ML17223B201

Summary of 910521 Meeting W/Florida Power & Light Co Re Implementation of Station Blackout Rule at Facility

ML17223B201
Person / Time
Site:	Saint Lucie
Issue date:	05/28/1991
From:	Norris J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9106060175
Download: ML17223B201 (40)

Text

'c Docket Nos.

50-335 and 50-389 I<ay 28, 199]

LICENSEE: Florida Power and Light Company (FPL)

FACILITY: St. Lucie Units 1 and 2

SUMMARY

OF THE MEETING TO DISCUSS IMPLEMENTATION OF THE STATION BLACKOUT RULE AT ST.

LUCIE 1

AND 2 On May 21, 1991, the NRC staff met with Florida Power and Light Company (FPL) to discuss implementation of the Station Blackout Rule, 10 CFR 50.63 (SBO) at the St. Lucie Plant.

Enclosure 1 lists the attendees.

Enclosure 2

contains the slides FPL used during the presentation.

After the introduction, FPL reviewed the chronology of SBO at the St. Lucie Plant and outlined the electrical design of the station, including the proposed crosstie between the units.

Then the operational and technical considerations of the required modifications were discussed.

Finally, FPL presented a list of proposed revisions to the staff's dr aft SER issued on November 21, 1990.

The staff agreed to review the proposed changes.

Original.-signed by

Enclosures:

As stated cc w/enclosures:

See next page Distribution Jan A. Norris, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation FC:LA: DII-NAME

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SUMMARY

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LUCIE RIIMHE CGER MPV q 9106060175 910528 PDR'DOCK 05000335 P

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Florida Power 5 Light Company St. Lucie Plant CC:

Jack Shreve, Public Counsel Office of the Public Counsel c/o The Florida Legislature 111 West Madison Avenue, Room 812 Tallahassee, Florida 32399-1400 Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.

Kwy A1A Jensen Beach, Florida 33457 State Planning 5 Development Clearinghouse Office of Planning 5 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Harold F. Reis, Esq.

Newman 5 Holtzinger 1615 L Street, N.W.

Washington, DC 20036 John T. Butler, Esq.

Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. James V. Chisholm, County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Inc.

12300 Twinbrook Parkway,=Suite 330 Rockvi 1 le, Maryland 20852 Mr. Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. R.

E. Grazio Director, Nuclear Licensing Florida Power and Light Company P.O.

Box 14000 Juno Beach, Florida 33408-0420 Mr. J.

H. Goldberg President - Nuclear Division Florida Power 5 Light Company P.O.

Box 14000 Juno

Beach, FL 33408-0420

Meeting Summary dated May 28.

1991 Distribution

'Doc 'Det 7 i !es NRC 5 Local PDRs T. Murley F. Miraglia J. Partlow S.

Varga G. Lainas PDII-2 RF D. Miller J. Norris H. Berkow OGC E. Jordan, MNBB F.

Rosa R. Auluck J. Knight M. E1-Zeftawy T.

Ross D. Dorman D.

Shum J.

Raval P. Gill K. Jabbour S. Elrod, RII R.

Lo C. Y. Liang A. Thadani G. Hubbard ACRS (10)

J. Nechselberger M. Sinkule, RII 3701

, 17-G-21

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MEETING BETWEEN FLORIDA POWER AND LIGHT COMPANY AND NRC STAFF - ST.

LUCIE PLANT ENCLOSURE 1

ATTENDANCE RECORD NAME Jan Norris Herbert Berkow Faust Rosa Rajender Auluck Jim Knight Bob Grazio Tedd Dillard Vittorio Pareto Med El-Zeftawy Roger Kulavich Thierry Ross Ron Pennenga J.

Laduca R.

C. Munter Dan Dorman Mike Schoppman David Shum Lamar McLaughlin J.

H. Rava 1 Paul Gill Gabe Sa lamon Thomas E. Roberts Kahtan N. Jabbour Stephen Elrod Ronnie Lo Chu-Yu Liang Ashok Thadani Ed Weinkam George Hubbard AFFILATION NRC/NRR/PDII-2 NRC/NRR/PDII-2 NRC/NRR/SELB NRC/NRR/PDII-2 NRC/NRR/DST/SELB FPL/Dir. Nucl. Lic.

FPL St. Lucie Devonrute NRC/ACRS FPL St. Lucie Tech. Staff NRC/NRR/PDII-4 FPL/St. Lucie/Operations FPL/Nuclear Engineering FPL/Nuclear Engineering NRC/NRR/PDII-2 FPL/Nucl. Licensing NRC/NRR/SPLB FPL/Plant Licensing NRR/SPLB NRR/SELB FPL/Turkey Point Licensing FPL/Engr. Proj. Mgr.

