ML13263A384

September 2013 Differences and Training Plan Report, Table of Contents Through Page 52

ML13263A384
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: ML13263A371 ML13263A383 ML13263A384
References
Download: ML13263A384 (51)

Text

1.

2.

Table of Contents Tagrg Or CONTENTS EXECUTIVE

SUMMARY

1.1 REGULAToRY CoxsrnnnlrroN...........

...........................3 1.2 UNrr 2 DTFFERENCnS Ovonvrnw................

....................5 TABLE I:UNn l/UNIT2 DIFFERENCSS OvTRvEw 5

1.3 TRATNTNG PLAN SuMMARy............

.............7 WATTS BARANALYSIS OF UNIT l AND UNIT 2 DIFFERENCES 2.1 Colrrnol oF DEsrcN DIFFERENCES................

...............9 2.2 NEARLYIotnrrcar, 2.3 NEARLy IDENTTcAL JusrrFrcATroN.............

................12 2.3.I FACILITY DESICN ANO SYSTEI\\4S RELEVANT TO CONTROT ROOM PERSONNEL 12 2.3.2 TEcHNTcAL SpBcmrcarroNs 12 2.3.3 PRocEDURES (AnNonver AND EMERGENcv PRocEounrs) 14 2.3.4 CONTROLROOMDESIGNANDINSTRUMENTLOCATION 14 2.3.5 OpsRArroNer CnenecreRrsrrcs 17 2.3.6 ADMTNISTRATTVE PRoCEDURES RELATED To CoNDUCT oT OpnRRnoNs FoR A MULTI-UNIT SITE 20 2.3.7 EXPECTED METHoD oF RoTATTNG PERSoNNEL BETWEEN UMTS AND RE-FAMILIARIZATIoN TRAINING To BE CoNDUCTED BEFoRE ASSUMING DUTY oN THE NEw UNIT 2I TRAINING AND OUALIFICATION PLAN 22 3.2 TRArNrNGPLANAssuMprroNs.......

,,........24 3.3 DEscRIprIoN oF TRATNING AND QUALIFTCATTON PLAN FoR PERSoNNET, Cunnpxrl,y LICENSED oN 3.

3.4 DnscRrprroN oF TRATNTNG AND Quar,rrrcarroN PLAN FoR IN PRocREss INrrrAL LrcENsE CLAss 3.3.1 LTCENSED OPERAToR REeuALrFrcATroN (LOR) TRAn[Nc PLAN DESTGN 3.3.2 LORTRATNTNG[,I-AN Sutr,ttrrenv 3.3.3 LOREXAMTNATIoN IMPACT oF PLANNED SnuuIRToR MoDIFICATIoNS 3.4.1 INrrrAL LrcENsE TRATNTNG (ILT) PLAN DEsrcN 3.4.2 ILTTRAINTNG PLAN

SUMMARY

3.4.3 ILT EXAMTNATION IMPACT OF PLANNED SIMULAToR MoDIFIcATIoNS 3.5.1 SrrrrurAToR CoNprcuRATroN PraN DpsrcN 3.5.2 STUIATOR CONpTGURATIoN PrnN SuuuARY TAnTB 2: DMT.ERENCES TRAINING Scopp, DURATIoN, AND ScUBnULE ATTACHMENT 2 -TPCHNICAL SPECIFICATIONS Dm.BneNCES ATTACHMENT 3 -NRC GUTDANCE ATTACHMENT 4-AcRoNYMS ATTACHMENT 5 _ UNIT COMPARISON CONTROL ROOI,T PTTOTOS FIGURE 1 _ INTEGRATED TIMELINE FIGURE 2 _ CoNrnoL RooM Lnyour 24 25 27 29 29 31 50 s3 56 58 73 74 27 28 28 3.5 MATNTATNTNc SruularoR ALTcNMENT wrrH THE RETERENcE UNrr 1..................

.............29 ATTACHMENT 1 _ DETAILED CoNTRoL RooM DESIGN AND INSTRT]MENT LocATIoN UNIT DIFFERENCES 33

L. Executive Summary This report confirms the criteria ofNUREG 1021; section ES 204 which defines utility requests for dual unit licenses for the licensed operators of the facility. Part of that request is to justiff why the utility believes the two units are "nearly identical" and to describe the training plan for operators to inform them of any existing unit differences. In addition this report provides the analysis required by Regulatory Guide 1.I49, C.2 - Use of Simulation Facility for Multiple Plants. Watts Bar intends to use its plant-referenced simulator (unit 1) to train and or examine operators and senior operators for more than one nuclear power plant (other than the reference plant), in this case WBN 2 in support of a dual unit license.

[n2007 Tennessee Valley Authority (TVA) decided to recommence construction on Watts Bar unit 2. During the lead up to this decision and continuing into construction activities, TVA management put in place expectations that the design and construction groups would maintain fidelity between Unit 1 and Unit 2. This expectation was enforced through memorandum, procedures and processes, which required all parties to ensure that Unit 2 would match Unit 1 to every extent possible.

This report justifies the TVA conclusion that the two units at Watts Bar are "nearly identical" and details a comprehensive dual unit license ffaining plan for Unit 1 licensed operators and operators currently in training for a license. This report provides assurance that the simulator maintains fidelity with its plant-referenced unit. Therefore, TVA requests NRC review and approval of the included training plan and based on this approval, TVA plans to submit 'dual unit' license applications (Multi Unit Amended to Include Additional Unit) with waivers of NRC administered written and operating examinations where appropriate.

1.1.1 Regulatory Consideration This plan provides the outline and approach to obtaining dual-unit operator licenses to support the loading of fuel at the Watts Bar Unit 2 nuclear station.

This is a two-step process as outlined in NUREG 1021, ES-204 which states, in part, that:

1. Facilities may request dual licensing for their operators.

2. Facilities may request a waiver of the examination requirement for the second unit.

In either case the facility must justiff that the units are'hearly identical" including:

o facility design and systems relevant to control room personnel (ES-204, RG 1.r49) o technical specifications (ES-204, RG 1.149) o procedures (mainly abnormal and emergency procedures) (ES-204, RG I.I49) o conffol room design and instrument location (ES-204, RG 1.149) o operational characteristics (ES-204, RG 1.149)

o administrative procedures related to conduct of operations for a multi-unit site (ES-204) o expected method of rotating personnel between units and re-familiarization training to be conducted before assuming duty on the new unit (ES-204)

1.1.2 Unit2 Differences Overview The design of Unit 2 was conducted with the constraint of maintaining unit differences at a minimum. Accordingly, every effort was made to minimize differences between the units when installing new components on Unit2, due to obsolescence of those components on Unit l. With Unit 2 design established, a thorough analysis of the unit differences has shown that the units remain nearly identical. Some of the differences are listed here and are discussed in more detail in Section 2.

Table 1 provides an executive summary of the main differences between Units I and2.

Table 1: Unit 1 lUnit 2 Differences Overview Steam I Unit I has the 68AXP Replacement Steam Generator. Unit2 has the D-3 Generators I Original Steam Generator.

(Photos not to scale)

Steam Generator Cross Section Steam Ouflet Uilr-:*:r Fl;rr rovvr

$rlr)* Rrlta0(: L giffi TtrF

$+r':sil a.\\

t

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["rir;r*vy Cuol*tt{

tlflnrl+s Unit L 68AXP hr. :j, tfrp(rrt Trrl:t s f-e cti'*.;rler f.lurrlio AuxFeedruater &B\\?

Main Fduu lnlet Steam Separators Preheater Outlet Freheater Sec'lion Main Feedruater lnlet Preheeter Or:tlet Primary C oolant lnlet U nit 2 D-3 Main Turbine The Unit 2 turbine has been upgraded to improve efficiency and power output and is more tolerant to condenser backpressure.

The Unit 2 turbine has no impulse chamber. A tap and pressure transmitter will be added to each of the four inlet lines from the control valves. For the urpose of input to rod control, steam dumps and turbine runback, the

control signal will be the median of four signals.

Moisture Separator Reheaters The secondary side Moisture Separator/Reheaters (MSR) for Unit 2 are an upgraded design to support the new Main Turbine.

Reactor Vessel Level Indication System (RVLTS) and Inadequate Core Cooling Monitor (rccM -

86)

Common Q Core Exit Thermo -

couples, RVLIS, and Core Saturation Monitor Unit I uses the RVLIS ICCM-86 system.

Unit2 will use the upgraded Common Qualified (Common Q) PostAccident Monitoring System (PAMS).

Reactor Fuel Unit 1 will have a steady state fuel load. Unit 2will have a new core. Unit I will have Tritium Producine Burnable Absorbers and Unit 2 will not.

Incore Probes Unit 1 uses Westinghouse movable probes.

Unit 2 will use the Westinghouse In-Core Information Surveillance &

Engineering (WINCISE) system (Incore fixed sensors).

1.1.3 Training Plan Summary o Plant and training staff used a systematic analysis to identiff the knowledge and skills for presentation in differences training for Unit 2. Licensed Operator Requalification (LOR) training covers operations of dual unit common systems, unit differences, Unit 2 procedures and Technical Specifications. The training will consist of classroom lectures, simulator demonstration and skill practice, Job Familiarization Guides and Task-Performance-Evaluation. This training will take place from January 2014 through August 2014 including the submittal for dual unit licenses for Unit 1 licensed operators. Additional training will continue through Unit2 hot functional testing, fuel load, initial criticality and start up testing, but will not be credited towards the request for dual unit licenses, since it occurs after the license application submittal.

o Watts Bar staff, with NRC approval of the Training Plan, will conduct comprehensive operator testing, both written and performance, for Ufit2 in lieu of NRC administered license exams in meeting 10CFR55.

o TVA has evaluated the ability to provide simulation capabilities for plant differences that will exist at the startup of Unit 2 using the Watts Bar simulator.

o The simulator has the capability of using temporary computer models for the original (D-3) steam generators which will be used for training the operators prior to Unit2 fuel load.

o The simulator has the capability of using temporary computer models for the initial core load which will be used for haining the operators prior to Unit2 fuel load.

o The Watts Bar simulator was initially upgraded to Distributed Control System (DCS) in January 2012. Subsequently, the Unit 1 plant was upgraded to DCS for the Steam Generator Level Control System in October 2012.The simulator will install additional DCS control in December 2013 and the Unit I plant will install these additional DCS controls in April2014 during RFO 12. The timing of the simulator upgrades allowed for a continuation of training on digital distributed controls prior to Unit2 hot functional testing, fuel load, start-up testing, power-ascension and prior to implementation of DCS on Unit 1 plant. This upgrade schedule provided additional reinforcement and proficiency on the DCS system.

Note: Initiol license classes are numbered with the year and month the class is scheduled to take the NRC exam when the class starts, i.e., class I 1-06 originally scheduled to tal(e the NRC exam in June of 201 I.

o Initial License Training (ILT) Class 13-10 is scheduled for their NRC Examinations in October 2013 which is prior to Unit 2 early fuel load of December 2014. This class will train and examine on the Unit I referenced simulator and their license applications will request a Unit 1 License. After receipt of their NRC licenses, these individuals will complete the LOR Unit Differences Training and examination described in section 3.0 of this report.

