ML20217G915

Summary of 970721 Meeting W/Fpc in Rockville,Md Re EDG Upgrade,Efs & 10CFR50 App R & Other Design Issues.Attendance List & Meeting Handout Encl

ML20217G915
Person / Time
Site:	Crystal River
Issue date:	08/01/1997
From:	Raghavan L NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9708080108
Download: ML20217G915 (37)

Text

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August 1, 1997 LICENSEE: Florida Power Corporati9n FACILITY: Crystal River Unit 3

SUMMARY

OF MEETING ON JULY 21, 1997 REGARDING EMERGENCY DIESEL l GENERATOR UPGRADE EMERGENCY FEEDWATER SYSTEM AND OTHER TECHNICAL ISSUES On July 21, 1997, representatives of the Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3 (CR3), met with members of the staff 1 at the U.S. Nuclear Regulatory Commission (NRC) Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees. Enclosure 2 contains copies of the handout distributed at the meeting.

This is a followup to June ll, and June 24, 1997 meetings relating to the licensee's proposed license amendment relating to emergency feedwater (EFW) flow and emergency diesel generator (EDG) upgrade, 10 CFR 50 Appendix R and other design issues.

The licensee discussed the EDG upgrade program and compared it to the EDG tests that were done in 1990, as part of power uprate program. The current test plan does not include a reliability test. The staff indicated that any EDG upgrade which involves " major" modifications as described in the Institute of Electrical and Electronic Engineers Standard 387, would require reliability tests (i.e., 30 starts and loading to 2800 kw). The licensee agreed to review the EDG modification and determine the need for performing such a test and provide appropriate documentation in support of its determination.

The licensee also discussed its proposed action for resolving Information Notice 92-18 issues relating to hot shorts. The licensee stated that prior to restart, it will complete its evaluations and necessary modifications for all hot shutdown valves and implement compensatory actions for all cold shutdown valves. The compensatory actions will address procedures, plans, and materials for repairing potentially damaged cold-shutdown valves.

Evaluations and modifications for the cold shutdown valves will be completed prior to restart from Refuel 11.

Original signed by L. Raghavan, Project Manager Project Directorate 11-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Attendance List

2. Meeting Handout cc w/ enclosures: See next page DOCUMENT NAME: G:\ CRYSTAL \970721. SUM e receive a copy of this document, indicate in the box: "C" = Copy without

tachment/ enclosure "E' - Copy with attachment / enclosure "N" - No copy 0FFICE PDil-3/PM PDil-3/LA C, PDil-3/D C l , T-NAME LRaghavan UL BClayton D/O FHebdon Q DATE 07/51/97 07/2l/97 9 07/t /97

_0FFICIAL RECORD COPY 9700000108 970901 PDR ADOCK 05000302 20 BilCEMB COPY cIIIIEE.42til

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0 Florida Power Corporation CRYSTAL RIVER UNIT N0. 3 GENERATING PLANT cc!

Mr. R. Alexander Glenn Senior Resident Inspector Corporate Counsel crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Comission MAC-A5A 6745 N. Tallahassee Road P.O. Box 14042 Crystal River, Florida 34428 St. Petersburg, Florida 3 M33-4042 Mr. James S. Baumstark Mr. Bruce J. Hickle, Director Director. Quality Programs (SA2C)

Nuclear Plant Operations (NA2C) Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Regional Administrator, Region 11 Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission B&W Nuclear Technologies 61 Forsyth Street, SW., Suite 23T85 1700 Rockville Pike, Suite $25 Atlanta, GA 30303-3415 Rockville, Maryland 20852 Mr. John P. Cowan Mr. Bill Passetti Vice President - Nuclear Production Office of Radiation Control De)artment of Health and Flo(NA2E) rida Power Corporation Tehabilitative Services Crystal River Energy Complex

' 1317 Winewood Blvd. 15760 W. Power Line Street Tallahassee, Florida 32399-0700 Crystal River, Florida 34428-6708 Attorney General Mr. Roy A. Anderson Department of Legal Affairs Senior Vice President, The Capitol Nuclear Operations Tallahassee, Florida 32304 Florida Power Corporation ATTN: Manager, Nuclear Licensing Mr. Joe Myers, Director Crystal River Energy Complex (SA2A)