NRC/NRR (Hatch PM)

NRR/Region II NRR/PD II-I NRR/DST/SRXB NRR/DST FPL NRR/SPLB

ENCLOSURE 2

St. Lucie Nuclear Plant OTk.T'IiQPf %3ILKQXQtUT MAY21, 1991 910401hfAC

FPL/NRC MEETING STATION BLACKOUT ST. LUCIE NUCLEAR PLANT MAY21, 1991 AGENDA INTRODUCTION/OBJECTIVES McLAUGHLIN LICENSING BACKGROUND WEINKAM ELECTRICAL DESIGN MUNTER OPERATIONAL CONSIDERATIONS PENNENGA TECHNICALCONSIDERATIONS MUNTER

SUMMARY

McLAUGHLIN

MEETING OBJECTIVES

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PRESENT FPL PLANS

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OBTAINA CONSISTENT UNDERSTANDING BETWEEN FPL AND NRC OF SBO REQUIREMENTS

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CONFIRM FPL'S PLANS MEET 10CFR50.63 AND LICENSING BASIS REQUIREMENTS

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DOCUMENT CONCLUSIONS FROM MEETING WORK TOWARD CLOSURE OF STATION BLACKOUT FOR ST. LUCIE

CHRONOLOGY OF 10 CFR 50.63 AT ST. LUCIE PLANT

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JUNE 21, 1988 NRC PUBLISHES SBO RULE IN FEDERAL REGISTER, EFFECTIVE JULY 22, 1988 APRIL 17, 1989 FPL RESPONDS TO SBO RULE FOR UNIT 1 AND UNIT2 (L-89-145)

FPL'S LICENSING ASSUMPTIONS FOR SBO MODIFICATIONDESIGN BASES ARE:

- 10 Minute clock defined

1. Starts at identification of SBO

2. Ends at powering of SBO unit bus

- 4 Hour SBO Duration

- 0.95 Emergency Diesel Generator (EDG) Reliability

- Hot Standby For 4 Hours

- FPL committed to complete the modifications by December 31, 1991

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OCTOBER 17-1 9, 1989 NRC AND SAIC CONDUCT SBO AUDITIN JUNO BEACH

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MARCH 7, 1990 FPL PROVIDES RESPONSE TO NRC COMMENTS/QUESTIONS FROM SBO AUDIT(L-90-58)

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NOVEMBER 21, 1990 NRC FORWARDS DRAFT SAFETY EVALUATIONON SBO AT UNIT 1; UNIT2 EXEMPTED BY REGULATIONS

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DECEMBER 21, 1990 FPL FORWARDS COMMENTTO NRC ON DRAFT SBO SAFETY EVALUATION(L-90-452)

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STATION BLACKOUTCHRONOLOGY AT ST. LUCIE UNIT2

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ON JULY 30, 1980, THE NRC'S ATOMICSAFETY AND LICENSING APPEAL BOARD, IN ALAB603:

Determines that the design of the circuits connecting St. Lucie Unit 2 to the offsite grid is in compliance with NRC regulations Concludes that the probability of a complete loss of electric power (other than onsite battery power) at the facility should be designated a "design basis event" Directs FPL to include in its FSAR an analysis demonstrating the ability of St. Lucie Unit 2 to withstand such a total loss of power

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IN DECEMBER 1981, ST. LUCIE UNIT2 OPERATING LICENSE REVIEW (NUREG-0843) SECTION 1 5.10.8 (SSER N)

Section 15.10.8 NRC Staff states that the event is a ~licensin basis event for St. Lucie Unit 2 NRC Staff finds "...that the plant system response is acceptable for total station blackout"

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ON NOVEMBER 21, 1990 THE NRC STAFF SAFETY EVALUATION ACKNOWLEDGESTHE ST. LUCIE UNIT 2 EXEMPTION FROM 10 CFR 50.63

ELECTRICALSYSTEM DESIGN ST. LUCIE PLANT

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ST. LUCIE IS A TWO UNITSITE WITHTWO COMBUSTION ENGINEERING PRESSURIZED WATER REACTORS

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THE TWO MAINGENERATORS ARE WESTINGHOUSE 1000 MVA GENERATORS THATPRODUCE APPROXIMATELY900 MWe AT 22 KV

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THE FOUR BAY240 KVSWITCHYARDPROVIDES SWITCHING CAPABILITYFOR EACH UNIT'S MAINGENERATOR ANDTWO STARTUP TRANSFORMERS ANDTHREE OUTGOING TRANSMISSION LINES THE ELECTRICALSYSTEM FOR EACH UNIT IS AN A/B TRAIN DESIGN WITH A SAFETY RELATED SWING BUS (AB)

THE SWING BUS CAN BE MANUALLYALIGNEDTO EITHER TRAIN EACH TRAIN HAS A SAFETY AND NON-SAFETY RELATED PORTION WITH EACH SAFETY RELATEDTRAIN HAVINGITS OWN EMERGENCY DIESEL GENERATOR

ST. LUCIE PLANTSIMPLIFIED ONE LINE DIAGRAM HUTCHINSON ISLANDSUB.

