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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] |
Text
_ _ _ _ _ _ . _ ._ _ _ _ _ _ _ _ _ __ _._._._._ _ _ _ _..._ _._
. . l I t 2.0 LIMITING CONDITIONS FOR OPERATION ,
2.7 Electrical Systems (Continued) i
- d. Either one of the 4.16 kV engineered safeguards buses, I A3 or I A4 may ,
be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the operability of the diesel ,
generator associated with the operable bus is demonstrated immediately l and there are no Jnoperable engineered safeguards components associated )
with the operab!c bus.
One of each group of 4160 V/480 V Transformers (T18 3A or 4A), ,
(TIB-3B or 4B), and (TIB-3C or 4C) may be inoperable for up to 81.ours provided there are no inoperable engineered safeguards components which are redundant to components on the inoperable transformer,
- f. One of the 480 V distribution buses connected to bus I A3 or connected to bus lA4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on the inoperable bus. -
- g. Either Group of MCC No.'s (3Al,3B1,3A2,3C1,3C) or (4A1,4A2, 4Cl,4C2) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable sai.' guards colaponents which are redundant to components on the inoperable MCC. MCC 3C1 may be inoperable in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if battery chargers No. I and No. 2 are operable. ;
- h. One of the four 120V a-c instrument buses (A, B, C or D) may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the reactor protect!ve and engineered ;
safeguards systems instrument channels supplied by the remaining three buses are all operable,
- i. Two battery chargers may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided battery charger No.1 (EE-8C) or No. 2 (EE 8D) is operable.
J. Either one of the emergency diesel generaton (DG-1 or DG 2) may be inoperable for up to seven days (total for both) during any month, the(WWisspeinbleTesginesfed 7sfeg6ards][componeiiG provided[j$
isskiated ith~thiioperable diesel generstdWl_f one'dieselfgenerator is inoperable ithij} 8 l hours [(iegasdiessi of Shenit%inopsrableidissej spnerstbrlisl restored;to operability)iEITHERj
_(1) Stsji the other diesel generator i :.:=ted to verify operability, shutdown ;nd ccatrc!: = lcf:in the :::cm;;ic med rad there are ac incpenbic engiacend =ferund: cm;mt: am-ia cd wkh the op;mb!: dic;;l gensator OR !
l l
l l
)
9210200197 921009 PDR ADOCK 05000285 P PDR l
(2); : Ensure the abserice~of?cohimon'canse fforflhidleselitienbrator ,
inoperability,for t!)e other diesel ggnera'srj t
e j
- k. Island buses 1B3A-4A,1H38-4B, and IB3C-4C may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on the inoperable bus (es). '
i
- 1. Either one of the 125V d-c buses No.1 or 2 (Panels EE-8F and EE-8G) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
4
! 2-34 Amendment No. 60,447 1
i
.i
)
1 5
A J
1 2.0 LIMITING CONDITIONS FOR OPERATION 2.7 li]ectrical SystcIns (Continued) 2
- d. Either one of the 4.16 kV engineered safeguards buses, I A3 or I A4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the operability of the diesel generator ssociated with the operable bus is demonstrated immediately and there are no inoperable engineered safeguards components associated with the operable bus.
- e. One of each group of 4160 V/480 V Transformers (TIB 3A or 4A),
i (TlB-3B or 4B), and (TlB 3C or 4C) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
! provided there are no inoperable engineered safeguards components which are redundant to components on the inoperable transformer,
- f. One of the 480 V distribution buses connected to bus I A3 or connected to bus I A4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no l inoperable safeguards components which are redundant to components on the inoperable bus. ,
l
- g. Either Group of MCC No.'s (3Al,3B1,3A2,1C1,3C2) or (4A1,4A2, 4Cl,4C2) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on
- the inoperable MCC. MCC 3Cl may be inoperable in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if battery chargers No. I and No. 2 are operable.
- h. One of the four 120V a-c instrument buses (A, B, C or D) may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the reactor protective and engineered safeguards systems instrument channels supplied by the remaining three buses are all operable,
- i. Two battery chargers may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided battery charger No.1 (EE-8C) or No. 2 (EE-8D) is operable.
, j. Either one of the emergency diesel generators (DG-1 or DG 2) may be inoperable for up to seven days (total for both) during any month, provided there are no inoperable engineered safeguards components associated with the operable diesel generator. If one diesel generator is inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (regardless of when the inoperable diesel generator is restored to operability) EITHER:
(1) Start the other diesel generator to verify operability, OR (2) Ensure the absence of common :ause for the diesel generator inoperability for the other diesel generator.
2-34 Amendment No. (4, 447,
-- -. -= ., . - -- -
t 2.0 1lMITING CONDITIONS FOR OPERATION 2.7 &citicaLSystems (Continued)
- k. Island buses IB3A-4 A,1838-48, and 183C-4C may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on the inoperable bus (es).
- 1. Either one of the 125V d c buses No.1 or 2 (Panels EE-8F and EE 80) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- m. Either one of the 125V d-c distribution panels Al 41 A or Al 41B may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,
- n. Either one of the 120V a-c instrumen: pnels Al 42A or Al 42B may bc ,
inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l The electrical system equipment is arranged so that no single fa!!ure can inactivate enough engineered safeguards tojeopardize the plant safety. The 480 V safeguards are arranged on nine bus sections. The 4.16 kV safeguards are supplied from two buses.