Division of Emergency Preparedness 15760 W. Power Line Street Department of Community Affairs Crystal River, Florida 34428-6708 2740 Centerview Drive Tallahassee, Florida 32399-2100 Mr. Kerry Landis U.S. Nuclear Regulatory Commission Chairman 61 Forsyth Street, SW., Suite 23T85 Board of County Commissioners Atlanta, GA 30303-3415 Citrus County 110 North-Apopka Avenue

Iverness Florida 34450-4245 Mr. Robert E. Grazio, Director NuclearRegulatoryAffairs(SA2A)

Florida Power Corporation ,

Crystal River Energy Complex 15760 W. Power Line Street Crystal River, Florida 34428-6708 L , _ . _

e CRYSTAL RIVER 3 MEETING JULY 21. 1997 Hart Oraanization Caudie Julian NRC- Ril L. Rat,havan NRR K. La,1 dis NRC-RIl Johns Jaudon NRC-Ri!

Fred Hebdon NRR Chris Cristensen NRC-Ril John J. Holden Florida Pt,wer Corp.

Mark Van Sicklen Florida Power Corp.

D. Kunsemiller Florida Power Corp.

Jim Baumstark Florida Power Corp.

Jim Terry Florida Power Corp.

Robert Grazio Florida Power Corp.

Steve Cahill NRC- Senior Resident Ed Connell NRR Thomas Koshy NRR Bob Benedict NRR Mark Hartzman NRR Barry Elliot NRR Don Sells FMPA/ Minority Owners Kamal manoly NRR Mark Prat NRR Saba Saba NRR Fran Sullivan Florida Power Corp.

Paul Fleming Florida Power Corp.

Noel Dudley NRR Jim Warren Florida Power Corp.

Jim Andrews Florida Power Corp.

Al Friend Florida Power Corp.

Albert Spear Florida Power Corp.

Stephen Roe Florida Power Corp.

Joe Maseda Florida Power Corp.

Enclosure 1 a

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SUMMARY

OF MEETING ON JULY 21, 1997. REGARDING CRYSTAL RIVER 3 RESTART PROGRESS

} ttribJtion:

WD CO)Y w/ Enclosures 1 and 2.

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PUBLIC L.-Raghavan Crvstal River Reading ,

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3. Co'11ns/R.-Mirag'la (SJC1.FJM)

R. Zimmerman (RPZ)

B. Boger (BAB2)

J. Zwolinski (JAZ)

F. Hebdon (FJH)  !

B. Clayton (BAC2)

D. Ross (SLM3)

J. Jaudon (JPJ)

H. Cristensen (HOC)

S. Cahill (SJC2) .

J. Johnson (JRJ)

C. Julian (CAJ) .

C. Cristensen (H0C)

E. Connell (EAC)

T. Koshy (TXK)

R. Benedict (RAB1)

M. Hartzman (HXH) '

-B.-Elliot (BJE) '

K. Manoly (kAM)-

M. Pratt (MDP)

5. Saba (SNS1)

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Technical Meeting July 21,1997

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AGENDA m EDG Power Uprate a Proposed Resolution to N 92-18 l

m BoronPrecipitation a HPI Nozzle NDE a UnresolvedIssue A-46 m SBLOCA Related USQs a Conclusion

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EDG Loading Issue

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• EDG Power Upgrade Sept "96 July '97 Old EDG Ratings New EDG Ratings 30 Min 3500 kW 30 Min 3500 kW 200 Hr 3250 kW 200 Hr 3400 kW 2000 Hr 3000 kW 2000 Hr 3200 kW Contin. 2850 kW Contin. 2850 kW Auto Connect Load Auto Connect Load 3159 idV 3057 kW l

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@. EDG Upgrade History m 1990 - CR3 upgraded to present ratings a 1993 /1994 - Vendor, Coltec / Fairbanks Morse,