MIDWAY¹3 MIDWAY¹2 MIDWAY¹3 240 KV WEST BUS S.T. ¹18 S.T. ¹28 M.T. ¹ 2 S.T. ¹2A S.T. ¹1A 240 KV WEST BUS M.T.¹I G2 G1 UAT¹28 UAT¹2A UAT¹1A UAT¹18 III ES Q

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RS I ml IIIN II El RR IIII RR II Im 283 2A3

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EDG 28 EDG EDQ 2A 1A 1AB EDQ 18

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10 CFR 50.63 MODIFICATION ST. LUCIE UNITS 1 AND 2

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INSTALLAN INTER-UNITCABLE CROSS TIE CAPABLE OF TRANSFERRING POWER FROM ANYEDG TO ANYSAFETY-RELATED4.16 KV SWITCHGEAR THROUGH THE SAFETY RELATED SWING BUS (6-1/c 350MCM POWER CABLES)

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THE STATION BLACKOUTCROSSTIE HAS BEEN DESIGNED TO CARRY MORE THANTWICE THE ANTICIPATEDSTATION BLACKOUTLOADS

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ADD APPROPRIATE CONTROL AND INDICATIONEQUIPMENT IN THE CONTROL ROOMS OF BOTH UNITS SUCH THATTHE CROSS-TIE CAN BE ACCOMPLISHED FROM THE CONTROL ROOMS

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THIS MODIFICATIONSATISFIES THE OBJECTIVES TO'ncrease flexibilityof the plant's electrical distribution to cope with emergency events Increase the capability of the operators to accomplish this from inside the Control Room Significantly decrease the amount of time and effort currently required to accomplish this task

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10 CFR 50.63 MODIFICATION ST. LUCIE UNITS 1 AND 2 EDG 2A EDG 1A 2A3 1A3 2AB 1AB

)'-'. (

SBO MODIFICATION:

'B3 1B3 EDG 2B EDG 1B NOTE:

SIMPLIFIED ONE LINE DIAGRAMOF THE 4.16KV SAFETY RELATED SWITCHGEAR

10 CFR 50.63 MODIFICATION CONTROL ROOM CONTROLS AND INDICATION ST. LUCIE UNITS 1 AND 2 G

R 4160V SWGR.

1AB UNIT X-TIE BKR G

A R

4 t 60V SWGR.

2AB UNIT X-TIE BKR NORMAL NOTE:

UNIT2 CONTROL ROOM MODIFICATIONSARE SHOWN.

UNIT 1 MODIFICATIONSARE SIMILAR.

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OPERATIONS DEPARTMENT SBO GOALS

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MAINTAINCONTROL OF ALLSAFETY FUNCTIONS ON BOTH UNITS

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MAINTAINHOT STANDBY (MODE 3) CONDITIONS Minimum amount of safety equipment requiring emergency AC Power Core Heat Removal readily accomplished by Natural Circulation Reduced stress compared to the actions required by performing an RCS cooldown Reduced RCS make-up demand

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TO QUICKLY CROSS CONNECT TO THE OTHER UNIT'S AC POWER

SUPPLY, PROVIDING POWER TO EQUIPMENT NECESSARY TO MAINTAINHOT STANDBY WITH THE MINIMUM AMOUNTOF OPERATOR ACTION

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TO PROVIDE UNIFORM AND DETAILED PROCEDURAL GUIDANCE TO OPERATIONS STAFF FOR HANDLINGSBO CONDITIONS Provide directions and precautions Reference point for both control rooms for event strategy 1

Uniform EOPs designed to enhance operator familiarity no matter which unit he is on 10

STRATEGY CHART GRID DISTURBANCE 1

I I

1 REACTOR TRIP I STANDARD POSTTRIP I

I ACTIONS PERFORMED I\\l SBO DIAGNOSTICS YES SBO NO CONFIRMED YES SBO SAFETY FUNCTION SATISFIED

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APPROPRIATE RECOVERY GUIDEUNE ESTABUSH SG FOR NAT. CIRCULATiON MAKEREADYAC BUSES FOR POWER RETURN RESTORE ESSENTIAL EQUIPMENT YES AC POWER NO AVAILABLE

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ATTEMPTTO RESTORE AC POWER GO TO LOOP FOR RECOVERY MINIMIZE

a. BATTERYLOADS

b. RCS LEAKAGE MAINTAINNAT.