ILT Class 15-06 is scheduled for their NRC Examinations in 2015 which is after Unit 2 fuel load in December 2014. These students will be trained on Unit 1 and Unit2 differences, during the course of their ILT class. This class will submit License Applications for a Dual Unit License.

Note: The Site Training Director shall plan in the Corrective Action Program receives dual unit licenses from NRC.

document deviations from this training until Initial License Training Class L5-06

2. Watts Bar Analysis of Unit 1 and Unit 2 Design Differences 2.1.1 Control of Design Differences TVA suspended construction of Watts Bar Nuclear (WBN) Unit2 in 1985, placed the unit in construction layup status, and formally defened WBN Unit2 in 2000. In2007 TVA decided to recommence construction on Watts Bar Unit 2. During the lead up to this decision and continuing into construction activities, TVA management put in place expectations that the design and construction groups would maintain fidelity between Unit 1 and Unit 2. This expectation was enforced through memorandum, procedures and processes, which required all parties to ensure that Unit 2 would match Unit 1 to every extent possible. The intent to maintain fidelity between units is spelled out in communications internal to TVA and also in communications to the NRC as demonstrated by the following; In a letter dated April 3, 2007 (L44 070403 00 I ) TVA asked for feedback from the NRC on certain assumptions TVA was making in the time leading up to a final decision to recommence construction on Unit2. TVA describes one assumption as being able to resume construction and "...use the existing Part 50 construction permit and the largely completed and well documented operating license review framework. This is the first key regulatory assumption. This first key regulatory assumption is grounded on the fact that WBN 2 is of the same vintage and will be virtually identical to WBN Unit 1. From a regulatory perspective, this means that the WBN Unit2licensing and design basis will be essentially the same as what presently exists for WBN Unit 1."

In a letter from the NRC to TVA dated July 25,2007 (Staff Requirements-SECY 0096-Possible Reactivation of Construction and Licensing Activities for the Watts Bar Nuclear Plant Unit 2), the NRC stated:

"The Commission supports a licensing review approach that employs the current licensing basis for Unit las the reference basis for the review and licensing of Unit2;'

In a letter from TVA to the NRC dated August 3,2007, titled "Watts Bar Nuclear Plant (WBN) - Unit 2 - Reactivation of Construction Activities" the following excerpts demonstrate TVA's intent to keep the two units similar:

"As background, on October 4,1976, TVA submitted a dual unit WBN Operating License (OL) for both WBN Unit I and Unit 2. WBN Unit I received a full power OL on February 7,1996. WBN Unit2 which was placed on deferred status would be operationally the same as Unit I at startup. TVA believes that, from regulatory, safety and plant operational perspectives, significant benefit is gained from aligning the licensing and design bases of WBN Units 1 and2 to the fullest extent practicable. The commission recognized these benefits in Reference 2."

(Reference 2 in this letter is referring to the NRC letter discussed above dated July 25,2007)

"In furtherance of this objective, TVA will complete WBN Unit2 in compliance with applicable regulations promulgated prior to and after the issuance of the WBN Unit I OL. In addition, the WBN Unit2licensing and design bases will incorporate modifications made to WBN Unit l, and those modifications currently captured in the WBN Unit I five-year plan. This alignment of the WBN Unit 1 and 2 licensing and design bases will ensure that there is operational fidelity between units and at the same time demonstrate and ensure that WBN Unit2 complies with applicable NRC regulatory requirements."

The Watts Bar Detailed Scoping, Estimating, and Planning (DSEP) study dated 06118107, provided guidance for the continuation of construction of Watts Bar Unit2 as follows:

"The Engineering Baseline and Modification organizations will prepare design criteria, design calculations, procurement and installation specifications, develop drawings and specifications, and issue procurement documents that provide detailed design for construction as required for completing WBN2. While Engineering work will be performed to the AIE's procedures, calculations and DCNs will conform to TVA's Engineering Change Control and Plant Modification procedures with an emphasis on ensuring fidelity with Unit 1."

(bolded emphasis was added)

The Watts Bar Unit I and 2 Memorandum of Understandins, which defines the division of responsibilities between unit I and unit 2, under the Design Engineering Interface, states:

"One of the goals of the Unit2 completion is to maintain as much consistency in configuration and processes with unit I as possible. Unit2 will develop requirements and a means for tracking differences that exist or are created between the two units. Part of the Unit2 scoping process will be to evaluate the as-constructed Unit 1 configuration against the Unit 2 as-designed configuration and Unit 2 walkdown results to determine what physical changes are required to Unit 2 to maintain configuration consistency. Differences between the two units will be reviewed and agreed upon by the two units."

The following provides an example of the management processes in place during Unit2 construction; the construction contractor had an Engineering procedure @!--3DP-"

G04G-00081) which required any differences between the units to be documented and reviewed by Operations, Maintenance and Engineering organizations. Part of this review process also included analysis of the differences for inclusion into the operator differences training.

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Unit I modifications were reviewed and a Unit 2 scope work list was developed from this review. For each Corrective Action Program (CAP) and Special Program (SP) a plan for Unit2 was developed to implement the changes associated with each program based upon a review of Problem Evaluation Reports (PER), Nuclear Central Office Tracking items (NCO), Corrective Action Tracking Documents (CATD), and Unit I corrective actions. Engineering Document Construction Releases (EDCR) were issued for the CAPs and SPs based on this review.

Due to equipment obsolescence some new designs for Unit 2were needed (e.g., Foxboro Distributed Control System (DCS), Unit2 Annunciator, Rosemount Transmitters).

Unit2 designs were evaluated for any unit differences with Unit 1. These differences were reviewed and approved by TVA operations, maintenance, and engineering groups.

As documented in the examples given above, during design and construction activities, every effort was made to minimize differences between the units. When installing new components on Unit 2 due to obsolescence of those components on Unit 1, similar controller type and sizes were used, wherever possible, to keep the control and indication locations the same on the Unit2 Main Control Panels.

2.1.2 Nearly Identical Summary This section will provide a brief overview of how the two units at Watts Bar have been determined to be "nearly identical", as the terminology in NUREG 1021 states. More detail follows in section 2.3.

o The units consist of identical nuclear steam supply system (NSSS) vendor designs and secondary plant designs. Unit 2will include the original D-3 steam generators. Unit I has installed 68AXP replacement steam generators.

o Initially, the units will have different core operating characteristics with Unit 1 being in a normal firsVsecond/third burn assembly fuel cycle. Unrt2 will consist of all first burn assemblies.

o Unit I uses Westinghouse movable incore probes. Unit2 will use WINCISE fixed sensors, which also house the Core Exit Thermocouples (CET).

o Unit I uses the RVLIS (ICCM-86) system for Reactor vessel level and subcooling monitoring. Unit 2wlll use the Common Q system. The Common Q system has slightly different mimics but the same information is displayed.

o The Technical Specifications and structure of the Emergency Operating Procedures (EOP) developed for Unit 2 will be nearly identical to those already in use for Unit 1.

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2.1.3 Nearly ldentical Justification This section includes the analysis and the nearly identical justification performed by Watts Bar to meet NUREG I02I, ES-204 / Regulatory Guide 1.149 guidance as listed below and will follow the format of the bulleted items listed in the NUREG.

2.1.4 Facility Design and Systems Relevant to Control Room Personnel Watts Bar has thoroughly reviewed the Unit 1 and Unit 2 Facility Design and Systems Relevant to Control Room Personnel and has determined that they are nearly identical based on the following nominal differences.

2.1.4.a The WBN Unit I steam generators were replaced. Unit 1 Steam Generators have a larger heat transfer area. The Unit 1 Heat transfer coefficient is slightly less than that of Unit 2, however, the higher tube volume and more surface area results in a higher Steam pressure and temperature at the same power level.

2.1.4.a.1 The Unit 2 generators are the original D-3 model, which has some operationally different setpoints.

There are differences between the units in their operational response to a Steam Generator Tube Rupture (SGTR) with regard to event milestone times and due to the elevation difference of the U tube bundle. Emergency Operating Procedures adequately mitigate the difference in response between the units. See section2.3.3 and 2.3.5.c.5 for more detail.

2.1.4.a.2 2.I.4.b The Unit 2 main turbine has been upgraded to improve efficiency and power output and is more tolerant to condenser backpressure.

This turbine has no impulse chamber. A pressure transmitter willbe added to each of the four inlet lines from the control valves to monitor the High Pressure Turbine Inlet Pressure which varies similarly to 1" stage impulse pressure. For the purpose of input to rod control, steam dumps and turbine runback, the control signal will be the higher median of four signals.

2.1.4.c The Unit 1 turbine has an impulse chamber and utilizes three pressure transmitters for generating control signals.

2.1.4.d The Unit 2 MSRs are an upgraded design to support the new Main Turbine. The Unit 2MainFeedwater Pump Turbines are connected to MSRs A-2 and B-2 as opposed to MSRs A-1 and B-1 on Unit 1.

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2.I.4.e The Unit 1 Inadequate Core Cooling Monitoring System (ICCM 86) for will be replaced with the Common Q platform for Unit 2.

Parameters present in the ICCM 86 will be replicated in the Common Q Post Accident Monitoring System (PAM) including Core Exit Thermocouple (CET) temperature, RVLIS, and Core Saturation Monitor.

2.1.4.f The Unit 2 incore probes will be WINCISE fixed probes as opposed to the Unit I Westinghouse movable probes. The WINCISE probes will also house the CETs. The WINCISE CET location will cause the forced flow at power indicated temperature to be slightly lower than Unit lbut will not impact post accident temperatures or EOP setpoints.

2.1.4.9 Unit I will complete the installation of DCS during Refuel Outage 12in2014. The Unit 1 DCS upgrade eliminates many operational differences, addresses obsolescent equipment issues, and deletes as many single points of failure as practical. Post outage the operational difference between the units will be DCS hotwell level conftol Unit2 only, a few annunciator windows, and the MCR Center Work Desk Area Displays. See Attachment 1 for detail referenced to EDCR 52378.

2.1.4.h Unit2 will eliminate the Post Accident Sampling System (PASS) and physically remove the associated equipment. Unit t has abandoned the PASS system in place.

2.1.4.i There will be only one Hydrogen Analyzer for Unit 2 anditwill be non-safety related.

2.I.4j The hydrogen recombiners on Unit t have been removed from Technical Specifications. The recombiner handswitches for Unit 1 are still on the control room panel 1-M-10. The hydrogen recombiners on Unit 2willbe abandoned in place and the handswitches in the control room have been removed from panel2-M-10.

2.1.5 Technical Specifications Watts Bar Unit 1 and Unit 2have separate Technical Specification(s) (TS) and Technical Requirements Manual (TRM).TVA used the WBN Unit 1 TS and TRM to develop the proposed WBN Unit2 TS and TRM. The numbers, setpoints, and parameters provided have been validated through the design phase of the construction completion project. All Nuclear Steam Supply System (NSSS) setpoints are identical; therefore TS related setpoints will be identical between the units. Final verification will be provided as part of the "as-built" phase of construction completion of WBN Unit 2.

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Watts Bar has thoroughly reviewed the Technical Specifications differences and determined that they are nearly identical based on minimal differences. Attachment 2 provides a detailed discussion for each of the identified technical specification differences.

