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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
. ,
U.S. Nuclear Regulatory Commission LIC-92-099A ATTACHMENT A
?!A 2288 M Ha88?os P PDR
Q TABLE 2-1 ENGINEERED SAFETY FEATURES SYSTE%f INITIATION INSTRU3fEST SETTING LI5flTS Functional Unit Channel Se* tine Lim _it
- 1. High Containment Pressure a. Safety Injection '15 psig
- b. Containment Spray *
- c. Cortainment Isolation
- d. Containment Air Cooler DBA Mode
- e. Steam Geaerator Isolation
- 2. Pressurizer low / Low Pressure a. Safety Injection 21600 psia *
- b. Containment Spray *
- c. Containment Isolation
- d. Containment Air Ccoler DBA Mode
- 3. Containment liigh Radiation Containment Ventilation Isohtion In accordance with the Offsite Dw Celwhtion Manual
- 4. Low Steam Generator Pressure a. Steam Line Isolation 1500 psia a
- b. Auxiliary Feedwater Actuation 1466.7 psia
- 5. SIRW low level Switches Recirculation Actuation 16 inches + 0, -2 in. above tank bottom
- 6. 4.16 KV Emergency Bus Low a. Loss of Voltage (2995.2 + IM, -20.8) volts Voltage 15.9* seconds } TRIP
- b. Degraded Voltage 1 -382L&2 4g29]4 volts i) Bus 1 A3 Side (4.8 i .5) seconds } TRIP 2-64 Amendmeet No. 44,65,86,408
,w TABLE 2-1 (Continual) l l ENGINEERED SAFETY FEATURES SYSTEM f"' ATION INSTRU5fENT SETTING LIMITS Channti Setting Limit Eunctional linit
- 6. (Continued) b. (Continued) 1 W34481978.6 volts ii) Bus I A4 Side (4.81 5) seconds } TRIP
- 7. lew Steam Generator Water Auxiliary Feedwater Actuation 128.2% of wide range tap span l level i
- 8. liigh Steam Generator Delta Auxiliary Em! water Actuation i 119.7 psid Pressure l
l L
l (1) May be bypassed below 1700 psia and is automatically reinztated above 1700 psia.
1 (2) May be bypassed below 550 psia and is ratometically reinstated above 550 psia.
(3) Simultaneous high containment pres.;ure and pressurizer low / low pressure.
(4) Applicable for bus voltage i 2995.2 - 20.8 volts only. (For voltage 1(2995.2 - 20.8) volts, time delay shall be > 5.9 sceonds.)
l 2-64a Ammammt No. 44,65,36
6 TABLE 2-1 ENGI;TrffRED SAFETY FEA'I1URES SYSTEM INITIATION INSTRUMENT SETTING LIMITS Eunctional Upjl Channel Settine Limit
- 1. High Containment Pressure a. Safety Injection 15 psig
- b. Containment Spray * ,
- c. Containnnt Isolation
- d. Containment Air Cooler -
DBA Mode
- e. Steam Generator Isolation
- 2. Pressurizer LowLru Pressure a. Safety injection 21600 psia *
- b. Containment Spray *
- c. Containment Isolation
- d. Containtnent Ait Cooler DBA Mode
- 3. Containment fligh Radiation Containment Ventilation Isolation In accordance with the Offsite Dose Calculation Manuci
- 4. Low Steam Generator Pressure a. Steam Line Isolation A 500 peia m
- b. Auxiliary Feedwater Actuation 1466.7 psia '
- 5. SIRW Iew Level Switches Recirculation Actuation 16 inches 4-0, -2 in. a'oove tank bottom
- 6. 4.16 KV Emergency Bus Low a. las of Voltage (2995.2 + iO4, -20.8) volts Voltage i 5.9'* seconds ) TRIP
- b. Degraded Voltage 14o29.4 volts l i) Bus I A3 Side (4.8 f. 5) seconds } TRIP 2-64 Amendment No. ^1,G,46.408
'~
TABLE 2-1 (Continued)
ENGINEERED SAFETY FEATURES SYSTEM INmATION IFRRUMENT SETTING LIMITS -
Functional Ifnit Channel Settine Limit
- 6. (Continued) b. (Continued)' 13978.6 volts {
ii) Bus I A4 Side (4.8 f_ .5) seconds } TRIP 7.1.ow Steam Generator Water Auxiliary Feedwater Actuation 128.4% of wide range tap span Level
- 8. liigh Steam Generator Delta Auxiliary Feedwater /.ctuation i 119.7 psid Pressure (1) May be bypassed below 1700 psia and is automatically reinstated above 1700 psia.
(2) May be bypassed below 550 psia and is automatically reinstated above 553 psia.
(3) Simultaneous high contairanent pressure and pressurizer low / low pressure.
(4) Apr8icable for bus voltage i 2995.2 - 20.8 volts only. . (For veltzge 1(2995.2 - 20.8) volts, time delsy shall be > 5.9 sawmis.)
2-64a AW-t No. 44,65,86 a
U U.S. Nuclear Regulatory Comission LIC-92-099A.