CIRCULATION

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SAFETY FUNCTIONS (EOP-01)

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REACTIVITYCONTROL

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MAINTENANCEOF VITALAUXILIARIES

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RCS INVENTORYCONTROL

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RCS PRESSURE CONTROL

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CORE HEAT REMOVAL

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RCS HEAT REMOVAL

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CONTAINMENTISOLATION

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CONTAINMENTPRESSURE/COMBUSTIBLE GAS FlQRIQAPOWER 4 UGNT R5~mC ST. WCIE PLANT UNITNO. 1 FLORIDA POWER@ UGIIT ET. IICtEPLANT mme UNITNO. 2 1-EOP41 REWSON 8 2-EOP41 REVIQOH 5

%YERN

%VEND SI'PRUNED IIP

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PEPE IJVeyEP fKVRKH

%VER%0 Sf fRR7fKO W OATE RQ CH a

PEEI IEPEEEI s

IR-Il-90 a-u-9o PVC Integer OPERAlCt4

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OPERATOR MILESTONES ON SBO ST. LUCIE UNIT 1 WITH LOOP ST. LUCIE UNIT2

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ENTER APPROPRIATE RECOVERY GUIDELINE ST. LUCIE UNIT 1 wilt implement EOP 10 ST. LUCIE UNIT 2 willimplement EOP 9

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ASSESS CORE AND RCS HEAT REMOVAL CAPABILITIES ON BOTH UNITS Establish flowvia C AFW pump Verify natural circulation

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ESTABLISH COMMUNICATIONS

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SECURE NON-ESSENTIAL UNIT 2 LOADS

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STRIP UNIT 1 EMERGENCY BUSES

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CLOSE SBO CROSSTIES

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RESTORE UNIT 1 VITALLOADS

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STABILIZEBOTH PLANTS RESTORE AC POWER

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EXIT EOPS, ENTER AN APPROPRIATE OPERATING PROCEDURE 13

EMERGENCY DIESEL GENERATOR ST. LUCIE UNIT2 LOAD RATINGS*

CONTINUOUS 3685 KW 2000 HR 3935 KW 200 HR 3985 KW 4HR 3985 KW 30 MIN 3985 KW

• NOTE:

1. The EDG ratings are based on a 104 F air intake temperature.

2. The EDG's are rated for worst case operating conditions.

An air intake temperature above 90 F

derates the engine capacity.

kw 4000 ST. LUCIE UNITS 1 AND 2 EDG LOAD PROFILE 200 HOUR RATING ( 3985 kw )

3641 kw ( 91% )

3500 3000 2500 A

CROSSTIE ACCOMPLISHED 2000 1500 1000 1736 kw(44%)

. EDG COOLING WTR. HTRS OFF

. EDG GEN. HTR. OFF

~ MOVS. REPOSITIONED

. AFW. PUMP SECURED

. BATCHRGS REDUCED TO EQUIVALENTOF 1

. RCP OILLIFT PUMP SECURED 500 UNT2 AUTO SEQUENCE UNTIE AUTOSEQUENCE

. MOVS REPOSITIONED

. 2 CONT. FAN COOLERS (2) SECURED

. HEATTRACING LOAD REDUCED 03 69 18 21 24 27 30 33 38 90 300 900 15001503 1518 1530 1560 15 25 26 28 30 40 50 60 90 120 2

4 6

8 NOTE: 1. THIS EDG LOADPRORLE IS BASED ON UNIT2 INA LOOP AND UNIT1 IN AN SBO EVENT.

2. THIS EDG LOADPRORLE IS FOR TRAIN"A" OF BOTH UNITS ( WORST CASE ).

EDG LOAD PROFILE ASSUMPTIONS ST. LUCIE UNITS 1 AND 2

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ELECTRICAL-LOAD FOR PUMP MOTORS IS BASED ON THE BRAKE HORSEPOWER AT PUMP RUN OUT OR OPERATING CONDITIONS h

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SHUTDOWN COOLING '(LPSI) PUMPS ARE NOT INCLUDED IN THE UNIT 1 OR 2 LOADS Both Units will maintain Hot Standby conditions The LPSI pumps are not automatically started for a LOOP event

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STEAM DRIVEN AUXILIARYFEEDWATER PUMPS ARE USED ON BOTH UNITS 'I AND 2

- 'team driven AFW pumps are available. Therefore, the motor driven AFW pumps are not required.

