ML17349A821
| ML17349A821 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/23/1993 |
| From: | Plunkett T FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17349A822 | List: |
| References | |
| L-93-108, NUDOCS 9304290172 | |
| Download: ML17349A821 (47) | |
Text
'y ACCELERAT D DOCUMENT DIST <BUTION SYSTEM REGULA Y INFORMATION DISTRIBUTIO YSTEM (RIDE)
ACCESSION NBR:9304290172 DOC.DATE: 93/04/23 NOTARIZED: YES DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Suppls 930211 application for amends to Licenses DPR-31 &
DPR-41,modifying TS Section 6.0, "Administrative Controls" to address licensed qualifications of operations manager,per 930323 meeting w/NRC.Curriculum for training course encl.
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P.O. Box 029100, Miami, FL, 33102-9100 1
p,pR RS 1993 L-93-108 PIPE 10 CFR 50.36 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed License Amendments 0 erations Mana er ualifications By letter L-93-033, dated February 11, 1993, Florida Power & Light Company (FPL) proposed to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41 by modifying the Turkey Point Units 3 and 4 Technical Specifications Section 6.0, "Administrative Controls," in accordance with 10 CFR 50.90. The purpose of these amendments was to address the licensed qualifications of the Operations Manager. FPL met with the NRC staff on March 23, 1993, to discuss the proposed license amendments. As a result of the March 23 meeting, FPL proposes to revise its February ll, 1993, submittal.
A Safety Analysis of the revised amendments request is provided in . FPL has determined that the proposed license amendments do not involve a significant hazard pursuant to 10 CFR 50.92. The no significant hazards determination in support of the proposed Technical Specification change is provided in Attachment 2. Attachment 3 provides the proposed revised Technical Specifications.
In accordance with 10 CFR 50.91 (b)(1), a copy of these proposed license amendments are being forwarded to the State Designee for the State of Florida. The proposed amendments have been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.
FPL requests that the NRC review and approve this amendments request as expeditiously as possible to permit the prompt implementation of organizational changes.
Should there be any questions on this request, please contact us ~
T. F. Plunkett Vice President Turkey Point Nuclear TFP/ew Attachments CC: Stewart D. Ebnetez, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mz. W. A. Passetti, Florida Department of Health and Rehabilitative Services y0 oo ppo Group ooropoop 7" ~~O1 PDR'DOCK 05000250 l P ,
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STATE OF FLORIDA )
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COUNTY OF DADE )
T. F. Plunkett being first duly sworn, deposes and says:
That he is Vice President Turke Point Nuclear Plant, of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.
T. F. Plunkett Subscribed and sworn to before me this day of 1993.
Name of Notary Public (Type or Print)
NOTARY PUBLIC, in and for the County of Dade, State of Florida 6 LLtAN DALE HERBEHlCK i': ~a'- MY COMMSSIN 0 CC 22064S EXP/RES: Augvst 9, 199$
My Commission expires Baehd The Motley PuMc Uddeyyfhfl Commission No.
T. F. Plunkett is personally known to me.
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L-93-108 ATTACHMENT 1 Safety Analysis
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L-93-108 Page 1 of 4 Safet Anal sis Introduction and Purpose To provide additional organizational flexibility, Florida Power 6 Light Company (FPL) proposes to change the Technical that the Opezations Manager either hold or have held a Specifications'equirement Senior Reactor Operator (SRO) License on the Turkey Point Plant, or have held a Senior Reactor Operator License on a similar plant. FPL believes that the proposed changes will result in the Operations depaztment off-shift management organization continuing to meet oz exceed the minimum facility staff qualifications of standard ANSI N18.1-1971 for comparable positions. The basis for FPL's conclusion is discussed below.
The proposed amendments revise Specification 6.0, "Administrative Controls," of the Turkey'Point Units 3 and 4 Technical Specifications.
FPL proposes to require that the Operations Manager either, (1) hold or have held a Senior Reactor Operator License at Turkey Point; or, (2) have held a Senior Reactor Operator License on a similar plant (i.e., another pressurized water reactor); or, (3) have held a Senior Reactor Operator License on a boiling water reactor and completed the Turkey Point Nuclear Plant Senior Management Operations Training Course. A description of, and justification for, these changes are provided below.
Current Requirements Turkey Point Units 3 and 4 Technical Specification 6.2.2.i requires The Operations Manager shall either hold or have held a Senior Reactor Operator License on the Turkey Point Plant, or have held a Senior Reactor Operator License on a similar plant (i.e. another pressurized water reactor).
