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| | issue date = 05/22/1985 | | | issue date = 05/22/1985 |
| | title = Application for Amend to License NPF-21,revising Tech Specs to Change Min Allowable Voltage Band on Auto Starting of Diesel Generators DG-1 & DG-2,making Band Consistent W/ Output Breaker Closure Permissive Setpoint.Fee Paid | | | title = Application for Amend to License NPF-21,revising Tech Specs to Change Min Allowable Voltage Band on Auto Starting of Diesel Generators DG-1 & DG-2,making Band Consistent W/ Output Breaker Closure Permissive Setpoint.Fee Paid |
| | author name = SORENSEN G C | | | author name = Sorensen G |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = BUTLER W R | | | addressee name = Butler W |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000397 | | | docket = 05000397 |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 10 | | | page count = 10 |
| | | project = |
| | | stage = Request |
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| {{#Wiki_filter:REG ATO INFORMATION DISTRIB ON STEM (RIDS)ACCESSION NBR:8505290460 DOC~DATE 85/05/22, NOTARIZED YES DOCKET FACIL:50-397 WPPSS Nuclear Projects Unit 2i Washington Public Powe'5000397 AUTH BYNAME AUTHOR AFFILIATION SORENSENiG.C, Washington Public Power Supply System RECIP~NAME RECIPIENT AFFILIATION BUTLERgW,Ro Licensing Branch 2 | | {{#Wiki_filter:REG ATO INFORMATION DISTRIB ON STEM (RIDS) |
| | ACCESSION NBR:8505290460 DOC ~ DATE 85/05/22, NOTARIZED YES DOCKET FACIL:50-397 BYNAME WPPSS Nuclear Projects Unit 2i Washington Public Powe'5000397 AUTH AUTHOR AFFILIATION SORENSENiG.C, Washington Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION BUTLERgW,Ro Licensing Branch 2 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for amend to License'PF 21irevising Tech'pecs to change min allowable voltage>>band on auto starting, of Diesel Generators DG 1 8 DG-2<making band consistent-w/output breaker closure permissive setpoint,Fee, paid.DISTRIBUTION CODE: A001D COPIES RECEIVED;LTR ENCL J SIZE: TITLE: OR Submi t tal: Gener al Di str ibuti on NOTES: OL:12/20/83 05000397 RECIPIENT ID CODE/NAME" NRR LB2" BC 01 INTERNAL: ACRS 09 ELD/HDS2 NRR/DL DIR NRR/DL/TSRG NRR/DSI/RAB RGN5 EXTERNAL'GSG BRUSKEgS NRC PDR 02 COPIES LTTR ENCL 7 7 6 6 1 0 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ADM/LFMB NRR/DE/MTEB NRR/DL/ORAB NR R/0 S I'/MET 8'PDR NSIC 03 05 COPIES LTTR ENCL'.1 1 1 0 1 1 1 1>>1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24 | | Application for amend to License'PF 21irevising Tech'pecs to change min allowable voltage>> band on auto starting, of Diesel Generators DG 1 8 DG-2<making band consistent- w/ |
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| | output breaker closure permissive setpoint,Fee, paid. |
| Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richiand, Washington 99352 (509)372-5000 May 22, 1985 G02-85-260 Docket No.50-397 Director of Nuclear Reactor Regulation Attention:
| | DISTRIBUTION CODE: A001D COPIES RECEIVED;LTR ENCL J SIZE: |
| Mr.W.R.Butler, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | TITLE: OR Submi t tal: Gener al Di str ibuti on NOTES: 05000397 OL:12/20/83 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME" LTTR ENCL ID CODE/NAME LTTR ENCL'. |
| | NRR LB2" BC 01 7 7 INTERNAL: ACRS 09 6 6 ADM/LFMB ELD/HDS2 1 0 NRR/DE/MTEB 1 1 NRR/DL DIR 1 1 NRR/DL/ORAB 1 0 NRR/DL/TSRG 1 1 NR R/0 S I'/MET 8 1 1 NRR/DSI/RAB 1 1 1 1>> |
| | RGN5 1 |
| | 'PDR EXTERNAL'GSG BRUSKEgS 03 1 NRC PDR 02 NSIC 05 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24 |
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| ==Dear Mr.Schwencer:== | | >> II '\ |
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| | Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richiand, Washington 99352 (509) 372-5000 May 22, 1985 G02-85-260 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| | ==Dear Mr. Schwencer:== |
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| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 4.8.1.1.2, ELECTRICAL POWER SYSTEMS (A.C.SOURCES)1)Letter, G02-85-207, G.C.Sorensen (SS)to J.B.Martin (NRC,, Region V),"NRC Enforcement Action EA 85-30", dated April 17, 1985 In accordance with the Code of Federal Regulations (CFR), Title 10, Parts'0.90 and 2.101, the Supply System hereby requests an amendment to the WHP-2 Technical Specifications. | | NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 4.8.1.1.2, ELECTRICAL POWER SYSTEMS (A.C. SOURCES) |
| Specifically, the Supply System is requesting a change to Surveillance Requirement 4.8.1.1.2 (Pages 3/4 8-3, 8-.5 and 8-6 attached)which changes the minimum allowable voltage band on auto starting of Diesel Generators DG-1 and DG-2 making it consistent with the output breaker closure permissive setpoint.
