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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17352A3821993-12-28028 December 1993 Third Ten-Yr ISI Interval IST Program for Pumps & Valves. ML17353A7621992-12-28028 December 1992 Pre-fire Plan Guidelines & Safe Shutdown Manual Actions. ML17349A7491992-12-0808 December 1992 Revised Odcm. ML17349A3711992-05-21021 May 1992 Rev 10 to Procedure PT-51-WS, Solidification Process Control Procedure. ML17349A2511992-03-27027 March 1992 Rev 0 to Pc/M 91-128, 480 Volt Undervoltage Protection Scheme Mod for Unit 3 ML17348B4121991-10-22022 October 1991 Health Physics Procedure 0-HPS-042.8, Dewatering Controls for Radwaste Liners. ML17348A2801990-05-31031 May 1990 Rev 1 to Emergency Power Sys Enhancement Project Testing Rept. ML17348A5381990-02-13013 February 1990 Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17347B4891989-12-18018 December 1989 Administrative Procedure AP 11550.92,Health Physics Procedure HP-92, Emergency Radiation Team Response - Offsite. W/891218 Ltr ML17347B3681989-10-0202 October 1989 Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves, Rev 2 ML17347B2851989-08-17017 August 1989 Change a to Rev 1 to JNS-PTN-200, Second Ten-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17347B2951989-03-21021 March 1989 Procedure 3-EOP-ECA-0.1, Turkey Point Nuclear Plant Unit 3 Loss of All AC Power. ML17348B4131988-03-10010 March 1988 Rev 8 to Procedure PT-51, Solidification Process Control Procedure. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17342A9971987-10-26026 October 1987 Procedure 0-ADM-019, Mgt on Shift. ML17342B0191987-10-24024 October 1987 Procedure 0-ADM-019, Mgt on Shift (Mos), Weekly Summary Rept for Wk Starting 871024 ML17342A8141987-07-24024 July 1987 Draft Revs to Procedures Generation Package. ML20076H2831987-05-31031 May 1987 Rev 0 to Technical Note 51187, Procedures for Repairing Prefabricated Panel & Preshaped Conduit Section Fire Barriers Installed at Plant ML17347A3081987-01-26026 January 1987 Emergency Procedure EP 20109, Criteria for & Conduct of Local Evacuations. ML17347A3071987-01-26026 January 1987 Emergency Procedure EP 20107, Fire/Explosion Emergencies. ML17347A2241986-12-22022 December 1986 Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr ML17342A9111986-11-18018 November 1986 Off-Normal Operating Procedure 3208.1, Malfunction of RHR Sys. ML20215L8241986-09-23023 September 1986 RCS Pressure Boundary Check Valves 4-874A & B Leak Test, for Unit 4 ML20215L7031986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-3-750 &/Or MOV-3-751 Leak Test, for Unit 3 ML20215L7881986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 3 ML20215L7791986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-4-750 &/Or MOV-4-751 Leak Test, for Unit 4 ML20215L8001986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 4 ML20215L8191986-09-23023 September 1986 RCS Pressure Boundary Check Valves 3-874A & B Leak Test, for Unit 3 ML20076H4411985-11-0606 November 1985 Rev 4 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4491985-10-11011 October 1985 Rev 3 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Precedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4531985-09-20020 September 1985 Rev 2 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20199E4531985-08-23023 August 1985 Off-Normal Operating Procedure 9408.2, Energizing 4 Kv Buses Using Cranking Diesels Bus Tie Lines or Startup Transformer from Opposite Unit ML20199E4611985-08-23023 August 1985 Off-Normal Operating Procedure 7308.1, Malfunction of Auxiliary Feedwater Sys ML20199E4111985-08-22022 August 1985 Operating Procedure 7201.1, Standby Steam Generator Feedwater Sys - Operating Instructions. Related Info Encl ML20199E4321985-08-22022 August 1985 Off-Normal Operating Procedure 9408.3, Loss of Voltage to 'C' 4,160 Volt Bus ML20076H4611985-03-28028 March 1985 Rev 1 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4721985-03-15015 March 1985 Rev 0 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Powecorp,Turkey Point Npp ML17346A8291985-02-0404 February 1985 Procedures Generation Package. ML17346A6701984-12-31031 December 1984 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents. ML17346A5621984-09-26026 September 1984 Revised Emergency Operating Procedures,Including O-ADM-110 Re Verification Guideline for Emergency Operating procedures,O-ADM-111 Re Emergency Procedure Validation Plan & Procedures Generation package.W/841001 Ltr ML17346A5391984-09-0101 September 1984 Emergency Plan Implementing Procedure 1107, Duties of Emergency Planning Supervisor,Offsite Emergency Organization. ML17346A5401984-09-0101 September 1984 Emergency Plan Implementing Procedure 1211, Activation & Use of Emergency News Ctr (Turkey Point),Offsite Emergency Organization. 1998-08-27
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5-FLORIDA POWER AND LIGHT COMPANY i
- j. TURKEY POINT UNITS 3 AND 4 0FF-NORMAL OPERATING PROCEDURE 9408.3
- AUGUST 22. 1985 1 .I
! I i'
1.0 Title
}
[ LOSS OF VOLTAGE TO "C" 4160 VOLT BUS l
2.0 Approval and List of Effective Pages:
l 2.1 Approval : .