Discussion To provide additional organizational flexibility, FPL proposes to amend Technical Specification 6.2.2.i. to permit, as an additional qualification condition for filling the Operations Manager position, having held a Senior Reactor Operator's license at a boiling water reactor, coupled with completion of the Turkey Point Nuclear Plant Senior Management Operations Training Course. FPL believes that the proposed changes will result in the Operations department off-shift management organization continuing to meet or exceed the minimum facility staff qualifications of ANSI N18.1-1971 for comparable positions.
FPL's operating organization at Turkey Point Plant is shown in the enclosed organizational chart (Enclosure 1) (Figure 1-2, Appendix A from the NRC-approved FPL Topical Quality Assurance Report (TQAR)).
While the Operations Manager is responsible for the plant's operating organization, his responsibilities also include management of the plant's Health Physics and Chemistry departments. The on-shift Operations organization is supervised by the Operations Supervisor, who is currently required by Technical Specification 6.2.2.h. to hold
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L-93-108 Attachment 1 Page 2 of 4 a Senior Reactor Operator License. The Operations Supervisor and Nuclear Plant Supervisors maintain SRO Licenses on Turkey Point.
The Turkey Point Plant on-shift Operations organization manning requirements aze called out in the Turkey Point Units 3 and 4 Technical Specification Table 6.2-1, MINIMUM SHIFT CREW COMPOSITION.
These minimum shift manning requirements for a two unit site with a common control zoom meet the requirements of 10 CFR 550.54(m) . FPL does not propose to change any shift manning requirements by this proposed change. Additionally, the on-shift and off-shift organizations provide for an individual who meets the requirements of 10 CFR 550.54(l) for a licensed individual who directs the licensed activities of licensed operators.
Standard ANSI N18.1-1971 states that the Operations Manager shall hold a Senior Reactor Operator's License at the time of appointment to the position.,FPL.proposes that the intent of this ANSI guidance can be met by the Operations Manager having operational experience on another power reactor other than Turkey Point. The Operations Manager will have thus gained the operational experience required for the Operations Manager position as well as that required for examination by the NRC for an SRO's license. Additionally, if this experience has been gained at a boiling water reactor, FPL believes that the proposed Technical Specification requirements will ensure that the Operations Manager can meet the training experience normally required for the Operations Manager position as well as that required for examination by the NRC for a SRO's license. The proposed change will permit the Operations Manager to have held an SRO at a boiling water reactor as long as the incumbent has completed the Turkey Point Nuclear Plant Senior Management Operations Training Course. The Turkey Point Nuclear Plant Senior Management Operations Training Course is discussed below.
Turkey Point Nuclear Plant Senior Management Operations Training Course Descri tion
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The Turkey Point Nuclear Plant Senior Management Operations Training Course provides SRO-level training on reactor plant fundamentals, plant systems, procedures, and operating principles to selected senior managers who do not hold an NRC SRO license for Turkey Point Units 3 and 4.
The Turkey Point Nuclear Plant Senior Management Operations Training Course is a tailored training course intended to meet the unique needs of managers at Turkey Point Nuclear who are responsible for the plant s operations, maintenance, engineering, and administration but who will not be completing all requirements foz an SRO license. All training materials used foz the Turkey Point Nuclear Plant Senior Management Operations Training Course have been developed using a Systems Approach to Training (SAT) process.
Ob ective The objective of the Turkey Point Nuclear Plant Senior Management Operations Training Course is to ensure that, upon completion of the course, the student will have successfully demonstrated an
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L-93-108 Page 3 of 4 understanding and knowledge of plant fundamentals, systems, and procedures used in plant operations by on-shift managers. The student also attains a knowledge and understanding of plant response, and the necessary operator actions, to prevent. or mitigate abnormal and emergency conditions. A representative curriculum foz the Turkey Point Nuclear Plant Senior Management Operations Training Course is, enclosed (Enclosure 2). The attached curriculum represents the scope of training recently conducted for this course; the content of the training course will be maintained current using the SAT process.
Achievement of the Turkey Point Nuclear Plant Senior Management Operations Training Course objective is verified by the student's satisfactory completion of a comprehensive written examination that is similar in scope and content to an NRC SRO licensing examination. The student enrolled in the Turkey Point Nuclear Plant Senior Management Operations Training Course is exposed to extensive simulator training and is also required to demonstrate the ability to complete various Job Performance Measures (JPMs) in the plant. A representative listing of JPMs for the Turkey Point Nuclear Plant Senior Management Operations Training Course is enclosed (Enclosure 3).
On completion of the Turkey Point Nuclear Plant Senior Management Operations Training Course, the student receives a certificate of completion indicating that the student has acquired the training normally required for examination by the NRC for a Senior Reactor Operator's license.
