ML13263A383
| ML13263A383 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/23/2013 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, NRC/RGN-II |
| Shared Package | |
| ML13263A381 | List: |
| References | |
| Download: ML13263A383 (11) | |
Text
ATTACHMENT 3 - NRC Guidance NUREG-1 0 21, ES-204, C. 1.c, PROCE S SING WAIVERS REQUE STED BY REACTOR OPERATOR AND SENIOR REACTOR OPERATOR APPLICANTS:
Facility licensees having units designed by the same nuclear steam supply system vendor and operated at approximately the same power level may request dual licensing for their operators. Similarly, if the units of a multi-unit facility are nearly identical, the facility licensee may request a waiver of the examination requirements for the second and subsequent units.
In either case, the facility licensee must justify to the NRC that the differences between the units are not so significant that they could affect the operator's ability to operate each unit safely and competently. Further, the facility licensee must submit for NRC review the details of the training and certification program. The analysis and summary of the differences on which the applicants must be trained will include the following, as applicable:
. facility design and systems relevant to control room personnel
. technical specifications
. procedures (primarily abnormal and emergency operating)
. control room design and instrument location
. operational characteristics
. administrative procedures related to conduct of operations at a multi-unit site (e.g., shift manning and response to accidents and fires)
. the expected method of rotating personnel between units and the re-familiarization ftaining to be conducted before an operator assumes responsibility on a new unit 7.2 Regulatory Guide 1.149, C.2, USE OF A SIMULATOR FOR MULTIPLE PLA}[TS If a licensee wishes to use a simulation facility to train or examine operators for more than one nuclear power plant, it must be able to demonstrate to the NRC that the differences between the plants are not so significant that they will result in negative haining. This demonstration should include an analysis and summary of the differences between each plant, including:
- 1. Facility design and systems relevant to control room personnel,
- 2. Technical specifications,
- 3. Procedures, primarily abnormal and emergency operating procedures,
- 4. Control room design and instrument/control location, and
- 5. Operational characteristics.
53
7.3 10CFR55.46 Simulation facilities.
(a) General. This section addresses the use of a simulation facility for the administration of the operating test and plant-referenced simulators to meet experience requirements for applicants for operator and senior operator licenses.
@) Commission-approved simulationfacilities and Commission approval of use of the plant in the administration of the operating test.
(1) Facility licensees that propose to use a simulation facility, other than a plant-referenced simulator, or the plant in the administration of the operating test under
$$ 55.45(b)(1) or 55.45(bx3)o shall request approval from the Commission. This request must include:
(i) A description of the components of the simulation facility intended to be used, or the way the plant would be used for each part of the operating test, unless previously approved; and (ii) A description of the performance tests for the simulation facility as part of the request, and the results of these tests; and (iii) A description of the procedures for maintaining examination and test integrity consistent with the requirements of $ 55.49.
(2) The Commission will approve a simulation facility or use of the plant for administration of operating tests if it finds that the simulation facility and its proposed use, or the proposed use of the plant, are suitable for the conduct of operating tests for the facility licensee's reference plant under $ 55.a5(a).
(c) P I antr efer enc e d s imul at or s.
(l) A plant-referenced simulator used for the administration of the operating test or to meet experience requirements in $ 55.31(a)(5) must demonstrate expected plant response to operator input and to normal, transient, and accident conditions to which the simulator has been designed to respond. The plant-referenced simulator must be designed and implemented so that it:
(i) Is sufficient in scope and fidelity to allow conduct of the evolutions listed in $$
55.a5(a)(1) through (13), and 55.59(c)(3)(iXA) through (AA), as applicable to the design ofthe reference plant.
(ii) Allows for the completion of control manipulations for operator license applicants.
(2) Facility licensees that propose to use a plant-referenced simulator to meet the control manipulation requirements in $ 55.31(a)(5) must ensure that:
(i) The plant-referenced simulator utilizes models relating to nuclear and thermal-hydraulic characteristics that replicate the most recent core load in the nuclear power reference plant for which a license is being sought; and (ii) Simulator fidelity has been demonstrated so that significant control manipulations are completed without procedural exceptions, simulator performance exceptions, or deviation from the approved training scenario sequence.
