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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
. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _
C1 WASHINGTON PUBUC POWER SUPPLY SYSTEM P.o. Box %8
- Richland, Washington 99352-0 % 8 * (509)372-5000 Docket No. 50-397 Decemkr 8, N GO2-95-265 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TO TECIINICAL SPECIFICATIONS
Reference:
Ietter GO2-95-261, dated November 23, 1995, JV Parrish (SS) to NRC,
" Schedule for Implementing the Improved Technical Specifications (ITS)
Program" In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications and Operating License. This proposed amendment revises the WNP-2 Technic 21 Specifications to be consistent with NUREG-1434, " Standard Technical Specification General Electric Plants, SWR 6." The conversion to the improved Technical Specifications (ITS) includes deviations from the NUREG and changes to the current WNP-2 Technical Specifications. Because of the size of this submittal, the Project Manager, JW Clifford, will provide distribution of the document within the NRC.
There are three open items relative to this submittal. The first iten involves proposed Specification 3.3.3.1, " Post Accident Monitoring Instrumentation." The Supply System License Condition 2.C.(16), Attachment 2, item 3.(b) requires the post accident monitoring neutron flux instrumentation be classified as Category 1, Type A as described in Regulatory Guide 1.97. A request to amend the License Condition is being prepared for submittal. If the change to the License Condition is not approved, the ITS submittal will be revised. The second issue concerns the submittal and approval of the methodo%gy usa.d to develop the curves for the Pressure Temperature Limits Report (PTLR). The WNP-2 ITS was developed predicated on approval of the PTLR methodology. If not approved, the ITS submittal will be revised to include the requirements that have been proposed for relocation to the PTLR. The third issue concerns Cycle 12 specific information. A revision to the ITS submittal will be made upon completion of the Cycle 12 specific analysis. This is only expected to impact the Bases and Chapter 5.0.
Current License Condition 2.C.(18) requires the installation of an ADS manual inhibit switch, incorporation of the use of the switch into the Plant Emergency Procedure, and a Technical Specification requirement _for the onerability of the inhibit switch. The Technical Specificat:on 95121204o1 951200 PDR ADOCK 05000397 /) .
PDR P -
[) C.
&LW FA A 120:5a %oI de l0k f1 $
Page 2 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS requirement for the inhibit switch is proposed to be relocated from the Technical Specifications, since the inhibit switch does not meet the Final Po' icy Statement criteria for inclusion in I Technical Specifications. Justification for this relocation is provided in this submittal.
Therefore, it is requested that License Condition 2.C.(18) be modified to delete the ADS inhibit switch requirements related to Technical Specifications.
The implementation of the ITS will require the performance of a number of new surveillance requirements. The Supply System intends to treat these new requirements as being " met" at the time ofimplementation of the ITS, with the first performance scheduled to be completed within the required frequency from the implementation date. Several other surveillance frequencies will be extended from 18 to 24 months. Upon implementation of the !TS, the due date will be changed to reflect the new required frequency based on the last performance date. Any revisions to the FSAR necessitated by the conversion to the ITS will be submitted in accorda,ce with the requirements of 10 CFR 50.71(e).
The following six attachments are included in this submittal:
- 1. Application of the Selection Criteria (Vol 1)
- 2. WNP-2 Technical Specifications (Vol 2)
- 3. Technical Specificat an Bases (Vols 3 and 4)
- 4. Comparison to Current Technical Specifications (Vols 5 and 6)
- 5. No Significant Hazards Considerations (Vol 7)
- 6. Deviations from NUREG-1434 (Vols 8, 9 and 10)
Enclosure 1 to this letter provides a description of each attachment and a brief discussion of the preparation of the submittal.
As discussed in a meeting held with the staff on November 29,1995, there are some changes proposed that might be considered beyond the scope of conversion to ITS. Enclosure 2 to this letter provides a summary of these proposed changes.
