Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to TsML20091L799 |
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Site: |
Vogtle ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
04/22/1991 |
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From: |
GEORGIA POWER CO. |
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To: |
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Shared Package |
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ML20091B437 |
List: |
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References |
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LO-LP-39201-06, LO-LP-39201-6, NUDOCS 9201280242 |
Download: ML20091L799 (14) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program. ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program. ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program. ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20091L8331989-05-19019 May 1989 Rev 0 to Corporate Guidelines 1.1.2, Positive Discipline ML20246N6241989-05-10010 May 1989 Rev 3 to Vogtle Electric Generating Plant Unit 1 Inservice Insp Program ML20078A5401988-11-15015 November 1988 Updated Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20195J9191988-11-11011 November 1988 Rev 4 to ISI-P-010, Preservice Insp Program Vogtle Electric Generating Plant Unit 2 ML20196B1551988-10-25025 October 1988 Rev 0 to ISI-P-014, Inservice Insp Program ML20195B3901988-10-18018 October 1988 Aw Vogtle Simulator Certification Plan ML20091L8931988-10-0303 October 1988 Voided Rev 9 to Procedure 10000-C, Conduct of Operations ML20155C0751988-09-15015 September 1988 Rev 0 to Abnormal Operating Procedures 18038-2, Operation from Remote Shutdown Panels ML20091L8821988-09-0808 September 1988 Voided Rev 10 to Procedure 35110-C, Chemistry Control of Rcs ML20155C0871988-08-19019 August 1988 Rev 9 to Procedure 12006-C, Unit Cooldown to Cold Shutdown ML20151G1851988-07-18018 July 1988 Rev 1 to ISI-P-006, Inservice Insp Program ML20151G1881988-07-18018 July 1988 Rev 2 to ISI-P-006, Inservice Insp Program ML20078A6221988-07-12012 July 1988 Readiness Review Program Module 20 - Instrumentation & Controls ML20078A5931988-06-28028 June 1988 Readiness Review Program Module 13B - Coatings ML20078A5831988-06-22022 June 1988 Readiness Review Program Module 12 - Electrical Cables & Terminations ML20091L7821988-06-0707 June 1988 Rev 0 to Procedure 49006-C, Health Physics & Chemistry Dept Outage Activities Implementing Procedure ML20078A5461988-05-12012 May 1988 Rev 1 to Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20078A5751988-04-13013 April 1988 Readiness Review Program Module 11 - Pipe Stress & Supports ML20151R0331988-04-13013 April 1988 Rev 3 to Inservice Test Program ISI-P-008, Summary of Changes ML20078A6311988-03-16016 March 1988 App F, Inspector Qualification of Vogtle Electric Generating Plant Unit 2 Readiness Review Program ML20148K4301988-03-0202 March 1988 Inservice Test Program 1998-05-25
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5 USERS COPY I i} A GEORGIA POWER COMPANY POWER CENERATION DEPARTMENT VOGTLE ELECTRIC CENERATING PLANT TRAINING LESSON P,*808 TITLE: INTRC' DUCTION TO TECHNIC..L SPECIPICATIONS NUMBER LO-LP-39201-06-C PROGRANt LICENSED OPERATOR TRAINING REVISION: 6 SME RUBIN DATIt 4/19/91 APPROVEDe Df.TE .g .}f INSTRUCTOR CUIDELINES
- 1. LESSON FORMAT
. A. Lecture with visuai aids II. MATERIALS .
A. Overhead projestor
% Transparencies C. White board with markers III. EVALUATION A. Written or oral exam in conjunction with other lesson plans IV. REMARKS .'
A. All Technical Specificationi Interpretations are contained in this Lesson 9201200242 911231 PDR ADOCK 05000424 '
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LO LP-39201-06-c [
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i Licensed operator objectives for this !