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| ==Reference:== | | ==Reference:== |
| | : 1) Letter, G02-85-207, G. C. Sorensen (SS) to J. B. |
| | Martin (NRC,, Region V), "NRC Enforcement Action EA 85-30", dated April 17, 1985 In accordance with the Code of Federal Regulations (CFR), Title 10, and 2.101, the Supply System hereby requests an amendment to the Parts'0.90 WHP-2 Technical Specifications. Specifically, the Supply System is requesting a change to Surveillance Requirement 4.8. 1.1.2 (Pages 3/4 8-3, 8-. 5 and 8-6 attached) which changes the minimum allowable voltage band on auto starting of Diesel Generators DG-1 and DG-2 making it consistent with the output breaker closure permissive setpoint. |
| | The technical specifications were developed to reflect appropriate system perform-ance acceptance criteria. However, as presently stated, the WNP-2 Technical Specification potentially allows the establishment of a condition which could preclude operation of the Diesel Generators without additional operator action. |
| | Design of the Division 1 and 2 generator output breakers will not allow closure of the breaker until voltage is within 94/ of rated voltage (3910 VAC). Current technical specifications state that voltage must be 4160 + 420 VAC. |
| | The 94K setpoint was established to ensure that the Diesel Generators will be able to accept the first load block during initial loading. From no load to full load (without operator action}, the voltage will not fall below 80Ã of rated voltage. The new voltage range on starting should be 4160 +420 VAC for DG-1 and DG-2, and 4160 + 420 VAC for DG-3. -250 850529'0464 850522 f I PDR ADOCK 05000397 P PDRQ ) |
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| | W. R. Butler Page Two May 22, 1985 REQUEST FOR ANENDblENT TO TECH. SPEC. SURVEILLANCE REQUIREMENT 4.8.1.1.2 The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will result from this amendment. |
| | The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not: |
| | : 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because this value is more conser-vative than the value presently in our technical specifications and therefore does not impact the accident analysis; or |
| | : 2) Create the possibility of a new or different kind of accident than previously evaluated because this change only corrects the technical specification allowable voltage range for checking diesel generator voltage on an outstart or surveillance; or |
| | : 3) Involve a significant reduction in a margin of safety because it will result in Surveillance Procedures which more closely parallel the design of the installed equipment and design basis. |
| | On April 6, 1983, the NRC published guidance in the Federal Register (48 FR 14870) concerning examples of amendments that are not likely to involve significant hazards consideration. One such example (ii) involves a change |
| | . that constitutes an additional limitation, restriction, or control not presently included in the technical specification: for example, a more stringent surveillance requirement." Accordingly, the proposed change to the technical specifications involves no significant hazards considerations. |
| | The Supply System has evaluated this request in accordance with the criteria contained in 10 CFR 170.21 and has included a warrant for One hundred fifty dollars ($ 150.00) as initial payment for this application for amendment under Facility Category A (Power Reactors). |
| | In accordance with 10 CFR 50.9l, the State of Washington has been provided a copy of this letter. |
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| The 94K setpoint was established to ensure that the Diesel Generators will be able to accept the first load block during initial loading.From no load to full load (without operator action}, the voltage will not fall below 80Ãof rated voltage.The new voltage range on starting should be 4160+420 VAC for DG-1 and DG-2, and 4160+420 VAC for DG-3.-250 The technical specifications were developed to reflect appropriate system perform-ance acceptance criteria.However, as presently stated, the WNP-2 Technical Specification potentially allows the establishment of a condition which could preclude operation of the Diesel Generators without additional operator action.Design of the Division 1 and 2 generator output breakers will not allow closure of the breaker until voltage is within 94/of rated voltage (3910 VAC).Current technical specifications state that voltage must be 4160+420 VAC.850529'0464 850522 f I PDR ADOCK 05000397 P PDRQ)
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| W.R.Butler Page Two May 22, 1985 REQUEST FOR ANENDblENT TO TECH.SPEC.SURVEILLANCE REQUIREMENT 4.8.1.1.2 The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will result from this amendment.
