 please Bdv1se ua Qlthln f1fteen days.,
OFFICE%
SURNAMEI$
DATE+
Form AEC-318 (Rev. 9-53) AECM 02+
- II.d. OOVddNNCNT JAINTINO OFTICd) 1929~99,2$ $
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0 Niagara Nohawk Power Corporation 2 Please contact us if you desire additional discus'sion or clarification of the information requested.
Sincerely, Original Signed bg D.e .Id,4 cog John P. Stolz, Chief Light Water Reactors Branch 2-1 Division of Reactor Licensing
Enclosure:
'equest for Additional Information This request for Generic Information was approved by GAO under a blanket Clearance No. B-180225 (R0072); this clearance expires July 31, 1977.
cc: LeBoeuf, Iamb, Leiby & HacRae Carmine J. Clemente, Esq.
ATTN: Hr. Arvi'n E. Upton, Esq. New York State Atomic 1737 N Street, N.W. Energy'ouncil Washington D. C. 20036 " Department of Commerce 99 Washington Avenue J. Bruce HacDonald, Esq., Deputy Albany, New York 12210 Commissioner and Counsel New Yoik State Department of Anthony Z. Roisman, Esq.
Commerce Roisman and Kessler
'erlin, 99 Washington Avenue 1712 N Street, N.IU.
Albany, New York 12210 Washington, D. C. 20036 E
Hiss Suzanne Weber
,78 West Senaca Street DISTRIBUTION:
Oswego, New York 13126 NRC PDR ACRS (14)
Local PDR TR Branches Hr. Richard Goldsmith Branch File LIUR 2 BC's Syracuse University Docket File J. Norris College of Law R. Klecker E. I. IUhite Hall, Campus F. IUilliams Syracuse, New York 13210 F. Schroeder V. Moore A. Kenneke R. DeYoung ELD t IE (3) bcc: J. R. Buchanan, ORNL IU. kane Thomas B. A bernathy, DTIE H. Smith OFF ICED L'L UR -1 L: LIUR 2-1 SURI4AMEQ Ir J bATEQ 4$ILU 44ZJ7S Form AEC-318 (Rev. 9-53) AECM 0240 *V,S, COVCRNIICN2 PRIN2INO OPFICCI I52$ ~55 ~ 555
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RE UEST FOR ADDITIO lcK Li "OP~~fATIOal RELIEF VALVE LOwJ)S
- 1. Specify the number of safety relief valves, their design flow rate, and discharge line size. Provide a listing of operating conditions under which these:valves would be operated either manually or auto-matically. Describe, with the aid of drawings, the routing o f the discharge line to, and orientation in, the suopression pool, and the design of the discharge line exit.
- 2. Provide the load specification for the suppression cha ber structure to accommodate adtuation of one or more safety relief valves.
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- 3. Provide the design load capability for the suppression chamber structure.
- 4. Provide justification for the load specification given in (2) above by the use of appropriate experi-ental data and analysis. If the General Electric (GE) Company is responsible for specifying these loads, a statement to that effect is sufficient.'.
Identify, with the aid of drawings, any components or structures in the suppression pool region, other than the bounding walls of the suppression chamber, and the location of such components relative to the relief valve discharge line exits. Discuss the structural capability of these components to accommodate loads due to relief valve actuation.
- 6. Estimate the maximum number of single and multiple relief valve openings over the life of your plant.
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- 7. identify the maximum temperature limits of the suppression pool with the reactor at power. This temperature limit should include I
provisions for the testing requirements of relief valves.
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- 8. Specify the operator actions that are planned when specified temperature limits are exceeded.
- 9. Present the temperature transient of the suppression pool starting from the specified limits in (1) for the following transients:
(a) main steam line isolation; (b) 'emi-automtic blowdown;. and, (c) stuck open relief valve..
For purposes of this analysis, the minimum water level should be assumed in the suppression pool.
- 10. The temperature instrumentation that will be installed in the pool and the sampling or averaging technique that will be applied to arrive at a definitive pool temperature.
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