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| | issue date = 06/18/1985 | | | issue date = 06/18/1985 |
| | title = Application for Amend to License NPF-21,requesting Emergency Tech Specs Change to Reflect Installation of Larger Fuses in Primary Containment Penetration Conductor Overcurrent Protective Devices.Fee Paid | | | title = Application for Amend to License NPF-21,requesting Emergency Tech Specs Change to Reflect Installation of Larger Fuses in Primary Containment Penetration Conductor Overcurrent Protective Devices.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 = 8 | | | page count = 8 |
| | | project = |
| | | stage = Request |
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| {{#Wiki_filter:REGULATu INFORMATION DISTRIBUTION TEM (RIDS)ACCESSIoN NBR:850e200156 Doc.DATE: 85/oe/18 NOTARIZED; YES DOCKET¹FACIL:50"397 NPPSS Nuclear Projectr Uni t 2i Washington Public Powe 05000397 AUTH BYNAME.AUTHOR AFF ILI ATION'SORENSENrG | | {{#Wiki_filter:REGULATu INFORMATION DISTRIBUTION TEM (RIDS) |
| ~C Washington Public Power Supply System RECIP~NAME>>RECIPIENT AFFILIATION BUTLERrN~RE Licensing Branch 2 SUBJECT;Application for amend to License NPF 2irrequesting emergency Tech Specs change to reflect installation of larger fuses" in primary containment penetration conductor over'current protective devices.Fee paid, DI'STRIBUTION CODE: A001D COPIES RECEI VED: LTR'ENCL SIZE o TITLE.: OR Submittal: | | ACCESSIoN NBR:850e200156 Doc.DATE: 85/oe/18 NOTARIZED; YES DOCKET ¹ FACIL:50 "397 BYNAME. NPPSS Nuclear Projectr Uni t 2i Washington Public Powe 05000397 AUTH AUTHOR AFF ILIATION |
| General Distribution NOTES: OL:12/20/83 RECIPIENT ID CODE/NAME NRR LB2 BC 01 COPIES LTTR ENCL 7 7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNAL: ACRS 09 ELD/HDS2 NRR/DL D IR NRR/DL/TSRG NRR/DS I/RAB RGA5 e e 1 0 1 1 1 1 1 1 1 ADM/LFMB 1 0 NRR/DE/MTEB | | 'SORENSENrG ~ C Washington Public Power Supply System RECIP ~ NAME>> RECIPIENT AFFILIATION BUTLERrN ~ RE Licensing Branch 2 SUBJECT; Application for amend to License NPF 2irrequesting emergency Tech Specs change to reflect installation of larger fuses" in primary containment penetration conductor over'current protective devices.Fee paid, DI'STRIBUTION CODE: A001D COPIES RECEI VED: LTR ' |
| '1 NRR/DL/ORAB 0 NR/I/METB 1 1 EG L 04 1 EXTERNAL: 24X LPDR Nsic 03>>05 1 1 1 1 1 1 EGS,G BRUSKE,S NRC PDR 02 1 1" 1 1~TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25 A 1 II i(r N ll ,,(g"I I'11 r'[~~II i II II 1)i i I H W V I(IA il Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richland, Washington 99352 (509)372-5000 June 18, 1985 G02-85-321 Docket No.50-397 Director of Nuclear Reactor Regulation Attention:
| | ENCL SIZE o TITLE.: OR Submittal: General Distribution NOTES: |
| Mr.W.R.Butler, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | 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 e e ADM/LFMB 1 0 NRR/DE/MTEB ' |
| | ELD/HDS2 1 0 1 NRR/DL D IR 1 1 NRR/DL/ORAB 0 NRR/DL/TSRG 1 1 NR / I/METB 1 1 NRR/DS I/RAB 1 EG L 04 1 RGA5 1 1 EXTERNAL: 24X 1 1 EGS,G BRUSKE,S 1 1" LPDR 03>> 1 1 NRC PDR 02 1 1 Nsic 05 1 1 |
| | ~TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25 |
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| | Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 June 18, 1985 G02-85-321 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. Butler:== |
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| ==Subject:== | | ==Subject:== |
| | NUCLEAR PLANT NO. 2 REQUEST FOR EMERGENCY TECHNICAL SPECIFICATION CHANGE TO TECHNICAL SPECIFICATION 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES |
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| ==Reference:== | | ==Reference:== |
| | Letter, G02-85-312, G. C. Sorensen (SS) to W. R. Butler (NRC), Same Subject, dated June 13, 1985 In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an emergency change to the WNP-2 Technical Specifications. Specifically, the Supply System is requesting a change to Technical Specification 3.8.4.2. |
