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| {{#Wiki_filter:ACCELERATED DI TRIBUTION DEMONS TION SYSTEM e REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9401140194 DOC.DATE: 94/01/06 NOTARIZED: | | {{#Wiki_filter:ACCELERATED DI TRIBUTION DEMONS TION SYSTEM e |
| NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION PARRISH,J.V. | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | ACCESSION NBR:9401140194 DOC.DATE: 94/01/06 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Provides updated info re resolution of SBO for WNP-2.DISTRIBUTION CODE: AO50D COPIES RECEIVED:LTR (ENCL 0 SIZE: 3 TITLE: OR Submittal: | | Provides updated info re resolution of SBO for WNP-2. |
| Station Blackout (USI A-44)10CFR50.63, MPA A-22 NOTES'D RECIPIENT ID CODE/NAME PDV PD INTERNAL: ACRS NRR/DE/EELB | | DISTRIBUTION CODE: AO50D COPIES RECEIVED:LTR ( ENCL 0 SIZE: 3 TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A-22 D NOTES' RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDV PD CLIFFORD,J A INTERNAL: ACRS AEOD/DSP/TPAB D NRR/DE/EELB NRR/DRPE/PDII-4 REG |
| +~A/PLB REG FILE 01 EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME CLIFFORD,J AEOD/DSP/TPAB NRR/DRPE/PDII-4 NRR/DSSA/SRXB NSIC COPIES LTTR ENCL A D D D NOTE TO ALL"RIDS" RECIPIENTS:
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| D D PLEASE HELP US TO REDUCE WASTE(CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL~4
| | FILE PLB 01 NRR/DSSA/SRXB D EXTERNAL: NRC PDR NSIC D |
| | D D |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE( CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL ~ 4 |
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| WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Bax968~3000George Wasbtngton Way~Rtchland, Wasbtngton 99352-096'8 | | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bax968 ~ 3000George Wasbtngton Way ~ Rtchland, Wasbtngton 99352-096'8 ~ (509)372-5000 January 6, 1994 G02-94-002 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen: |
| ~(509)372-5000 January 6, 1994 G02-94-002 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: | |
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| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT NO.2, OPERATING LICENSE NPF-21 UPDATED INFORMATION REGARDING STATION BLACKOUT RESOLUTION (TAC No.M68626) | | NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 UPDATED INFORMATIONREGARDING STATION BLACKOUT RESOLUTION (TAC No. M68626) |
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| ==References:== | | ==References:== |
| | : 1. Letter GO2-92-057, dated March 6, 1992, GC Sorensen (SS) to NRC, "Safety Evaluation of the Washington Public Power Supply System Nuclear Project Number 2 Station Blackout Analysis" |
| | : 2. NUMARC 87-00, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," revised August 1991 |
| | : 3. Letter, dated December 30, 1991, PL Eng (NRC) to GC Sorensen (SS), |
| | "Safety Evaluation of the Washington Public Power Supply System (WPPSS) Nuclear Project Number 2 Station Blackout Analysis (TAC No. |
| | M68626)" |
| | : 4. Letter GO2-91-091, dated May 7, 1991, GC Sorensen (SS) to NRC, "Additional Information Regarding SBO (TAC No. 68626)" and Letter GO2-91-091, dated May 7, 1991, GC Sorensen (SS) to NRC, "Additional Information Regarding SBO (TAC No. 68626)" |
| | : 5. Letter GO2-92-099, dated April 15, 1992, GC Sorensen (SS) to NRC, "Safety Evaluation of the Washington Public Power Supply System Nuclear Project Number 2 Station Blackout Analysis (TAC No. M68626)" |
| | : 6. Letter GO2-92-183, dated July 31, 1992, GC Sorensen (SS) to NRC, "Station Blackout Supplemental SER and Implementation Schedule, 10CFR50.63(c)(4), TAC No. M68626" |
| | : 7. Letter, dated June 26, 1992, RR Assa (NRC) to GC Sorensen (SS), |
| | "Supplemental Safety Evaluation (SSE) of the Washington Public Power Supply System Nuclear Project No. 2 (WNP-2) Station Blackout Analysis (TAC M68626)" |