200 HOUR RATING OF THE EDGs WILLBE USED l~ ~

Power willbe restored within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> i

EDG tested every 18 months for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rating

REACTOR COOLANTSYSTEM INVENTORY ST. LUCIE UNIT 1

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COMBUSTION ENGINEERING NSSS

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THERMALCORE RATING OF 2700 MWt

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2 STEAM GENERATORS WITH 4 REACTOR COOLANT PUMPS

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3 CHARGING PUMPS. RATED AT 44 gpm EACH TOTAL RCS INVENTORY (NORMAL OPERATION) OF 75,000 GALLONS PRESSURIZER LIQUIDVOLUME (NORMAL OPERATION) OF 4500 TO 6000 GALLONS 17

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REACTOR COOLANT SYSTEM INVENTORY ST. LUCIE UNIT 1

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ASSUMPTIONS IN DRAFT SER FOR RCS LEAKAGE Maximum allowable RCS leakage per plant Technical Specifications (12 gpm for identified and unidentified) 25 gpm per pump losses through Reactor Coolant Pump seals (4 RCPs)

Therefore, a total of 112 gpm I

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FPL ASSUMPTIONS FOR RCS LEAKAGE Unit 2 SBO analysis is applicable to Unit 1 Maximum allowable RCS leakage per plant Technical Specifications (11 gpm for identified and

unidentified)

Nominal RCP seal leakage of 1.25 gpm per pump (4 RCPs)

Therefore, a total of 16 gpm 18

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REACTOR COOLANTSYSTEM INVENTORY ST.

I UCIE UNIT 1

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BASIS FOR RCP SEAL LEAKAGEASSUMPTION RCP seal maintains integrity after seal cooling is lost 1

A test by the pump manufacturer in August 1980 Greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> at Hot Standby conditions without cooling Maximum seal leakage was less than 0.3 gpm (16.1 gph)

Operational experience at St. Lucie Units 1 and 2 (approx.

23 reactor years) 13 RCP seals subjected to loss of cooling No significant increase in seal leakage

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HVAC EVALUATION ST. LUCIE UNIT 1

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AN ENGINEERING EVALUATIONWAS PERFORMED FOR THE CONTROL

ROOM, REACTOR CONTAINMENT BUILDING, AUXILIARYBUILDINGAND ELECTRICAL EQUIPMENT ROOMS FOR THE SBO EVENT

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THE EVALUATIONCONCLUDED THAT ROOM TEMPERATURES REMAIN BELOW PREVIOUSLY ANALYZEDVALUES 20

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SUMMARY

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OPERATOR ACTIONS REQUIRED FOR SBO AND NBO UNITS

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FPL LICENSING ASSUMPTIONS STATION BLACKOUTMODIFICATION

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REQUESTED REYISIONS TO SAFETY EVALUATION

REQUESTED REVISIONS TO NRC DRAFT SAFETY EVALUATIONON SBO PROPOSED CHANGE Add St. Lucie Unit 2 docket number to the SE.

Delete the recommendation that FPL verifythe NBO unit's auxiliary or startup transformer capacity sufficiency.

Revise SBO and NBO units SBO/LOOP loads.

SE SECTION/

SE PAGE Cover letter and page 1 of SE Section 2.1/

page 3 Section 2.2.2/

pages 5 and 6 REASON FOR CHANGE=-

The Unit 2 licensing basis for SBO is being amended by the SE.

FPL concurs that St. Lucie Unit 1 should be classified as independence of offsite power group l3.

The SBO and LOOP loads have been recalculated by FPL.

Clarifythat the time to repower SBO bus is 10 minutes from identification.

Section 2.2.2/

page 6 Section 2.3.5/

page 7 FPL has committed to repower the SBO unit's bus with the AACsource within 10 minutes following confirmation that an SBO has occurred.

Delete requirement to'power motor<riven AFW pump and LPSI pump on AACsource for the NBO unit.

Section 2.2.2/

page 6 FPL willprovide decay heat removal for the NBO unit using the turbine-driven AFW pump. FPL willmaintain the SBO and NBO units in Hot Standby; therefore there is no need to provide for forced cooling decay heat removal.

Revise the AACsource load limit rating to the 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> rating.

Section 2.2.2/

page 6 FPL tests the NBO EDGs for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rating every 18 months.

Event postulated to last no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

REQUESTED REVISIONS TO NRC DRAFT SAFETY EVALUATIONON SBO PROPOSED CHANGE Delete the reference to diesel-driven air compressors.