The normal source of auxiliary power with the plant at power for the safeguards buses is from the house service power transformers being fed from the 161 kV incoming line with on site emergency power from either one of two diesel generators and off site standby power via the unit auxiliary transformers.(0 The loss of the 161kV incoming line renders the house service transformers (TI A-3 and TI A-4) inoperable in that the transformers cannot supply power to the 4.16kV safeguards buses l A3 and 1 A4.
Inoperability of the house seMee transformer (s) or loss of the 161kV incoming line is not reportable pursuant to 10 CFR 50.72 criteria; however, the NRC will be promptly notified of these events via the NRC Operations Center.
The two emergency diesel generators on site do not require outside power for start up or operation.
Upon loss of normal anci standby power sources, the 4.16 kV buses l A3 and 1 A4 are energized from the diesel generators. ' Bus load shedding, transfer to the diesel generator and pickup of critical loads are carried out automatically
- When the turbine generator is out of service for an extended period, the generator can be isolated by opening motor operated disconnect switch DS-Tl in the bus between the generator and the main transformer, allowing the main transformer and the unit auxiliary power transformers (TI A-1 and TI A-2) to be returned to service.m The auxiliary power transformers are not considered inoperable during these normal plant startup/ shutdown l 2-35 Amendment No. 76,147,
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4 U.S. Nuclear Regulatory Commission LIC-92-306A ATTACHMENT B
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DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATIONS f
DISCUSSION AND JUSTIFICATION t OPPD pro +
The Station Omaha Unit Public Power District No.1 Technical Spec (ifica) tion 2.7(2)j.-
poses totorevise reduce thethe Fort Calhoun number of unnecessary diesel starts by providing an alternative to starting the remaining -!
diesel generator every time a diesel ir declared inoperablo. !
Currently Technical Specification 2.7(2 j. requires that, if either of the diesel .
generators becomes inoperable,;the othe)r diesel generator be started to-verify- !
operability. The proposed change would-provide an alternative to. starting the '
other diesel:if it can be proven by analysis and reasoning that there is not a potential common cause for a failure in the remaining diesel- generator. The l
purpose thus providing-. of starting the other itL assurance diesel is to prove is operable to-absence performofitsicommon safety function, cause failuref -i !
needed. In providing an alternative of ensuring no common cause failures by- t analysis and reasoning unnecessary diesel starts can be avoided when a diesel +
is declared inoperable due to routine ) replanned prever.tative maintenance or >
testing. These situations do not const'tute a failure of the' diesel _ generator and therefore an analysis is more than adequate to ensure that the remaining diesel is operable. This change is similar to guidance contained in draft NUREG- r 1432 " Standard Technical Specifications Combustion Engineering Plants," and will reduce unnecessary wear on the emergenc,y diesels. l' As _ with all amendments to the. Technical Specifications. OPPD will conduct a review of procedures upon issuance of the amendment. This review will ensure that the requirement to conduct an analysis to determine the absence of common '
cause failure is adequately proceduralized.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION:
The proposed changes do not involve significant hazards considerations because ' ."
operation of Fort Calhoun Station Unit No. 1_in accordance with these changes would not:
(1) Involve a significant increase-in the probability or consequences of an accident previously evaluated.
The proposed changes only provide an alternative method of I' determining if a potential common cause failure exists when a diesel generator is inoperable. The current' method of determir.ing : the. 1 absence of a common cause failure requires.that the other diesel be ;
started to verify o)erability. The proposed : change. .would i allow analysis and reason < ng to---determine the . absence _ of common cause ;
failure'in situations. such as when-a diesel is declared ino l to conduct preplanned preventative maintenance or testing. perable 13
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OPPD has committed to the development of an emergency diesel !
generator reliability program in accordance with the gufdance of l Re O.gulatory Guide 95 Reference 2 .1.155, Section 1.2 and to a target reliability of the t(arget, corre)ctive actions will be required to be taken toIf the reliability of restore the reliability of the diesel. The proposed changes would reduce the number of unnecessary diesel starts and would not affect the corrective actions which will be required to maintain a reliability of 0.95. Therefore these proposed changes do not involve a significant increase in the probability or consequences of an accident.
(2) Create the possibility of a new or different kind of accident from any previously analyzed.
It has been determined that no new or different kind of accident will be created due to the proposed changes. The proposed changes will not introduce any new or different kind of operation for plant equipment. The surveillance testing requirements for the diesel generators remain unchanged. The proposed changes only allow an alternative to starting a diesel to determine the absence of common cause failures ir order to reduce the number of unnecessary diesel generator starts. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from ny pt ,viously evaluated.
(3) Involve a significant reduction in a margin of safety.
The proposed changes will not change the minimum number of diesel generators required to be operable to respond to an unlikely potential accident, the time a diesel may be out of service, or the surveillance test requirements of the diesel generators. The proposed changes only allow for an alternative to starting a diesel to determine the absence of common cause failure in the operable diesel generator when the other diesel is declared inoperable.
Therefore, the proposed chan do not involve a significant reduction in margin of safety.ges Therefore, based on the above considerations, it is OPPD's position that this 3roposed amendment does not involve significant hazards considerations as defined
. )y 10 CFR 50.92 and the proposed changes will not result in a condition which significantly alters the impact of the Station on the environment. Thus, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22 e assessment need be pre (pa)r(ed.9) and pursuant to 10 CFR 51.22(b) no environmental 2
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