ML20154J972
| ML20154J972 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/12/1988 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8805270204 | |
| Download: ML20154J972 (17) | |
Text
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NUCLEAR REGULATORY COMMISSION
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May 12,1988 Docket tio. 50-302 LICENSEE:
Florida Power Corporation FACILITY:
Crystal River Unit 3
SUBJECT:
SUMMARY
OF MARCH 30, 1988 NEETitiG ON CRYSTAL RIVER UNIT 3 (CR-3) ON OSTI AND EFW ISSUES On March 30, 1988, representatives of Florida Power Corporation (FPC) met with representatives of the NRC staff to discuss the matters sumarized below.
The list of attendees and slides presented during the meeting are enclosed.
1.
_Epergency Diesel Generator (EDG) Issues The licensee noted that with the present plant configuration the worst-case scenario EDG loading is approximately 3113 KW, but that no scenario requires both the emergency feedwater pump (EFW) pump and the decay heat (DH) pump at the same time.
The proposed EFW pump block / trip circuitry, which would prevent such concurrent operation, was described.
With this circuitry, the controlling scenario then becomes an intermediate loss of Coolant Accident (LOCA) where reactor coolant system pressure does not drop below 500 psi, in which case the EFW pump is reeded and the OH pump is not.
The EDG load in this case is 2882.5 KW, Coments regarding the block / trip solution included:
a.
There is concern in removing the diverse low pressure injection (LPI) actuation signal (4 psi RB pressure).
Can the 30 psi RB pressure signal be used instead?
b.
The question of long-term need for loads not needed immediately must be addressed, i
l c.
The possibility of additional risk or problems being introduced by the block / trip design in other perhaps more likely or more serious scenarios must be examined carefully.
It must be assured that failures which could prevent operation of EFW or of decay heat removal are not made more likely, d.
The battery charger and other loads as appropriate should be added back on the EDG.
i The licensee noted that it intended to install the block / trip modification during the next refueling outage. The schedule for submittal of the design is before the fall of 1988, with earlier responses to the concerns raised above.
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. With regard to EDG room temperature, current analysis indicates that 95'F ambient temperature will result in a combustion air inlet temperature to the EDG of 106.6*F, which could require EDG derating. The licensee is implementing an HVAC modification which would provide sufficient outside ambient air near the EDG suction to assure inlet temperatures below 105'F.
The licensee continues to examine various EDG upgrades.
Those that are presently scheduled for the next refueling outage were described. These are intended primarily to improve EDG reliability rather than increase capacity, although by this summer any capacity benefits from these modifications will be defined.
Further upgrades may be selected when costs and capacity benefits are available from the manufacturer.
2.
Auxiliary Feedwater Pumo The design basis for this pump was discussed.
In addition to those items on the slide (see Enclosure 2) it was noted that while the design is still developing, the capacity of the pump is expected to be 300-400 GPM.
It will be independent of EFIC and powered from the reactor coolant pump transformer windings. Consideration is being given to use of the pump as a normal startup pump, in which case its discharge may be directed to either the normal feed nozzles on the steam generator or to the EFW feed ring. Tests and surveillance intervals will be defined in the Preventive Wintenance Program.
The licensee indicated that the earliest fim commitment for implementation which could be made at the present time is the refueling currently scheduled for the fall of 1993. The earliest possible date would be the 1991 refueling, which would require close cooperation with and by the NRC staff. The licensee is also considering proposing alternate AC power sources within several months to partially resolve the station blackout issue.
3.
Ultimate Heat sink The licensee stated that the maximum observed raw water inlet temperature in the last 10 years is 90.5*F.
Recent analysis shows that a temperature of 92*F will permit maintenance of the design basis temperature of 105'F in the Nuclear Services Closed Cycle Cooling System and the Decay Heat Closed Cycle Cooling System.
In order to provide margin, the licensee desires to revise the raw water design basis (and the ultimate heat sink TS) to 95'F, which would cause a small increase in the closed cycle systems temperature. The licensee stated that a written comitment would be provided shortly to maintain a maximum raw water temperature of 92*F or shut down.