The evaluations contained in Attachment 5, described above, conclude that the proposed changes to the WNP-2 Technical Specifications do not involve a significant hazards consideration. In addition, as discussed herein, the proposed changes do not create a potential for a significant change in the types or a significant increase in the amount of any effluent that may be released offsite, nor do the changes involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the changes meet the eligibility criteria for a categorical exclusion as set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b),
an environmental assessment of the changes is not required.
This Technical Specification amendment request has been approved by the Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. In accordance with 10 CFR 50.91, the State of Washington has also been provided a copy of this letter.
L
Page 3 REQUEST FOR AMENDMENT TO TECIINICAL SPECIFICATIONS Implementation of the proposed amendment is tentatively scheduled for the fourth quarter of 1996. This date is based on the training schedules for both licensed and nonlicensed personnel, the timing of the implementation with respect to the refueling outage, the licensed operator examination schedule, and the time required for procedure revisions and the development of the new programs. The Supply System will inform the NRC when the ITS implementation actions are complete. The implementation date is also predicated on NRC issuance of an SER in June ,
1996.
l The Supply System requests a meeting at your earliest convenience to discuss a review schedule !
and the content of the submittal package.
Should you have any questions or desire additionalinformation regarding this matter, plea call me or D.A. Swank at (509) 377-4563.
Sincerely,
'.. A ,
.V. Parrish (Mail Drop 1023)
Vice President, Nuclear Operations ,
MGE/Im Attachments
- 1. Application of the Selection Criteria (Vol 1)
- 2. WNP-2 Technical Specifications (Vol 2)
- 3. Technical Specifications Bases (Vol 3 and 4)
- 4. Comparison to Current Technical Specifications (Vol 5 and 6) ,
- 5. No Significant Hazards Considerations (Vol 7)
- 6. Deviations from NUREG-1434 (Vol 8,9 ano 10) '
Enclosures
- 1. WNP-2 Improved Technical Specification Submittal Synopsis
- 2. Changes to WNP-2 Current Technical Specification 1
cc: LI Callan - NRC RIV l KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office !
NS Reynolds - Winston & Strawn (w/o attachments)
JW Clifford - NRC DL Williams - BPA/399 (w/o attachmens)
NRC Sr. Resident Inspector - 927N i FS Adair - EFSEC l l
STATE OF WASHINGTON )
Subject:
Request for Amendment to
) Technical Specifications COUNTY OF BENTON )
i I. J. V. PARRISH, being duly sworn, subscribe to and say that I am the Vice President, Nuclear ;'
Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have the 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 December 8,1995 !,
. I t
i J. V. 'sh, Vice Prt.; dent Nu Operations i
On this date personally appeared before me J. V. PARRISH, to me known to be the individual ;
who executed the foregoing instrument, and acknowledged that he signed the same as his free l' act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this day of Offfanhf/L 1995.
i Antx $, '1 e)
Notary Public in and for the STATE OF WASHINGTON
( .
1
,~.
Residing at bmavhMfh,WO I i l'
My Commission Expires 9f9, l
EN'LOSURE1 WNP-2 IMPROVED TECHNICAL SPECIFICATION SUBMITTAL SYNOPSIS The Supply System Improved Technical Specifications (ITS) submittal consists of six documents contained in ten volumes. ' A brief description of each docunnent is provided below:
- ATTACHMENT 1 - APPLICATION OF THE SELECTION CRITERIA (Volume 1)
This attachment provides a discussion of the application of the NRC Final Policy Statement criteria to the current WNP-2 Technical Specifications (CTS). It includes a matrix that cross references the following documents:
a) WNP-2 current Technical Specifications b) Proposed ITS, where applicable c) Applicable selection criteria.
Several Technical Specification requirements did not meet the selection criteria and have not been retained in the proposed ITS. This attachment includes an explanation of the application of the criteria for these relocated requirements.
ATTACHMENT 2 - WNP-2 TECHNICAL SPECIFICATIONS (Volume 2)
This attachment is the proposed WNP-2 ITS in the NUREG-1434 format. Relocated specifications are not included in the ITS volume.