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| 1.2.3.4.5.6.7.Letter GO2-92-057, dated March 6, 1992, GC Sorensen (SS)to NRC,"Safety Evaluation of the Washington Public Power Supply System Nuclear Project Number 2 Station Blackout Analysis" NUMARC 87-00,"Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," revised August 1991 Letter, dated December 30, 1991, PL Eng (NRC)to GC Sorensen (SS),"Safety Evaluation of the Washington Public Power Supply System (WPPSS)Nuclear Project Number 2 Station Blackout Analysis (TAC No.M68626)" Letter GO2-91-091, dated May 7, 1991, GC Sorensen (SS)to NRC,"Additional Information Regarding SBO (TAC No.68626)" and Letter GO2-91-091, dated May 7, 1991, GC Sorensen (SS)to NRC,"Additional Information Regarding SBO (TAC No.68626)" Letter GO2-92-099, dated April 15, 1992, GC Sorensen (SS)to NRC,"Safety Evaluation of the Washington Public Power Supply System Nuclear Project Number 2 Station Blackout Analysis (TAC No.M68626)" Letter GO2-92-183, dated July 31, 1992, GC Sorensen (SS)to NRC,"Station Blackout Supplemental SER and Implementation Schedule, 10CFR50.63(c)(4), TAC No.M68626" Letter, dated June 26, 1992, RR Assa (NRC)to GC Sorensen (SS),"Supplemental Safety Evaluation (SSE)of the Washington Public Power Supply System Nuclear Project No.2 (WNP-2)Station Blackout Analysis (TAC M68626)" 940fx40X9O 94OXa~.PDR'.ADOCK.05000397,':."-',.P.'-...'"'";.PBR.=,'.
| | 2'age Two UPDATED INFORMATIONREGARDING STATION BLACKOUT (TAC No. M68626) |
| 2'age Two UPDATED INFORMATION REGARDING STATION BLACKOUT (TAC No.M68626)The purpose of this letter is to provide updated information regarding resolution of Station Blackout (SBO)for WNP-2.Prima on inmen Tem eratures and Pr ur In Reference 1 the Supply System provided the initial temperature assumptions and the final temperatures and pressures calculated for a four hour Station Blackout at WNP-2 as: ace Initial T~em'F Final T~em'F Pressure sl Dry well Wetwell air Wetwell water 135 135 90 280 240 240 40 42 These temperatures and pressures were calculated based upon an assumed primary system leakage rate of 200 gpm.This leakage value was chosen as the resolution of Generic Issue 23 (Reactor Coolant Pump Seal Integrity) was uncertain at the time the original analysis was performed. | | The purpose of this letter is to provide updated information regarding resolution of Station Blackout (SBO) for WNP-2. |
| The Supply System recognized that a leakage value greater than the 18 gpm/pump value for BWR SBO resolution might be required upon resolution of Generic Issue 23.It now appears that such a value will not be required of BWRs and the rulemaking to achieve resolution of Generic Issue 23 will only apply to PWRs.Consequently, we have completed the primary containment heatup analysis for WNP-2 for an assumed primary system leakage rate of 61 gpm which includes the 18 gpm/pump required by Appendix I of Reference 2 for BWRs plus the maximum Technical Specification value of 25 gpm.With a leakage rate of 61 gpm, the four hour primary containment temperatures and pressures are: Initial T~em'F Final T~em'F Pressure~sia/)~si~Dry well Wetwell air Wetwell water 135 150 90 229 179 209 35.3/20.6 29.7/15.0 The initial temperature assumption for the wetwell airspace was changed from 135 to 150'F to reflect the fact that there is no Technical Specification limit on this parameter but that a annunciator response procedure does require action at 147'F.The above temperatures and pressures were determined for an initial power of 3629 MWt which is greater than the currently planned power uprate level of 3486 MWt. | | Prima on inmen Tem eratures and Pr ur In Reference 1 the Supply System provided the initial temperature assumptions and the final temperatures and pressures calculated for a four hour Station Blackout at WNP-2 as: |