| | kl. R. Butler Page Three May 22, 1985 |
| The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not: 1)Involve a significant increase in the probability or consequences of an accident previously evaluated because this value is more conser-vative than the value presently in our technical specifications and therefore does not impact the accident analysis;or 2)Create the possibility of a new or different kind of accident than previously evaluated because this change only corrects the technical specification allowable voltage range for checking diesel generator voltage on an outstart or surveillance; or 3)Involve a significant reduction in a margin of safety because it will result in Surveillance Procedures which more closely parallel the design of the installed equipment and design basis.On April 6, 1983, the NRC published guidance in the Federal Register (48 FR 14870)concerning examples of amendments that are not likely to involve significant hazards consideration.
| | , REQUEST FOR AMENDMENT TO TECH. SPEC. SURVEILLANCE REQUIREMENT 4.8. 1. 1.2 t |
| One such example (ii)involves a change.that constitutes an additional limitation, restriction, or control not presently included in the technical specification:
| | t This Technical Specification change has been reviewed and approved by the lJNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). Should you have any questions, please contact Mr. P. L. |
| for example, a more stringent surveillance requirement." Accordingly, the proposed change to the technical specifications involves no significant hazards considerations.
| | Powell, Manager, l<NP-2 Licensing. |
| The Supply System has evaluated this request in accordance with the criteria contained in 10 CFR 170.21 and has included a warrant for One hundred fifty dollars ($150.00)as initial payment for this application for amendment under Facility Category A (Power Reactors).
| | Very truly yours, P- G. C. Sorensen, Manager Regulatory Programs HLA/tmh Attachments cc: JO Bradfute - NRC l<S Chin - BPA C Eschels - EFSEC JB - |
| In accordance with 10 CFR 50.9l, the State of Washington has been provided a copy of this letter.
| | Martin NRC RV E Revell BPA AD Toth - NRC Site |
| 0 0~~1 t kl.R.Butler Page Three May 22, 1985 , REQUEST FOR AMENDMENT TO TECH.SPEC.SURVEILLANCE REQUIREMENT 4.8.1.1.2 t t This Technical Specification change has been reviewed and approved by the lJNP-2 Plant Operations Committee (POC)and the Supply System Corporate Nuclear Safety Review Board (CNSRB).Should you have any questions, please contact Mr.P.L.Powell, Manager, l<NP-2 Licensing. | | |
| Very truly yours, P-G.C.Sorensen, Manager Regulatory Programs HLA/tmh Attachments cc: JO Bradfute-NRC l<S Chin-BPA C Eschels-EFSEC JB Martin-NRC RV E Revell-BPA AD Toth-NRC Site | | ~ ~ ~ ~ |
| ~~~~C STATE Of WASHINGTON | | C |
| ))County of Benton
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| | )o~r ten/men( Io'Tech.Vpec. |
| | Surveillance Requirement 4.8.1.1.2, Elec. Power STATE Of WASHINGTON |
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| ==Subject:== | | ==Subject:== |
| )o~r ten/men(Io'Tech.Vpec.
| | Systems (A.C. Sources) |
| Surveillance Requirement 4.8.1.1.2, Elec.Power Systems (A.C.Sources)I, R.B.GLASSCOCK, being duly sworn, subscribe to and say that I am the Director of Licensing and Assurance, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein;that I have full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.DATE 1985.B.Glasscock, Director Licensing and Assurance 1985.On this day personally appeared before me R.B.GLASSCOCK to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.