2.1.6 Procedures (Abnormal and Emergency Procedures)

Watts Bar has thoroughly reviewed the Unit 1 abnormal and emergency procedures against the intended structure and content of the Unit2 procedures and has determined that they are nearly identical.

The Unit 2 Emergency Operating Instructions (EOIs) were developed to the same revision level and the exact format as the suite of Unit 1 EOIs currently in use today. The EOIs are symptom-based procedures and there is no change in logic for implementation as a result ofany differences in design and control.

In the case of a narrow range of SGTRs on unit l, with reactor coolant pumps running, the isolated steam generator may depressurize during subsequent cool down and require a transition from the optimal EOl to a contingency EOI. This does not occur on Unit 2.

However, the EOIs adequately mitigate the difference in response between the Units.

The majority of the setpoint calculations pertaining to EOI actions have been completed at this time. As remaining setpoint data is received, any differences will be rolled into the scheduled operator training. Based on completed calculations, these setpoint differences are not significant. Unit specific EOIs were developed to prevent human errors related to combining Unit procedure steps.

The Unit 2 Abnormal Operating Instructions (AOIs) were developed to the same revision level and two-column format as the suite of AOIs utilized to operate Unit 1. A numbering system is in place to allow for Unit specific AOIs, where needed, to prevent human effors related to combining Unit procedure steps. The majority of the AOIs have been written and entry conditions and symptoms described in the AOIs are the same for Unit 2 as for Unit 1.

2.1.7 Control Room Design and Instrument Location Watts Bar has thoroughly reviewed the control room design and instrument locations and determined that they are nearly identical.

The Unit 2 Main Control Board layout is a rotated image of the Unit 1 Main Control Boards. On panels M-l through M-6, the left-right relationship for controls and indications is nearly identical.

The DCN and EDCR processes both require a Human Factors Engineering evaluation and a Unit Differences evaluation which are directed at minimizing the impact of operational differences between the units.

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The following provides an overview of the identified control room design and instrument location differences. Attachment I provides specific panel details.

2.I.7.a Main Control Board Pan el 2-M-I "Auxiliarv Power" 2.I.7.a.I Main Control Room panel 2-M-1 has an ICS display monrtor 2-MON-47 -120. This monitor duplicates the functionality of obsolete recorders 2-TR-47 -l and 2-TR-47 -2. On Unit I these recorders (l-TR-47-I and 1-TR-47-2) were abandoned and the inputs to these recorders were provided to the plant integrated computer system (ICS).

2.1.7.b Main Control Board Panel 2-M-3 "Feedu,ater and Condensate" 2.r.7.b.r Hand switch 2-HS-3-45 is a 4-position switch to warm the main feedwater lines through forward and back flush operations. The Unit 1 STEAM GENERATORS were replaced, which eliminated the need for back flush operations: 1-HS-3 -45 is a two-position switch, without the back flush operation mode.

Status light box 2-XX-3-235 retains additional lights related to back flushing operations for the Unit 2 steam generators.

2.I.7.c Main Control Board Panel 2-M-4 "Reactor Controls" 2.I.7.c.l 2,1.7.d 2.1.7.d.l 2.I.7.e 2.I.l.e.I Core Exit Temperature recorder 2-TR-94-1 0 1, switch 2-XS 101, and RVLIS indicator 2-XI-68-100 will not be installed on2-M-4. The new COMMON Q display 2-MON-68-100 will perform these functions for Unrt 2.

Main Control Board Panel 2-M:5. "Reactor Coolant Systenl" No operationally significant differences.

Main Control Board Panel 2-M-6 "Engineered Safeguards" (2-M-6 Right Halfl (2-M-6 Left Halfl The Cold Leg Accumulators group of indicators (LI-63 -129, -

ll9, - 109, -99, -89, -8 I, -82, and -60 and PI-63 -I28, - 126, - 108, -

106, -88, 86, -6I, and -6I) are located below the new COMMON Q driver RVLIS - ICCM monitor (2-MON-68-110) on panel2-M-6. On Unit, I these indicators are located above RVLIS display (1-XI-68-110) on l-M-6. This was done to fit the new l5-inch COMMON Q display.

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2.I.7.e.2 Incore flux / temperature recorder TR-94-102 is not installed on panel2-M-6. This instrumentation will be handled through COMMON Q monitor 2-MON-68-110 on 2-M-6 which replaces the functions supported by XI-68-l10, XS-68-111, and TR 102 on 1-M-6.

2.1.7.f Main Control Board Panel 2-M-l0 Temperaturc Monitorins 2.1.7.f.1 One of the Hydrogen Analyzers is being eliminated.

2.1.7.9 Main Control Board Panel 2-M-l I Sparc (Generator Corc Condition Monitor-Unit l) 2.1.7.g.I The Hydrogen Purity Meter will be eliminated and placed on ICS.

2.I.7.h Main Control Board Panel 0-M-12 (Common Panel) 2.1.7.h.l The following Radiation Monitors replaced with Digital Units:

2-RM-90-002 Personal Access Area Monitor (Personnel Airlock) 2-RM-90-059 Upper Cntmt Area Monitor (Hatch) 2-RM-90-060 Upper Cntmt Area Monitor (Airlock) 2-RM-90-061 Incore Instrumentation Room o 2-RM-90-106 Lower Cntmt Air o 2-RM-90-l I2Upper Cntmt Air o 2-RM-90-119 Condenser Vacuum Exhaust o 2-RM-90-120 Steam Generator Building Effluent o 2-RM-90-121 Steam Generator Building Effluent 2.1.7.i Main Control Board Panel2-M-13 Excore Neutron Instrumentation 2.1.7.i.1 The Source and Intermediate Range Detectors will be replaced with upgraded instruments that contain digital indications in place of the Unit 1 analog meters.

-2.I.7 j Main Control Board Panel2-M-18 Westinshouse lncore Instrurnentation 2.1.7 j.L The movable Incore Probes have been replaced with WINCISE and removed from 2-M-18.

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2.I.7.k Main Control Board Panel 2-MJIA Appendix R 2.1.7.k.l No operationally significant differences.

2.1.7.I Main Control Board Panel

( Radiation) MoniJgri ng 2-M-30 Post Accident and SG 2.r.l.l.I The followitrg Radiation Monitors replaced with Digital Units 2-RM 255 Condenser Vacuum Exhaust Low Range 2-RM 256 Condenser Vacuum Exhaust High Range 2-RM 27 l Upper Cntmt High Range 2-RM-90-272Upper Cntmt High Range 2-RM-90-273 Lower Cntmt High Range 2-RM 274 Lower Cntmt High Range 2-RM 421 Main Steam Line Post Accident Monitor 2-RM 422 Main Steam Line Post Accident Monitor 2-RM 423 Main Steam Line Post Accident Monitor 2-RM 424 Main Steam Line Post Accident Monitor 2.1.7.m Auxilrary Control Room Panels 2 -L-1 1A/B and L-10 2.1.7.m.l Corresponding controllers on the ACR panels will be changed out to include the same type of Foxboro Il A & Spec 200 controllers that are used on the Main Control Room panels.

Switches on Unit2 L-11A/B panels are located in different locations than the Unit 1 Counterparts.

2.1.7.m.2 2.1.8 Operational Characteristics Watts Bar has thoroughly reviewed the operational characteristics of both units and determined that they are nearly identical. The following provides an analysis of the identified operational characteristics differences.

2.1.8.a Unit 2 Reactor Core 17

2.1.8.a. I 2.1.8.a.2 2.r.9.b.2 Unit 2 will start up with a "clean" core and without Tritium Producing Burnable Absorbers. Initially, the units will have different core operating characteristics requiring different boron concentrations: Unit 1 in a nonnal first/second/third burn assembly fuel cycle, Unit 2 with all first burn assemblies.

Unit 2 Core Thermal Power will be limited to 34ll vs. 3459 MW for Unit 1, until the Leading Edge Flow Monitor system is commissioned.

2.1.8.b Unit 2 Turbine Upgrade 2.1.8.b.1 The Unit 2 turbine has been updated to improve efficiency and power output by installing a new HP Turbine (Rotor, Inner Cylinder, Blade Rings) and two LP Turbines (Rotors and Inner Casings). The HP turbine has no impulse chamber. Turbine Impulse Pressure control will be different between the units.

The Unit 1 turbine has an impulse chamber and utilizes three pressure transmitters for generating control signals.

On Unit 2 there will be a higher median select of four HP turbine inlet pressure transmitters. LJnit 2 will have a different configuration for the turbine load signal (inlet pressure).

The Turbine Supervisory Instrumentation (TSI) system for Unit 2 is physically smaller than the Unit 1 TSI system. The Unit 2 system is more compact because the technology has decreased the size of the components needed to serve the same function and become more reliable.

2.1.8.c.2 Unit 2has the original D-3 steam generators and Unit I has installed 68AXP replacement steam generators.

Unit 1 Steam Generators have a larger heat transfer area (20,000 ft2 more) an d aheat transfer perforrnance characteristic of 28.8

-MW/F. The Unit 2 Steam generator has a characteristic of 22.81 -MW/F. The Unit 1 Heat transfer coefficient is slightly less than Unit 2, however, the Unit t higher tube volume and more surface area results in a higher steam pressure and temperature at the same power level.

2.1.8.c Unit 2 Steam Generator Response and Preheat Operations 2.I.8.c. I 1B

2.1.8.c.3 The differences in steam generator design result in slightly different response characteristics. The Unit 1 Steam Generators have a higher recirculation ratio, resulting in greater indicated level changes in response to transient/upset conditions. This has been tempered to some extent by increasing the span of the level instrumentation. The Unit2 Steam Generator indicated level response is slightly slower. This slight difference in steam generator operations and response is similar to that experienced at other two unit sites after upgrading their steam generators.

These upgrades are typically done at different times on opposite units, resulting in the two units having different steam generators for some period of time.

2.I.8.c.4 The Unit 1 Steam Generators use a forward flush to warm the Main FW lines to the steam generators, but no longer require a back flush. The Unit 2 Steam Generators require a back flush for warming the Main FW lines to the steam generators. This is accomplished by using an additional position added to the Unit2 switch that controls the forward and back flush operation.

2.1.8.c.5 There is a difference between the units in their operational response to a Steam Generator Tube Rupture (SGTR) due to the higher elevation of the Unit 1 U tube bundle. Emergency Operating Instructions adequately mitigate the difference in response between the units.

FSAR SGTR Time Response calculations identi$r the following minor variations :

o Time to identiff/isolate (Units l&2 :15 mins) o Time to start C/D and start Depress (Unit 2:33 mins/55 mins, Unit I:33 mins/51.6 mins o Time to Terminate SI after Depress Stopped Unit2

4.1 mins, Unit 1 :4.0 mins) o Break flow terminated (Unit 2: 83.8 mins, Unit I :

77.8 mins In summary even though the times for Unit 2 response changed, most of the Key times for operator actions are essentiallv the same.

2.1.8.d Unit2 Moisture Separator Reheaters 19

2.1.8.d.1 The Unit 2 MSRs are higher capacity reheaters. Along with the Main Turbine difference, the MSR will operate at a slightly lower steam pressure (about 45 psi lower). This will cause slightly different flows throughout the system (extraction steam, heater drain flows) that will require different alarm setpoints.

