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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
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TABLE 2-1 ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUNIENT SETTING LIMITS -
DCJ Mo N
c-2> 4 co Functional Unit Channel Settine Limit om nw X" 1. liigh Contaiament Pressure a. Safety Injection A 5 psig oc b. Containment Spray *
$$ c. Containment Isolation g
Orap
- d. Containment Air Cooler DBA Mode
%a e. Steam Generator Isolation MON 2. Pressurizer Low / Low Pressure a. Safety injection A 1600 psia *
- b. Containment Spray *
- c. Containment Isolation
- d. Containment Air Cooler DBA Mode
- 3. Containment liigh Radiation Containment Ventilation Isolation In accordance with the Offsite Dose Calculation Manual
- 4. Low Steam Generator Pressure a. Steam Line Isolation 1500 psia *
- b. Auxiliary Feedwater Actuation 2 466.7 psia
- 5. SIRW Low Level Switches Recirculation Actuation 16 inches +0, -2 in. above tank bottom
- 6. 4.16 KV Emergency Bus Low a. less of Voltage (2995.2 + 104, -20.8) volts Voltage 15.9* seconds } TRIP
- b. Degraded Voltage A ?c2%52 3989 volts i) Bus I A3 Side (4.81 5) seconds }TRIr-2-64 Amendment No. 44,65,36,408
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TABLE 2-1 (Continued)
ENGINEERED SAFETY FEATURES SYSTENI INITIATION INSTRUSIENT SETTING LI511TS -
Functional Unit Channel Settine Limit
- 6. (Continued) b. (Continued) 14734,08 3990.d volts 2
ii) Bus I A4 Side (4.8 .5) seconds } TRIP
- 7. Low Steam Generator Water Auxiliary Feedwater Actuation 128.2% of wide range tap span Level
- 8. liigh Steam Generator Delta Auxiliary Feedwater Actuation 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 550 psia.
(3) Simultaneous high containment pressure and pressurizer low / low pressure.
(4) Applicable for bus voltage 12995.2 - 20.8 volts only. (For voltage 2 (2995.2 - 20.8) volts, time delay shall be > 5.9 seconds.)
2-64a Amendment No. 44,65,86
U. S. Nuclear Regulatory Comission LIC-93-0096 ATTACHMENT B
DISCUSSION. JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION Omaha Public Power District (OPPD) 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 voltage from the 161 KV offsite power supply to 4.16 KV safeguards buses lA3 and 1A4 exists during an accident, the electrical distribution system has been equipped with a degraded voltage protection system referred to as Offsite Power low Signal (0PLS). The OPLS provides protection to safeguards equipment when a degraded voltage condition is detected on 4.16 KV bus IA3 or lA4, concurrent with a Safety Injection Actuation Signal (SIAS). When a degraded voltage condition exists concurrent with a SIAS, the OPLS isolates 4.16 KV buses lA3 and 1A4 from the 161 KV offsite power supply and initiates automatic actions to load the safeguards equipment onto the emergency diesel generators.
The OPLS setpoints were originally designed to ensure that the voltage supplied to the 4.16 KV and 480 V loads does not drop below 90% of the nameplate voltage <
rating during an accident. The motor manufacturers recommend that terminal voltage be maintained at a minimum of 90% of motor nameplate rating to protect the motors from overheating due to excessive 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 actuating 0PLS. 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 subsequently revised on June 21, 1991. Interim corrective actions included placing administrative restrictions on equipment retation 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 implemented during the 1992 refueling outage.
The 1992 modification altered the existing logic circuitry such that, upon receipt of a SIAS, the large 4.16 KV motors and equipment i.e., feedwater, heater drain and condensate pumps) not required to mitigate th(e consequences of an accident are automatically load shed. The modification also raised the OPLS setpoints so that actuation occurs (assuming a concurrent SIAS) at a higher level of decreasing voltage on 4.16 KV safeguards buses IA3 and 1A4 based on Engineering Analysis EA-FC-90-057.
Subsequent to the installation of the modification described above, it has been determined that it is possible to permit the operation of a single main feedwater/ condensate pump train following a SIAS by establishing additional load shedding and modifying the OPLS setpoints. This conclusion is documented in Engineering Analysis EA-FC-92-081. Although it is not necessary to operate any main feedwater or condensate pumps to mitigate the consequences of any design basis accident, it is desirable to provide the option of operating a single main feedwater train in certain SIAS scenarios in order to provide more operational flexibility during the response to an accident. Therefore, another modification is planned for the 1993 refueling outage which will provide this flexibility.
