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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] |
Text
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST FIRE PROTECTION Revision 1, dated November 21, 1985, to the entire February 5, 1985 Inspection and Testing of Fire Protection Devices and Assemblies Change Request and to the Fire Protection portion of the November 11, 1984 Change Request, rca5i:12b0419 , . \ PDR
.. c* p IC0785-0256-NL04 Control Room Habitability November 21, 1985 6 Pages CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: I. Changes The attached revision of proposed changes to the Palisades Technical Specifications includes clarification of, deletions from and additions to the existing Technical Specifications 3.22 and 4.17. This revision supersedes the proposed changes to Technical Specifications 3.22 and 4.17 submitted on November 19, 1984 and February 5, 1985. These revisions of previously proposed changes to the Technical Specifications are the result of (1) a July 1, 1985 telephone conversation with an NRC staff representative, during which recommendations to modify the proposed fire protection Technical Specifications to bring them into closer alignment with the Standard Technical Specifications were made; (2) fire protection modifications and clarifications resulting from compliance with 10CFR50.48 and Appendix R; and, (3) the addition of fire protection equipment as part of the Control Room/Technical Support Center HVAC system modifications and .the associated Auxiliary Building Addition.
Proposed changes are identified by a line in the right-hand margin. The following are brief descriptions of the proposed changes. Specification
- 3. 22 .1.1. -Clarifies statement to read "The minimum fire detection instrumentation
- ," deletes the reporting requirements, increases the time interval before hourly fire watch patrols are initiated when a fire.detector becomes inoperable; and, includes specific action when detectors inside containment become inoperable.
Specification 3.22, Table 3.22.1 -The first item has been clarified to include a better description of the zone affected by the detector.
Specification 3.22, Table 3.22.1 -The second item has been expanded to show fire protection zones along with appropriate number and type of detection instrumentation in that zone. (New items No. 2-5, Old Item 2) Specification 3.22, Table 3.22.1 -Clarified item in table pertaining to fire protection zone "Turbine Building 590 1 Col H-9" To read: "Southwest Cable penetration, Col H-10" (New Item 9, Old item 5) Specification 3.22, Table 3.22.1 -New detectors have been added under items 5, 6, 10, 11, 32, 33, 34 and 35. The. numbering for Table 3.22.1 has.been revised accordingly.
TSOP0785-0256-NL04 Palisades Plant 2 TSCR -Fire Protection System Specification 3.22.2.1 -Statement clarified to specify the diesel fire pump south of the fire barrier as this is the only fire pump that would remain operable in the event of a fire in Room 136 which causes the other fire pumps and Service Water Pumps to become inoperable.
The Action statement has been modified to conform to Standard Technical Specifications and superfluous reporting requirements have been deleted. The Basis for LCO 3.22.2 has been revised to reflect the proposed requirements.
Specification 3.22.3.1 -Item "a'; has been clarified to state "Cable Spreading Room/Switchgear Room IC." New items "h-", "i", and "j" have been added to address sprinkler systems in the North Cable Penetration Room, the Electrical Equipment Room, and the Charging Pump Room. The ACTION statement has been re-stated to conform with Standard Technical Specifications.
- Specification 3.22.4.1 -Outside Fire Hose Station #5 was added as item "j". Previously existing items."j
and "k" have been given new alpha characters to maintain consistency of hose station listings.
The change in the alpha characters has also been reflected in items "1" and "2" of .the ACTION statement, and the ACTION statement has been modified to conform with Standard Technical Specifications.
- Specification 3.22.5 -This specification was totally revised to include all fire rated assemblies
- and fire protection assemblies along with penetration sealing devices. Specification 4.17.4.1 and 4.17.4.2 -Corrects alpha characters for consistency with Specification 3.22.4.1 and changes hose testing pressure test criteria to conform with Standard Technical Specifications.