2.I.8.d.2 Mass flow rates to all MSR drain tanks increase because of improvements to the high pressure turbine and the new MSRs.

Mass flow rates through the MSR operating vents decrease because of improved MSR design. Mass flows from the MSR low pressure operating vents will be directed to the low pressure reheater drain header instead of the Number 2 extraction steam lines as on Unit 1.

2.1.8.d.3 The Unit 2MainFeedwater Pump Turbines are connected to MSRs A-2 and B-2 as opposed to MSRs A-1 and B-1 on Unit 1.

2.I.8.d.4 Controls in the MCR are the same for both units.

2.1.9 Administrative Procedures related to Conduct of Operations for a Multi-Unit Site The administrative procedures related to conduct of operations at a multi-unit Watts Bar Site will be the same as those used for the Sequoyah Site and are contained in TVA NPG Standard Department Procedure (OPDP-l). Requirements for shift manning are summarized below:

2.I.9.a A SM with an active SRO license, who is also a member of the Operations shift crew, shall be on site at all times when fuel is in the reactor.

2.I.9.b In addition to the SM on site, a second active licensed SRO shall be in the control room at all times. The SM may, from time to time, act as relief Operator for the licensed SRO assigned to the control room.

2.I.9.c In addition to the staffing requirements stated above, shift crew assignments during periods of core alterations shall include a licensed SRO to supervise the core alterations. This SRO shall not have any other concurrent operational duties.

2.I.9.d Additional personnel may be required on shift because of unusual plant conditions or operational needs. The SM, or designee shall obtain the additional personnel as necessary.

2.I.9.e Deviations in shift complement maybe made, provided minimum manning and license requirements of TS are met.

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2.1.9.f Operations personnel should not be shifted from one unit to another unit without sufficient time for the individual tci becoine familiar with its conditions.

2.I.9.g The following table summarizes minimum staffrng requirements:

Shift Manager (SRO)

Unit Supervisor (SRO)

Unit Operator (RO)

Non-licensed (AUO)

STA The SM, a US or the WCC may be the STA and one US will be the Incident Commander. The STA need not be licensed. Two active-licensed SROs are required for Unit Supervisor positions and a third active licensed SRO is required as Shift Manager.

2.1.10 Expected Method of Rotating Personnel between Units and Re-Familiarization Training To Be Conducted Before Assuming Duty on the New Unit Watts Bar Nuclear Plant Operations Shift Schedule is a continuous five-week rotation for each crew-including four weeks in Plant and one week in Training. Each crew will consist of sub-crews (for example, Crew 1A, Crew 1B, Crew 2A,Crew 2B etc.).

Management expectation is that each sub-crew will assume the shift on the opposite Unit after every training week. "Crew 1A" would assume the shift for Unit 1 for four weeks, attend training week, assume the shift for Unit 2 for four weeks, attend training week, assume the shift for Unit 1 for four weeks. etc. while "Crew lB" would assume the shift on the opposite Unit.

21

3. Training and Qualification Plan This training plan provides a best estimate outline of the expected scope, duration, and delivery schedule based on the analysis of the unit differences, the Unit2 testing and startup schedule, and initial license needs. Certain assumptions have been made to develop this plan and those are discussed in section 3.2.It is expected that the training schedule and duration discussed will be sufficient to accommodate the results of any further training needs analysis resulting from any differences not already identified.

The training plan must be flexible in nature while still maintaining the integrity of the overall concept of the design. As Unit 2 fuel load approaches, it is recognized that additional differences may be identified or some design changes may occur. The procedures and processes are in place and functioning that force any new plant changes (Unit 1 or Unit 2) to be reviewed by training personnel for impact on operator training programs. This is also true for changes to setpoints, procedures, technical specifications and other changes that may occur.

The training plan can accommodate any future training needs identified over and above those currently known. The approximate number of hours is flexible, as well as the specified hours per topic described in the plan.

Unit2 fuel load and startup have been carefully coordinated with Unit 1 refuel outages, Unit 1 upgrade to digital controls, Simulator upgrade to digital controls, LOR differences training for startup and the licensing dates for initial license classes. Furthermore, if there are any issues with meeting the scheduled Unit 2 fuel load and startup date, there will be no impact on this training plan.

3.1.1 TrainingAnalysis The Training and Qualification Plan was developed in accordance with the systems approach to training. Accordingly, Watts bar performed a Training Needs Analysis (TNA) for each DCN/EDCR issued that identified unit differences. TNAs were reviewed by an expert panel of dedicated operations resources to determine required unit differences training for Operators. This panel ensured that a consistent review was performed and minimized the potential that a change might be missed and not covered in training. Unit differences with operational impact that required new or modified tasks with regard to the Licensed Operator/Senior Operator Jobs were determined.

As of 616/13, I00yo of issued Unit 1 DCNs and Unit 2 EDCRs have been reviewed.

Approximately 15% of DCNsIEDCRs have been screened as requiring operator training and have a completed training needs analysis. Approximately 90% of the DCNs/EDCRs screened as requiring some level of operator training are relatively minor. The other 10%

of differences will require a more comprehensive level of operator training.

Four tasks were identified as unique to Unit 2. Seven tasks were modified (Unit 1 only or Unit 1 and2) due to unique unit 2 skills and/or knowledge's. Lastly, Unit differences 22

with operational impact were identified for specific operator training and subsequently continued through the SAT process.

Only one new Unit 2 Task, "Operate Common Q Inadequate Core Cooling Monitor" has safety related significance with regard to monitoring reactor vessel level, subcooled margin, and core exit temperatures. The task requires a simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed.

At this time, no Unit2 difference has been identified to have a significant impact on Probabilistic Risk Assessment (PRA), Key Operator Actions. WBN 2will continue to evaluate this until the PRA is finalized.

No Unit 2 difference in contol room design and instrument location was identified that created an unrecoverable step or action that, if performed improperly, would impact safe plant operation, cause damage to equipment, the environment, or injury to personnel. Main Control Room (MCR) Operational Impacts are detailed in Attachment l.

No Unit 2 difference was identified that impacted a time critical operator action. (SGTR Time Response has minor variations).

The design freeze is complete and the training staff continues to track design changes for both units to identiff differences, conducting formal training needs analyses, analyzing unit differences, and revising or developing the associated training materials for DCNs/EDCRs as they are issued. It is estimated that less than 1% of the total number of DCNs/EDCRs are yet to be issued. These will be reviewed for training needs as they are issued.

Watts Bar is committed to ensuring the operators are trained and evaluated in both knowledge and skill based tasks to ensure continued safe operation of Unit 1 and the safe start up and operation of Unit 2. To this end, the unit differences training will be evaluated by a comprehensive written examination and a Task Performance Evaluation of Common Q and NIS. The comprehensive written examination will sample across all unit differences with operational impact but will not conform to the specifications of NUREG 1021; ES-602 Requalification Written Examinations due to the limited scope and level of knowledge of the unit differences.

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3.1.2 Training Plan Assumptions 3.1.3 The full-scope Distributed Control System (DCS) will be installed in Unit 2.

3.1.4 Unit 1 will have a similar full-scope DCS at fuel load. Feedwater level control portions of the DCS were installed in UI-RFOII in09120I2. Unit 1 will install additional DCS controls in Ul-RFOl2 in 0412014. The Unit 1 simulator will be modified with these additional Unit 1 DCS controls in I2/20I3, approximately 4 months in advance of the reference unit.

3.1.5 The training content for unit differences training will be delivered during the normally scheduled LOR training cycles, as well as some structured on shift Job Familiarization Guides (JFG).

3.1.6 Unit2 hot functional testing is scheduled to begin on08ll6/I4. Fuel load is scheduled for I2lI8/14. Initial criticality is 03/5/15.

3.1.7 Dual-unit operator licenses will be applied for at the completion of Unit 2 differences training in July and August 2014 and, issued to support fuel load in December 2014.

3.1.8 Unit differences will be tested in a comprehensive exam during LOR cycle 3. In addition to the Unit differences comprehensive written exaln, there will be performance based JPM evaluations on Common Q and NIS.

3.1.9 The NRC grants the waiver request for the NRC administered written and operating examinations for Unit 2. The justification for the dual-unit license application waiver will be this NRC approved Training Plan plus the results of any associated NRC training inspections that support acceptability of the station's training program.

3.1.10 Description of Training and Qualification Plan for Personnel Currently Licensed on Unit I 3.1.11 Licensed Operator Requalification (LOR) Training Plan Design The standard two year LOR training program is designed using a template of 12 training cycles, each 6 weeks in duration. To accommodate the Unit 1 schedule and Unit 2projectschedule,2014willconsistof 5 cycles. Cycle 14-01 (scheduledJanuarythrough February 2014) begins structured class room training. JFGs will be distributed in cycle 13-06 to overview plant differences. Cycle 14-02/03 provides the balance of the class room training and includes focused Unit 2 simulator training and culminates with a comprehensive (samples across all unit differences) written examination and demonstration of task mastery is required for NIS and Common Q.

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3.1.12 LOR Training Plan Summary When dual unit license applications are submitted, starting in July 2Ul4,licensed operators with Unit I licenses will have received approximately 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> of haining on the Unit 2 differences. The remaining hours of requalification training time for cycles 14-01102103 will be normal Unit 1 proficiency training.

This training plan includes:

o Completion of unit differences JFGs o Designed as a formal strucfured document for operators to use as guidance in locating and understanding unit differences. Once issued, these guides can be used on a self-paced basis, but must be completed before dual unit license applications are submitted.

o Class room training on dual unit common systems, unit differences, Unit 2 procedures and Technical Specifications o In conjunction with the classroom presentation on Common Q (RVLIS, Core Exit TCs, Core Saturation Monitor), screen captures from the Common Q user's manual will be compiled into a software environment that will allow each student to navigate the various menu screens on individual laptops. Through a process of instructor-led exploration the students will gain a familiarity with the Common Q menu structure and demonstrate competency in locating and ffending RVLIS/ICCM parameters as well as acknowledge and reset alarms associated with the Common Q system.

o Formal Qualification on selected Unit 2 differences in accordance with the SAT process.

o TPE for Source Range and Intermediate Range Monitors will be conducted in the Unit 2 Control Room at Panel 2-M-13 to familiarizethe Operators with the differences associated with abnormal operation of the new monitors.

o TPE for Common Q may be conducted on a software simulation because the plant installed system will not be completely operable until fuel is loaded and the reactor is reassembled.

o Simulator Training for Unit 2 Operational Characteristics o Temporarily modiffing the simulator to allow demonstration of the D-3 steam generators to include the forward and back flush hardware and software. The associated switch and indicators on the lower right of M-3 will be emulated for use in the U2 Demonstration Load.

o Temporarily modiffing the simulator to allow demonstration of a cold clean core initial criticality approximating the U2 core design data.

The training is designed to have several components for both knowledge and performance training and evaluation (see Table 2 below for details).