ATTACHMENT B
01}CUS$10N. JUSTIFICATION AND H0 SlaNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION Omaha Public Power District (0 PPD) proposes to change Fort Calhoun Station Unit No.1 Technical Specification 2.14, Table 2-1, Item No. 6.b. that specifies the setpoint limit for degraded voltage protection.
To ensure that adequate vo. age from the 161 KV offsite power supply to 4.16 KV safeguards buses lA3 and 'A4 exists during an accident, the electrical distribution system has been equipped with a degraded voltage protection system referred to as Offsite Power Low Signal (OPLS). The OPLS provides protection to safeguards equipment when a degraded voltage condition is detected on 4.16 KV buses a When IA3 or lA4, concurrent degraded with a Safety voltage condition exists injection Actuation concurrent Signalthe with a SIAS, (SIAS)s.
0?m isolates 4.16 KV buses lA3 and 1A4 from the 161 KV cffsite power supply- and initiates automatic actions to load the safeguards equipment onto the emergency diesel generators. The GPLS setpoints were originally designed to ensure that the voltage supplied to the 4160 V and 480 V loads does not drop below 90% of the nameplate voltage rating during an accident. The motor manufacturer recommends that terminal voltage be maintained at a minimum of 90% of motor nameplate rating to protect the motors from overheating due to excersive current.
An engineering analysis revealed that during an accident in which safeguards equipment would be required to operate, the voltage supplied to some 480 V safeguards loads could degrade to approximately 87.5% of rated voltage without attuating OPLS. Therefore, in February 1991, the- 0PLS was determined to be outside its design basis. This situation was reported to the NRC in Licensee Event Report 50-285/91-04 dated March 21, 1991, which was subsequent'.y revised on June 21, 1991. Interim corrective actions included placing administrative restrictions on equipment rotation and bus loading configurations. Also, the OPLS setpoints were increased to provide protection consistent with the allowable configurations. In order to remove the operational restrictions of the interim corrective actions, a modification was 1mplemented during the 1992 refueling outage.
This mo61fication alters the existing logic circuitry such that upon receipt of a SIAS, the large 4160 volt motors and equipment (i.e., feedwater, beater drain and condensate pumps) ne required to mitigate the consequences of an accident are automatically load shed. Controls have been modified so that during normal operations, plant personnel have additional flexibility in loading equipment onto 4.16 KV buses lA3 and 1A4. The modification raises the OPLS setpoints so that it actuates (assuming a concurrent SIAS) at a higher level of decreasing voltage or. 4.16 KV safeguards buses IA3 and 1A4 based on Engineering Analysis EA-FC 057. As a result, the current OPLS setpoints listed in Technical Specification 2.14, Table 2-1 Item No. 6.b. must be increased.
Admin;strative Chanaes Amendment number 108 is being added to the bottom of page 2-64 as the current revision to this page. Presently this amendment number is not legible on pag?
2-64.
1
l BASIS FOR NO Sl@ilFICANT HAZARDS CONSl0 ERAT 10H The proposed changes do not involve significant hazards considerations because operation of Fort Calhoun Station Unit No.1 in accordar.ce with these changes would not:
(1) Involve a significant increase ir. the probability or consequence:; of an accident previously evaluated.
OPLS actuates only when a degraded voltage condition is detected on 4.16 KV safeguards buses lA3 or lA4 concurrent with a SIAS. The proposed change to Technical Specification 2.14, Table 2-1, item No. 6.b. (0PLS setpoints) prcvides additional assurance that the safety related loads that are sequenced on in this situation will have adequate voltage to accelerate to rated speed. In addition, the proposed increase in OPLS setpoints will insure that voltage is maintained at a minimum of 90% of "
nameplate rating to protect the 480 V motors from overheating due to excessive current. The proposed change to Technical Specification 2.14,
- Table 2-1, Item No. 6.b. restores the level of safety intended by the design basis of OPLS. Therefore, neither the probability nor consequences of an accident previously evaluated are increased.
(2) Create the possibility of new or different kind of accident from any previously analvzed.
The proposed change will cause OPLS to actuate at a higher level of decreasing voltage (concurrent with a SIAS) on 4.16 KV buses lA3 and 1A4.
For reasons stated in the response to Item 1 above, this proposed change ensures the level of safety intended by the design basis of OPLS and provides additional protection to safeguards loads, it does not create the possibility of a new or different kind of accident.
(3) Involve a significant reduction in a margin of safety.
The proposed increase in Technical Specification 2.14, Table 2-1, Item No.
6.b. (OPLS setpoints) revises a nonconservative limit that currently exists in Technical Specification 2.14, Tabla 2-1, item No. 6.b. The a proposed change provides assurance that safety related loads will have adequate voltage to accelerate to rated speed and that the voltage on 4.16 KV buses lA3 and 1A4 does not drop below 90% of the nameplate voltage rating during an accident. Therefore, the proposed change to Technical Specification 2.14, Table 2-1, Item No. 6.b. (OPLS setpoints) increasns the margin of safety as compared with the current Technical Specification 2.14, Table 2-1, Item No. 6.b. setpoints.
Thereforc, based on the above considerations, it is OPPD's position that this .
proposed amendment does not i n .>ol ve a significant hazards consideration as defined by 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 change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(e)(9) and pursuant to 10 CFR 51.22(b) no environmental assessment need be preparad.
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