lesson plan can be found in the Licensed r operator systes Master Plan Section 2.3 (Qualification signotf criteria) l
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Latest Revision of ;
cluster Technical specifications 4
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8' LO-LP-39201-06-C 2NTENTIONALLY LETT BLANK
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f LO-LP-39201-06-C RETERENCES:
- 1. 10CFR50.36
- 2. TECH SPECS VEGP UNIT 1 DOCKET No. 50-424
- 3. TRANSPARENCIES:
LO-TP-39201-001 OBJECTIVES LO-TP-39201-002 REQUIRED TECH SPEC CATEcoRIES LO-TP-39201-003 TECH SPEC FORMAT LO-TP-39201-004 TORMAT FOR LCOs AND SURVEILLANCE 5 LO-TP-39201-005 TECH SPEC INTERPRETATION REQUEST FORM
- 4. Procedure 10000-C
- 5. COMMITMENTS Yr 88.028 CYCLE 2 7.5. CHANGE
- 6. Technical specifications Interpretatier.s e
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4 LO-LP-39201-06-c LESSON OUTLINas NOTES
!. INTRODUCTION This lesson is designed to familiarise the students LO-TP-39201-001 with where the requirements for having technical specifications ccee from and to teach the format that the technical specifications are arranged in II. PRESENTATION A. Requirements for Technical Specifications
- 1. Required by 10cFR50.36 Objective 1
- a. Code of Federal Regulations
- b. Chapter 10 is Energy
- c. Part 50 is the entitled the Domestic Licensing of Production and Utilisation Facilities
- d. section 50.36 is Technical specifications
- 2. Requires each applicant to submit a draft
- a. In accordance with the following section
- b. Nust include summary statement of bases or
- 1) Other than administrative
- 2) Shall not become part of specifications
- 3. Each license authorizing operation will include technical specifications
- a. Will be derived free. evaluation of FSAR-
- b. comunission may include those it finds appropriate B. Will include the following categories (also LO-TP-39201-002 daecribed in 10CTR50.36)
- 1. Gafety Limits, Limiting safety system settings
'* a. safety Limite
- 1) Definition- operating limits imposed in objective 3 the plant to prevent damage to the fuwl 5
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__..m__ _ _ _ _ _ _ _ . _ _ _ . . . _ _ . _ _ _ . _____.__ ______._ _ _ _ _
s a
Lo-LP-39201-06 c LESSON OUTLINE: NOTES cladding ah4 RCS piping and thereby 1 prevent the r.';ase of radioactivity l to the environment i
- 2) protects the fuel cladding by limiting l the departure f rom nucleate boiling of the RCS
- a. as the departurn from nucleate boiling increases, the heat transfer from the fuel decrsases
- b. regulation of DNB is accomplished by limiting RCS Tave for a given RCS pressure
- 3) protects the Acs piping by limiting ncs pressure-
- 4) If exceeded, required actione ares i
a) Reactor shall be shtt down
. b) Notify coussission c) submit report - LER d) Not startup until permission from NRC
- b. limiting safety System settings i) settings for sutomatic protective devicae
- 2) Designed to protect aga'. net exceeding safety limite a) Must be set before safety limit is reached l 3) If protective action does not occur l a) Take appropriate action which may include shutting down the reactor l- , b) Notify comunission l c) Submit report
- 2. Limiting Condition for openation l
6
LO*LP-39201-06-c LESSON OUTLINE: 43's
- a. Lowest functional cepability or performance level for equipment required for omte operation
- b. When LCO not met
- 1) Follow the ' ACTION
a) If compliance not met within
' ACTION" time, shutdown may be required
- 2) Notify the commiselon
- 3) Review the matter and f.ecord the results of the review
- 3. surveillance Requirements
- a. Requiremente related to test, celibration or inspection
- b. Provides assurance that:
- 1) Necessary quality of systems and Objective 4 componente is mainte,ned
- 2) Facility operation will be within the eafety-limite
- 3) Limiting conditions for Operation will be met
- 4. Design Features
- a. Features of facility whicht
- 1) Would have a significant affect on safety if altered or modified, or
- 2) -Are not covered in safety L! mite, Lcos, or surveillances k Esamples are:
- 1) NatorialJ of constriction
. 2) Geometric arrangenets
, 5. Administrative controle
- a. Provisione necessary to sesure operation of 7
LO-LP-39201-06-c LESSON OUTLINE: NOTES facility in a safety manner
- 1) organisetion and management
- 2) Procedures
- 3) Record keeping
- 4) Review and audit
- 5) Reporting
- 6) Initial Notification a) Reporta to cossaission in response to requir:monts of this section C. Format of Technical specificatione ir Addresses categories of 10crR '
- 2. Consists of six sections (modified It standard Lo-TP-39201-003 .
Tech specs /WUREG 1247 modified for Vogtle design) Objective 2
- a. section 1.0 - Definitions
- b. section 2.0 - safety Limite and L8ss
- c. section 3.0 - Limiting conditions for Operation
- d. Section 4.0 - Surveillence Requirements
- o. sectica 5.0 - Design Features
- f. section 4.0 - Administrative controls
- 3. Lcos and surveilla.n'es presented in combined objective 2 format (sections 3 and 4)
- a. LOO appears at top of page
- b. Followed immediately by applicable surveillance requirement
- c. Combined section 3/4 further subdivided
. into 12 subsections
. 1) Reactivity control - Section 3/4.1 LO-TP-39201-004
- 2) Power Distribution - section 3/4.1 0
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LO-LP-39201-06-c
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LESSON CUTLINE: NOTES
- 3) Instrumentation - Section 3/4.3
- 4) Reacter Jelalt system - Section 3/4.5
- 5) Emergency Core cooling system -
Section 3/4.5
- 6) Containeent systems - section 3/4.6
- 7) Plant systems - Section 3/4.7
- 8) Electricel systems
- 9) Refueling - section 3/4.9
- 10) special Test Exceptions -
Section 3/4.10
- 11) Radioactive Effluents - Section 3/4.11
- 12) RaGJ1ogic61 Environment Monitcring -
section 3/4.12
- d. - Explain'the LCO and surveillance requirements in section 3/4.0 Applicability and give examples of each. ,
D. Technical specification clarification objective 5
- 1. . Implemented per plant proc.~1ure 10000-c
- a. obtain copy of the curtant T.S. T.s.