The licensee agreed to submit a TS change request by July 1988 for 95'F maximum raw water temperature if analysis supports this figure, or failing such analytical support by that time, for 92'F.
It was noted that in its analysis the licensee should assure that the actual fouled heat exchanger capability is at least that used in the analysis.
L_____________________
Mr. W. S. Wilgus Crystal River Unit No. 3 Nucleer Florida Power Corporation Generating Plant cc:
Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee Mr. F. Alex Griffin, Chairman Director, Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apooka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsum Mr. E. C. Simpson Babcock & Wilcox Director, Nuclear Site Nuclear Power Generation Division Florida Power Corporation Support 1700 Rockville Pike, Suite 525 P.O. Box 219 Rockville, Maryland 20852 C ystal River, Florida 32629 Resident inspector U.S. Nuclear Regulatory Connission 15760 West Powerline Street Crystal River, Florida 32629 Pegional Administrator, Region 11 U.S. Nuclear Pegulatory Connission 101 Marietta Street N.W., Suite 3100 Atlanta, Georgia 30323 Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Administrator Departnent of Environmental Reculation Power Plant Siting Section State of Florida 2600 Blair Stone Road i
Tallahassee, Florida 32301 Attorney General Departrent of Legal Affairs The Capitol Tallahassee, Florida 32304 i
i
ENCLOSURE 1 EDG/EFW/VHS Meeting MARCH 30, 1988 NAMES ORGANIZATION H. Silver NRR, PM T. Stetka NRC, SRI, CR-3 J. W. Craig NRR, SPLB G. C. Lainas NRR, ADRII R. V. Crlenjak NRC, RII DRP H. N. Berkow NRR PDII-2 R. H. Bernhard Region II, CRS/EB/TPS S. Varga NRR J. S. Wermiel NRR/ DEST /SPLB H. J. Wong NRC/0E J. O. Schiffgens NRR J. Lazevnick NRR/ DEST /SELB R. C. Jones NRR/ DEST /SRXB W. R. Wilson FPC/Mgr. Nuclear Licensing W. S. Wilgus V. P. Nuc. Ops. FPC E. C. Simpson FPC, Director, Nuc. Ops. Engr.
& Projects R. C. Widell FPC, Manager, Nuclear Operations Engineering F. Rahman Sr. Electrical Engineer, FPC, Nuc. Engr.
J. R. Maseda FPC, Nuclear Engineering Supervisor G. W. Castleberry FPC, Nuclear Engineering Supervisor R. E. Clausen FPC, I&C Engineering R. Architzel NRR, RSIB S. F. Kobylarz Consultant G. J. Querbeck Consultant J. Stewart NRR, ICSB P. R. Tanguay FPC, Mgr. Mech /Struct Engrg.
A. Thadani NRR/ DEST F. Rosa NRR/ DEST /SELB S. Saba NRR/ DEST /SELB 1
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ENCLOSURE 2
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aaee..mso on APRNDDC A Auto Cwd loads on EDG-A CAIC.
TEST murwarr Hs W
_HL asp-1A 1600 197 185.7 (2) swp-1A 850o(1) 480.5 485.5 (2)
!UP-1A 600 600 615.5 (2)
W P-2A 15 500 ( 1) 507.7 537.8 (2) me-3A
................................... losoo 195 194.5 (2) tHP-1A 3250 282 273.6 (2)
EFP-1 43o 522 527.9 (2)
EECAY lEAT CL CYCIE CJOLDG WNIER RMP DCP-1A 340o 74 74 (3) ammoL caeIEx LIcarDG...........................
32.6 32.6 (3)
DNr.2nucS...........................................
58.9 58.9 (3)
MISC AC DISIRIHJIICli PANEIS.........................
14.7 14.7 (3)
MISC RMPS AND SGI.L !CICR IDADS....................
34.3 34.3 (3)
REACICR BID 3 FAN AHF-1A.............................
61 61 (3)
EECAY HEAT CICSID CYCIE CCOLDG FAN AHF-15A.........
2.8 2.8 (3)
FIDSH WNIER RMP D3P-2A.............................
8.9 8.9 (3)
TPANSEUEER AND CABIE ICSSE3........................
