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MONTHYEARML20206A2321987-03-26026 March 1987 Proposed Tech Specs,Reflecting Correction to Basis of Tech Specs for Containment Cooling Project stage: Other ML20205T6951987-03-26026 March 1987 Application for Amend to License DPR-40,correcting Basis of Tech Specs for Containment Cooling Project stage: Request ML20205T6821987-03-26026 March 1987 Forwards Application for Amend to License DPR-40,correcting Tech Specs Re Containment Cooling.Fee Paid Project stage: Request ML20215A6381987-06-10010 June 1987 Safety Evaluation Re Bases to Tech Spec 2.4, Containment Cooling. Proposed Changes to Bases for Section 2.4 Serves to Editorially Change Error,Make Phrases & Statements More Accurate & Reflect Current Terminology Project stage: Approval ML20215A6281987-06-10010 June 1987 Forwards Safety Evaluation Re Bases to Tech Spec 2.4, Containment Cooling. Proposed Changes Would Correct Bases of Amount of Heat That Can Be Removed by Three Component Cooling Water HXs Project stage: Approval 1987-03-26
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
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ATTACHMENT A i
2.0 LIMITING CONDITIONS FOR OPERATION 2.h Containment Cooling (Continued) component cooling heat exchangers and shutdown heat exchangers. A full-capacity diesel-generator is connected to each of the two engineered safeguards 4.16-kV buses. Three engineered safeguards 480-Volt double-ended load centers are provided; of the six transformers, three are connected to each of the two 4.16-kV buses. Two load centers are operated as two-bus-section units; the third is provided with a center bus manually transferable to either associated end section. The center
- bus section supplies HPSI Pump SI-20, CS Pump SI-30 and Charging Pump CH-lc any of which can thus be supplied from either h.16-kV bus if required.- Threecomponentcoolingheatexchangegshavesufficient
- to removelh20lx 10 BTU /hr following a capacity ( ith .-accident.
,1; r;;;$ I)'The containment sprays initially take g loss-of-coolant i coolant from the safety injection and refueling water (SIRW) t l Before this supply of water is exhausted (at least 2h minutes)g.
l the spray system is transferred to the recirculation mode and the pumps take suction from the containment sump. One shutdown cooling heat ex-changer is sufficient to satisfy the spray s
+ the long-term containment cooling period.(3)ystem requirements In addition, in the during un-likely event of the component cooling water supply being lost, rav
- vater can be utilized for dire cooling of the shutdown heat exchangers
! and containment cooling coils, f The containment spray system is redundant with the containment air recirculation, e ng and iodine removal system for the containment cooling function. The spray system is sized such that two of the j three spray pumps would limit the containment pressure to below the i air coolers design value following or the cooling capacity of a DBA the safety without taking credit injection system.t for f
tpi Similarly,
- two cooling and filtering units or one cooling and filtering unit and both pressurecooling underunits the same havecondi',
the capability ions as twoof limiting spray pumps. the(e7ntainment
- The redundant cooling equipment provided to limit the containment pressure following a DBA is divided between the independent power
- supply systems. The rav vater and component cooling water pumps are j similarly distributed on the h.16-kV and 480 Volt buses to serve the above cooling groups. Each cooling group has a design capacity equal to that required to restrict the containment pressure to below the design value. In the event of a DBA, loss of normal power sources and
- failure of one diesel-generator to operate, better than one full group .
vould be connected to the available diesel-generator, thus providing more than ample reserve. Any one unit removed from a given bua does not restrict the groups.which can be connected t_o one diesel-generator .
from fulfilling their design function The removal;of-two units-from -
. buses which can be connected to one dusel-generator could limit the capability of the associated cooling groups; therefore, to ensure i availability of the power supply to the redundant equipment in the l event of loss of normal power sources, the diesel-generator serving l this redundant equipment is started to demonstrate operability. During ;
8704070454 870326 1 PDR ADOCK 05000285 i P PDR
)
l 1
, 2-26 l
- s. ,
l 2.0 LIMITING CONDITIONS FOR OPERATION 2.h Containment Cooling (Continued) normal power operation either two air coolinit and filtering units or two air cooling units and one air cooling an' filtering unit are in
~
operationto(gqmoveheatlostfrompipingancequipmentwithinthe containment. / In addition, if during th~e -; Jst-accident phase the -
component cooling water supply is lost, containment cooling could be
~
maintained until repairs are effected. The component cooling system pumpsandheatexchanger,thespraypumpsandteautjovnheatex-changers are located in the auxiliary building. 9) 10 'he ~ pen:nt
- ling cycter equiprrnt is seceerible for repair e Ner 2 lece-ef--
- - ' " - - ' ' - The rav vater pumps are located in the intake structure.k5)nt.