• performed type testing for BG&E for new 200 and 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> ratings

• sister engine / generatcr

• CR31990 EDG configuration plus dual pass intercoolers and turbochargers with different nozzle rings a 1994 - BG&E upgraded to new ratings a Present - CR3 will achieve new ratings by replacing intercooler, turbochargers' nozzle rings, radiators, & testing I

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EDG Upgrade m Replace intercooler and turbochargers' nozzle rings a Fuel oil storage increase in day tank and storage tanks a Engine room cooling increece - run both fans in room (USQ) m Appendix R cable routing changes for control circuits for engine room cooling fans s No electrical impact - 3500 kW maximum rating unchanged

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i a Radiators upgrade

• Larger core radiators for increased cooling capacity

• Radiator also compensates for low cooling air flow

• Missile shield / flood barrier modified to reduce pressure drop for air to radiator room

• Low temperature operation - up-rated fan drive /

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• Engine and control room HVAC improvements - filters

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• Supports final upgrade to 4150 kW

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a Radiator discaarge air recirculation path to be eliminated

• Some of the hot air discharging from exhaust is recirculating to the inlet E

• Modifications will be installed to correct the problem

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• New intercoolers and nozzle rings installed

• New radiators installed with modified fan drive, antifreeze, and missile shield changes

• Day tank instrumentation setpoint changes

• HVAC modifications installed and system balanced

• Modification to eliminate radiator recirculated air installed

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EDG Testing Objectives m Achieve operating stability at new rating a Demonstrate engine operates within specified limits at new power ratings

• Key engine parameters - turbocharger RPM, intercooler discharge temperature, firing pressures

• Other EDG parameters such as jacket water and lube oil temperatures

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m Demonstrate generator wil: perfom1 as required at new power ratings

• Temperatures

• Exciter amps

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EDG Testing Objectives-3 m Demonstrate new radiator will perform its function at new ratings

• Air flow rate

• Heat transfer across radiator

• Heat transfer between engine components and radiator

• Radiator fan performance E

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@. EDG Testing Objectives - 4 m Demonstrate radiator discharge air recirculation eliminated

• air temperature in radiator room same as outdoor l temperature a Demonstrate room and component temperatures within criteria

• Room temperature and room delta T are acceptable ,

• Various component / cabinet temperatures are acceptable

• Temperature stability achieved during data gathering

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m 0000 - start EDG and load to 2750 kW m 0800 -load to 2800 kW

• monitor conditions and temperatures and confirm within criteria limits a 1800 - reduce load to 2750 kW m 2000 - perform exciter power factor tests at various

power levels a Approximately 2300 return to 2750 kW and maintain till next day testing

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Preliminary n 0000 - Maintain power at 2750 kW m 0800 -load to 3150 kW

• monitor conditions and temperatures and confirm within criteria limits a 1800 - reduce load to 2750 kTN m 2000 - increase load to 3325 to 3375 - perform HVAC one fan flow tests

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EDG Test - Day 3, 200 Hour Rating - Preliminary

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n 0000 - maintain power at 3325 to 3375 kW m 0800 - operate both room cooling fans

• monitor conditions and temperatures and confirm within criteria limits a 1800 - prepare for load rejection tests a 2000 - perform load rejection tests I

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EDG Test - Day 3/4, ge

.L.~ Other Testing - Preliminary a Load Rejection and Hot Restait testing

• Largest single load rejection test

• Full load rejection test (greater than 3300 kW)

• Hot restart n 0300 (day 4) - Shutdown EDG .

• Perform evaluations of test results with the vendor for l 3400 kW rating a Prior to restart - perform combined ES actuation with simulated . LOOP test

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Comparison to 1990 power

... , . uprate testmg program Title Description 1997 Test Start and load run start and run at 2800 kW for I hour X Fast start time to start & reach voltage and freq. X Combined ES Act de-energize safety bus, EDG auto-start X and LOOP and auto-load sequencing, load > 5 min.