~Summar The Turkey Point Nuclear Plant Senior Management Operations Training Course provides SRO-level training on reactor plant fundamentals, plant systems, procedures, and operating principles to selected senior managers who do not hold an NRC SRO license for Turkey Point Units 3 and 4. The training course is tailored to meet the unique needs of managers at Turkey Point Nuclear who are responsible for the plant's operations, maintenance, engineering, and administration. All training materials used for the Turkey Point Nuclear Plant Senior Management Operations Training Course have been developed using the SAT process.
The content of the training course will be maintained current using the SAT process. On completion of the training course, the student receives a certificate of completion indicating that the student has acquired the training normally required for examination by the NRC for a Senior Reactor Operator's license.
Proposed Technical Specifications Changes FPL proposes to change Technical Specification 6.2,2.i. to read as follows (with the proposed changes in bold-face type).
The Operations Manager shall either:
(1) hold or have held a Senior Reactor Operator License on the Turkey Point Plant; oz, (2) have held a Senior Reactor Operator License on a similar plant (i.e., another pressurized water reactor); or, (3) have held a Senior Reactor Operator License on a boiling
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L-93-108 Attachment 1 Page 4 of 4 water reactor and completed the Turkey Point Nuclear Plant Senior Management Operations Training Course.
Justification: The proposed revision to Technical Specification 6.2.2.i. discussed above will ensure that the individual filling the Operations Manager's position has held, at some point in time, an SRO License. This requirement will ensure that the Operations Manager has the operational experience required by ANSI N18.1-1971 for the Operations Manager position as well as that required for examination by the NRC for a Senior Operator's license. Additionally, if this experience has been gained at a boiling water reactor, FPL believes that the proposed Technical Specification requirements will ensure that the Operations Manager can meet the pressurized water reactor training experience normally required for the Operations Manager position as well as that required for examination by the NRC for a
,Senior Operator's license. The proposed change will permit the Operations Manager to have held an SRO at a boiling water reactor as long as the incumbent has completed the Turkey Point Nuclear Plant Senior Management Operations Training Course. This change will permit FPL to exercise additional discretion in the assignment of highly qualified individuals to Operations'anagement positions.
FPL proposes to permit three options for Senior Reactor Operator licensing for the Operations Manager at Turkey Point. Any of these three options meets the intent of ANSI N18.1-1971 with respect to the Operations Manager having the experience and training necessary to successfully and safely direct the activities of the Operations department.
FPL's proposed changes are consistent with the intent of ANSI N18.1-1971 with respect to the standard's guidance for a licensed senior operator in the Operations'rganization off-shift management chain of command. The qualifications guidance of standard ANSI N18.1-1971, as required by Turkey Point Technical Specification 6.3.1, FACILITY STAFF lt "
the individual filling the Operations Manager position has the requisite education, training, and experience for the management position. Additionally, the proposed changes do not impact nor change, in any way, the minimum on-shift manning or qualifications for those individual responsible for the actual licensed operation of the facility. The Operations Supervisor and Nuclear Plant Supervisors maintain SRO Licenses on Turkey Point. FPL's operating organization at Turkey Point Plant is presented in Figure 1-2, Appendix A of the NRC-approved FPL TQAR.
Wt L-93-108 Enclosure 1 to Attachment 1 FPL Topical Quality Assurance Report Appendix A, Figure 1-2
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L-93-108 Enclosure 2 to Attachment 1 Representative Curriculum for the Turkey Point Nuclear Plant Senior Management Operations Training Course
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATION PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE SD-140 MAIN POWER DISTRIBUTION TS SECTION 1 TS SECTION 2 TS 3.8.3 SD-144 125VAC/120VDC DIST.
TS 3.8.2 SD-137 EMERGENCY DIESEL GENERATOR SD-137 EMERG DIESEL GENERATOR TS 3.8.1 ONOP-23.2 EDG FAILURE TS SECTIONS 3.0 & 4.0 SD-170 EMERG LOAD SEQ/STRIPPING SD-139 MAIN GENERATOR & CONTROLS SD-127 MAIN TURBINE CONTROL ONOP-9108.1 MAIN TRANS. MALF.
SD-165 INTAKE COOLING SYSTEM TS 3.7.3-4 SD-132 TURBINE PLANT COOLING WATER ONOP-008 TPCW MALFUNCTION SD-123 CONDENSER & CIRC WATER ONOP-014 LOSS OF COND. VAC.
SD-117 AUXILIARY FEEDWATER SYSTEM TS 3.7.1.2-3, 3.7.1.6 ONOP-7308.1 AFW MALFUNCTION SD-11 STEAM GENERATOR TS 3 '.1.1, .4-5 SD-104 MAIN & EXTRACTION STEAM SD-105 STEAM DUMP SD-153 ASP & FIRE PROTECTION SD-112 CONDENSATE AND FEEDWATER SD-111 FEEDWATER HEATERS & DRAINS SD-68 RADIATION MONITORING & PROT.
