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Summary of Meeting with FPL Energy Point Beach, LLC on the Auxiliary Feedwater Modification Amendment
	ML092920127
Person / Time
Site:	Point Beach
Issue date:	10/28/2009
From:	Justin Poole; Plant Licensing Branch III
To:	; Florida Power & Light Energy Point Beach
	Poole Justin/DORL/LPL3-1/ 301-415-2048
References
	TAC ME1081, TAC ME1082
	Download: ML092920127 (45)
	v • d • e

{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 28, 2009 LICENSEE: FPL Energy Point Beach, LLC FACILITY: Point Beach Nuclear Plant, Units 1 and 2 SUB~IECT:

SUMMARY

OF THE SEPTEMBER 3, 2009, MEETING WITH FPL ENERGY POINT BEACH, LLC, ON THE AUXILIARY FEEDWATER MODIFICATION AMENDMENT (TAC NOS. ME1081 AND ME1082) On September 3, 2009, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of FPL Energy Point Beach, LLC (the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the Auxiliary Feedwater (AFW) modification and the location of AFW modification information in the licensee's Extended Power Uprate (EPU) submittal. A list of attendees is provided as Enclosure 1. The licensee's presentation is provided as Enclosure 2. DISCUSSION The meeting began with the licensee's presentation describing the relationship between the AFW modification and the EPU license amendment request (LAR). Specifically, the licensee described a matrix that listed the sections of the EPU where the AFW modification is proposed in the LAR. Also, the licensee listed the EPU Chapter 14 accident analysis for AFW flow requirements and the associated methodologies. The majority of public meeting focused on the design of the AFW modification. The licensee summarized the design and the design approach and then talked in detail to the different design features. During the remainder of the meeting, the licensee detailed specific portions of the AFW system design (seismic, flow, electrical, instrumentation and control, etc.) and the NRC staff asked clarifying questions to gain a better understanding of the licensee's proposed design changes. During the discussion on the electrical design, the NRC staff stated that further justification would be needed for the worst-case maximum voltage dip for emergency diesel generator transient loading. The NRC staff had previously asked this question in a request for additional information (RAI) prior to this meeting and the licensee was in the process of responding to the RAI. The NRC staff from the Balance of Plant Branch described a few draft questions that they had developed during their review and planned to submit as formal RAls.

- 2 Members of the public were not in attendance. Public Meeting Feedback forms were not received. Please direct any inquiries to me at 301-415-2048, or Justin.Poole@nrc.gov. Justin C. Poole, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosures:

1. List of Attendees

2. Licensee's Presentation cc w/encls: Distribution via Listserv

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Point Beach Agenda

Opening
Purpose
Applicable Safety Analyses
AFW EPU LAR Review Matrix
AFW Design
Plan Going Forward

'era ENE~ RUOURCES 2

Point Beach Qpening

Appreciate Staff support to date
NextEra committed to resolving long standing items (RIS 2005-20) and improving the plant
AFW System upgrade is very important to nuclear safety and is integral with improving overall plant safety margin as part of the extended power uprate
NextEra committed to working with Staff to support and facilitate an efficient review
Encourage active dialog between NextEra and Staff to gain the most benefit from the meeting 3

Point Beach Purpose

Discuss applicable safety analyses related to AFW System design
Summarize AFW EPU LAR review matrix
Present AFW System design details
Review schedule

'era ENE.RRGiX~ ~:I)URCES 4

Point Beach ~Iicable Safety Analyses

AFW Flow Optimization
EPU Chapter 14 accident analysis for AFW flow requirements LONF - Loss of Normal Feed LOAC - Loss Of all AC power to the station auxiliaries SGTR - Steam Generator Tube Rupture SBLOCA - Small Break Loss Of Coolant Accident MSLB - Main Steam Line Break Discuss applicable safety analyses related to AFW System design
Revised Methodologies RETRAN GOTHIC rera ENS~

5

Point Beach AFW EPU LAR Review Matrix 2 long standing (RIS 2005-20) items Associated EPU LAR sections Auxiliary Feedwater/Condensate Storage Offsite, AC Onsite and DC Onsite Power Systems EDG Fuel Oil and Service Water RPS/ESFAS and Control Systems Setpoint Methodology SBLOCAlAccident and Transient Analyses Loss of Normal Feedwater/Loss of AC Power Steam Generator Tube Rupture Mass and Energy Releases/Containment Integrity Station Blackout/ATWS Fire Protectionllnternally Generated Missiles/EQ/Human Factors Safety Related Pumps and ValvesNentilation Systems RETRAN, GOTHIC methodology changes -- LONF, LOAC, Containment Integrity See review matrix handout '*'-era ENER0:tfa /fJ"ftf" RUI)URCU 6

Point Beach AFW System Desi9.!l

Design Attributes of new MDAFW pump trains Unitize MDAFW pump trains 1000/0 capacity pumps Powered by 4 kV safety related switchgear Controls in control room and local Pumps will be automatically started for SG low low level, LOOP and SI signals and can be manually operated New suction line from Condensate Storage Tank (CST) supply for new MDAFW pumps Auto transfer of normal suction source from CST to Service Water (SW) for MDAFW and TDAFW pump Anticipated Transient Without SCRAM Mitigating System Actuation Circuitry (AMSAC) Start Signal