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3.1.12.a.8

3. 1. 12.b 3.1.12.b.l 3.1.12.b.2 3.1.12.b.3 3.1.12.b.4 3.1.12.b.5

3. I. 12.c 3.1.12.c.I 3.1.12.c.2 3.1.12.c.3 3.1.12.c.4

3. I. 12.d Cycle 14-01, starting in January 2014 will include:

Turbine and Secondary Plant Changes Unit 2Impact on Common Systems WINCISE Incore Flux Mappitrg Common Q including software simulation and TPE Electrical and Fire Protection Differences Expanded LOR Changes Lesson Plan covering minor differences Unit 2In-Plant SVIR Nuclear Instrumentation JPM Walkthroughs (Unit 2 MCR)

Unit 2 Differences discussions for associated Unit 1 Simulator Scenarios Cycle 14-02, starting in May 2014, will include:

Unit 2D-3 SGs Unit 2 Procedure Differences (EOIs)

Unit 2 SG Startup Demo and Practice Unit 2 Differences discussions for associated Unit I Simul ator Scenarios Simulator Scenarios using U2 EOIs and AOIs as far as possible and Unit 2 differences in the EOI and AOI response will include an instructor-facilitated di scussion Cycle 14-03, starting July 2014, will include:

Unit 2 Cycle 1 Core Design Unit 2 Start up Physics Testing Simulator Demonstration Unit 2Inttial Criticality Procedures on simulator model of Unit 2 Core Design Unit Differences comprehensive written examinations.

'Inactive' staff licensed operators will be required to spend4 hours in the control room reviewing design and instrument locations differences prior to resumption of Licensed duties. Thes e 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> may be included as part of the minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions required under I 0CFR55.53(0(2).

26

3.1.I2.e Additional training will be administered for Unit 2 during cycles 14-03 and beyond, starting in July 2014, and contains training on Unit 2 Hot Functional, Engineered Safety Features and Power Ascension Tests procedures and requirements; review of topics covering fuel cycle one core design, initial criticality procedures and' just in time' start up training on Unit 2. This will include a temporary modification to the Unit 1 simulator to allow training on a new clean core for Unit2 startup. When this training is complete the WBN simulator will again be returned to Unit I fidelity. This training will be completed during the appropriate cycles based on the Unit2 Startup Schedule and will be after license application submittal, but before Unit2 fuel load.

3.1.13 LOR Examination Impact of Planned Simulator Modilications A basic timeline for the normally scheduled LOR annual operating examinations with respect to the installation of the simulator DCS modification is as follows:

o 0912013 LOR Simulator Exam DCS Feedwater Conkols only o I2/20I3 Install additional Unit 1 DCS controls on Unit 1 plant-referenced simulator o 0412014 Install additional DCS contols on Unit 1 during Refueling Outage o l2l20l4 Unit2 Fuel Load o tll20l5 LOR Simulator Exam Full Unit 1 DCS Controls (11 months practice on digital controls)

More information concerning the simulator is contained in section 3.5.

The timeline for the differences training integrated with other key training and station milestones is provided in Figure 1.

Table 2 provides a breakdown of the differences training into the individual LOR training cycles.

3.1.14 Description of Training and Qualification Plan for In Progress Initial License Class Personnel 3.1.15 Initial License Training (ILT) Plan Design Note: Initial license classes are numbered with the year and month the class is scheduled to take the NRC exam when the class starts, i.e., class l3-10 originally scheduled to take the NRC exam in October of 2013.

ILT classes have been coordinated with Unit I refuel outages, Unit2 initial fuel load and start up, Unit differences training, Simulator upgrade with additional DCS, and Unit 1 27

upgade with additional DCS. ILT Class 13-10 will be the last class to initially obtarn a Unit I license, and then attend differences training with LOR. Their dual unit license applications will be submitted in accordance with the LOR schedule. Subsequent classes will receive differences training during ILT, such that they apply directly for dual unit licenses.

3.1.16 ILT Training Plan Summary Initial Licensing Training will continue to be conducted in accordance with TVA Nuclear Power Group Procedures.

3.I.I6.a ILT Classes l3-10 is scheduled for their NRC Examinations in October 2013 which is prior to Unit 2 fuelload in December 2014.

The class will train and examine on the Unit 1 referenced simulator and their license applications will request a Unit 1 License. After receipt of their NRC licenses, these students will subsequently receive differences training by enrolling in LOR starting cycle 14-01.

3.1.16.b A request to waiver the NRC-administered license examination for ILT 13-10 operators will occur during LOR application for dual unit licenses. The class will receive all of the differences trainine outlined for current incumbent operators.

3.1.16.c ILT Class l5-06 will take theirNRC Examination after Unit 2 fuel load; these students will be trained on Unit 1 and Unit 2 differences during the course of their ILT class. This class will submit License Applications for a dual unit license.

3.1.17 ILT Examination Impact of Planned Simulator Modifications A basic timeline for the ILT simulator examinations with respect to Unit 2 Fuel Load and the installation of additional DCS in the simulator is as follows:

r0t20r3 12t20t3 0412014 12l20r4 06l20rs ILT Class 13-10 NRC Install additional Unit simulator Install additional DCS Unit 2 Fuel Load ILT Class 15-06 NRC Exam DCS Feedwater Controls I DCS controls on Unit 1 plant-referenced controls on Unit 1 during Refueling Outage The timeline for the differences milestones is provided in Figure Exam Full Unit I DCS Controls training integrated with other key training and station 1.

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3.1.18 Maintaining Simulator Alignment with the Reference Unit I 3.1.19 Simulator Configuration Plan Design This plan was designed to support Unit 2 fuel load and start-up, Unit 1 upgrade to DCS, support of LOR training for unit differences training, support of LOR training following Unit2 start-up and support of ILT such that personnel are examining on the reference unit simulator.

3.1.20 Simulator Configuration Plan Summary The WBN simulator will be maintained certified as a Unit 1 Reference Simulator.

3.1.20.a In support of steam generator differences training the simulator will temporarily be loaded with a Unit2 steam generator model to demonstrate the operational characteristics of the Unit 2 steam generators. This is scheduled for LOR Cycle 14-02 as part of the unit differences training and will be part of the ILT Program for 15-06.

3.I.20.b In support of reactor core differences training topic the simulator will temporarily be loaded with a Unit2 reactor core model to demonstrate the operational characteristics of the Unit2 reactor core. This is scheduled for LOR Cycle 14-03, in order to support Unit2 startup training prior to the Unit 2 license application and request for waiver of the NRC administered Unrt2license examination.

3.1.20.c At Unit 2 fuel load in December 20I4,Unit 2 will be equipped with a comprehensive DCS. DCS was installed for feedwater level control for Unit 1 in September 2012, during refueling outage Rl1.

The Unit 1 plant-referenced simulator was modified in advance of the reference plant by installing DCS in January 2012, or about 10 months ahead of the plant. Modifying the simulator on this schedule will also provide the operators with a hands-on DCS operating simulation prior to Unit 2 hot functional testing, fuel-load and power ascension testing. Modifying the simulator to DCS on this time line will result in simulator examinations as follows:

0912013 r0t20t3 I2l2013 LOR Simulator Exam ILT Class 13-10 NRC Exam Install additional Unit 1 DCS simulator DCS Feedwater Controls DCS Feedwater Controls controls on Unit 1 plant-referenced Install additional DCS controls on Unit I during Refueling Outage o 0412014 29

I o I2l20I4 o 06120t5 o Ill20I5 Unit 2 Fuel Load ILT Class 15-06 NRC Exam LOR Simulator Exam Full Unit 1 DCS Controls Full Unit I DCS Controls The timeline for the differences training integrated with other key training and station milestones is provided in Fizure l.

Table 2 provides a breakdown of the differences training into the LOR training cycles.

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Table 2: Differences Training Scope, Duration, and Schedule Training/

Activity Start Date Approx Hours Topics LOR Cycle 13-06 10ltfil13

-2 Classroom: Differences Overview followed by issuance ofjob familiarization guides (JFGs) to be completed on shift.

Simulator DCS Modification r2l02l13 Simulator upgraded to include additional DCS which will be installed in Unit I during UI-RFOI2 LOR Cycle 14-01 0yr3l14 LOR Cycle I Unit 2 differences training topics:

-2 Common Q (RVLIS, Core Exit TCs, Saturation Monitor)

-1.5 WINCISE Incore Flux Mapping

-3 Turbine and Secondary Plant Changes (MSRs, Heater Drains)

F' ryJ Unit 2Impact on Common Systems (ERCW, CCS, Control Air)

-2 Electrical and Fire Protection Differences

-2 Expanded LOR Changes Lesson Plan covering minor differences

-1.5 Unit 2 Differences discussions for associated Unit 1 Simulator Scenarios (three 30 min sessions)

-2 Weekly Exam to include Unit Differences On Shift unit 2In-Plant SR/IR and Common Q JPM Walkthroughs (Unit 2 MCR)

UI-RFO12 03124114 U1-RFO12 besins LOR Cycle 14-02 0sl26l14 LOR Cycle 2 Unit 2 differences training topics:

-6 Unit 2D-3 (OSGs)

-4 WBN* Simulator: Unit 2 SG Stanup Demo and Practice

-2 Classroom: Unit 2 Procedure Differences (EOIs)

-2.5 Simulator Scenarios using U2 EOIs and AOIs as far as possible and Unit 2 differences in the EOI and AOI response will include an instructor-facilitated discussion.

-1.5 Unit 2 Differences discussions for associated Unit I Simulator Scenarios (three 30 min sessions)

-2 Weekly Exam to include Unit Differences 31

Training/

.Activity..

Start Date Approx Hours LOR Cycle 14-03 07l2ur4 LOR Cycle 3 Unit 2 differences training topics:

-2 Unit 2 Cvcle 1 Core Design

-2 WBN Simulator: Unit 2 S1'art up Physics Testing Simulator Demonstration

-2 WBN Simulator: Unit 2Initial Critic ality Procedures (Unit 2Initial Criticality Procedures on simulator model of Unit 2 Core Design**)

-3 Comprehensive written exam Submit 398's 08104114 Submit dual unit license applications after each week of LOR Cvcle 14-03 Total Training Hours for Unit Differences

-46 Total time includes testing LOR Cycle 14-04 and beyond Unit 2 Hot Functional, Engineered Safety Features, and Power Ascension Tests, Procedures and requirements etc.

HFT 08/ 16l 14 Unit 2 Hot Functional Testing starts Fuel Load r2l2l14 Unit 2 Fuel Load starts ILT NRC Exam 06lrs ILT Class I5-06 Initial Criticalitv 03lOsl15

• To support unit difference training, a simulator load using the original steam generator (OSG) model will be developed to include the forward and back flush hardware and software. The OSG model can be used for training demonstrations during unit difference training, including the operating characteristics of the original steam generators and the forward flush / back flush procedure.

• • The Unit I simulator will be temporarily modified to model Unit2 core data.

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ATTACHMENT 1 - Detailed Control Room Design and Instrument Location Unit Differences The purpose ofthis table is to provide dstrail ofthose aspecs ofthe Urit differences that will b apparent to operators. Watts Bar has thoroughly reviewed the control roon design and ilstumert locations and determined they are trot so significaot that they could atrct the operator's ability to operate each unit safely and competently.

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT s2358 MI ICS display monitor 2-MON-47-120 is installed in place of TR-47-0001 and TR-47 -0002 Turbine Supervisory This monitor duplicates the functionality of obsolete recorders 2-TR-47 -0001 'Bearing Metal Temperature' and 2-TR-47-0002'Control Start Temperature'.