| ta i4 Jagt'.Three UPDATED INFORMATION REGARDING STATION BLACKOUT (TAC No.M68626)Condensate Invento The Reference 3 SBO Safety Evaluation for WNP-2 states in Section 2.3.1 that"The licensee indicated that the Technical Specifications (TS)require a minimum condensate storage tank reserve of 135,000 gallons of water".In Reference 4 the Supply System corrected a previous statement in this regard and informed the NRC that the Technical Specification value of 135,000 gallons only applies in Modes 4 and 5.In Reference 4 other means of ensuring the inventory of water during Mode 1 were discussed. | | Initial Final Pressure ace T~em 'F T~em 'F sl Drywell 135 280 40 Wetwell air 135 240 42 Wetwell water 90 240 These temperatures and pressures were calculated based upon an assumed primary system leakage rate of 200 gpm. This leakage value was chosen as the resolution of Generic Issue 23 (Reactor Coolant Pump Seal Integrity) was uncertain at the time the original analysis was performed. The Supply System recognized that a leakage value greater than the 18 gpm/pump value for BWR SBO resolution might be required upon resolution of Generic Issue 23. It now appears that such a value willnot be required of BWRs and the rulemaking to achieve resolution of Generic Issue 23 will only apply to PWRs. Consequently, we have completed the primary containment heatup analysis for WNP-2 for an assumed primary system leakage rate of 61 gpm I |
| These other means of ensuring the inventory are acknowledged in Section 2.3.2 of the Safety Evaluation. | | which includes the 18 gpm/pump required by Appendix of Reference 2 for BWRs plus the maximum Technical Specification value of 25 gpm. |
| Batte R om Heatin In Reference 5 it was stated that the battery room temperatures would be maintained to 74+1'F in the heating and cooling modes.As part of the implementation of improved setpoint methodology for WNP-2, the setpoints for the battery room heaters have been recalculated. | | With a leakage rate of 61 gpm, the four hour primary containment temperatures and pressures are: |
| The Lower Analytical Limit used in these calculations is the Technical Specification value of 60'F.This limit was not established at 74'F as the consideration for the 6'F deadband and environmental, accident and other effects would have resulted in excessively high battery room temperatures. | | Initial Final Pressure T~em 'F T~em 'F ~sia/ )~si ~ |
| To ensure that the rooms containing batteries B1-1 and Bl-2 are maintained at or above 74 F during normal operation, administrative controls are in place to require corrective action should the temperature be less than 74'F..Parrish (Mail Drop 1023)ssistant Managing Director, Operations AGH/bk CC: KE Perkins-NRC RV NS Reynolds-Winston 8c Strawn JW Clifford-NRC DL Williams-BPA/399 NRC Site Inspector-927N}} | | Drywell 135 229 35.3/20.6 Wetwell air 150 179 29.7/15.0 Wetwell water 90 209 The initial temperature assumption for the wetwell airspace was changed from 135 to 150'F to reflect the fact that there is no Technical Specification limit on this parameter but that a annunciator response procedure does require action at 147'F. |
| | The above temperatures and pressures were determined for an initial power of 3629 MWt which is greater than the currently planned power uprate level of 3486 MWt. |
| | |
| | ta i4 Jagt'. Three UPDATED INFORMATIONREGARDING STATION BLACKOUT (TAC No. M68626) |
| | Condensate Invento The Reference 3 SBO Safety Evaluation for WNP-2 states in Section 2.3.1 that "The licensee indicated that the Technical Specifications (TS) require a minimum condensate storage tank reserve of 135,000 gallons of water". |
| | In Reference 4 the Supply System corrected a previous statement in this regard and informed the NRC that the Technical Specification value of 135,000 gallons only applies in Modes 4 and |
| | : 5. In Reference 4 other means of ensuring the inventory of water during Mode 1 were discussed. These other means of ensuring the inventory are acknowledged in Section 2.3.2 of the Safety Evaluation. |
| | Batte R om Heatin In Reference 5 it was stated that the battery room temperatures would be maintained to 74 +1'F in the heating and cooling modes. |
| | As part of the implementation of improved setpoint methodology for WNP-2, the setpoints for the battery room heaters have been recalculated. The Lower Analytical Limit used in these calculations is the Technical Specification value of 60'F. This limit was not established at 74'F as the consideration for the 6'F deadband and environmental, accident and other effects would have resulted in excessively high battery room temperatures. To ensure that the rooms containing batteries B1-1 and Bl-2 are maintained at or above 74 F during normal operation, administrative controls are in place to require corrective action should the temperature be less than 74'F. |
