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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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Text
Proceoure No.r Proc
Title:
Page:
51 Approval oate 0-ADM-200 Conduct of Operations 5.9 S ecial Instruction Book 5.9.1 The Special Instruction Book is maintained to improve communications between the plant management staff and shift personnel in the Control Room.
CA UTION Special Instructions shall not be used to circumvent established procedural requirements, nor shall Special Instructions be construed to supersede procedural requirements.
5.9.2 The Special Instruction Book contains instructions that may be issued as needed to identify temporary changes in plant conditions and provides guidance for handling situations that have short-term applicability.
5.9.3 The NPS is responsible for informing members of their crew as appropriate.
5.9.4 Special Instructions shall be approved by the Operations Manager.
5.9.5 The Operations Supervisor or designee shall review the Special Instruction Book at least once per quarter to verify the validity and currency of all active instructions.
5.9.6 Copies of each new instruction placed in the Special Instruction Book shall be forwarded to the QC Supervisor and to the Plant General Manager.
5.IO 5.10.1 The Night Orders Book is maintained to provide a communications channel between plant management and the operating shifts where face to face communication is not practical.
CA UTION Night Orders shall not be used to convey management Information that should have been delineated in other plant documents such as Quality Instructions, procedures, or instructions.
5.10.2 . The Night Orders Book contains information about upcoming events, notification of policy changes, evolutions to be performed on the backshifts and problems encountered during normal operations.
9607080268 960628 PDR ADQCK 05000250 V PDR
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Proceoure No.: Proc ure
Title:
52 Approvat oate 0-ADM-200 Conduct of Operations 5.10.3 Entries in the Night Orders Book shall be made when necessary by the Operations Supervisor, NPS, ANPS, or NWE, to provide short term information to the shift crews.
5.11 Dailv Lot.s - Operator Logsheets are utilized by operating personnel to provide a method for recording system and equipment operating data and characteristics during routine performance of their assigned duties. Rounds and logsheets shall be performed in accordance with the following:
5.11.1 O-ADM-203, Shift Operating Practices 5.11.2 3/4-OSP-201.1, RCO Daily l.ogs 5.11.3 O-OSP-201.2, SNPO Daily Logs 5.11.4 3/4-OSP-201.3, NPO Daily Logs 5.11.5 O-OSP-201.4, ANPO D'aily Logs 5.12 0 erations Testin - The Operations Manager is responsible for the overall control and coordination of all surveillance testing.
5.12.1 Operations Surveillance Tests
- l. The Operations Surveillance Testing Program shall be conducted in accordance with the guidelines of O-OSP-200.1, Schedule of Plant Checks and Surveillances.
- 2. The Operations Department is responsible for the performance, documentation, and initial review of Operations Department surveillance tests.
- 3. The NPS's approval shall be obtained prior to the commencement of any surveillance testing. IF a step is not completed for any reason. THEN the reason must be recorded on'he procedure. When a test is performed and does not meet the specified acceptance criteria, the NPS, ANPS. or NWE shall be notified and corrective action shall be initiated.
- 4. The NPS or his/her SRO designee shall review all Operations Department surveillance tests performed on his/her shift for completeness and accuracy and shall so indicate by signing and dating the procedure in the appropriate space. In addition, he/she shall ensure that completion of the test(s) is documented in accordance with the appropriate test scheduling procedures.
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. SENIOR REACTOR OPERATOR Page 41 QUESTION: 067 (1.00)
Which ONE of the following describes a restriction on overtime?
- a. Ifa licensed operator is required to work in excess of eight hours continuously then his duties at the control boards should be zestzicted to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or less.
- b. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight including shift turllover time,
- c. There should be at least eight hours break between all work periods not including shift tuznover time.
- d. An individual should work no more than seventy-two hours in any seven day period.
QUESTION: 068 (1.00) (KO R~)
Which ONE of the following describes an entry which would be made in the Night Order Book?
- a. Notification of a change in procedures for preparing clearances for air systems.
- b. Guidance for handling situations that have short-term applicability.
- c. Safety related maintenance in progress.
- d. Problems encountered during normal operations.
SENIOR REACTOR OPERATOR Page 81
.ANSWER: 065 (1.00) d.
REFERENCE:
0-ADM-103 pg 8 194001A112 [3.1/4.1]
194001A112 .. (KA's)
ANSWER: 066 (1.00) d.
REFERENCE:
O-ADM-212, pg 21 194001A102 [4.1/3.9]
194001A102 .. (KA's)
ANSWER: 067 (1.00) d.
REFERENCE:
O-ADM-200, pg 36
~4001A103 [2.5/3.4]
194001A103 .. (KA's)
ANSWER: 068 (1.00) (Cd 't<)
d.
REFERENCE:
O-ADM-200, pg 51 194001A103 [2.5/3.4]
194001A103 ... (KA's) i ANSWER: 069 (1.00) d.
REFERENCE:
O-ADM-204, pg7 194001A106 [3.4/3.4]
194001A106 .. (KA's)
SRO QUESTZON 95 Plant Conditions, Unit 3:
A Loss of Coolant Accident has occurred.
The crew is performing 3-EOP-E-1, "Loss of Reactor or Secondary Coolant."
An ORANGE Path condition is noted on the computer for Containment Integrity The Nuclear Plant Supervisor directs transition to 3-EOP-FR-Z.1, "Response to High Containment Pressure.>>
As the procedure reader is reviewing the Symptoms or Entry conditions of 3-EOP-FR-Z.l, the ORANGE path indication clears on Containment Integrity and turns YELLOW.
Which one of the. following describes the action to be taken?
ANSWERS B. Return to 3-EOP-E-1 without initiating 3-EOP-FR-Z.1 REFERENCE'-ADM-211, page 23.
COMMENT The statement above, "As the procedure reader is reviewing the symptoms or entry conditions... ", implies entry into the FRP has already occurred (see attached copy of ADM-211, section 5.1.1)
Although entry into FR-Z.1 based on computer indication may have been inappropriate, entry was made. Once entered, the FRP must be completed unless higher priority terminus occurs. (section 5.10.6, ADM-211).
RECOMMENDATION:
Delete the question as there is NO correct answer.