2-M-l will contain2 19" displays while 1-M-1 will contain only 1 17" display.

On Unit I these recorders ( I -TR 0001 and 1 -TR-47 -0002) were abandoned and the inputs to these recorders were provided to the plant computer system (ICS) by DCN 52846.

Future plans call for the replacement of the recorders with a monitor like Unit 2.

Improved information display 52460 52378 M2 Hotwell Level control transmitter selector switches will not be used on Unit 2.

Condensate Unit t has level switches LS'2'12A,'I28, '1009A, and

'10098 Installed to signal annunciator XS'55'3A-45D

HOTWELL HVLO LEVEL ALARM.

Unit 2 did not install these level switches or manual hand switches (which transfer between Zone A and Zone C). DCS software will select the best signal for control and alarms on Unit 2 so no operator actions are required for a failed instrument.

Simplification 52623 s23s9 M2 2-Xr-47 -2000 indicators for Main Turbine Throttle and governor valves, demand and valve limit Turbine Generator Unit I replaced obsolete Throttle and Governor Valve indications on 1-XI-47 -2000 with indicators made by Yokogawa. Unit 2 installed original indicators made by Westinghouse.

Improved information display 33

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 53600 s2360 M3 FW Pre-Heating Flush Selector HS 45 differs between Unit 1 and Unit 2.

Status light box 2-XX-3 -235 retains additional lights related to back flushing operations Feedwater Handswitch 2-HS-3-45 is a 4-position switch to warm the main feedwater lines through forward and back flush operations. The Unit 1 steam generators were upgraded which eliminated the need for back flush operations; therefore, 1-HS-3 -45 is a two-position switch without the back flush operation mode. The Unit 2 Steam Generators remain a Model D3. As such, the need for Feedwater Preheat, and fonvard and back flush capabilities remain in Unit 2.

Simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed 523sr M4 Temperature recorder 2-TR 101, switch2-xs 101 and RVLIS indicator 2-XI 100 will not be installed on 2-M-4.

ICCM-86 The new COMMON Q display 2-MON-68-100 on 2-M-4 will perform these functions for Unit 2.

Improved information display 52343 52427 M4 Motor Driven Auxiliary Feedwater pump discharge pressure controllers 2-PDIC-3 -122A and l32Lhave been replaced with Foxboro SPEC 200 controllers.

AFW These PDIC controllers perform the same function as the components used in Unit l. On Unit I these components GEMAC controllers.

The reason for this difference is that the GEMAC (Bailey) controllers are obsolete and the Foxboro model controllers have been used in other Unit I applications.

Simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed 58210 s83 87 M4 Hand switches for Nitrogen back rp system for MDAFW SG LCVs & PCVs and TDAFW SG LCVs.

AFW*

Unit 1 added 2new HSs (1-HS-77-2561A &2562A) with indicatitrg lights to 1-M-4. Thes e 2 new HSs are used to isolate leaking nitrogen by takitrg HS to "CLOSE" position.

Unit 2 assigned this function to existing HSs 2-HS-3-164A &

174A on2-M-4. These switches are taken to the "CLOSE, Pull to Lock" position to isolate nitrogen. Both unit design packages added FSVs to isolate N2 leaks but the assigned hand switches are different.

Simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed 34

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 537 56 M4 Reactor Vessel Head Vent Throttle Valve controllers }-HIC-68-396 and}-HIC-68-3 97 have been replaced with Foxboro SPEC 200 controllers.

Reactor Vessel Head Vent These controllers perform the same function as the Westinghouse controllers used in Unit l.

Simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed s2690 M5 UNIT 2 RECORDERS o 2-PR-068-0063 RCS Wide Range Pressure Reactor Coolant Unit 2 will have Paperless digital recorders. Unit 1 is replacing these recorders as they fail.

Improved information display 52378 52420 M5 Annunciator 2-XA-55-5C window 107 A And window 96-F Reactor Coolant Unit 2 has an alarm to detect failure of the pressurizer level controll charging system, designated "pressurizer overfill" on the annunciator. Unit 1 does not plan to implement this alarm.

Each RCP on Unit 2 will have an accelerometer mounted on RCP casing flange. The accelerometers are not cuffently used on Unit 1. Unit 2 will require the Operator to query ICS in the event of an alarm on 2-M-5, window 96-F for RCP vibration to determine the exact cause of the alarm.

Addressed via Alarm Response Instructions s2378 M6 Annunciator 2-XA-55-64 window 109D Chemical and Volume Control Unit 2 has two VCT high level alarms to provide the operators a detection method for an inadvertent boron dilution event. (RG 1.70 rev 3)

Addressed via Alarm Response Instructions 52351 M6 Cold Leg Accumulators Level and Pressure indicators (LI l2g,-119,-109, -99,

-89, -8 1, -82, and -60 Safety Injection The Cold Leg Accumulator group of indicators is located below the new Common-Q monitor (2-MON-68-110) on panel 2-M-6. They are located above RVLIS display (1-XI-68-110) on l-M-6. This was done to fit the new 15-inch Common-Q display in the layout area.

Improved information display 35

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EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT and PI-63 -128, - 126,

-108, -106, -88, 86, -

61, and -61) are located below the new Common Q monitor 5235r M6 Incore flux/temperature recorder TR-94-102 is not installed on panel 2-M-6.

Incore Neutron Monitoring Data points will be included on Common Q monitor 2-MON-68-110 on 2-M-6.

Improved information display 5235r M6 The RVLIS display XI I l0 and its keypad XS-68-111 on panel 1-M-6 are replaced with 2-MON-68-110 ICCM86 Common Q monitor 2-MON-68-110 replaces the functions of XI-68-l 10 and XS-68-1 I 1.

Improved information display M6 Boric Acid Tank C Recirc Flow Chemical and Volume Control BAT C recirc controls on 1-M-6 and not on 2-M-6. BAT C can be aligned to either unit (original design).

None 52343 M6 Panel XA-55-6F (windows I45D, 146D, and l47D)

Annunciator In the Unit 2 annunciator window box XA-55-6F (windows 145D,I46D, and l47D), annunciation for fuses blown in ACR PNLs 2-L-l 1A, 2-L-1 18 and 2-L-10 will be combined into window I46D and will have the re-flash function. In Unit 2, wrndow I47D will be used for power failure in PNL 2-L-381A CMPT A, B or C and will have the re-flash function.

Unit 2 window 145D will be a spare window.

Addressed via Alarm Response Instructions 36

DCN/

EDCR PANEL INDICATIONS &

COi\\TROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 52427 M6 Panel XA-55-6F Windows I45A &

146A Annunciator Due to the replacement safety related BOP instrument loops and the installation of equipment in new panels 2 R-129 (Train A) and 2-R-132 (Train B), several loss of power alarms are no longer needed - TRN A/B P..I27 lI28ll43 &

Rl30/13 1 lI40 are deleted.

Addressed via Alarm Response Instructions 52453 M6 Panel XA-55-6E-A Window 12, 13, 80 and XA-55-6F-B Window 12, 13, 80 Annunciator Window I2:Unit 1 for 1-FCV-32-80 (Phase "8").

Unit 2 for 2-FCV-32-8I (Phase "8"). Window 13:

Unit I for 1-FCV-32-1 10 (Phase "B"), Unit 2 rs Blank.

Window 80: Unit I for 1-FCV-65-52 (Phase "A"),

Unit 2 for 2-FCV 5 (Phase "A").

Window l2:Unit 1 for I-FCV-32-102 (Phase "8"),

Unit 2 for 2-FCV-32-103 (Phase "B"). Window 13:

Unit 2 for 2-FCV-32-1 11 (Phase "B"), Unit 1 is Blank.

Window 80: Unit 1 for I-FCV-65-53 (Phase "A"),

Unit 2 for 2-FCV 4 (Phase "A").

Addressed via Alarm Response Instructions s2690 M6 UNIT 2 RECORDERS o 2-PDR-030-0133 Containment Pressure Narrow Range o 2-PR-030-0045 Containment Pressure Wide Range Ventilation Unit 2 wiII have Paperless digital recorders. Unit I is replacing these recorders as they fail.

Improved information display 52366 M9 Ventilation and Ice Condenser Indications and Controls Ventilation, Ice Condenser 1-M-9 contains the controls for chillers and fans that are common to both Units. This is part of the original design.

The following Unit-l components are located only on Unit-l None 37

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT Panel 1-M-9 & corresponding Unit-2 components do not exist:

1-XI-030-0 136, 1-XI-030-0 r39, 1-XI-030-0 r59, 1-XI-030-0162, l-xl-030-027 4, l-xl-O 30-027 8, l-xl-03 I -03 42, l-XI-03 1 -0343, 1-XI-030-0103, l-XI-030-0 t02, 1-XI-03 1 -003 50, 1 -

xI-03 I -03 65, 1-HS-030-0103A, 1-HS-030-0 102A, I -HS-030-0106, I-HS-030-0086, 1-HS-030-0107, 1-HS-030-0097, l-HS-030-0158, 1 -HS-030-0269, 1-HS-030-0160, I -HS-030-0166, I -HS-030-0 161, I-HS-030-0 t67, I -XI-030-0 tsg, 1-HS-030-0159A, 1-HS-030-0 162A,l-XI-030-0 162, 1-XI-061-0089A, l-xl-061-00898, 1-XI-061-0089C, 1-XI-061-00ggD, 1-XI-061-0089E, I -XI-06I -0089F The following Unit-2 associated components are located on Unit-l Panel l-M-9 : 2-XI-030-0 104, 2-XI-030-0 1 05, 2-HS-030-0104A, 2-HS-030-0 105A, 2-HS-030-0109, 2-HS-030-0021, 2-HS-030-0109, 2-HS-030-0022, 2-HS-03 0-0270, 2-H S - 0 3 0 -027 1, 2 -HS -0 3 0 -027 5, 2 -HS - 0 3 0 -027 2, 2 -HS -0 3 0 -

027 6, 2 -Xr-03 0 -027 4, 2 -H S -0 3 0 -0 27 4 A, 2 -H S -0 3 0 -0 27 g A, 2 -

xr-03 0-0278 54172 M9 CRDM Cooler Motor Controls Ventilation, Control Rod Drive Mechanism Unit 2 has four CRDM Cooler Motors compared to eight CRDM Cooler Motors in Unit 1. There will be four hand-switches (2-HS-30-80A, -83A. -88A, -92A) on panel 2-M-9 in the Main Control Room. The labels of the hand-switches will differ from those seen on the Unit 1 Main Control Room panel 1-M-9 since there will only be one motor per loop. The hand switches 2-HS-30-80A, -83A. -88A, and -92Awill be labeled "CRDM CLR D-B", "CRDM CLR A-A", "CRDM CLR C-A", and "CRDM CLR B-B" respectively.

None 52694 52367 Ml0 The Unit 2 Train B Hydrogen Analyzer hand switches and indicators xI-043-0200A, xI-Post Accident Sampling Unit 2 has one train of Hydrogen Analyzers and 4 containment isolation valves. Unit t has 2 trarns of Hydrogen Analyzers and 8 isolation valves.