| | . Parrish (Mail Drop 1023) ssistant Managing Director, Operations AGH/bk CC: KE Perkins - NRC RV NS Reynolds - Winston 8c Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Site Inspector - 927N}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999
Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required
ML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
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
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
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML20206U4501999-05-19019 May 1999
Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
ML20196K6961999-03-30030 March 1999
Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p)
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML20204F0261999-03-19019 March 1999
Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML17292B5991999-03-16016 March 1999
Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3)
ML17292B5911999-03-16016 March 1999
Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5901999-03-11011 March 1999
Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted
ML17292B5681999-03-0101 March 1999
Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1
ML17292B5651999-02-22022 February 1999
Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint
ML17292B5581999-02-0404 February 1999
Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999
1999-09-09
[Table view] |
Text
ACCELERATED DI TRIBUTION DEMONS TION SYSTEM e
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9401140194 DOC.DATE: 94/01/06 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides updated info re resolution of SBO for WNP-2.
DISTRIBUTION CODE: AO50D COPIES RECEIVED:LTR ( ENCL 0 SIZE: 3 TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A-22 D NOTES' RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDV PD CLIFFORD,J A INTERNAL: ACRS AEOD/DSP/TPAB D NRR/DE/EELB NRR/DRPE/PDII-4 REG
+~A/
FILE PLB 01 NRR/DSSA/SRXB D EXTERNAL: NRC PDR NSIC D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE( CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL ~ 4
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bax968 ~ 3000George Wasbtngton Way ~ Rtchland, Wasbtngton 99352-096'8 ~ (509)372-5000 January 6, 1994 G02-94-002 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 UPDATED INFORMATIONREGARDING STATION BLACKOUT RESOLUTION (TAC No. M68626)
References:
- 1. Letter GO2-92-057, dated March 6, 1992, GC Sorensen (SS) to NRC, "Safety Evaluation of the Washington Public Power Supply System Nuclear Project Number 2 Station Blackout Analysis"
- 2. NUMARC 87-00, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," revised August 1991
- 3. Letter, dated December 30, 1991, PL Eng (NRC) to GC Sorensen (SS),
"Safety Evaluation of the Washington Public Power Supply System (WPPSS) Nuclear Project Number 2 Station Blackout Analysis (TAC No.
M68626)"
- 4. Letter GO2-91-091, dated May 7, 1991, GC Sorensen (SS) to NRC, "Additional Information Regarding SBO (TAC No. 68626)" and Letter GO2-91-091, dated May 7, 1991, GC Sorensen (SS) to NRC, "Additional Information Regarding SBO (TAC No. 68626)"
- 5. Letter GO2-92-099, dated April 15, 1992, GC Sorensen (SS) to NRC, "Safety Evaluation of the Washington Public Power Supply System Nuclear Project Number 2 Station Blackout Analysis (TAC No. M68626)"
- 6. Letter GO2-92-183, dated July 31, 1992, GC Sorensen (SS) to NRC, "Station Blackout Supplemental SER and Implementation Schedule, 10CFR50.63(c)(4), TAC No. M68626"
- 7. Letter, dated June 26, 1992, RR Assa (NRC) to GC Sorensen (SS),
"Supplemental Safety Evaluation (SSE) of the Washington Public Power Supply System Nuclear Project No. 2 (WNP-2) Station Blackout Analysis (TAC M68626)"
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2'age Two UPDATED INFORMATIONREGARDING STATION BLACKOUT (TAC No. M68626)
The purpose of this letter is to provide updated information regarding resolution of Station Blackout (SBO) for WNP-2.