<<era EN~ 7

Point Beach AFW System Design - Summary Increased Flow Margin MDAFW Pump Flow Margin: -- New MDAFW train needs 275 gpm @ -2800 ft -- New MDAFW pump is capable of 275 gpm @ 3050 ft Flow limited to 385 gpm with single failure of a discharge control valve Turbine Driven Auxiliary Feedwater (TDAFW) Pump Flow Margin -- TDAFW train needs 275 gpm @.... 2925 ft -- TDAFW pump is capable of 275 gpm @ 3010 ft Capable of -430 gpm with full open discharge valve 480 V System Margins Gained With Replacement Reduces operator manual action requirements Reduce risk of motor trip on start Retains original MDAFW pumps as SSG pumps Use for normal startup and shutdown Improves overall plant safety margin AFW reliability improved Reliability is dominated by Operator failing to switch AFW pump suction to SW Auto switch-over eliminates this operator action and interruption of AFW flow oorera EN~~~ 8

Point Beach AFW System Design - Overall Design A(Wroach MDAFW TDAFW Power Supply Train B (Unit 1) Train A (Unit 2) Train A (Unit 1) Train B (Unit 2) Primarily AC

DC for switchgear control power and pump and valve controls
DC supply for SW Suction Supply Valve
DC supply to inverters for 120 Vac vital instrumentation busses Primarily DC
AC to battery chargers Tera ENER~

,".?........RHOURCU 9

Point Beach AFW System Design - Overall Design Al;Wroach MDAFW TDAFW Location 8 ft Elevation of PAS 8 ft Elevation of Control Building Hydraulic Design Pump design point 275 gpm at 3050 ft Flow control valves with backup pneumatic supply system Cavitating venturis to prevent excess flow on loss of controller Pump capability 275 gpm at 3010 ft Fixed position thrattle valves Initiation Signals Low-low water level in either steam generator, Loss of both 4.16 kV buses supplying the main feedwater pump motors, ATWS Mitigation System Activation (AMSAC) signal, or r\\IF)(Ter~ Safety Injection sequence ENER~ 10

Point Beach AFW System Design t~EX5J'.§.tfZ!I'L.:J1Q1Q[_LLQ~LE.Q1Jl§__E.fZr:.....UQjJ With Shored Standby Steam Generator {SSG) DUrrp System 10 ""11 2 $tDCml G.,,.,.,..Qttr ~E"YltE ** lEA.,,~*. o TO....11 2 5" IoIOICII 2 ~I" N ~~ TO UHfT 2 SR .HeR ----j lCEllm~~) WO"OROAIV[~Pt.M' I..... n) SSG PlM' i I I I ! r f 1(Jj 1 S(l..,.t~ ae'atec: PullP ~ ~ l:d CST 1:1 .'4 MAl" 'HO ...T[A "!'HRClhrO [. '~.!; t:::l-1--f'..J-----{X] I TO UIIl1 S1"l!tCft Clrf'lCIrc't-or lm-A>>SQ~=1~:*M~~ ~ ~ ....J.. a SSG fJ1lP tS ' I:; ~ cst I:! "I" ,,"YICl.AlE" CS1 "-I'l-- 0 I""~~"-'"...".",...,,,,,. SrqYlC£..... tER..... I -1 IOO'X. a ELECTRic CS TANK CS TANK O'lIYU PU'" ~I:~~~ ~ I 'era ENERGY@ ,'7.**C~ES 11

Point Beach AFW System DesiQ.!! LAKE SIDE Unit 2 TB tIIJlIiI

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Unit 1 TB ~

Tera ENEf3GVR
- ,~m 12

Point Beach AFW System Design - Single Failure Criteria

Two 100% Capacity AFW Pumping Systems Per Unit One TDAFW One MDAFW
Independent Power Supplies for Redundant Pumping Systems.
No Active Components Shared Between Redundant Pumping Systems.

'era ENERG.'{~ /*""",", ~UOU~tU 13

Point Beach AFW System Design - Seismic Design Classification

MDAFW Pumps, Motors, Piping, Valves, Electrical Components and Instrumentation are Seismically Qualified.

Pumps and motors qualified by supplier by analysis to PBNP specific g-values - Piping qualified by analysis per PBNP Design Guides - Valves qualified by suppliers to bounding g-values Electrical components qualified by analysis or testing to PBNP specific or bounding g-values or via SQUG methodology Instrumentation qualified by analysis or testing to bounding g-values Electrical raceway qualified by combination of analysis and SQUG methodology °Tera ENERCl~ ,<iA~""" .~ ./~V RESOURCES. 14

Point Beach AFW System Design - MDAFW Pumping System Environmental Conditions

Temperatures Normal PAS maximum temperature 85°F Abnormal temperature less than 130°F 8 ft Elevation of PAS not subject to HELS temperatures
Pressure Normal PAS pressure slightly above atmospheric 8 ft Elevation of PAS not subject to HELS pressurization
Radiation Normal radiation level 1300 RAD 60 year TI D Abnormal radiation level in MDAFW pumps rooms due to CVCS demineralizer flushing operations less than 20-30 mRem/hr at the floor level. The elevated dose rates exist for approximately 10 hrs/year.