38

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EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 043-0210A, XI-043-0210,H2r-043-42r0 HS-043-02078, 02088,0207 A, 0208A, &0210A are removed from 2-M-10 and two hand switches were added' 2-HS-043-02018,2-HS-043-02028 Unit 2 non-lE, commercial grade Hydrogen Analyzer will perform the same analysis function as Unit I IE, Train A Hydrogen Analyzer. There is no Unit 2 redundant Hydrogen Analyzer as there is on Unit 1 (Train B) in accordance with 10CFR50.44 and Regulatory Guide l.l.

Unit 2 will have fewer switches and indicators on the control room panel.

Simplification 52329 52367 s3920 Ml0 The following components are located only on Panel l-M-10 (Not on PaneI2-M-l0):

xr-043-0200A, xr-043-0210A, xr-043-0210, Hz-043-02r0, TR-061-0138, HS -043-02078, HS-043-02088, HS-043-0207 A, HS-043-0208A, HS-043-0210A, HS-043-02s0A, HS-043-0309A, HS-043-0287 A, HS-043-03 18A, HS-043-0342A, HS-043-0341A, Hydrogen Recombiner The Unit 2 hydrogen recombiners have been abandoned in place. Accordingly, the Controls in PaneI2-M-10, which are part of this abandoned system, ffia not required.

Unit 2 will have reduced operator actions.

None 39

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EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT HS-043-0307 A, HS-043-0325A, HzC-083-0001, HzC-083-0002.

52322 M10 ICE Condenser Recorder is being removed TR-061-0138 ICE Condenser Unit 2 will not have a Control Room ice bed temperature recorder. The Ice Bed Temperatures will be monitored in the control room using the ICS. A new ICS display shows status of the 48 Ice Condenser temperature points.

Improved information display 534r7 M10 Annunciator Window I44-D alarm Annunciator The Unit 1 Annunciator window 1 44-D does not have reflash and ARI instructs operators to check the Ice Bed Temperature Recorder on Panel l-M-10. For Unit 2 the recorder is not located on a main control room panel. Due to this unit difference, reflash is added to Annunciator window 144-D, to allow the operator to distinguish between a HI and HI-HI alarm without the operator having to go to the recorder.

Improved information display 52322 Ml1 Generator Core Condition Monitor Display 2-XI-035-0060 will be replaced with ICS Generator Cooling 2-M-11 will have all components removed and the GCCM will interface with ICS for operator displays; 1-M-I I components still exist. The Unit I GCCM Display, oo Panel 1-M-11, will be replaced by ICS in Unit 1, 5-year plan.

Improved information display 5234r 52338 l/4r2 Radiation Monitors replaced with Digital Units o 2-RM-90-002 Personal Access Area Monitor (Personnel Airlock) o 2-RM-90-059 Upper Cntmt Area Monitor (Hatch)

Radiation Monitor Unit 1 is Analog.Unit 2 is Digital. The new rate meters have the same function (indicated value, alarms, display ranges, etc.) to the ones cuffently installed in Unit 1.

Improved information display

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 2-RM-90-060 Upper Cntmt Area Monitor (Airlock) 2-RM-90-061 Incore Instrumentation Room 2-RM-90-106 Lower Cntmt Air 2-RM-90-rl2 Upper Cntmt Air 2-RM-90-l 19 Condenser Vacuum Exhaust 2-RM-90-r20 Steam Generator Building Effluent 2-RM-90-l2r Steam Generator Building Effluent 5242r M13 2-Nl-92-13 1-D Channel I Source Range Signal Processor 2-N1-92-132-E Channel2 Source Range Signal Processor 2-N1-92-r33-D Channel 1 Shutdown Excore Neutron Monitoring Unit I has the Gamma-Metrics source, intermediate range system model RCS-300. Unit 2has the new 300i NFMS (neutron flux monitoring system).

Source Ran gellntermediate Range Signal Processor Improvements:

o The source and intermediate signal processors come with upgraded bar graph liquid crystal displ&ys, as the Unit 1 analog meters are obsolete.

\\

o In Unit l, the Source and Intermediate range signal processors have "Counts per second" or "Percent power level" displays, respectively. Unit 2 source Simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed 41

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT Monitor 2-N1-92-r34-E Channel2 Shutdown Monitor 2-Nr-92-r35-D Channel I intermediate Range Signal Processor 2-Nl-92-r36-E Channel2 Intermediate Range Signal Processor range signal processors include indication for both neutron level in counts per second, and decades per minute on the instrument rack. The intermediate range signal processors will include not only decades per minute, but will also indicate percent power on the instrument rack.

The selector knobs for Unit 2 on the intermediate range signal processor are set up differently than on Unit 1. There are a total of 3 dials on Unit I includittg level trip, adjust, and operation selector. On Unrt 2 there are a total of 5 knobs including test selector and output selector in addition to those previously mentioned. The selector knobs for Unit 2 on the source range signal processor are set up differently than on Unit 1. There are a total of 3 dials on Unit 1 includittg level trip, operation selector, and high flux at shutdown. On Unit 2 there are a total of 4 knobs including level test and output selector in addition to level trip and high flux at shutdown.

The scales and indicators on 2-M-4, which are used by the operators during startup and operation, are unchanged except that the displays are digital.

The shutdown monitor on Unit 2 will not contain an alarm reset button, which was used to manually disable the alarm during the drawer latching process.

The alarm reset function is now obsolete as this feature can be handled at the annunciator.

42

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 52454 52378 I[dl4,

M16, M194'

&B Center Work Desk Area and Displays The differences in the Unit 1 and Unit 2 workstation desks are primarily those of a cosmetic nature. The work area "footprint" is consistent between units and provides for the same number of operators in the seatin g arrangement. The work area and work surface of the Unit 2 consoles is improved over that of Unit 1 in that the Unit 2layout provides a slightly larger dimension between work surfaces.

None s2378 DCS work station Center Work Desk Area and Displays DCS Unit 2 DCS work station is capable of controlling No. 3 Heater Drain Tank level controls (LIC-6-105, LIC-6-106) and No. 7 Heater Drain Tank level controls (LIC 190A, LIC 1908) due to different controllers installed in the field which are incorporated into Unit 2 DCS.

Improved control capability 52370 Ml5 2-}l4-15 will have 3 control switches that have different numbers than Unit 1 switches on 1-M-15, but perform the same functions.

1-M-15 contains common "Unit designator 0" equipment not required to be installed on 2-M-15.

Various Reactor Bldg Traitr A, B, and Non-Essential Isolation (Aux Air) Hand switches HS-32-80A, HS-32-102A, & HS 1 10A on Unit 1 vice HS-32-81A, HS 1034, & HS 1 1 1A on Unit 2. These switches perform the same functions.

This is part of the original design.

1-M-15 contains common "IJnit designator 0" equipment.

The following shared items are located on Unit 1 panel and are not duplicated on Unrt 2:

Fire pumps l-A-A, 1B-8,2A-A &2B.B Raw Cooling Water Pumps A, B, C, D, E, F &G Component Cooling Pumps 1A-A, lB-8, 2A-4,28-8, & C-S Essential Raw Cooling Water Pumps A-A, B-A, C-A, D-A, E-B, F-8, G-B &H-8. This equipment has been used since Unit 1 startup and is original plant design There are no MCR controls/indications for cooling tower draining and blow down required for Panel 2-M-15.

None 43

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EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 52385 M15 Ml5 Alarm inputs Annunciator Unit I Panel 1-M-15 Motor Tripout annunciation receives inputs for a motor tripout from: Unit 1 CCW Pumps, Raw Cooling Water Pumps, Component Coolitrg Water Pumps and ERCW Pumps. The previously mentioned common components buzzers and relays are relayed ONLY to Unit 1.

Unit 2PaneI2-M-15 Motor Tripout annunciation (COND CIR WTR PMPS 2/^, 2B., 2C, 2D MOTOR OVERLOAD) receives motor tripout input ONLY from Unit 2 CCW Pumps.

None 5232r Ml8 Unit 2 uses WINCISE for functions performed by Unit 1 Moveable Incore Detectors Incore Monitoring System The replacement for the Moveable Incore Detector System housed in panel 2-M-18 is the WINCISE System. Panel2-M-18 will have its front panel modules removed where the legacy Moveable Incore system was operated from.

None 52378 Ml8(C)

Unit 2 Annunciator 2-XA-55-5C Annunciator Window l07A adds a Pressurizer Overfill alarm to warn the operators of a potential malfunction of PPLC or CVCS. Unit 1 does not have this alarm.

None 523t5 s2839 I[/d2I Unit I Panel XA 15A and XA-55-158 will be replaced on unit 2 with xA 15A.

Annunciator The pertinent alarms from Unit 1 A and B panels will be displayed on the 2XA-55-15A panel.

Unit 2 has all MCR annunciator loads powered from 2-BD-55-001 located in lll4.zI and the Unit 2 annunciator Inverter.

All Unit 2 Anrrunciator Ronan supplied equipment will be powered from the Unit 2 anrnnciator Inverter. Unitl remotes are powered from other plant power sources.

Unit 2 annunciators will be Windows based. Unit 1 remains DOS based. Disable/Enable of alarms will be different on Unit 2 thart Unit 1. Unit 2 also has 2 redundant independent channels of Annunciation.

Addressed via Alarm Response Instructions 44

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT Unit 2 has a special operator "end to end" channels test feafure. Unit I does not.

Windows 135 A, B and D for the annunciator inverter will be different. A11 Annunciator power/failure alarms will actuate 135,4. and I35BlD will be spared on Unrt 2.

s7938

}/4.23A TBBP FLOW DIFF SGNL INTERUPT Handswitches CCS Orientation of TBBP handswitches 2-HS-70-8 l BA and 2-HS-70-8 lEA ("Normal" on left and "Blocked" on right) is reversed from those on Unit l("Blocked" on left and "Normal" on right).

No significant operational differences to the component function between the units and no change to methods of operation 58390 57938 l/{23A Header Vent Valve Transfer Switch Control Air Switch 1-XS-32-II2 was installed on unit 1 (APP R) as a dual power supply selector switch for venting non-essential air to containment. Panel 2-M-23A does not have this selector switch nor is the function required for unit 2.

None s2338 52340 M30 Radiation Monitors replaced with Digital Units 2-RM-90-255 Condenser Vacuum Exhaust Low Range 2-RM-90-256 Condenser Vacuum Exhaust High Range 2-RM-90-27r Upper Cntmt Radiation Monitoring Unit I is Analog. Unit 2 is Digital. The new rate meters have the same function (indicated value, alarms, display ranges, etc.) to the ones currently installed in Unit l.

Improved information display 45

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EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT High Range 2-RM-90-272 Upper Cntmt High Range 2-RM-90-273 Lower Cntmt High Range 2-RM-90-274 Lower Cntmt High Range 2-RM-90-42r Main Steam Line Post Accident Monitor 2-RM-90-422 Main Steam Line Post Accident Monitor 2-RM-90-423 Main Steam Line Post Accident Monitor 2-RM-90-424 Main Steam Line Post Accident Monitor 52354 M3 1 Condenser Vacuum Exhaust Monitor RM-90-450 removed on Unit 2 Radiation Monitoring 1-M-3 I has the Condenser Vacuum Exhaust Monitor RM 450 mounted. This monitor will be removed before Unit 2 operation. Then both 1-M-3 land 2-M-31 will be blank.