Revise the hypothesized RCS inventory loss rate to 16 gpm from the 112 gpm presented in the SE.

SE SECTION/

SE PAGE Section 2.3.3/

page 7 Section 2.3.6/

page 7 REASON FOR CHANGE The instrument air compressors at St. Lucie Plant are not diesel driven; the air compressors can be powered from the EDGs.

FPL has tested the St. Lucie Units 1 and 2 RCP seals under operating conditions without cooling. The leak rate determined by this testing was significantly less than the postulated value in the draft SER.

Revise the SE Section discussing the proposed modifications implementation schedule to reflect the 10 CFR 50.63 (c) (3) rule requirement of implementation within 2 years of the completion of the NRC's regulatory assessment.

Section 2.5/

page 8 FPL requests that the NRC Staff reflect in the SBO rule-required Safety Evaluation the scheduler requirements for implementation of the SBO modifications as specified in 10 CFR 50.63.

Revise the SE discussion of AAC power sources to accommodate securing of non-essential LOOP loads (NBO Unit).

Section 2.2.1/

pages 4-5 Section 2.2.2/

page 6 Selective load reduction is a desirable element of LOOP recovery for a NBO Unit.

UNIT e'ABLE 5.2 A UNIT Z LOOP - UNIT 1 SBO EOP 10

& APPENDIX X/XX TRAIN RA4 -

BOTH UNITS KM KM LOAD RUHNING BLOCK TOTAL TINE KM AUTO/HAN TOTAL (LOAD BLOCKS) 2 2

2 2

2 2

2 Emerg. Lighting Pnls HOVs: V-2553g2555g3614g3642gFCV-25-11 HV-09.09,21-03,21-4A PoNer Pnls: PP-201,201A,211,220,246,250 262g263g268g203 233g234 RCP Oil Lift Pumps Security Bld Conputer A/C HVA-10A Hydrogen Analyzer CSAC 0/G Cooling 'Mater Htrs D/G/ Turbo Lub Oil Papa 2A1-1 and 2A2-1 D/G Soak Back Lub Oil Pfrps 2A1-1 and 2A2-1 D/G Air Cogrpressor Fire/Security UPS Vital (Non-IE) UPS 0 sec 82.4 A

0 sec 6.4 A

0 sec 115.4 A

0 sec 18.0 A

0 sec 77 A

0 sec 1.6 A

0 sec 60.0 A

0 sec 3.6 A

0 sec 1.8 A

0 sec 6.7 A

0 sec 30.0 A

0 sec 20.0 A

353.6 353.6 t

Contairment Fan Coolers 2 HVS-1A and 18 3 sec 141.0 A

Cntmt Fan Htrs PP-201 0/G Fuel Oil Transfer Pap 2A 3 sec

-0.6 A

3 sec 2.7 A

143.1 496.7 2

2 SI SSS 1111ggSS SSCSSSSS'111 SSI'1 1' 1 1 11 SSSSSSSSS 111$ 111111111S SSSSSSSSSS C

11111 CCM P 2A 6 sec 368.9 A

CCM P Htrs PP.201 6 sec

-1.1 A

367.8 864.5 tt S S

51115111 RSSSSSSSS I 1 1111 I SCSS 15111 1

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$11111111111 ICM P ZA 9 sec 476.8 A

ICM P Ntrs'P-201 9 sec

-0.9 A

475.9 1340.4 5

I 1 5 SC 555 EE Rm Fan 2 HVS-5A EE Fan HVS-5A Htr PP-201 Reactor Cavity Suppi,y 2 HVS-2A Reactor Support Cooling 2 HVE-3A Support Cool Fan Htr PP-201 18 sec 72.8 A

18 sec

.0.2 A

18 sec 13.7 A

18 sec 21.8 A

18 sec

-0.3 A

107.8 1448.2 1 I I I

CSS 11 111 11 SCCSS 1

11 tt 2

2 2

EE Rm Exhaust Fan 2 RV.3 Battery Rm Exhaust Fan 2 RV-1 intake Btd Exhaust Fan 2 HVE-41A 21 sec 21 sec 21 sec 4.5 A