| | Testing for the first eighteen (18} month surveillances required by the WNP-2 Technical Specifications is now in progress. As a result, Surveillance Re-quirement 4.8.4.2.a.3 has prompted a review of the fuses listed in Table 3.8.4.2-1 (revised in Amendment 6 dated October 12, 1984 due to a change request from March 9, 1984}. This review disclosed that as a result of cer tain plant modifications the fuses listed in the Table were replaced with largel fuses. Supply System design change procedures have ensured in all such cases that the new fuse sizing is within the design bases. A safety analysis has been performed on each change to'confirm that the design change remains within the design margin, of the plant. |
| | The Supply System first. became aware of the possible need for the requested technical specification change on June 6, 1985 and immediately commenced the internal review procedure which resulted in the request, submitted in the F'.ao referenced letter. We understand the changes requested by. the referenced letter can not be granted prior to.plant startup. Therefore, in view of the 8506200156 850ji8>97 Pl PDR ADOCK 05000397 |
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| | W. R. Butler Page Two June 18, 1985 REQUEST FOR EMERGENCY TECH. SPEC. CHANGE TO TECH. SPEC. 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES need for plant technical specifications to conform with actual plant configuration prior to startup, the Supply System is requesting the attached changes be processed on an emergency basis and the changes submitted in the referenced letter be approved through the normal pro-cess contemplated by Section 50.91. Accordingly, the Supply System hereby requests an emergency change be granted in accordance with 10 CFR Parts 50.91(a)(5) and 2.106 to support WNP-2 starting up on June 21, 1985. Again, this request is being sought promptly after the need for the technical specification modification was identified and the Supply System has not created this emergency to take advantage of Section 50.91(a)(5). It appears in the judgment of the Supply System that startup will be delayed unless the requested amendment is granted by June 21, 1985. It should be noted that the potential for missing the June 21 startup date exists. This potential has been discussed with members of your staff and as soon as a definite change is realized your staff will be informed. |
| | The fuses listed, in the proposed Table 3.8.4.2-1 (attached) have been changed to reflect design changes made to plant equipment. The fuses have been's'ized'to ensure service to the associated equipment yet still be within |
| | 'the design margin of the containment penetration assembly. As designs to electrical loads within containment are revised to support plant modifica-tions these fuses will be changed, however at all times within the control of the WNP-2 design process, to ensure continued design margin. |
| | The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will result from this amendment. This technical specification change has been review'ed and approved by the WNP-2 Plant Operations Committee'and the Supply System Corporate Nuclear Safety Review Board. |
| | 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 the changes are within the design margin. Previously. evaluated events will remain bounding. Therefore no increases in probability or consequence is conceivable. |
| | : 2) Create the possibility of a new or different kind of accident than previously evaluated',because no new accident scenarios are credible. |
| | All 'changes remain within design margin and installed equipment to respond to accidents remains 'the same. |
| | : 3) involve a significant. reduction in a margin of safety because the sizing of fuses within the design margin does *not encroach on the overall margin of safety. ' |
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| NUCLEAR PLANT NO.2 REQUEST FOR EMERGENCY TECHNICAL SPECIFICATION CHANGE TO TECHNICAL SPECIFICATION 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES Letter, G02-85-312, G.C.Sorensen (SS)to W.R.Butler (NRC), Same Subject, dated June 13, 1985 In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an emergency change to the WNP-2 Technical Specifications.