None 46

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 5267 r ACR Auxilrary Control Room Controllers New hand stations and instruments at 2-L-11A,z-L-l 1B AND z.L-rc Main Steam CVCS ECCS RHR Unit 2 will replace auxiliary control room non-safety-related instrument loops with new Foxboro VA digital controls.

ACR Controllers 2-HTC-62-89C-CHRG HDR FLOW CNTL 2-HTC-62-56C-EXCES S LTDN FLOW 2-HIC-74-16C-RHRHX A OUTL CNTL 2-HIC-74-32C-RHR HX A/B BYPASS 2-HIC-62-83C-RHR LTDN FLOW CNTL

}-PIC-I-6C-SG 1 PORV CNTL 2-PIC-1.24C-SG 3 PORV CNTL 2-HIC-62-1 3 OC-VCT LEVEL CONTROL 2 -HTC.62-93C -CHARGING FLOW CNTL 2-HIC.63-65C-CL ACCUM N2 VENT 2-HIC-62-78C-LTDN HX OUTL TEMP 2-HTC-62-81 C-LTDN PRES SURE CNTL 2-HIC.74-28C-RHR HX B OUTL CNTL 2-PIC-I-13C-SG 2 PORV CNTL 2.PIC-1-3 IC-SG 4 PORV CNTL Simple skill performance that inherently provides task-intrinsic feedback and is procedurally addressed s2356 ACR Auxilrary Control Room Layout configuration of components on panel 2-L-ll A panel and 1-L-11 A panel.

Various Minor switch position location variances exist between Unit 1's 1-L-11A and Unit 2's 2-L-11A due to panel internal stiffener locations.

The location of LIC 1 5 68 and LIC I 648 on pan eI 2-L-11A was not moved due to panel stiffeners as stated above.

In Unit 1 the AFW Foxboro SPEC200 system is located in the large l-L-11A Panel. In Unit2 the location of the equipment will be in the smaller "Bailey Section" 2-L-11A Panel, which is located next to the large 2-L-1 1A Panel.

O-XS-62-241 Boric Acid Tank C Recirculation flow is a common loop and installed on 1-L-1lA panel only. There No significant operational differences to the component location between the units and no change to methods of operation.

47

DCN/

EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT will be no matching transfer switch for Unit 2Iocated in this location on 2-L-1 1A.

52357 ACR Auxiliary Control Room Layout configuration of components on panel 2-L-lI B panel and 1-L-11 B panel.

Various The instruments on the panels are installed opposite hand. On 1-L-11 B, panel layouts of components start with system 77 switches as you enter the room and progresses to the system I components. For 2-L4I B, panel layout starts with the system I switches as you enter the room and progresses to the system 77 components. This difference in the layout of components will cause the panel stiffeners for panel 2-L-Il B to interfere with the relocation of the some of the instruments mounted on the panel.

The locations of LIC-3-148B and L1C-3 -I7l B on panel 2-L-11 B were not moved on panel2-L-l1 B due to panel stiffeners as stated above.

No significant operational differences to the component location between the units and no change to methods of operation.

52690 ACR L10 UNIT 2 RECORDER 2-XR-068-0003C RCS Temperature Trend Reactor Coolant Unit 2 wiII have Paperless digital recorders. Unit 1 is replacing these recorders as they fail.

Improved information display 5242r ACR L10 Neutron flux monitor Excore Neutron Monitoring The wide range signal processor in pan eI2-L-10 will be in a different location than in Unit 1. The backup source range drawer is being removed from 2-L-10 due to obsolescence, and the wide range signal processor will be mounted in its place.

In Unit I due to cable routing, there was a potential for both channels to be functionally disabled due to a possible appendix R event. To address this, Unit I provided the ability to remove the wide range signal processor from the auxili ary control room, to get signal directly from the channel 1 optical isolator, and get power from channel2 amplifier. Unit 2 will route cables for the device in such a way that appendix R event will not be a concern.

No significant operational differences to the component location between the units.

48

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EDCR PANEL INDICATIONS &

CONTROLS SYSTEM DIFFERENCE OPERATIONAL IMPACT 5267 l ACR L10 Panel 2-XA-055-0L10 Annunciator 2-XA-055-0L10 will have different window numbering (300-306) than 1-XA-055-0L10 (273-279). This change is implemented to make the window numbers on adjacent panels increase as operators look around the room as requested by Operations.

• Both ulits ilstalled a bachrp nihogdl system that aulomatically supplies the AFW Level Control Valves and Pressure Conhol Valves should Control Air be lost.

49

ATTACHMENT 2 -Technical Specifications Differences

a. Technical Specification (TS) Definitions Section 1.1: Rated Thermal Power (RTP)

Definition - Unit I 3459 MWt, Unit 2 341 1 MWt. Unit I TS approved Power Uprate using Leading Edge Flow Meter (LEFM).

b. TS 3.1.8 and Surveillance Requirement (SR) 3.1.8.1 - uses Rod Position Indication (RPD. Unit I uses Analog Rod Position Indication (ARPD

c. TS 3.1.8 and SR 3.2.I.2,3.3.I.3, and 3.3.1.6 - Unit 1 reference to either movable incore detectors or PDMS, Unit2 changed reference to PDMS only

d. SR 3.3.1.3 - note 2 requirement is within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after Thermal Power is> 25Yo RTP. Unit 1 requirement is within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after Thermal Power is > 15% RTP.

e. TS Table 3.3.1-l:

i. Function 5, Source Range Neutron Flux, allowable values are < 1.33 E5 cps. Unit 1 allowable values are < 1.5 E5 cps.

ii. Function 11, Undervoltage RCPs, nominal trip setpoint is 5400 V. Unit 1 nominal trip setpoint is 4830 V.

iii. Function 14, Turbine Trip, allowable value is Z 38.3 psig. Unit 1 allowable value is > 43 psig.

f. *TS Table 3.3.1-1 and3.3.2-t - added footnotes in accordance with TSTF-493 that directs how to reset setpoint values during surveillance. No setpoints were changed.

g. TS Table 3.3.2-l - function 6e, Auxiliary Feedwater, Trip of all Turbine Driven Main Feedwater Pumps, allowable value is > 43.3 psig. Unit 1 allowable value is > 48 psig.

h. SR 3.3.2.5 and 3.3.6.5 - added allowance for use of Potter Brumfield MDR series relays. Unit 1 references Westinghouse relays only.

i. TS Table 3.3.3 footnotes F and H reflect new Common Q post-accident monitoring system. Unit I references the ICCM system.

j. SR 3.4.1.4 - removed "or elbow tap AP" as a method for verifying RCS total flow tate.

k.

• TS 3.4.6, 3.4.7,3.4.I0,3.4.I2 and SR 3.4.12.7-Unit 1 references a temperature of 350oF. Unit2 uses Cold Overpressure Mitigation System (COMS) arming. TS 3.4.10 and3.4.I2 - also expanded the APPLICABILITY to include Mode 4 based on all RCS cold leg temperatures relative to the COMS arming temperature specified in the PTLR. UNit 1 APPLICABILITY iS MOdCS I.2.ANd3.

50

1.

m.

n.

TS 3.4.7.b, SR 3.4.5.2, SR 3.4.6.3, and SR 3.4.7.2 - SG secondary side water level value changed to > 6%onarrow range. Unit 1 value is >32% naffow range.

SR 3.4.12.1 and,3.4.12.2 - frequency uses RCS cold legs decreasing below 225 oF.

Unit I uses RCS cold legs decreasing below 325 "F.

TS 3.4.17, 5.7.2.12,5.9.9, and SR 3.4.17.2 - steam generator tube integrity uses tube plugging or repair criteria and tubes shall be plugged or repaired. Unit 1 uses tube repair criteria and tubes shall be plugged SR 3.5.1.4 and,3.5.4.3 - Unit 1 includes "Notes" discussing TPBARs. Unit 2 does not have TPBARs. All other requirements in the Technical Specification and surveillance are identical.

TS 3.7.1 Action for one or more steam generators with one MSSV inoperable. Unit2 reduce Thermal Power to 359%o RTP. Unit I reduce Thermal Power to < 58% RTP.

Additionally, TS Table 3.7.I-l Allowable rated thermal power for Main Steam Safety Valves:

q. TS 5.7.2.I2.b.2 - accident induced leakage performance criteria includes "Leakage is not to exceed I gpm per SG, except for specific types of degradation at specific locations as described in paragraph c. of the Steam Generation Program." Unit I includes "For design basis accidents that have a faulted steam generator, accident induced leakage is not to exceed 1.0 gallon per minute (Spm) for the faulted steam generator and 150 gallons per day (gpd) for the non-faulted steam generators. For design basis accidents that do not have a faulted steam generator, accident induced leakage is not to exceed 150 gpd per steam generator."

r.

• TS 3.8.1, 3.8.2,3.8.4, and 3.8.5 - Removed the note referencing the C-S DG.

• TS 3.8.1 - Unit 2 has Condition "B" for one or more DG(s) in Train A or B inoperable with changes in Completion Times. Unit I has Condition "B" for one required DG inoperable and Condition "C" for two required DGs in Train A or B inoperable.

TS 4.2 and4.2.2 - Removed reference to Tritium Producins Burnable Absorber Rods (TPBARS).

TS 5.7.2.I2 - SG program differences associated with inspection frequency requirements.

TS 5.9.5.b - Core Operating Limits Report (COLR):

i. Removed clari$ing information and an analytical method associated with the use of the LEFM.

o.

p.

S.

t.

ll.

1. of Operable MSSV Unit 1 Rated Thermal Power Unit 2 Rated Thermal Power 3

<4IOA

<4204 2

<2504

<260 V.

51

d.

Analytical method listed as 2aupdated with newer method for Heat Flux Hot Channel Factor (HCF) and Enthalpy Rise HCF.

w. TS 5.9.6 - Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PrLR):

i. Added additional information related to the COMS.

ii. Differences in the listed analytical methods used for the PTLR.

TRM Differences:

a. TRM Definitions: Rated Thermal Power, Unit I 3459 MWt, Unit23411 MWt Unit 1 TS approved Power Uprate using Leading Edge Flow Meter (LEFM).

b. TRM 3.3.3: Unit t has movable incore detectors. Unit2 used fixed incore detectors referred to as Power Distribution Monitoring System (PDMS).

c. TRM 3.3.6: Unit t has a six sensor Loose Parts Detection Svstem. Unit 2has a twelve sensor Loose Parts Detection Svstem.

TRM 3.3.7: Unit I has a technical requirement in support of leading edge flow meters (LEFMs). Unit2 will not implement LEFM associated power uprate until NRC licensing review and approval of the LEFM uprate is completed.

TRM 3.3.8: Unit t has two Hydrogen Monitors. Unit2 has one Hydrogen monitor.

TRM 3.3.9: Unit 1 TR for Power Distribution Monitoring System (PDMS). Not used for Unit 2.

• These sections will be changed in Unit 1 Technical Specifications to match Unit2.

Upon completion of the Unit I changes these differences will be eliminated.

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