ATTACHMENT 3 - WNP-2 ITS BASES (Volumes 3 and 4)
This attachment, the proposed WNP-2 Bases for the ITS, contains the basis for each proposed specification.
ATTACHMENT 4 - COMPARISON DOCUMENT (Volumes 5 and 6)
This attachment is a copy of the CTS annotated to show the disposition of the existing requirements into the ITS submittal. The CTS pages are presented in the order of the ITS requirements. For example, ITS 3.5.1 contains pages from applicable CTS sections of 3/4.5.1 and 3.3. The annotated CTS pages are followed by the discussion of each of the proposed changes.
The CTS pages reflect Amendments issued as of November 9,1995 (correction to Amendment 137). No outstanding Technical Specification amendment requests are reflected in the CTS pages.
The ITS number is noted on the top rtht corner of each CTS page, indicating the ITS location of the CTS requirements. Items on the CTS page that are located in a different ITF location have the appropriate location noted adjacent to the item. When the ITS requirement differs from the CTS requirement, the CTS being revised is annotated with an alpha-numeric designator.
This designator relates to the appropriate Discussion of Change (DOC). Each DOC provides
Enclosure 1 Page 2 of 3 a justification for the proposed change. As discessed, the DOC associated with each ITS section immediately follows the marked up CTS pages. The alpha-numeric designator also relates the proposed change to the applicable no significant hazards consideration (NSHC) evaluation contained in Volume 7.
The marked CTS pages and the applicable DOCS for each Section in the ITS are followed by a page detailing which CTS pages have not been included because they were pages of the CTS Bases or pages " intentionally left blank" in CTS.
When a CTS page contains requirements that are located in more than one ITS section, the CTS page is repeated in each of the applicable ITS sections. The repeated page is annotated with alpha-numeric designators applicable only to the ITS section in which it is contained.
The alpha-numeric designator is based on the category of the change and a sequential number within that category. The changes to the CTS are categorized as follows:
A ADMINISTRATIVE - associated with restructuring, interpretation, or rearranging of requirements, and other changes that do not revise existing requirements.
R RELOCATED - specific LCO requirements that do not satisfy the NRC Final Policy Statement selection criteria, TECHNICAL CHANGES M MORE RESTRICTIVE - proposed changes to the CTS that result in added restrictions or eliminated flexibility.
L LESS RESTRICTIVE - proposed changes to the CTS that result in relaxed or eliminated requirements or new flexibility. The LESS RESTRICTIVE TECHNICAL CHANGES have been categorized as specific or generic. Each less restrictive specific change has a specific NSHC. The less restrictive generic changes have been divided into six groups; each group has a single NSHC. The generic groups are. l l
LA relocation of details from the CTS to a licensee controlled document; LB extension of allowed outage times or surveillance test intervals based on NRC approved topical reports; LC elimination of alarm or indication only instrumentation that does not meet the NRC Final Policy Statement selection criteria; LD increasing the surveillance interval of 'R' from eighteen months to twenty four months, for surveillances other than CHANNEL CALIBR.ATIONS; LE increasing the surveillance interval of 'R' from eighteen months to twenty four months for CHANNEL CALIBRATIONS; and
i Enclosure 1 i
Page 3 of 3 LF. changes in instrumentation Allowable Values to be consistent with current setpoint calculations. i A'ITACHMENT 5 - NO SIGNIFICANT HAZARDS CONSIDERATION (Volume 7) )
This attachment, the 10CFR50.92 NSHCs for the proposed changes, shows that the changes do not constitute significant hazard considerations. As described for the DOC, the NSHC evaluations are categorized as Administrative, Relocated, More Restrictive, less Restrictive -
Generic, and less Restrictive - Specific and are identified by an alpha-numeric designator relating the marked up CTS and the DOC to the applicable NSHC evaluation. )
I A'ITACHMENT 6 - DEVIATIONS FROM NUREG-1434 (Volumes 8, 9, and 10) )
This attachment contains a copy of NUREG-1434 annotated to indicate deviations taken in the development of the WNP-2 ITS. The justifications for the deviations follow the applicable Chapter or Section of the NUREG. ' The deviations are based upon Revision 1 of the NUREG as modified by generic changes submitted prior to November 30,1995.