| | W. R. Butler Page Three June 18, 1985 REQUEST FOR EMERGENCY TECH. SPEC. CHANGE TO TECH. SPEC. 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES This change does not involve a significant hazards consideration. Example (i) |
| Specifically, the Supply System is requesting a change to Technical Specification 3.8.4.2.Testing for the first eighteen (18}month surveillances required by the WNP-2 Technical Specifications is now in progress.As a result, Surveillance Re-quirement 4.8.4.2.a.3 has prompted a review of the fuses listed in Table 3.8.4.2-1 (revised in Amendment 6 dated October 12, 1984 due to a change request from March 9, 1984}.This review disclosed that as a result of cer tain plant modifications the fuses listed in the Table were replaced with largel fuses.Supply System design change procedures have ensured in all such cases that the new fuse sizing is within the design bases.A safety analysis has been performed on each change to'confirm that the design change remains within the design margin, of the plant.The Supply System first.became aware of the possible need for the requested technical specification change on June 6, 1985 and immediately commenced the internal review procedure which resulted in the request, submitted in the referenced letter.We understand the changes requested by.the referenced letter can not be granted prior to.plant startup.Therefore, in view of the 8506200156 850ji8>97 PDR ADOCK 05000397 F'.ao Pl<JAP
| | P 14870 of the Federal Register, April 6, 1983, is cited as justification. |
| | This change is administrative in that it changes the technical specification to achieve consistency with plant design. The plant has been modified within the design margin and the technical specifications would be in error were these changes not made. |
| | 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 50.91, the State of Washington has been provided a copy of this letter. |
| | Should you have any questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing. |
| | Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/tmh Attachments cc: JO Bradfute - NRC WS Chin - BPA C Eschels - EFSEC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCPSR AD Toth - NRC Site |
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| W.R.Butler Page Two June 18, 1985 REQUEST FOR EMERGENCY TECH.SPEC.CHANGE TO TECH.SPEC.3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES need for plant technical specifications to conform with actual plant configuration prior to startup, the Supply System is requesting the attached changes be processed on an emergency basis and the changes submitted in the referenced letter be approved through the normal pro-cess contemplated by Section 50.91.Accordingly, the Supply System hereby requests an emergency change be granted in accordance with 10 CFR Parts 50.91(a)(5) and 2.106 to support WNP-2 starting up on June 21, 1985.Again, this request is being sought promptly after the need for the technical specification modification was identified and the Supply System has not created this emergency to take advantage of Section 50.91(a)(5).
| | STATE OF WASHINGTON ) |
| It appears in the judgment of the Supply System that startup will be delayed unless the requested amendment is granted by June 21, 1985.It should be noted that the potential for missing the June 21 startup date exists.This potential has been discussed with members of your staff and as soon as a definite change is realized your staff will be informed.The fuses listed, in the proposed Table 3.8.4.2-1 (attached) have been changed to reflect design changes made to plant equipment.
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| The fuses have been's'ized'to ensure service to the associated equipment yet still be within'the design margin of the containment penetration assembly.As designs to electrical loads within containment are revised to support plant modifica-tions these fuses will be changed, however at all times within the control of the WNP-2 design process, to ensure continued design margin.The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will result from this amendment.
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| This technical specification change has been review'ed and approved by the WNP-2 Plant Operations Committee'and the Supply System Corporate Nuclear Safety Review Board.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 the changes are within the design margin.Previously.
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| evaluated events will remain bounding.Therefore no increases in probability or consequence is conceivable.
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| 2)Create the possibility of a new or different kind of accident than previously evaluated',because no new accident scenarios are credible.All'changes remain within design margin and installed equipment to respond to accidents remains'the same.3)involve a significant.
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| reduction in a margin of safety because the sizing of fuses within the design margin does*not encroach on the overall margin of safety.'