Single load reject. single largest rejected, volt. & freq. X Full load rejection reject max. load, voltage & no overspeed X Endur. & margin 22 hrs @ 2800 kW & 2 hrs @ 3135 kW X Hot restart full temp. restart - volt., freq. & time X I Reliability 30 starts & load to 2800 kW

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m a Large motor load field testing a Transient loading motor testing a Loads converted to Diesel Generator Load using software modeling

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- Appendix "R" / Fire Protection Accomplishments

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a Full compliance with App. "R" requirements prior to restart a Modified / Refurbished RCP Oil Collection System a Extensive modifications to protect against consequences of postulated fires and subsequent Hot Shorts a Revised Cold Shutdown calculations and revised operating procedures a Updated and Validated Safe Shutdown Analysis a Updated and Validated Fire Hazards Analysis

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@. IN 92-18 EVALUATION m Fire-Induced Failure Mechanism

• Single Hot Short

• Bypasses Limit and Torque Switch Valve Protection a Original Evaluation

• Was limited in scope and also took credit for thermal overloads not being bypassed.

m Re-evaluation

• Expanded Fire Areas to Include All Plant Areas (including the Control Room and Cable Spreading Room)

• Remote Shutdown Panel and Manual Operation 1

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IN 92-18 EVALUATION m Proposed Resolution - Ensure availability of one train of Components for Each Fire Area

• Determine if manual operation of valves is possible OR

• Circuit Modifications (to prevent a single, fire-induced, hot short from bypassing limit and/or torque switch protection) m Control Room / Cable Spreading Room Fire

• 10 valves for Hot Shutdown

• 7 valves for Cold Shutdown l m Other Plant Area Fires 1

• 5 valves for Hot Shutdown

• 3 valves for Cold Shutdown ng

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@. IN 92-18 EVALUATION m Will complete evaluations and/or modifications for all (15) Hot Shutdown valves prior to restart a Hot Shutdown valve protection ensures that plant can be put in stable condition. If additional failure occurs, this will allow time to make field repairs.

m Will complete (10) Cold Shutdown valve evaluations and/or modifications by the end of Refuel 11. Will complete portions of this work on-line.

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@. Boron Precipitation m Active Methoc.s

• Dropline to RB Sump

• Hotleg Injection via Reverse Dropline Flow Above Two Methods are Not Single Failure Proof l

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• Hot Leg Nozzle Gaps

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@. Boron Precipitation Sample RB Sump IS RCS Saturated 9 '

IF Concentration < Predetermmed Value,

- THEN Establish Active Method.

N peramit -Ifsampling unavailable, Then establish active method.

Is RCS Pressure = RB Pressure?

Continue Cooldown and Establish DHR Yes No Align Dropline Establish Hot LegInjection

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to RB Sump If Neither Active Method can be Established, Then Reliance on Passive Method (Gap Flow).

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@). U.S.I. A-46 ISSUE m There are One Hundred-Eleven (111) outlying Tag numbers. These 111 outliers are categorized into Restart and Post-Restart groups.

m Out of the 111 outliers, FPC will resolve 70 outliers by restart, December,1997.

m The remaining 41 outliers will be worked based on a work-I off curve that will be developed prior to restart. All outliers are required to be resolved before December,2000.

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. , m m w _ w =L m 2_ K_ _ cm SBLOCA USQs 12 ModificationsIdentified a Most Resolve XRC Identified USQs a EDG Power Uprate - Tech Spec Change

• EDG Fans - may involve a USQ Operator Actions a EFV-12

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V;s3 . CHANGES a Appendix R CT Protectors in Safety Circuits a Remote Shutdown Panel Added Components a AHF-1C EDG Load Control for Bus Transfer a EDG Protective Trip Relays a BoronPrecipitation m Operator Action - Letdown Line Rupture l m Operator Actions for EOPs and APs

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=re% W USQ RESOLUTION m Several USQs Require Approval Prior to Operation a Some USQs Require Approval Prior to Installation Examples:

• Appendix R CT Protectors;

• IN 92-18 Mods a Methodology forProcessing

• Prepare Submittal per 50.90

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