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| GIVEN under my hand and seal this~%ay of r r r j o ary u sc sn a or e State of Washington Residing at 0~I 4"'k'll g I~4/~4~-I4 s'0~~}} | | ) |
| | County of Benton I, R. B. GLASSCOCK, being duly sworn, subscribe to and say that I am the Director of Licensing and Assurance, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true. |
| | DATE 1985 |
| | . B. Glasscock, Director Licensing and Assurance On this day personally appeared before me R. B. GLASSCOCK to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned. |
| | GIVEN under my hand and seal this ~%ay of 1985. |
| | o ary u sc sn a or e State of Washington Residing at r r r |
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Letter Sequence Request |
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MONTHYEARML17277B7491985-05-22022 May 1985 Application for Amend to License NPF-21,revising Tech Specs to Change Min Allowable Voltage Band on Auto Starting of Diesel Generators DG-1 & DG-2,making Band Consistent W/ Output Breaker Closure Permissive Setpoint.Fee Paid Project stage: Request ML20198C1251985-10-15015 October 1985 Discusses 850522 Proposed Tech Spec Changes to Surveillance Requirement 4.8.1.1.2 Re Electrical Power Sys.Proposed Change Reflects Appropriate Sys Coordination to Improve Availability of Diesel Generators & Acceptable Project stage: Other 1985-10-15
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17284A9101999-10-13013 October 1999 Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8501999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8471999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level. ML17284A8441999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a. ML17284A8431999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring ML17284A8401999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl ML17292B6441999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6321999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4861998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML17284A8071998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl ML17284A7161998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7051998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17292B3401998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi ML17292B1301997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0261997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line ML17292A9401997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A8631997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7561997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A5491996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl ML17292A5381996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A4081996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage ML17291B2781996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing ML17291B2071996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B0921995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A8421995-06-0606 June 1995 Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles ML17291A8381995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 ML17291A8321995-06-0606 June 1995 Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16 ML17291A7551995-04-25025 April 1995 Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A4791994-10-31031 October 1994 Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4741994-10-31031 October 1994 Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys. ML17291A4201994-09-26026 September 1994 Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis ML17291A3941994-09-18018 September 1994 Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3171994-08-0808 August 1994 Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program. ML17291A2151994-07-12012 July 1994 Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits ML17291A2201994-07-0808 July 1994 Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17290B1711994-05-0606 May 1994 Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication ML17290B1551994-05-0505 May 1994 Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves. ML17290A9631994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing ML17290A9601994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations ML17290A9551994-02-0808 February 1994 Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63 ML17290A9031994-01-13013 January 1994 Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation. ML17290A8961994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements ML17290A8781994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures ML17290A8921994-01-0606 January 1994 Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2 ML17290A8391993-12-20020 December 1993 Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys. ML17290A8181993-12-0606 December 1993 Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys ML17290A8221993-12-0606 December 1993 Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H 1999-07-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17284A9101999-10-13013 October 1999 Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8501999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8471999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level. ML17284A8441999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a. ML17284A8431999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring ML17284A8401999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl ML17292B6441999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6321999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4861998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML17284A8071998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl ML17284A7161998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7051998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17292B3401998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi ML17292B1301997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0261997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line ML17292A9401997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A8631997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7561997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A5491996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl ML17292A5381996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A4081996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage ML17291B2781996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing ML17291B2071996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B0921995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A8421995-06-0606 June 1995 Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles ML17291A8381995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 ML17291A8321995-06-0606 June 1995 Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16 ML17291A7551995-04-25025 April 1995 Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A4791994-10-31031 October 1994 Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4741994-10-31031 October 1994 Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys. ML17291A4201994-09-26026 September 1994 Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis ML17291A3941994-09-18018 September 1994 Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3171994-08-0808 August 1994 Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program. ML17291A2151994-07-12012 July 1994 Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits ML17291A2201994-07-0808 July 1994 Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17290B1711994-05-0606 May 1994 Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication ML17290B1551994-05-0505 May 1994 Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves. ML17290A9631994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing ML17290A9601994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations ML17290A9551994-02-0808 February 1994 Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63 ML17290A9031994-01-13013 January 1994 Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation. ML17290A8961994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements ML17290A8781994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures ML17290A8921994-01-0606 January 1994 Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2 ML17290A8391993-12-20020 December 1993 Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys. ML17290A8181993-12-0606 December 1993 Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys ML17290A8221993-12-0606 December 1993 Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H 1999-07-29
[Table view] |
Text
REG ATO INFORMATION DISTRIB ON STEM (RIDS)
ACCESSION NBR:8505290460 DOC ~ DATE 85/05/22, NOTARIZED YES DOCKET FACIL:50-397 BYNAME WPPSS Nuclear Projects Unit 2i Washington Public Powe'5000397 AUTH AUTHOR AFFILIATION SORENSENiG.C, Washington Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION BUTLERgW,Ro Licensing Branch 2
SUBJECT:
Application for amend to License'PF 21irevising Tech'pecs to change min allowable voltage>> band on auto starting, of Diesel Generators DG 1 8 DG-2<making band consistent- w/
output breaker closure permissive setpoint,Fee, paid.
DISTRIBUTION CODE: A001D COPIES RECEIVED;LTR ENCL J SIZE:
TITLE: OR Submi t tal: Gener al Di str ibuti on NOTES: 05000397 OL:12/20/83 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME" LTTR ENCL ID CODE/NAME LTTR ENCL'.