TS 3.3.3.1, .5-6, 3.11-12 ONOP-66 ARMS ONOP SD-2 REACTOR VESSEL & INTERNALS SD-3 INCORE INSTRUMENTATION TS'.2.2-3, 3.3.3.2 SD-4 EXCORE NUCLEAR INST TS 3.2.1, 3.2.4 ONOP-59 SERIES NZS MALF.
SD-7 REACTOR COOLANT SYSTEM TS 3.4.1-11 ONOP-41.4 EXCESSIVE RCS ACTIVITY
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATION PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE ONOP-41.3 EXCESSIVE RCS LEAKAGE SD-8 REACTOR COOLANT PUMPS SD-9 PRESSURIZER TS 3.2.5 ONOP-1208.1 PORV MALFUNCTION SD-29 CONT. VENT & HEAT REMOVAL TS 3.6.1, 3.6.4 SD-13 CHEMICAL VOLUME CONTROL TS 3 ' '-2 &
SD-25 CONTAINMENT SPRAY TS 3.6.2-3 SD-28 CNMT POST ACC MON. & PASS TS 3.3.3.3, 3.6.5-6 SD-21 ECCS TS 3.5 SD-6 ROD POSITION INDICATION ONOP-46.1 EMERGENCY BORATION ONOP-47.1 LOSS OF CHRGNG MODE 1-3 ONOP-2608.2 CVCS BORON MALF.
SYSTEMS EXAM 42 SD-5 ROD CONTROL TS 3.1.3.1, ~ 4-6, 3 '0.1-3 ONOP-28 SERIES ROD CNTRL. MALF.
SD-63 REACTOR PROT & SAFEGUARDS TS 3.3.1-2 SD-44 FUEL HANDLING TS 3.9 ONOP-33.3 ACC. INVL. SPENT FUEL ONOP-33.2 REF. CAVITY SEAL FAIL.
SD-40 COMPONENT COOLING WATER TS 3.7.2 ONOP-30 LOSS OF CCW ONOP-3108.2 HIGH ACTIVITY IN CCW ONOP-019 LOSS OF ICW ONOP-1108.1 RCP OFF-NORMAL ONOP-11108.1 PROC. RAD. ONOP SD-121 WATER TREATMENT SD-48 PRI MU & DEMIN WATER ONOP-105 CONTROL ROOM EVACUATION SD-46 PRI SAMPLING SYSTEM SD-47 PRI CHEMISTRY SD-118 SEC SAMPLING & CHEMISTRY SD-49 LIQUID WASTE DISPOSAL SD-50 GASEOUS WASTE DISPOSAL SD-51 SOLID WASTE DISPOSAL
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATION PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE TS 3/4.11 SD-166 VENTILATION & AIR COND SD-164 COMPRESSED GAS SD-133 MAIN GEN GAS AND SEAL OIL SD-130 TURBINE, TURB OIL & GS SD-155 PLANT AIR SYSTEMS SD-41 SFP COOLING AND VENT ONOP-33.1 SFP COOLING MALF.
SD-119 CONDENSATE DEMZNERALZZERS SD-102 SG BLOWDOWN SD-103 SG WET LAYUP/RECZRC SD-106 AUX STEAM & COND RECOVERY "SD-160 SCREENWASH & INTAKE SD-152 PLANT COMMUNICATIONS TS SECTION 6.3 6.5 TS SECTION 6.6 6.10 SYSTEMS EXAM ()3 NUCLEAR PHYSICS CH. 2 (211)
NUCLEAR REACTIONS CH. 3 (211)
NEUTRON PHYSICS CH. 4 (211)
REACTOR PHYSICS CH. 5 (211)
NEUTRON KINETICS CH. 7 (211)
SUBCRITICAL MULT CH. 8 (211)
REACTOR CORE CONSTR CH. 1 (219)
REACT & FTC EFFECTS CH. 2 (219)
MTC & TOTAL PWR DEF CH. 3 (219)
FISSION PROD POISONS CH. 4 (219)
CHEMICAL SHIM CONTROL CH. 5 (219)
CONTROL ROD REACTIVITY CH. 6 (219)
SHUTDOWN REACTIVITY CH ~ 7 (219)
CORE POWER DIST CH. 8 (219)
REACTIVITY CONT OPS CH. 9 (219)