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| W.R.Butler Page Three June 18, 1985 REQUEST FOR EMERGENCY TECH.SPEC.CHANGE TO TECH.SPEC.3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES This change does not involve a significant hazards consideration.
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| Example (i)P 14870 of the Federal Register, April 6, 1983, is cited as justification.
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| This change is administrative in that it changes the technical specification to achieve consistency with plant design.The plant has been modified within the design margin and the technical specifications would be in error were these changes not made.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).
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| In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.Should you have any questions, please contact Mr.P.L.Powell, Manager, WNP-2 Licensing.
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| Very truly yours, G.C.Sorensen, Manager Regulatory Programs PLP/tmh Attachments cc: JO Bradfute-NRC WS Chin-BPA C Eschels-EFSEC JB Martin-NRC RV E Revell-BPA NS Reynolds-BLCPSR AD Toth-NRC Site STATE OF WASHINGTON
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| ))County of Benton)
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| ==Subject:== | | ==Subject:== |
| 5 I, G.C.Sorensen, being',duly | | 5 |
| 'sv>orn, subscribe to and say that I am the Manager, Regulatory Programs 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~8 Jccnra:, 1985.Sore en, Manager Regulatory Programs On this day personally appeared before me G.C.SORENSEN 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~l day of 5'1985.Notary Pu sc nd for t e State of Washington Residing at | | County of Benton ) |
| ~g 1 I J I t g"e I~~~~t'-E+~D c'J\P}} | | I, G. C. Sorensen, being',duly 'sv>orn, subscribe to and say that I am the Manager, Regulatory Programs 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 ~ 8 Jccnra:, 1985 |
| | . Sore en, Manager Regulatory Programs On this day personally appeared before me G. C. SORENSEN 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 ~l day of 5' 1985. |
| | Notary Pu sc nd for te State of Washington Residing at |
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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. 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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 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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. 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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
REGULATu INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSIoN NBR:850e200156 Doc.DATE: 85/oe/18 NOTARIZED; YES DOCKET ¹ FACIL:50 "397 BYNAME. NPPSS Nuclear Projectr Uni t 2i Washington Public Powe 05000397 AUTH AUTHOR AFF ILIATION
'SORENSENrG ~ C Washington Public Power Supply System RECIP ~ NAME>> RECIPIENT AFFILIATION BUTLERrN ~ RE Licensing Branch 2 SUBJECT; Application for amend to License NPF 2irrequesting emergency Tech Specs change to reflect installation of larger fuses" in primary containment penetration conductor over'current protective devices.Fee paid, DI'STRIBUTION CODE: A001D COPIES RECEI VED: LTR '
ENCL SIZE o TITLE.: OR Submittal: General Distribution NOTES:
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 e e ADM/LFMB 1 0 NRR/DE/MTEB '
ELD/HDS2 1 0 1 NRR/DL D IR 1 1 NRR/DL/ORAB 0 NRR/DL/TSRG 1 1 NR / I/METB 1 1 NRR/DS I/RAB 1 EG L 04 1 RGA5 1 1 EXTERNAL: 24X 1 1 EGS,G BRUSKE,S 1 1" LPDR 03>> 1 1 NRC PDR 02 1 1 Nsic 05 1 1
~TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 June 18, 1985 G02-85-321 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. Butler:
Subject:
NUCLEAR PLANT NO. 2 REQUEST FOR EMERGENCY TECHNICAL SPECIFICATION CHANGE TO TECHNICAL SPECIFICATION 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
Reference:
Letter, G02-85-312, G. C. Sorensen (SS) to W. R. Butler (NRC), Same Subject, dated June 13, 1985 In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an emergency change to the WNP-2 Technical Specifications. Specifically, the Supply System is requesting a change to Technical Specification 3.8.4.2.