NRR LB2" BC 01 7 7 INTERNAL: ACRS 09 6 6 ADM/LFMB ELD/HDS2 1 0 NRR/DE/MTEB 1 1 NRR/DL DIR 1 1 NRR/DL/ORAB 1 0 NRR/DL/TSRG 1 1 NR R/0 S I'/MET 8 1 1 NRR/DSI/RAB 1 1 1 1>>
RGN5 1
'PDR EXTERNAL'GSG BRUSKEgS 03 1 NRC PDR 02 NSIC 05 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richiand, Washington 99352 (509) 372-5000 May 22, 1985 G02-85-260 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 4.8.1.1.2, ELECTRICAL POWER SYSTEMS (A.C. SOURCES)
Reference:
- 1) Letter, G02-85-207, G. C. Sorensen (SS) to J. B.
Martin (NRC,, Region V), "NRC Enforcement Action EA 85-30", dated April 17, 1985 In accordance with the Code of Federal Regulations (CFR), Title 10, and 2.101, the Supply System hereby requests an amendment to the Parts'0.90 WHP-2 Technical Specifications. Specifically, the Supply System is requesting a change to Surveillance Requirement 4.8. 1.1.2 (Pages 3/4 8-3, 8-. 5 and 8-6 attached) which changes the minimum allowable voltage band on auto starting of Diesel Generators DG-1 and DG-2 making it consistent with the output breaker closure permissive setpoint.
The technical specifications were developed to reflect appropriate system perform-ance acceptance criteria. However, as presently stated, the WNP-2 Technical Specification potentially allows the establishment of a condition which could preclude operation of the Diesel Generators without additional operator action.
Design of the Division 1 and 2 generator output breakers will not allow closure of the breaker until voltage is within 94/ of rated voltage (3910 VAC). Current technical specifications state that voltage must be 4160 + 420 VAC.
The 94K setpoint was established to ensure that the Diesel Generators will be able to accept the first load block during initial loading. From no load to full load (without operator action}, the voltage will not fall below 80Ã of rated voltage. The new voltage range on starting should be 4160 +420 VAC for DG-1 and DG-2, and 4160 + 420 VAC for DG-3. -250 850529'0464 850522 f I PDR ADOCK 05000397 P PDRQ )
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W. R. Butler Page Two May 22, 1985 REQUEST FOR ANENDblENT TO TECH. SPEC. SURVEILLANCE REQUIREMENT 4.8.1.1.2 The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will result from this amendment.
The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because this value is more conser-vative than the value presently in our technical specifications and therefore does not impact the accident analysis; or
- 2) Create the possibility of a new or different kind of accident than previously evaluated because this change only corrects the technical specification allowable voltage range for checking diesel generator voltage on an outstart or surveillance; or
- 3) Involve a significant reduction in a margin of safety because it will result in Surveillance Procedures which more closely parallel the design of the installed equipment and design basis.
On April 6, 1983, the NRC published guidance in the Federal Register (48 FR 14870) concerning examples of amendments that are not likely to involve significant hazards consideration. One such example (ii) involves a change
. that constitutes an additional limitation, restriction, or control not presently included in the technical specification: for example, a more stringent surveillance requirement." Accordingly, the proposed change to the technical specifications involves no significant hazards considerations.
The Supply System has evaluated this request in accordance with the criteria contained in 10 CFR 170.21 and has included a warrant for One hundred fifty dollars ($ 150.00) as initial payment for this application for amendment under Facility Category A (Power Reactors).
In accordance with 10 CFR 50.9l, the State of Washington has been provided a copy of this letter.
0 0 ~ ~ 1 t
kl. R. Butler Page Three May 22, 1985
, REQUEST FOR AMENDMENT TO TECH. SPEC. SURVEILLANCE REQUIREMENT 4.8. 1. 1.2 t
t This Technical Specification change has been reviewed and approved by the lJNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). Should you have any questions, please contact Mr. P. L.
Powell, Manager, l<NP-2 Licensing.
Very truly yours, P- G. C. Sorensen, Manager Regulatory Programs HLA/tmh Attachments cc: JO Bradfute - NRC l<S Chin - BPA C Eschels - EFSEC JB -
Martin NRC RV E Revell BPA AD Toth - NRC Site
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Surveillance Requirement 4.8.1.1.2, Elec. Power STATE Of WASHINGTON
Subject:
Systems (A.C. Sources)
)
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County of Benton I, R. B. GLASSCOCK, being duly sworn, subscribe to and say that I am the Director of Licensing and Assurance, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
DATE 1985
. B. Glasscock, Director Licensing and Assurance On this day personally appeared before me R. B. GLASSCOCK to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this ~%ay of 1985.
o ary u sc sn a or e State of Washington Residing at r r r
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