REACTOR HEAT TRANSFER CH. 3 (221)
REACTOR & PRZR THERMO CH. 4 (221)
HEAT EXCHANGERS CH. 5 (221)
STEAM GENERATOR THERMO CH. 6 (221)
TURBINE/THERMO/RANKINE CH.7 (221)
TURB FLUID MECH CH. 8 (221)
PUMP FLUID MECH CH. 10 (221)
DESIGN/OPER LIMITS CH. 13 (221)
COMP FUND MECH SYS COMPONENTS COMP FUND ELECTRICAL SYS COMPONENTS COMP FUND INST, SENSORS &
DETECTORS COMP FUND AIR OPER VALVES &
CONTROLLER
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATION PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE NEUTRON SOURCES, 1/M, SU TECH SPECS REACTOR SU & SUBCRZTICAL MULTIPLICATION REF. REACTIVITY'CC, SDM FUNDAMENTALS COMPREHENSIVE EXAM
- REACTOR START-UPS (3)
GOP-503 CSD TO HSBY GOP-301 HSBY TO POWER
- REACTOR START-UPS (3)
SELF-STUDY FOR SU CERTIFICATION
- REACTOR START-UP
- REACTOR START-UP
- REACTOR START-UP
- REACTOR START-UP SOER 88-2: PREMATURE CRITICALITY
- REACTOR START-UP
- REACTOR START-UP
- REACTOR START-UP EVALUATIONS (2)
GOP-103 POWER TO HSBY GOP-305 HSBY TO CSD
- REACTOR START-UP EVALUATIONS (3)
E-PLAN OVERVIEW NOTIFICATIONS/COMMUNICATIONS EMERGENCY CLASSIFICATIONS TRANS'F CONT. INJURED PERS.
MGT. CONTROL OF EMERGENCIES RAD ASSESSMENTS/PARS TECHNICAL SUPPORT CENTER EP1P-20126 OPERATIONAL SUPPORT CENTER EVACUATION & ACCOUNTABILITY ADM-211 EOP & ONOP USAGE E-0 RX TRIP OR SI ES-O.O REDIAGNOSIS ES-0.1 RX TRIP RESPONSE ES-0.2 NATURAL CIRC COOLDOWN ES-0.3 N/C CD WITH VOID (RVLMS)
ES-0.4 N/C CD WITH VOID (NO RVLMS)
E-1 LOSS OF RX OR SEC COOLANT ES-1.1 SI TERMINATION ES-1.2 POST-LOCA CD ES-1.3 XFER TO COLD LEG RECIRC ES-1.4 XFER TO HOT LEG RECIRC E-2 FAULTED SG ISOLATION ONOP-67 INADV. GAS RELEASE E-3 SG TUBE RUPTURE
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATlON PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE ES-3.1 SGTR CD USING BACKFILL ES-3.2 SGTR CD USING BLOWDOWN ES-3.3 SGTR CD USING STM DUMPS ECA-3.1 SGTR/RCS SUBCOOLED ECA-3.2 SGTR/RCS SATURATED ECA-3.3 SGTR/NO PRES CONTROL ECA-O.O LOSS OF ALL AC ECA-0.1 RECOVERY W/0 SZ ECA-0.2 RECOVERY WITH SI F-0 CSF STATUS TREES FR-S.1,2 ATWS/LOSS OF S/D FR-C.1-3 CORE COOLING FR-H.1-5 SEC HEAT SINK FR-P.1,2 PRES THERMAL SHOCK FR-Z.1-3 CONTAINMENT FR-I . 1-3 INTEGRITY ECA-1.1 LOSS OF EMERG RECIRC ECA-1.2 LOCA OUTSIDE CNMT ECA-2.1 DEPRES OF ALL SG'S SELF-STUDY EOP/EPIP EAXM PREP EPIP/EOP EXAM
- SECONDARY PLANT LOADING
- INADVERTANT REACTOR TRZP ONOP-100 FAST LOAD REDUCTION ONOP-089 TURBINE RUNBACK ONOP-041.3 EXCESSIVE RCS LEAKAGE ONOP-41.5 PRZ PRESS. CNTRL. MALF.