References usut (1) -F6AR, Section 9 7 5 (2) Section 6.2.3 1 usart (3) FSAR, Section 6.2.3.h as ut.
(h) FSAR, Section 9.8.2 UCA12_
(5) -FSAR, Section 6.h.5
<JAAn (6) -FSAR, Section 6.3.5 4 d2AP (7) FSAR, Section 14.16.5 (8) F , Section 9 10.2.3 (9) M Section 9.7 (10) N , Section 6.3 dSM (11) F6AR, Section 9.8 2-27
, . ATTACHMENT B Discussion, Justification, and No Significant Hazards Considerations The Safety Systems Outage Modification Inspection (SS0MI) Team conducted inspections in late 1985 and early 1986. Among findings of the team was an apparent typographical error in the basis to Technical Specification 2.4.
The basis of the Technical Specification has remained in its current state since original issue of the Operating License. Further, the statement being corrected was not included in its current form at the time when the Technical Specifica-tions were a part of the FSAR.
The statement to be changed currently reads, "Three component cooling water heat exchangers have sufficient capacity (with ample reserve) to remove 420 X 106 BTU /hr following a loss-of-coolant accident." The statement has been revised to read, "Three component cooling water heat exchangers have sufficient capacity to remove 402 X 106 BTV/hr following a loss-of-coolant accident." USAR(Updated Safety Analysis Report) section 9.7.5 (consistent with the FSAR) specifies the accident capacity of a component water heat exchanger as 134 X 106 BTV/hr, resulting in a total of 402 X 106 BTV/hr for three CCW heat exchangers. The note regarding " ample reserve" has been removed. " Ample" is a subjective term which l is better served by reference to the Updated Safety Analysis Report. Information in the USAR is definitive and allows for a determination of the Technical Specification basis, whereas "with ample capacity" does not.
In addition, the statement, "The component cooling water system equipment is accessible for the repair after a loss-of-coolant accident," has been removed from the basis. Radiation studies done after the incident at Three Mile Island indi-cate that this statement may be somewhat misleading. Further, the basis to Technical Specifications should be founded in fact rather than sweeping general-izations. Because of this, and the fact that removing the statement has no impact on the specification, OPPD has chosen to eliminate it.
Finally, the references to "FSAR" in Section 2.4 have been reworded to "USAR".
This change is simply in keeping with the current terminology. In 1982, the first annual update of the FSAR was submitted pursuant to 10 CFR 50.71(e). As various portions of the Technical Specifications are amended for other reasons, the references are updated from "FSAR" to "USAR".
No Significant Hazards Considerations Pursuant to 10 CFR 50.36(a), the licensee is required to have Technical Specifi-cations. Included is the requirement for a basis to each Technical Specification.
Although required by regulation, the bases are specifically not a part of the
- - - - , , - - y -
,.,e l Technical Specifications. [ Reference 10 CFR 50.36(a)] As such, significant hazards considerations pursuant to 10 CFR 50.92 are not expressly required.
However, to alleviate any potential for confusion on this matter, the following is presented.
Will the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
No. The physical heat removal capacity of the component cooling water heat exchangers has not changed. The value appearing in the Technical Specifications is,inalllikelihood,typographicalinnagure. The actual capacity always has been 402 X 106 BTU /hr, based upon 134 X 10 BTU /hr for each of 3 component cooling water heat exchangers. This is still sufficient capacity for heat removal during normal and accident operational modes. The removal of vague statements from the basis is intended to eliminate confusion. There are no physical changes being made; nor are any operational limits being made less restrictive.
Will changes create the possibility of a new or different kind of accident from any accident previously evaluated?
No. This " correction" does not effect the physical characteristics of any existing system. Further, it does not introduce any new equipment or new modes of operating existing equipment. The changes to the basis do not reduce the Limiting Conditions in any way, thus all existing limits remain in effect.
Therefore, as this change does not impact existing equipment or its operation, the potential for a new or different kind of accident is not created.
Will this involve a significant reduction in a margin of safety?
Again, as no equipment or its limiting conditions for operation have been altered, no reduction in any margin of safety is involved.
For the above reasons, the Omaha Public Power District does not believe the proposed change constitutes a significant hazards consideration.