Specification 4.17.5.1 and 4.17.5.2 -New surveillance requirements are outlined reflecting the proposed revision to Specification 3.22.5. II. Discussion These proposed Technical Specifications changes are requested in order to reflect the existing fire protection practices and equipment at the Palisades Plant. The specific reasons for each proposed change are discussed below. Since the charging pumps are important to safe shutdown, the Fire Suppression System for the Charging Pump Rooms must be operable.
Consequently, this system was added to Specification 3.22.3 and to Specification 3.22, Table 3.22.1. According to 10CFR50.48, which endorses Branch Technical Position 9.5-1, Specifications 3.22.5 and 4.17 were revised to include all fire related assemblies.
This requirement was combined with the necessity for including fire protection assemblies (radiant heat shields) in the Technical Specifications.
These additions .result in an LCO that more accurately reflects the fire protection surveillance programs presently in effect at Palisades.
TSOP0785-0256-NL04 Palisades Plant 3 TSCR -Fire Protection System Changes to the 3.22.1.1 added an ACTION statement in the event of inoperable fire detectors inside containment.
Reporting requirements in 3.22.1.1, 3.22.2.1, and 3.22.3.1 were eliminated in view of the fact* that reporting requirements are now delineated in 10CFR50.72 and 50.73. The diesel fire pump south of the fire barrier in room 136 (the traveling Screen Room) is essential for safe shutdown in the event of a postulated fire wherein all other equipment in that room is rendered inoperable and offsite power is lost. Specification 3.22.2 has been modified in consideration of that condition.
The_ test criteria of Specifications 4.17.4.1.c.(2) and 4.17.4.2.c.(2) were increased to require testing at 50 psi above the maximum fire main operating pressure.
This change aligns the requirement with the Standard Technical Specifications requirement.
The remaining changes in fire detection instrumentation, fire sprinkler systems and fire hose stations result from the physical additions to the Auxiliary Building which were completed to facilitate the Control Room Emergency Air Cleanup System. Analysis*
of No Significant Hazards Consideration Power Company (CPC) presents this evaluation of the hazards considerations involved with the proposed amendment, focusing on the three conditions set forth in 10CFR50.92(c) as quoted below: "The Commission may make a final determination, pursuant to the procedures in §50.91, that a proposed amendment to an operating license for a facility licensed under §50.2l(b) or §50.22 or for a testing facility involves no hazards considerations, if it finds that operation of the facility in accordance with the proposed amendment would not: 1. Involve a significant increase in the probability.or consequences of an aciident previously evaluated; or 2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3. Involve a significant reduction in a margin of safety." .CPC concludes that the activities associated with this amendment request do not meet any of the significant hazards consideration standards of 10CFR50.92(c);
and, accordingly, a no significant hazards consideration finding is justified.
In support of this determination, the following analysis is provided.
TSOP0785-0256-NL04
--Palisades Plant 4 TSCR -Fire Protection System Analysis (1). Involve a significant increase in the probability or consequences of an accident previously evaluated.
Changes to Table 3.22.1 and Specifications 3.22.1.1 Action Item 2, 3.22.2, 3.22.3, 3.22.S, 4.17.4.1, 4.17.4.2, 4.17.S.l and 4.17.S.2 add fire suppression equipment and/or fire rated assemblies or require more fire suppression equipment and fire rated assemblies to be operable, add an LCO, increase surveillance criteria, or delete redundant reporting procedures.
For example: a. Specification 3.22.1.1 ACTION statement
- 2 requires that the zone, or the zone above it inside containment, that contains less than the required number of operable listed in Table 3.22.1 be observed on an hourly basis with the TV camera. Previously, no action for an inoperable detector inside containment was specified.
- b. Specification 3.22.3.1 adds sprinkler systems to the list of sprinkler systems which are required to be operable.
- c. Specification 4.17.4.1.c.2 requires testing at SO psi greater than maximum fire main pressure instead of so psi greater than maximum pressure at the fire hose station. d. Deleting the requirement to file a Special Report, as required by existing Specification 3.22.1.1 ACTION statement
- 4, when the number of operable fire detectors is less than that number listed in Table 3.22.1 does not increase the probability or consequences of an accident previously evaluated as reports of this nature are now made in accordance with 10CFR2S0.72 and lOCFRS0.73.