0.7 A

6.7 A

11.9 1460.1 SSC11$ 1151 I 1 $51111 I CSC 1

1 S

1$

I 2

2 Control Rm A/C 2 HVA-3A and ACC.3A CR HVA/ACC-3A Htrs PP-20'I 24 sec 49.4 A

24 sec

-0.4 A

49.0 1509.1 2

2 CVCS Heat Trace Battery Chargers 2A,2AA, and 2AB 27 sec 3.5 A

27 sec 105.6 A

109.1 1618.2 SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS SSSCSggSS 1

SCSSSSSS'SSS CSSSS111111111111111SSSS 1

111111 2

2 AFM P 2A AFM P Heater PP-201 30 sec 30 sec 254.1 A

.1.1 A

253.0 1871.2 11 CSSSSStggt 111111155 S I 1 5 SSCSCC 11111 SSSS 1111111$ 11111 111 SSS 551 11111 2

2 RAB Supply Fan 2 HVS-4A RAB Fan HVS-4A Htr PP-206/201 33 sec 106.6 A

33 sec

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106.3 1977.5

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2 EE Rm Exhaust Fan 2 HVE-11 EE Rm Fan HVE.11 Htr PP-201 38 sec 38 sec 39.4 A

-0.3 A

39.1 2016.6 SC

$$$$5$ $5$1$ 115$ $$ $$$ $$$$11$ $$$$

51 1 5$ $$$$$115$ $ $$5$ $$$$$$5$

SSSSSSSSCS SSSCSSSSSIS 0/G Cool Mater Htrs 90 sec

-60.0 A

UNIT TABLE 5.2 A UNIT 2 LOOP - UNIT 1

SBO EOP 10 F APPENDIX X/XX TRAIN >>A>> -

BOTH UNITS 7 IHE KN KN LOAD RUHNING BLOCK TOTAL AUTO/HAH TOTAL (LOAD BLOCKS) 2 2

5 55 55555 5555555555555 SSSCSRSSSSS S55555$ 55555555 D/G Gen Htr PP.211 90 sec

-4.5 A

90 sec

-6.4 A

-70.9 1945 ~ 7 555555 555 CSS 5 5 5 555

'5'5555'RRRR S5555555 5

555555 5

5 2

2 2

2 2

Charging Pap 2A Charging Pap Htr PP-201 Battery Chargers EE Rm A/C 2 HVA-ACC-4 CVCS Heat Trace (1/2) 300 sec 300 sec 300 sec 300 sec 300 sec 52.1

.0.6

.52.0 11.7 1.7 A/H A

A 9.5 1955.2 2

2 2

2 2

1 2

1 1

1 1

1 1

1 1

1 1

1 1

1 1

~

1 1

AFM P 2A 900 sec .254.1 H

AFM P Htr PP-201 RCP Oil Lift Pwps Charging Pmp 2C Charging Pmp Htr PP-203 RCP Oil Lift Psp. Secured 900 sec 900 sec 900 sec 900 sec 900 sec 1.1

.18.0 52 F 1

.0.6 0.0 A

H H

A H

-219.5 1735.7 RSSSSSRSS S5555555555 S

5 RSC 5

5 CSCRRS SSSSSSSSSSRSSRSSCSSSSS Close SBO 2AB/1AB Tie Bkrs 1500 sec 0.0 H

Close 480V LC Bkr 1500 sec 0.0 H

0/G Oil Pmp 0/G Air Compressor D/G Fuel Oil Transfer Pwp 1A Emerg. Lighting Pnls.

HOVs: V-3481,3644,3651,3659 Power Pnls PP-101,111, '114,135,PP-103,134 Boric Acid HU Pmp 1A or 18 BA HU Pmp Htr PP-101 Cable Spread Rm A/C Cable Spread Rm Fan Computer Rm A/C 1 ACC.10A Computer Rm Fan 1 HVA-10A Hydrogen Analyzer Charging Pmp 1A Charging Pmp Htr PP-101 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1500 sec 1.8

&.7 4.5 125.8 9.4 122.3 16.2

-0.3 31.5 4.5 8.0 2.7 1.6 70'

.0.6 A

A A

A A

A A

A A

A A

A A

404.6 2140.3 5555cscR 55$555555555 5555 5 55 555 Ras'Seas s '5'5'sssas 555$ 5$$5555$ 555 55555sa55555 Contairvent Fan Coolers 1 HVS.1A and 18 1503 sec 123.0 A Cntmt Fan Htrs PP-101 1503 sec -0.9 A 122.1 2262.4 55555555555 5555555 5 55555 5 5555 555 SSSSSSS 5 5 5555 5 SRSSSSCS 5555 55 Boric Acid Heat Trace Control Rm A/C 1 ACC.3A Control Fan 1 HVA-3A RAB Supply Fan 1 HVS>>4A Reactor Cavity Supply Fan HVS-2A Reactor Support Fan HVE-3A CVCS Heat Trace Boric Acid Tank Heaters 1518 sec 1518 sec 1518 sec 1518 sec 1518 sec 1518 sec 1518 sec 1518 sec 33.8 29.3 6.7 41.7 15.5 21.6 10.1 13.5 A A A A A A A A 172.2 2434.6 ss5ssssaaaasssss5ssss5asssass5s55ssasssssss55ss5ss5s5asaa55asaaaaa555aaaaaaaaaaasaaassasaaaaaaaa Battery Chargers 1A,1AA 1530 sec 104.0 A 104.0 2538.6 c 'ss'55$ 555$ 5'55'5'5 $55555555555 5555$ 5$555 5$55555 555555assssSsssSRRSRRRRRR 5 cs 555555555555 1560 sec 1560 sec HOVs Boric Acid Tank Heaters -9.4 -13.5 A A -22.9 2515.7 5555555555555555555555555555555 55555555 5555555$ 55555555555555555555$ 5555555555555555555$ 5555$