Testing for the first eighteen (18} month surveillances required by the WNP-2 Technical Specifications is now in progress. As a result, Surveillance Re-quirement 4.8.4.2.a.3 has prompted a review of the fuses listed in Table 3.8.4.2-1 (revised in Amendment 6 dated October 12, 1984 due to a change request from March 9, 1984}. This review disclosed that as a result of cer tain plant modifications the fuses listed in the Table were replaced with largel fuses. Supply System design change procedures have ensured in all such cases that the new fuse sizing is within the design bases. A safety analysis has been performed on each change to'confirm that the design change remains within the design margin, of the plant.
The Supply System first. became aware of the possible need for the requested technical specification change on June 6, 1985 and immediately commenced the internal review procedure which resulted in the request, submitted in the F'.ao referenced letter. We understand the changes requested by. the referenced letter can not be granted prior to.plant startup. Therefore, in view of the 8506200156 850ji8>97 Pl PDR ADOCK 05000397
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W. R. Butler Page Two June 18, 1985 REQUEST FOR EMERGENCY TECH. SPEC. CHANGE TO TECH. SPEC. 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES need for plant technical specifications to conform with actual plant configuration prior to startup, the Supply System is requesting the attached changes be processed on an emergency basis and the changes submitted in the referenced letter be approved through the normal pro-cess contemplated by Section 50.91. Accordingly, the Supply System hereby requests an emergency change be granted in accordance with 10 CFR Parts 50.91(a)(5) and 2.106 to support WNP-2 starting up on June 21, 1985. Again, this request is being sought promptly after the need for the technical specification modification was identified and the Supply System has not created this emergency to take advantage of Section 50.91(a)(5). It appears in the judgment of the Supply System that startup will be delayed unless the requested amendment is granted by June 21, 1985. It should be noted that the potential for missing the June 21 startup date exists. This potential has been discussed with members of your staff and as soon as a definite change is realized your staff will be informed.
The fuses listed, in the proposed Table 3.8.4.2-1 (attached) have been changed to reflect design changes made to plant equipment. The fuses have been's'ized'to ensure service to the associated equipment yet still be within
'the design margin of the containment penetration assembly. As designs to electrical loads within containment are revised to support plant modifica-tions these fuses will be changed, however at all times within the control of the WNP-2 design process, to ensure continued design margin.
The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will result from this amendment. This technical specification change has been review'ed and approved by the WNP-2 Plant Operations Committee'and the Supply System Corporate Nuclear Safety Review Board.
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 the changes are within the design margin. Previously. evaluated events will remain bounding. Therefore no increases in probability or consequence is conceivable.
- 2) Create the possibility of a new or different kind of accident than previously evaluated',because no new accident scenarios are credible.
All 'changes remain within design margin and installed equipment to respond to accidents remains 'the same.
- 3) involve a significant. reduction in a margin of safety because the sizing of fuses within the design margin does *not encroach on the overall margin of safety. '
W. R. Butler Page Three June 18, 1985 REQUEST FOR EMERGENCY TECH. SPEC. CHANGE TO TECH. SPEC. 3.8.4.2, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES This change does not involve a significant hazards consideration. Example (i)
P 14870 of the Federal Register, April 6, 1983, is cited as justification.
This change is administrative in that it changes the technical specification to achieve consistency with plant design. The plant has been modified within the design margin and the technical specifications would be in error were these changes not made.
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 50.91, the State of Washington has been provided a copy of this letter.
Should you have any questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.
Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/tmh Attachments cc: JO Bradfute - NRC WS Chin - BPA C Eschels - EFSEC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCPSR AD Toth - NRC Site
STATE OF WASHINGTON )
Subject:
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County of Benton )
I, G. C. Sorensen, being',duly 'sv>orn, subscribe to and say that I am the Manager, Regulatory Programs 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 ~ 8 Jccnra:, 1985
. Sore en, Manager Regulatory Programs On this day personally appeared before me G. C. SORENSEN 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 ~l day of 5' 1985.
Notary Pu sc nd for te State of Washington Residing at
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