The addition *of fire detectors, fire rated assemblies, fire suppression equipment and systems, increasing the observation of* areas, increasing the test pressure of hose stations, and deleting a redundant reporting requirement*does not involve a significant increase in the probability or consequences of an accident previously evaluated.
With the possible exception of the deletion of the duplicate reporting requirements, all of the above listed changes decrease the.probability of or consequences of accidents previously evaluated.
The change to Specification 3.22.1.1, ACTION statement
- 1, is the only other change which may increase the probability or consequences of a previously evaluated accident.
By increasing the allowed time to initiate fire patrols, once an inoperable detector is identified, to 2S hours, instead of the existing one hour requirement, this Technical Specification is aligned with the Standard Technical Specification.
The probability of a fire occurring in any given twenty-five hour period is considered extremely low. Furthermore, it is reasonable to expect increased TSOP078S-02S6-NL04 Palisades Plant 5 TSCR -Fire Protection System operator attention to an area containing one or more inoperable fire detectors during the 25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period before an hourly fire patrol is initiated.
Therefore, CPC has concluded that the proposed change to Specification 3.22.I.I, ACTION statement
- I does not significantly
- increase the probability or consequences of an accident previously
- (2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
This proposed change, with the exception of ACTION statement
- I of Specification 3.22.I.I, only to the amount of fire protection equipment, increases surveillance criteria, or deletes redundant reporting requirements.
All additional equipment is of proven design and does not increase the possibility of a new or different kind of The proposed changes increase the level of fire protection and would not create the possibility of a new or different kind of accident from any accident previously analyzed.
The proposed change to Specification 3.22.I.I, does increase the time which may elapse between the time a required fire -detector becomes inoperable and the time, if the detector is not restored to operable status, an hourly fire.watch must be initiated; The increased allowed time from one hour to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />; aligns* .the Palisades Technical Specifications with the Standard Technical Specifications and does not create the possibility of a 6r different kind of accident from any accident previously evaluated.
Fires are the type of accident under consideration and the possibility of fires has been evaluated in all the areas of the plant. (3) Involve a significant reduction in the margin of safety. . . This proposed change with the exception of ACTION statement II I of Specification adds to the margin of safety by increasing the amount of fire protection equipment to which Technical Specification requirements are applied, upgrades surveillance criteria, or deletes redundant reporting requirements.
For example: Deleting the requirement to file a Special Report, as required by the existing Specification 3.22.3 after a sprinkler system is inoperable for more than I4 days, does not involve a significant reduction in the margin of safety. Adequate reporting requirements exist in IOCFR50.72 and 50. 73.
- The proposed change to Technical Specification 3.22.I.I ACTION statement III does increase to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> the allowable time between the time a detector becomes inoperable and the time at which an hourly fire patrol must be initiated.
Existing Technical Specifications state the hourly fire watch patrol must be initiated within one hour when the number of operable detectors in a zone is less than that number required by Table 3.22.I. In most cases, referring to Table 3.22.I, if a zone has multiple detectors, more than one detector must be inoperable before a fire watch patrol is TSOP0785-0256-NL04 Palisades Plant 6 TSCR -Fire Protection System required.
Plant administrative controls require the fire watch patrol to be initiated within one hour after any fire detector becomes inoperable, resulting in additional attention paid to a zone with an inoperable detector.
This proposed change may reduce the margin of safety when compared to the existing Technical Specification, however, the amount of reduction is considered to be insignificant.
None of the fire detectors required to be operable by Table 3.22.1 actuate fire suppression systems. III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question.
However, we have determined that this change does not involve a significant hazards consideration.
This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License. CONSUMERS POWER COMPANY President Nuclear Operations Sworn and subscribed to before me this 21st day of November 1985. Helen I Dempski, Notary Jackson County, Michigan . My commission expires October 12, 1987. " ,*'. TSOP0785-0256-NL04