ONOP-004 LOSS OF OFF-SITE POWER
- SECONDARY PLANT LOADING
- FEED REG VALVE FAILURE/ATWS
- GUIDED STUDY / JPMS ONOP-41.6 PRZ LEVEL CONTRL. MALF~
ONOP-208.14 PROT CHANNEL FAILURE
- FEED REG VALVE FAILURE/ATWS
- INADVERTANT SAFETY INJECTION
- LBLOCA
- SBLOCA ONOP-004.2 LOSS OF "A" BUS ONOP-004.3 LOSS OF "B" BUS ONOP-004.4 LOSS OF "C" BUS ONOP-004.5 LOSS OF "D" BUS
- LARGE BREAK LOCA
- STEAM BREAK OUTSIDE CONTAINMENT
- STEAM BREAK ZC/ATWS (IOA DRILL)
- PRESSURIZER STEAM SPACE BREAK ONOP-004.1 REST. FOLLOWING LOOP
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATION PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE ONOP-71 SG TUBE LEAK
- STEAM BREAK INSIDE CONTAINMENT
- LBLOCA/LOSS OF OFFSITE POWER
- LOSS OF ALL FEED ATWS ONOP-046.1 EMERG BORATION ONOP-11108.1 PRMS OFF-NORMAL ONOP-059.X NIS FAILURES
- LOSS OF ALL AC
- STEAM GENERATOR TUBE LEAK ONOP-003.7 LOSS OF 3P07 ONOP-003.4 LOSS OF 3D01
- STEAM BREAK IC/ATWS
- LOSS OF 3P07/FEEDWATER BREAK ZC ONOP-3208.1 LOSS OF RHR INVENTORY ONOP-050 LOSS OF RHR ONOP-019 ICW MALFUNCTION
- SELECTED IOA DRILLS (5)
ONOP-028.X ROD CONTROL MALF'S
- JPMS FOR COLD AND HOT LEG RECIRC
- LOSS OF TURBINE LOAD/ATWS (IOA DRILL)
- LOSS OF TURB LOAD/ATWS (IOA DRILL)
- SBLOCA/ATWS
- STEAM GENERATOR TUBE RUPTURE ONOP-1108.1 RCP MALFUNCTIONS ONOP-047.1 LOSS OF CHG MODE 1-4 ADM-031 INDEPENDENT VERIFICATION
- STEAM BREAK OC (ZOA DRILL)
- LOSS OF ALL AC
- LOSS OF ALL FEED/HEAT SINK
- STEAM BREAK IC/ATWS ADM-200 CONDUCT OF OPERATIONS ADM-215 PLANT SURV TRACKING ADM-212 EQUIP CLEARANCE ORDERS
- STEAM BREAK IC/ATWS/LOSS OF 3A 4KV BUS
- LOSS OF ALL AC/PORV STUCK OPEN
TAA-ABNORMAL TRANSIENT ANAL.
TAA-INTRO TO ACCIDENT ANAL.
- SIMULATOR EVALUATIONS
- SIMULATOR EVALUATIONS
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04/21/93 NUCLEAR MANAGEMENT OPERATIONS TRAINING AND CERTIFICATION PROGRAM TOPIC LISTING
(* On the Simulator)
LESSON TOPIC OR SIMULATOR EXERCISE FINAL COMPREHENSIVE EXAM TAA-INCREASED HEAT REMOVAL ACC.
TAA-DECREASED HEAT REMOVAL ACC.
TAA-PRI REACTIVITY ADD. ACC.
TAA-LOSS OF COOLANT ACC.
TAA-STEAM GEN TUBE RUPTURE TAA-LOSS OF FLOW ACC.
MCD-REACTIVITY AND THERMO (REVIEW)
MCD-SYSTEMS (REVIEW)
MCD-CRITICAL PARAMETERS MCD-PROCEDURES (REVIEW)
MCD-SUBCRITICALITY MCD-CORE COOLING MCD-HEAT SINK MCD-INTEGRITY MCD-CONTAINMENT MCD-ACC RESPONSE OF INSTRUMENTS MCD-CORE ASSESSMENT DAMAGE MCD-RAD. ASPECTS OF CORE DAMAGE TAA/MCD EXAM
L-93-108 Enclosure 3 to Attachment 1 Representative Job Performance Measures (JPMs) for the Turkey Point Nuclear Plant Senior Management Operations Training Course
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02/26/93 SELECTED JPM'S FOR NUCLEAR OPERATIONS MANAGEMENT TRAINING SEQ JPM/MODULE JPM TITLE EXAMINER DATE NO. NUMBER INITIALS
/ /
003 24200016300 RESPOND TO CR EVAC AS INSIDE SNPO / /
006 14200014300 RESPOND TO CR EVAC AS NON-FIRE BRIGADE NPO
/ /
012 01050007300 RESPOND TO LOSS OF RHR W/0 RCP'S / /
013 01050005500 ALIGN FOR COLD LEG RECIRCULATION / /
019 01046029100 SET UP BLENDER FOR AUTO OPERATION / /
034 01028022100 CONDUCT A 1/M PLOT (STARTUP CERT) / /
036 01028010300 PERFORM A DROPPED ROD RECOVERY / /
044 01005023300 POWER B 4KV BUS FROM THE BLACKSTART DESIELS
/ /
045 01005021300 POWER THE C 4KV BUS FROM THE OPP UNIT C TRANS
/ /
047 01005018100 TRANSFER FROM AUX TRANS TO SU TRANS
/ /
054 01062012500 ALXGN SX FOR HOT LEG RECXRC / /