TABLE 5.2 A UNIT 2 LOOP - UNIT 1 SBO EOP 10 8 APPENDIX X/XX TRAIN SA" BOTH UNITS KM KM LOAD RUHHING BLOCK TOTAL UNIT T IHE KM AUTO/HAN TOTAL (LOAD BLOCKS) 55 5 5555 55555 1 Containnent Fan Coolers 28 min -122.1 N -122.1 2393.6 SSRSSSSSSSSRSSSSSSSSSSS 555555 SSR 5555 555555555555555555555555555555555 S 555 5 1 1 2 ~ 2 2 2 Boric Acid Heat Trace (1/2) 30 min -16.9 CVCS Heat Trace (1/2) 30 min -5.1 Przr Htrs 30 min 200.0 Inst. Air Compressor 2A 30 min 54.0 Inst. Air Cool Fan 30 min 4.5 Inst. Air Cool Pmp 30 min 6.8 A A H H H H 243.3 2636.9 55 RSSSSRSS 55555555 5 55 5 5 5 5'SSSS 5 5555555SR 55555 1 D/G Fuel Oil Transfer Pay 35 min -4.5 -4' 2632.4 Inst. Air compressor 'lA Inst. Air Comp Fan Inst. Air Cool Mater Pmp 40 min 40 min 4D min 32.8 6.7 1.8 H N N 41.3 2673.7 5555 55 555555555 5 55 S S 55555 5 5 555555555 55555555 5555 55555 1 ICM P 1A 1 ICM P Htrs PP-101 45 min 45 min 451.0 ~ 2 449.8 3123 ' 55555555555555555555555555555555'55555555555555555555555555555555555555555555555555RRSSSSSSSSSSSS CCM P 1A CCM P Htrs PP-101 50 min 50 min 368.9 -1.1 H A 367.8 3491.3 55555 555 555 555 5 55 >> 5 SS 555 555555 55555555 55 5 5 55 PRZR Htr* Charging Pmp 1A* Charging Pmp Htrs PP-101 5 55 min 55 min 55 min 186.0 -70.5 0.6 N H A 116.1 3607.4 1 2 2 60 min 60 min 60 min 61.1 -6.7 -5.0 Contaire>>nt Fan Cooler H A A -52.0 20.0 20.0 90 min 90 min 90 min A N N Battery Chargers Fire/Security UPS Vital (non.IE) UPS -12.0 3644.8 -3.6 3641.2 SS 'SSSSRRS 555555555 5 5555555 55555555 SSSSSSSSSSS SRRSSSSSSRSS SRSSSSSSSSS SSSSSSSSSS RS 1.3 4.1 27.0 -31.5 .4.5 120 min 120 min 120 min 120 min 120 min H N N N II EE Rm Roof Fan 1 RV.3 EE Rm Exhaust Fan 1 HVE-11 EE Rm Supply Fen 1 HVS-5A Cable Spread Rm A/C Cable Spread Rm Fan SSSRSR RSSRSSRSSR 55 555 5 5 5 555 5 5555555555 SSSSS5555555555555555 5 5555555 5 D/G Air Compressor Battery Chargars 49.4 3656.8 SS55SSSSSSSS5SSSSSSSSSSSS555S5SSSSSSSSSS5SSSSSSSSSSSSSSSSSSSSSS5S5SSSSSSSSSSSSSSSSSSSSSSSSSSSSSS DISCRETIONARY LOADS I 1 0/G Bld PP 111 Ckts 1, 7, 8, 11 8 12 1 D/0 Air Compressor 1 EE Rm Supply Fan 1 HVS-5A 1 Balance of BA 8 CVCS Heat Trace II 1 Boric Acid HU Pump 3207 -6.7 -27.0 -21.9 -15.9 -88.3 .15.9 SNOTEI The Unit 1 Pressurizer Heaters and Charging Pump are alternately cycled. TBS2ARQl.MK1

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