j Change Dated 8/22/85 Reviewed by Plant Nuclear Safety Committee: 85-139 and Approved by Plant Manager - Nuclear: ~ 8/22/85 l 2.2 List of Effective Pages: t i -
- Page Date Page Date Page Date
- i 1 8/22/85 2 8/22/85 3 8/22/85 i
3.0 Purpose and Discussion: ,
1 j 3.1
Purpose:
3 This procedure provides the actions to be taken in the event of loss of ower on either "C" 4160
- volt bus. If a-loss of power also occurs in both p'A" and "B" 4160 volt buses, refer to E0P 20004. If a loss of voltage occurs on either "A" or "B" 4160 volt bus, refer to ONOP 9408.1. i
3.2 Discussion
3.2.1 The loss of a "C" 4160 volt bus normally' occurs due to -protective relaying, which can be found in the"C" . bus protection logic . sheet. ,
This procedure only covers the symptoms, immediate, automatic, .and )
2 operator actions.- This procedure directs the operator to pertinent j procedures for the subsequent actions of recovery.
l 3.2.2 It is important to remember that at the present time, the "C" 4160
- volt bus is powered from the opposite unit's "C" auxiliary j transformer.
! 4.0 Symptoms: -
j 4.1 All supply'. breakers on the affected 4160 volt bus are OPEN.
4.2 No voltage indication on the affected 4160 volt. bus.
s B603270217 960106 i
PDR FOIA wErsse5-729 PDR D/S y ww w w r y. ,e -rr.v er,w w-w - m-,ay --g -. w e% ,g+*e- -w-
,--,+,-y.- .,imr.., y u .- ,g, _y--es.,-m,,y 9cp_,,y-.,.,,-ym,v,, msgg
8/22/85 0FF-NORMAL OPERATING PROCEDURE 9408.3, PAGE 2 .
,, ~LOSS OF VOLTAGE TO "C" 4160 VOLT BUS 4.3 "B" steam generator feed pump will be off.
NOTE: If affected unit is greater than 60% power, a governor runback should be' occurring.
i
, 4.4 Steam flow greater than feedwater flow alarm on at least one steam generator.
4.5 Decreasing level jn at least one steam generator.
, 4.6 Increasing Tavg and RCC pressure until control rods are driven in by 4
operator action.
i 4.7 Actuation of steam dump to condenser.
NOTE: If "C" condensate pump was in service prior to loss of voltage, the i
symptoms would occur in a faster sequence and will probably result in a reactor trip. If reactor trips, refer to ON0P 0208.1.
5.0 Instructions
l 5.1 Imediate Automatic Action:
5.1.1 Governor runback if reactor power is greater than 60"..
1 5 .1.2 Actuation of steam dumps.
5.2 Immediate Operator Action:
5.2.1 Orive control rods in to maintain Tavg within 5 degrees F of Tref.
5.2.2 Reduce load until steam flow is less than or equal to feedwater flow to recover steam generator. level. .
l 5.2.3 Verify operability of pressurizer PORV's if required by system pressure.
- NOTE
- If the reactor trips, refer immediatel_y to ON0P 0208.1.
5.3 Subsequent Operator Actions:
l 5 .3.1 As soon as the unit is in a stable, non-transient. condition, power should be restored to the "C" 4160 volt bus. To restore power to the affected "E", "F" and "G" Load Centers from their opposite unit busses, refer to *-0P-005.1, 4160 Volt Bus C. To restore affected unit "C" 4KV Bus and associated load centers to their normal i
configuration, refer.to *-0P-005.1, 4160 Volt Bus C.
J 5.4 Important Equipment Supplies by "C 4160 Volt Bus: ,
The following is a list of equipment besides the steam generator feed pump and condensate pump fed from "C" 4160 volt. bus that could ' result in further
! plant problems if power is not restored as soon as possible.
l
' ' . 8/22/85 0FF-NORI1AL OPERATING PROCEDURE 9408.3, PAGE 3
,, LOSS OF VOLTAGE T0 "C" 4160 VOLT BUS i I
E.4.1 "B" and "C" RCP oil lift pumps.
5.4.2 Water treatment plant (normally fed from Unit 3).
5.4.3 Polishing demineralizer hold pumps.
5 .4.4 Traveling screens I 5.4.5 Circulating water pump discharge f40V's.
5.4.6 Primary water pumps. 1 i
- 5.4.7 lStandbySteamGeneratorFeedPumpsAandBl 1 6 .0
References:
' l l
6.1 ONOP 9408.1, Unit 3 Loss of "A" or "B" 4KV Bus.
6 .2 E0P 20004, Loss of Off-site Power.
i 6.3 ONOP 0208.1, Shutdown Resulting from Reactor Trip or Turbine Trip. .
l 6.4 *-0P-005.1, 4160 Volt Bus C.
7.0 Records Required:
Normal log entries.
i e . -