055 01062013500 ALIGN SI FOR COLD LEG RECIRC / /
073 01046054300 PERFORM POST ACCIDENT RCS CHEM INJECTION
/ /
080 02001011400 REPORT SIGNIFICANT EVENTS / /
083 01094001500 PLACE POST ACC HYD MONITOR IN'PER
/ /
086 02016007400 RESPOND TO A PLANT FIRE / /
092 14028020100 PARALLEL MOTOR GENERATOR SETS / /
101 01041064300 VERIFY NAT/CIRC FROM THE ASP / /
104 24094001500 PLACE POST ACC HYD MONITOR IN SER / /
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02/26/93 SELECTED JPM'S FOR NUCLEAR OPERATIONS MANAGEMENT TRAINING SEQ JPM/MODULE JPM TITLE EXAMINER DATE NO. NUMBER INITIALS 108 14200056500 RE-ENERGIZE BU HEATERS ON EDG / /
110 14003026100 TRANSFER INST BUS FROM CVT TO NORMAL INVERTER (EXT)
/ /
112 14005011100 RACK-IN AN A/B 4KV BUS BREAKER / /
115 14005010100 RACK-OUT C 4KV BUS BREAKER / /
128 02001013400 MAKE EMERGENCY NOTIFICATIONS / /
129 02201022400 RESPOND TO A MEDICAL EMERGENCY / /
138 01028012100 PERFORM A REACTOR STARTUP (STARTUP CERT)
/ /
140 02200004300 RESPOND TO CR EVAC NPS / /
141 02200019300 RESPOND TO CR EVAC AS ANPS / /
142 01200011300 RESPOND TO CR EVAC AS UNIT 3 RCO / /
144 01200013300 RESPOND TO CR EVAC AS THIRD RCO / /
146 01041048300 RESPOND TO RCP MOTOR HIGH TEMP i RX PWER )454
/ /
186 01046007101 BORATE THE RCS VIA THE BLENDER / /
191 01028002100 PERFORM AN E.C.C. (STARTUP CERT) / /
247 14003029100 PLACE THE SPARE BATTERY IN SER ON / /
A VITAL BUS 427 02201071100 APPROVE CLEARANCE REQUEST / /
428 02201015100 APPROVE EQUIPMENT CLEARANCE / /
ORDERS 429 02201056100 REVIEW EQUIPMENT CLEARANCE ORDERS / /
430 02201047100 APPROVE TEMPORARY SYSTEM / /
ALTERATION 999 022010524XX CLASSIFY EVENTS (96'03 i 404 i 4 1 1 i / /
412i413i414i OR 415) 999 022010544XX EVALUATE PARS 410)
(13 2 i 4 05 g 4 06 i 407 / /
408, 409 OR
Page No.
02/26/93 SELECTED JPM'S FOR NUCLEAR OPERATIONS MANAGEMENT TRAINING SEQ JPM/MODULE JPM TITLE EXAMINER DATE NO. NUMBER INITIALS
- TEST TYPE MODULE XXXX 0901004 MAINTAIN OVERTIME BOOK / /
XXXX 0901006 AUTHORIZE PLANT WORK ORDERS / /
XXXX 0901007 REVIEW LOCKED VALVE LIST / /
XXXX 0901008 REVIEW SHIFT LOGS / /
XXXX 0901011 CHECK EQUIPMENT STATUS / /
XXXX 0901015 SUPERVISE REFUELING / /
XXXX 0901016 MAKE AUTHORIZATION JUDGEMENT / /
XXXX 0901018 AUTHORIZE CONST WORK PERMIT / /
XXXX 0901019 AUTHORIZE RADIATION WORK PERMIT / /
XXXX 0901020 AUTHORIZE RADIOACTIVE RELEASE / /
XXXX 0901023 AUTHORIZE PROT CHANNEL IN BYPASS / /
XXXX 0901025 AUTHORIZE PROCEDURE CHANGES / /
XXXX 0901027 AUTHORIZE LOAD CHANGE / /
XXXX 0901028 COORDINATE STARTUP / /
XXXX 0901030 AUTHORIZE ACCESS / /
XXXX 0901031 VERIFY CNMT INTEGRITY / /
XXXX 0901032 IDENTIFY/RESPOND TO OFF-NORMAL EVENT
/ /
XXXX 0901038 DIRECT RESPONSE AS EMERG COOR / /
Attachment 2 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION
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L-93-108 Page 1 of 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Description of Proposed License Amendments Turkey Point Units 3 and 4 Technical Specification (TS) 6.3.1 requires each member of the unit staff meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. Besides education and experience requirements, the Operations Manager must hold, or have held, an NRC Senior Reactor Operator (SRO) license on Turkey Point, or have held an SRO License on a similar plant (i.e.
another pzessurized water reactor) per TS 6.2.2.i.