The deviations are identified as generic or plant specific. Ge eric changes to the NUREG are labeled with the applicable generic change package number. Plant specific deviations are indicated by small " bubbles," numbered sequentially.
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ENCLOSURE 2 CHANGES TO WNP-2 CURRENT TECHNICAL SPECIFICATIONS !
The Supply System has also taken the opportunity to propose changes outside the scope of the i Improved Technical Specifications (ITS) conversion process. These changes are included in this submittal in lieu of submitting separate amendment requests for each of these changes. These i changes are as follows:
l The RHR Shutdown Cooling Suction Flow Rate - High isolation instrumentation has been .
deleted from the Technical Specifications since other isolation instrumentation retained i in the ITS provides adequate protection should a RHR line break occur. (ITS: 3.3.6.1, -j comment L.11)
The Control Room Emergency Filtration System Actions have been modified to provide ,
more appropriate Actions when one or more main control room ventilation radiation '
monitors (which provide only an alarn; function) are inoperable. (ITS: 3.3.7.1, i comments M.4, L.2, and L.3) l The required number of Ioss of Voltage channels for each division and the number of l Degraded Voltage channels for Divisions 1 and 2 have been reduced by one. (ITS: l 3.3.8.1, comment L.1) -l I
The Allowed Outage Times for one low pressure ECCS subsystem, two low pressure j ECCS subsystems, HPCS concurrent with one LPCI subsystem, one ADS valve ;
concurrent with one low pressure ECCS subsystem, one SW subsystem, one diesel l generator, and two diesel generators out of service have been extended consistent with !
a GE analysis that is based upon WNP-2 plant-specific probabilistic safety assessment !
data. (ITS: 3.5.1, comment L.3; ITS: 3.7.1, comment L.1; and ITS: 3.8.1, comment j L.3) l The Primary Containment Internal Pressure LCO has been deleted since the upper limit l' cannot be exceeded without resulting in a reactor scram and the lower limit cannot be exceeded due to operation of the reactor building-to suppression chamber and suppression chamber-to drywell vacuum breakers. (CTS: 3/4.6.1.6, comment L.1)
In addition, the following changes have been proposed to match the current Technical '
Specifications requirements with the current setpoint calculations or analysis assumptions:
Numerous instrumentation Allowable Values have been modified (both more and less restrictive with respect to the current Allowable Value). (ITS: 3.3.1.1,3.3.4.2,3.3.5.1, 3.3.5.2,3.3.6.1,3.3 6.2, 3.3.8.1, and 3.3.8.2, comment LF.1; ITS: 3.3.4.2, comment M.2, ITS: 3.3.5.1, comments M.6 and M.7; ITS: 3.3.6.1, comment M.6; ITS: 3.3.8.1, comment M.4; and ITS: 3.3.8.2, comments M.2 and M.3) 1 The number of required ADS valves has been reduced by one. (ITS: 3.5.1, comment L.1)
The suppression pool cooling flow rate has been reduced from 7450 gpm to 7100 gpm. l (ITS: 3.6.2.3, commen; L.2)
Enclosure 2 Page 2 of 2 The diesel generator start time has been increased from 10 seconds to 15 seconds. (ITS:
3.8.1, comment L.20) 1 Current License Condition 2.C.(18) requires the installation of an ADS manual inhibit switch, incorporation into the Plant Emergency Procedures the usage of the inhibit switch, and Technical i Specifications requirements for the inhibit switch. This Condition was met prior to startup from i the first refueling outage as required. The Technical Specification requirements for the inhibit ]
switch are proposed to be relocated from the Technical Specifications, since the inhibit switch :
does not meet the Final Policy Statement criteria for being included in Technical Specifications. l Justification for this change is provided in the submittal. Therefore, it is requested that License Condition 2.C.(18) be modified to delete the ADS inhibit switch requirements related to ;
Technical Specifications. !
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