-clarifications and review with class clarifications sAct clarification
- controlled copy.
- 2. Helps to clear up discrepincies when may be obtained clarification problems arise from the trg ctr
- library
! - 3. Tech spec clarification is the responsibility l_
of the operations Department Management.
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[ 4. Imp 1wentation Procedure
- a. When an immediate need exists for an l- clarification, the requestor will centact one of the following individuals who will l: give a verbal clarification and a written l request form may follow
- shift superintencent l-i 9
1 Lo-LP-39201-06-C '
LESSON OUTLINE: NOTES
- An operations superintendent
- b. If there is not an urgent need for Lo-TP-39201-005 clarification, a for1m contained in 10000-C is used to request a clarification
- c. the requestor fille out the first two portions of the clarification form and forwards it to the Manager of operations
- d. after the opwrations Manager clarifies, i.he original is placed in the Clarification scok that is maintained in the Control Room E. Making Changus to Technical Specifications
- 1. Licensing Document change Request (LDCR) Procedure 00402-is generated-
- a. Can be done by anyone on site
- 2. LDCR must be processed through chain
- a. Each individual reviewing LDCR can approve it and send it to next evaluator on ,
disapprove it and return it to previous individual
- b. Each LDCR requires safety evaluation
- c. .R11 questions must be reviewed cad approved '
- 1) NSAC coordinates changes
- d. PRE approval required t
- e. GM approval required i; f. NRC reviews documents change III. SUMMART l- .
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LO-LP-39201-06-c LESSON OUTLINs NOTES
- 1. Define the requirements placed on the plant to have Tech specs.
- Required by 10CTR50.36
- 2. List and dsscribe the sections and subsections required in Tech specs.
- Consists of six sections (modified W standard Tech specs /NUREG 1247 modified for Vogtle design)
- a. Doction 1.0 - Definitions
- b. Section 2.0 - safety Limits and Lsss
- c. set. tion 3.0 - Limiting conditions for Operation
- d. Section 4.0 - surveillance Requirements
- e. Section 5.0 - Design Features
- f. Section 6.0 - Administrative controla 9
- 3. Define " safety Limit." state what the safety Limits are designed to protect.
- Definition- operating limits-imposed on the plant to prevent damage to the fuel cladding and RC* piping and thereby prevent the release of radioactivity to the environment
- protects the fuel cladding-
- protects the RCS piping
- 4. List the assurances that surveillance requirements provide.
- Necessary quality of systems and components is maintained
- Facility operatiou will be within the safety limits
- Limiting conditions for operation will
,be met
- 5. State how Tech specs interpretations are made.
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I LO-LP-39201-06-c LESSON OUTLINE NOTES
- I:nplemented per plant procedurs 10000-c
- Implementation Procedure
- a. When an issnedtate need exists for an interpretation, the requestor will contact one of the following individuals who will give a verbal interpretation with a follow-up written request form
- onshift operation supervisor
- Operations Superintendent
- b. if there is not an urgent need for interpretation, a form contained in 10000-c is used to request a interprotation O
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1D.CL.39 06 LICENSED OPERATOR OMECTIVES 14.LP.39201.C I PURP05E 5TATEMENT
. Following completion of this lesson, the ste. tent will t ossess those knowledges systematically identified for the performance of the INTRODUCTION TO TECH SPECS tasks.
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II LI5T OF OBJECTIVE 5
- 1. Define the requirements placed cn the plant to have Tech Speen.
- 2. List and describe the sections and subsections required in Tech Specs,
- 3. Define ' Safety Limit." State what the Safety Limits are designed to protect.
4 List the assurances that surveillance requirements provide.
- 5. State how T.S. clarific.ations are made.
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F.N CL.39 DidfNff9fMC/TECM ETAFF OLf ECTIVES
, I rustro5E ITf.faJan Following completion of this lesson, the student will possess those knowledges systematically identified for the performance of the INTRODUCTION TO TECH SPECS tasks.
II LI3T OF DBJECTIVE3 1.
Define the requirements placed on the plant to have Tech specs.
(Obj ective: 1D.LF.39201 01) 2.
List and describe the sections and subsections required in Tech Specs.
(Obj ective: LO.LP.39201 02) 3.
Define " Safety Limit." state what the safety Limits are designed to protect.
(Objective: 14.LF.39201 03) 4 List the assurances that surveillance requirements provida.
(Obj ective: ID.LP.39201 04)
- 5. State how T.S. interpretations are made.
(objective: 14.LP.39201 03)
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