As in the case of the 1992 modification, the 1993 modification will require the OPLS setpoints to be changed. The proposed change to the technical specification 1 limit for OPLS actuation is necessary to ensure the limit is consistent with the more restrictive limits specified in EA-FC-92-081.
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In a March 26, 1993 telephone conversation between OPPD and Mssrs. Steve Bloom and Mark Pratt of the NRC, it was requested that OPPD respond to the following ,
4 questions: j
- 1. What type of en i Explain in detaif neering analysis was performed originally for OPLS?
i The original 0PLS analysis assumed, as its design criteria, that the Engineered Safety Features (ESF) motors would accelerate their respective loads to full-speed at 270% of motor nameplate voltage and that the motor voltage would recover to 290% of terminal voltage after motor acceleration. The plant bus loading was based on loading measurements taken during power operation. These loads were then used to calculate the worst case ESF motor voltage during starting. The OPLS setpoint was based .
on assuring that 270% motor terminal voltage was maintained. Individual motor acceleration calculations were not performed. A requirement that i the twelve safety injection Motor Operated Valve (MOV) contactors pickup at 285% of 120 V was also established. The original OPLS analysis was ,
reviewed and approved by the NRC in Amendment No. 41 dated November 27, l 1978.
- 2. Was there a new calculation for the new OPLS values and was this calculation down to the 120 V level?
The calculation documented in EA-FC-92-081 was based on detailed computer ~!
modeling of the plant electrical system and loads. Worst case models were !
established for both ESF trains. The setpoints were established to assure i 290% motor operating voltages following ESF motor acceleration. ESF motor i acceleration calcuTations were performed to assure the ESF loads would l accelerate with voltage at the OPLS setpoint. The acceleration !
calculations included ESF sequen:er timer uncertainties. A calculation contactor level was alsoautomatically to verify performed atoperated the 120M0V V Motor Controlwould contactors Center pic(MCC) kup and hold in !
during the starting voltage transients. '
- 3. What type of field verification was done to validate the data used for both initial and revised OPLS calculations?
The field verification conducted for the original OPLS analysis involved the starting of several ESF motors and measuring the voltage transients.
This data was used to verify the OPLS methodology and model adequacy.
OPPD considers the present electrical distribution model which was used to derive current OPLS setpoints to be valid based on the Diesel Generator l Transient Analysis. The same model (i.e., motors, pumps, fans, cable, transformer, etc.
Diesel Generator ) Transient Analysis.used Thisin analysis the currentwas OPLS analysis verified by was used in comparing the diesel generator automatic operation data taken during the 1992 refueling outage to the computer generated transient load profile.
The results showed acceptable agreement between the model and the actual equipment operation.
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- 4. What controls will be used in the future to update the calculation if bus loads change? How will it be determined if increased bus loading is a concern?
OPPD has in place procedural controls which govern modifications to the facility. Part of these controls require an Electric System Interaction i Evaluation be performed. This interaction evaluation is in the form of '
checklists which prompt that an analysis be performed if bus loading is impacted. Bus loading is a critical input of the OPLS analysis and as such the procedural controls would address possible future changes.
Administrative 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 page 2-64.
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i BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION j The proposed changes do not involve significant hazards considerations because operation of Fort Calhoua Station Unit No.1 in accordance with these changes l would not: )
(1) Involve a significant increase in the probability or consequences of an <
accident previously evaluated. l l
OPLS actuates only when a degraded voltage condition is detected on 4.16 1 KV safeguards buses lA3 or IA4 concurrent with a SIAS. The proposed I change to Technical Specification 2.14, Table 2-1, Item No. 6.b. (0PLS Setpoints) provides 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. provides the level of safety for the OPLS, which is currently being maintained by plant operating procedures. Therefore, neither the probability nor consequences of an accident previously evaluated are increased.
(2) Create the possibility of a new or different kind of accident from any previously analyzed.
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. l 6.b. (0PLS Setpoints) revises a nonconservative limit that currently l exists in Technical Specification 2.14, Table 2-1, Item No. 6.b. The !
proposed change provides assurance that safety related loads will have )
adequate voltage to accelerate to rated speed and that the voltage on 4.16 l KV buses IA3 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) increases the margin of safety as compared with the current Technical Specification 2.14, Table 2-1, Item No. 6.b. setpoints.
Therefore, based on the above considerations, it is OPPD's position that this proposed amendment does not involve a significant hazards consideration as defined by 10 CFR 50.92 and the proposed changes will not result in a condition 4 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 4)(9) assessment need be pre (pared. and pursuant to 10 CFR 51.22(b) ao environmental 4
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