Prima on inmen Tem eratures and Pr ur In Reference 1 the Supply System provided the initial temperature assumptions and the final temperatures and pressures calculated for a four hour Station Blackout at WNP-2 as:
Initial Final Pressure ace T~em 'F T~em 'F sl Drywell 135 280 40 Wetwell air 135 240 42 Wetwell water 90 240 These temperatures and pressures were calculated based upon an assumed primary system leakage rate of 200 gpm. This leakage value was chosen as the resolution of Generic Issue 23 (Reactor Coolant Pump Seal Integrity) was uncertain at the time the original analysis was performed. The Supply System recognized that a leakage value greater than the 18 gpm/pump value for BWR SBO resolution might be required upon resolution of Generic Issue 23. It now appears that such a value willnot be required of BWRs and the rulemaking to achieve resolution of Generic Issue 23 will only apply to PWRs. Consequently, we have completed the primary containment heatup analysis for WNP-2 for an assumed primary system leakage rate of 61 gpm I
which includes the 18 gpm/pump required by Appendix of Reference 2 for BWRs plus the maximum Technical Specification value of 25 gpm.
With a leakage rate of 61 gpm, the four hour primary containment temperatures and pressures are:
Initial Final Pressure T~em 'F T~em 'F ~sia/ )~si ~
Drywell 135 229 35.3/20.6 Wetwell air 150 179 29.7/15.0 Wetwell water 90 209 The initial temperature assumption for the wetwell airspace was changed from 135 to 150'F to reflect the fact that there is no Technical Specification limit on this parameter but that a annunciator response procedure does require action at 147'F.
The above temperatures and pressures were determined for an initial power of 3629 MWt which is greater than the currently planned power uprate level of 3486 MWt.
ta i4 Jagt'. Three UPDATED INFORMATIONREGARDING STATION BLACKOUT (TAC No. M68626)
Condensate Invento The Reference 3 SBO Safety Evaluation for WNP-2 states in Section 2.3.1 that "The licensee indicated that the Technical Specifications (TS) require a minimum condensate storage tank reserve of 135,000 gallons of water".
In Reference 4 the Supply System corrected a previous statement in this regard and informed the NRC that the Technical Specification value of 135,000 gallons only applies in Modes 4 and
- 5. In Reference 4 other means of ensuring the inventory of water during Mode 1 were discussed. These other means of ensuring the inventory are acknowledged in Section 2.3.2 of the Safety Evaluation.
Batte R om Heatin In Reference 5 it was stated that the battery room temperatures would be maintained to 74 +1'F in the heating and cooling modes.
As part of the implementation of improved setpoint methodology for WNP-2, the setpoints for the battery room heaters have been recalculated. The Lower Analytical Limit used in these calculations is the Technical Specification value of 60'F. This limit was not established at 74'F as the consideration for the 6'F deadband and environmental, accident and other effects would have resulted in excessively high battery room temperatures. To ensure that the rooms containing batteries B1-1 and Bl-2 are maintained at or above 74 F during normal operation, administrative controls are in place to require corrective action should the temperature be less than 74'F.
. Parrish (Mail Drop 1023) ssistant Managing Director, Operations AGH/bk CC: KE Perkins - NRC RV NS Reynolds - Winston 8c Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Site Inspector - 927N