FPL proposes to change Technical Specification 6.2.2.i. to read as follows (with the proposed change in bold-face type).
The Operations Manager shall either:
(1) hold or have held a Senior Reactor Operator License on the Turkey Point Plant; oz, (2) have held a Senior Reactor Operator License on a similar plant (i.e., another pressurized water reactor); or, (3) have held a Senior Reactor Operator License on a boiling water reactor and completed the Turkey Point Nuclear Plant Senior Management Operations Training Course.
Introduction The Nuclear Regulatory Commission has provided standards for determining whether a significant hazards consideration exists (10 CFR 50.92(c)) . A proposed amendment to an operating license for a facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not (l) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new oz different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Each standard is discussed below foz the pzoposed license amendments.
Discussion (l) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The change being proposed is administrative in nature, addresses organizational and personnel qualifications issues, and does not affect assumptions contained in plant safety analyses, the physical design and/or operation of the plant, noz does it affect Technical Specifications that preserve safety analysis assumptions.
The individual Florida Power & Light Company (FPL) chooses to
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L-93-108 Page 2 of 3 fill the position of Operations Manager will have extensive educational and management-level nuclear power experience meeting
,the criteria of standard ANSI N18.1-1971. The Operations Supervisor and Nuclear Plant Supervisors maintain SRO licenses on Turkey Point. The current Technical Specifications do not require the Operations Manager to hold an SRO License at Turkey Point. In fact, the current Technical Specifications permit the Operations Manager to have held an SRO License on a similar plant (i.e.
another pressurized water reactor). The proposed change will continue to require that the Operations Manager has been licensed at another commercial nuclear power plant and that the individual has completed the Turkey Point Nuclear Plant Senior Management Operations Training Course if the incumbent's previous SRO license was held at a.boiling water reactor. The Turkey Point Nuclear Plant Senior Management Operations Training Course ensures that the Operations Manager has the training on plant-specific systems and procedures at Turkey Point.
The on-shift Operations'rganisation is, and will continue to be, supervised and directed by the Operations Supervisor, who is currently required by Technical Specification 6.2.2.h. to hold a Senior Reactor Operator License.
Additionally, the proposed changes do not impact nor change, in any way, the minimum on-shift manning or qualifications for those individuals responsible for the actual licensed operation of the facility.
Based on the above, the proposed changes do not affect the probability oz consequences of accidents pzeviously analyzed.
(2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The change being proposed is administrative in nature, addresses personnel qualifications issues, does not affect assumptions contained in plant safety analyses, the physical design and/or operation of the plant, nor does it affect Technical Specifications that preserve safety analysis assumptions.
The proposed changes address organizational and qualifications issues related to the criteria used for assignment of individuals to the Operations'rganization off-shift management chain of command.
In light of the above, and since the proposed change does not impact nor change, in any way, the minimum on-shift manning or qualifications for those individuals responsible for the actual licensed operation of the facility, operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
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L-93-108 Page 3 of 3 The proposed change addresses organizational and qualifications issues related to the criteria used for assignment of individuals to the Operations'rganization off-shift management chain of command. The proposed change does not impact nor change, in any way, the minimum on-shift manning or qualifications for those individuals responsible for the actual licensed operation of the facility.
FPL's operating organization at Turkey Point Plant is shown on Figure 1-2, Appendix A of the NRC-approved FPL Topical Quality Assurance Report (TQAR) . Since changes to the TQAR are governed by 10 CFR 550.54(a)(3), any changes to the TQAR that reduce commitments previously accepted by the NRC require approval by the NRC prior to implementation.
While the Operations Manager is responsible for the plant's operating organization, his responsibilities also include management of the plant's Health Physics and Chemistry departments. The on-shift Operations'rganization is supervised and directed by the Operations Supervisor, who is required by Technical Specification 6.2.2.h. to hold a Senior Reactor Operator License. The Turkey Point Units 3 and 4 Technical Specifications do not require that the Operations Manager maintain an SRO License (nor even that the incumbent has ever held a Senior Reactor Operator License at Turkey Point) . The qualifications, guidance of standard ANSI N18.1-1971, as required by Turkey Point Technical Specification 6.3.1, FACILITY STAFF UALIFICATIONS, will ensure that, other than license certification, the individual filling the Operations Manager position has the requisite education, training, and experience for the management position.
As a result, operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
Based on the above, FPL has determined that the amendments request does not (1) involve a significant increase in the probability oz consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety; and therefore the proposed changes do not involve a significant hazards consideration as defined in 10 CFR 50.92.
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