(3) A simulation facility consisting solely of a plant-referenced simulator must meet the requirements of paragraph (c)(1) of this section and the criteria in paragraphs (d)(1) and (4) of this section for the Commission to accept the plant-referenced simulator for conducting operating tests as described in $ 55.a5(a) of this part, requalification training as described in $ 55.59(c)(3) of this part, or for performing control manipulations that affect reactivity to establish eligibility for an operator's license as described in $
ss.3l (a)(s).
54
7.4 10CFR50.120 Training And Qualification Of Nuclear Power Plant Personnel and 10CFR55 Operators' Licenses speciff the systems approach to training (SAT) by which applicants and licensees shall develop, implement, and evaluate personnel training programs. Consistent with the SAT process, each applicant and licensee is required to include the following key elements in its training programs: (1) analysis ofjob performance requirements and training needs, (2) derivation of learning objectives based upon the preceding analysis, (3) design and implementation of the training program based upon the learning objectives, (4) trainee evaluation, and (5) program evaluation and revision based upon the preceding evaluations.
55
ATTACHMENT 4 - Acronyms NE Architecture Engineer AEH Analog Electro-Hydraulic AMSAC (ATWS) Mitigating System Actuating Circuitry AOI Abnormal Operating Instructions ATWS Anticipated Transient Without SCRAM AUO Non-Licensed Operator BEACON Best Estimate Analysis of Core Operations BOP Balance of Plant CAP Corrective Action Program CATD Corrective Action Trackitrg Documents COMS Cold Overpressure Mitigation System DCS Distributed Control System DCN Design Change Notice DSEP Detailed Scoping Estimating and Planning EDCR Engineering Document Construction Release EOI Emergency Operating Instructions EP Emergency Preparedness FSAR Final Safety Analysis Report GO General Operating Procedures GPM Gallons per Minute HFE Human Factors Engineering UA Intelligent Automation ICCM Inadequate Core Cooling Monitoring System ICS Integrated Computer System ILT Initial License Training JFG Job Familiarization Guide JPM Job Performance Measure LEFM Leading Edge Flow Meter LOR Licensed Operator Requalif,rcation Training MCR Main Control Room MFP/MFPT Main Feedwater Pump / Main Feedwater Pump Turbine MFW Main Feedwater MCR Main Control Room NCO Nuclear Central Office Tracking Items NIS Nuclear Instrumentation System NSSS Nuclear Steam Supply System OJT On-the-Job Training OL Operating License PAMS Post Accident Monitoring System PASS Post Accident Sampling System PDMS Power Distribution Monitoring System PER Problem Evaluation Report PORV Power Operated Relief Valve PPM Parts per Million RO Reactor Operator RVLIS Reactor Vessel Level Indication System SM Shift Manager SOI Standard Operating Instructions 56
SP Special Programs SQN Sequoyah Nuclear Plant SR Surveillance Requirements, also Service Report SRO Senior Reactor Operator STA Shift Technical Advisor TNA Training Needs Analysis TPBARs Tritium Producing Burnable Absorber Rods TPE Training Performance Evaluation TRM Technical Requirements Manual TSM Technical Specification Monitor TVA Tennessee Valley Authority UPS Unintemrptible Power Supply WBN Watts Bar Nuclear Plant WINCISE Westinghouse ln-Core Information Surveillance & Engineering 57
ATTACHMENT 5 - Unit Comparison Control Room Photos M-l Auxiliarv Power ES\\\\= L n*"*"-l f*
Jn ft*
- r1r, tt{rt i'*{rt
+r
- ,,*l qrr
- ilI l+'tr? Jry 3Ir
- {J UI\\IT 1 M-l Auxiliarv Power
- '*I*I, l"*rr,,t*]:
ftr rf{
-I.-J I
IRTF rn-\\
UNIT 1 N f-z Turbine Generator Control N{-2 Turbine Generator Control UNIT 2
UNIT 1 M-3 Feedwater & Condensate UNIT 2 M-3 Feedwater & Condensate
M-4 Reactor Control UNIT 2 M-4 Reactor Control 61
Rea cto r C9
-ql f_nf. Syste g M-5 Reactor Coolant Svstem ffiffi
UNIT 1 M-6 left) En eered Saf ards and Aux Systems
- ffiffiffi rn ru m
hH
'l*':"
UNIT 2 M-6 (left) Engineered Safeguards and Aux Systems Itr ffi
,ffin ffiilil ffiffiffi F
E
,E irl{i.rc{T"ta Sffil Inee rrmpn ffiffi
'!dloL* {*1*t*
U*t*-Lt