Accident radiation - AFW Pump are not required to operate during recirculation phase of a Loss of Coolant Accident and thus need not be qualified for post LOCA harsh radiation levels on 8 ft Elevation of PAS "!"era ENE.=RGYA ~~cu 15

Point Beach AFW System Design - MDAFW Performance Parameters

Pump Performance Design Point 275 gpm at 3050 ft Flow control valves set to deliver minimum of 137.5 gpm flow to each steam generator Control valve approximately 55°~ open with design pump performance and steam generator pressure equal to lowest safety valve setting plus steam line losses
Pump Motive Force 337 HP at 275 gpm Approximately 295 gpm at 350 HP (motor rating)
Pump NPSH NPSH Required at 300 gpm < 12 ft absolute Water height to meet NPSH requirement - 4 ft 16

Point Beach Auxiliary Feedwater (AFW) Flow Rate

Hydraulic model developed to determine AFW flow rates for various operating scenarios and single failures
The minimum required AFW flow rate to two SGs is 275 gpm for LOAC and LONF events
Minimum AFW established based on:

SG lowest pressure main steam safety valve lift setpoint plus steam line pressure losses Assumed single failure of a TDAFW or MDAFW Pump ~~~era ENER~i(~ -*#,~,jif'l"""* ' AE SiI)U ACES 17

Point Beach Auxiliary Feedwater (AFW) Flow Rate Maximum AFW flow rates established for MSLB mass and energy inputs Both MDAFW and TDAFW Pump operating Pump design curves MDAFW flow control valve failed open Maximum AFW flow rates established for SG tube rupture event Both MDAFW and TDAFW Pump operating Pump design curves AFW flow control valves set at upper flow control limit "Tera ENERG'{G ~RCES 18

Point Beach AFW System Design - Electrical System Impacts

AC system analyzed for impact of new MDAFW pumps The MDAFW pump motors will not be the AC degraded grid safety limit voltage limiting components. The MDAFW pump motors can successfully start and run at the safety limit voltages.

AC degraded grid performance for the existing limiting safety related equipment improved by moving MDAFW pump from 480V to 4160 V. The maximum momentary asymmetrical and interrupting fault currents for 4160 V busses are within the ratings of the bus and breakers. - Short circuit duty reduced for 480 V safety buses during DBA.

New MDAFW pump breakers sized to protect power cables and coordinate with upstream breakers
Power cables have significant ampacity margin "era ENE~~

f'" WESOURCU 19

Point Beach AFW System Design - Electrical System Impacts

EDG Static Loading G-01 / G-02 (Train A) - Continue to operate within 2000 hr rating of 2850 kW for the worst case design basis accident EDG electrical loading condition.

-- G-01 2801 kW -- G-02 2800 kW G-03 / G-04 (Train B) - Continue to operate within 200 hr rating of 2951 kW for up to 24 hours and remain within 2000 hr rating of 2848 kW after that for the worst case design basis accident EDG electrical loading condition. -- G-03 2877 kW -- G-04 2874 kW rera ENE~ >/,,- RESOURCES 20

Point Beach AFW System Design - Electrical System Impacts

EDG Transient Loading Worst Case Maximum Voltage Dip - The resulting worst case calculated transient voltage dip is approximately 48%. Based on ETAP results, this voltage dip has no adverse affect on the ability of G-01 or G-02 to accept and accelerate all auto connected loads. For G-03 and G-04, EDG transient voltage dips remain above 75%.

Motor Acceleration Times - The most significant increase in motor acceleration time is associated with the new MDAFW pump, which is due to a worst case conservative lumped load of MDAFW pump/Sl/CCW/MCC loads at EDG breaker closure. The increase is from 2.72 seconds to 3.84 seconds with an acceptance criteria of - 5.0 seconds. Generator Frequency Response - The transient frequency response of all four EDGs remains above 57 Hz at all times. <<i'era EN~~~ 21

Point Beach AFW System Design - Electrical System RAls

Information on cables routed through duct banks and design features to prevent cable submergence and periodic cable testing Duct bank inspections Cable testing
Clarification of time delays for 4.16 kV and 480 V Loss of Voltage Relays and EDG design basis 22

Point Beach AFW System Design - Electrical System RAls

Request for additional supporting documentation used in developing response to acceptance review questions 1 through 7

- Calculation List -- ETAP -- EDG Loading - Static - Dynamic -- EDG Fuel Oil -- Cable Ampacity -- Breaker Coordination -- Loss of Voltage Relay Calculations - Calculation Summaries -rera ENERG"L~ >~URCU 23