5.1 5.1 (3)
TCTIAL IDAD CH ED3-A 6
3076.5 3112.8 (The Operator has been provided guidance to shed loads when in excess of 3000 W.)
Noteg (1) The design flow rates have been revised. 'Iha justification for these revisions is attadied.
(2) ' Dest values watumi for kw instrument error.
(3) Durirg SP-417 thane loads tested at 134.7 m (error corrected).
- Hcuever, the more ctriservative calculated value of 292.3 W is bairq used to calculats the total IDG-A load.
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THE BASIS FOR OUR PROPOSED MODIFICATION IS TO INITIATE ES EQUIPMENT
SECONDARY DECOUPLING.
THE LPI PUMP IS NOT NEEDED UNTIL RCS PRESSURE REDUCE 5i TO A POINT WHERE FLOW IS POSSIBLE.
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t Auto Coanected loads on "A" Emergency Diesel Generator (LB/LOCA with 500 # EFP-1 Trip /DHP.lA Start Modification)
CALC.
TEST EQUIPMENT FLOW KW KW i
BSP.lA 1600 197 185.7 f SWP-1A 8500 480.5 485.5 J MVP-1A 600 600 615.5 /
RWP 2A 15500 507.7 537.8 il l
RWP.3A 10500 195 194.5 1 DHP.lA 3250 282 273.6(
EFP-1 0
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i DECAY HEAT CL CYCLE COOLIkG WATER PUMP DCP 1A 3400 74 32.6()
74 CONTROL COMPLEX LIGHTING 32.6
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INVERTERS..............................................
58.9 58.9
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MISC AC DISTRIBUTION PANELS............................
14.7 14.7 4
MISC PUMPS AND SMALL MOTOR LOADS 34.3 34.3 (
1 REACTOR BLOG FAN AHF-1A 61 61 ( /
DECAY HEAT CLOSED CYCLE COOLING FAN AHF-15A 2.8 2.8 l
8.9(()
FLUSH WATER PUMP DOP-2A 8.9 i
TRANSFORMER AND CABLE LOSSES 5.1 5.1
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TOTAL LOAD ON EDG 3A 2554.5 2584.9 4
Manually connected loads applicable to both "A" and "B" Diesei Gerleritors.
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SPENT FUEL COOLANT PUMP 4l CHILLED WATER SUPPLY PUMP 17
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CONTROL COMPLEX WATER CHILLER 193 t
EFIC CONTROL COMPLEX FAN 13 CONTROL COMPLEX EMER DUTY SUPPLY FAN...................
50 CONTROL COMPLEX RETURN AIR FAN 17 EDG "A" loads that are tripped and must be reconnected by Operator action HEAT TRACING 40 3 BATTERY CHARGERS 93.1 Manually applied swing load normally alligned to "8" side ES MCC 3AB 91 i
NOTES (1) TES; VALUES CORRECTED FOR KW INSTRUMENT ERROR.
l (2) DURING SP-417 THESE LOADS TESTED AT 134.7 KW(ERROR CORRECTED).HOWEVER, i
THE MORE CONSERVATIVE CALCULATED VALUE OF 292.3 KW IS BEING USED TO L
CALCULA7f THE TOTAL EDG "A" LOAD.
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Auto Connected loads on "A"_ Emergency Diesel Generator (ID/LOCA with e
500 f EFP-1 Trip /DHP-1A Start Modification)
CA LC.
TEST I
EQUIPMENT FLOW KW KW BSP-1A 1600 197 185.7 (1)
SWP-1A 8500 480.5 485.5 (1)
MUP-1A 600 600 615.5 (1)
RWP-2A 15500 507.7 537.8 (1)
RWP-3A 10500 195 194.5 (1)
DHP-1A 0
0 0
EFP-1 550 560.9 571.2 (1)
DECAY HEAT CL CYCLE COOLING WATER PUMP DCP-1A 3400 74 74 (2)
CONTROL COMPLEX LIGHTING 32.6 32.6 (2)
INVERTERS..............................................
58.9 58.9 (2)
MIS C AC DISTRIBUTION PANE LS............................
14.7 14.7 (2)
MISC PUMPS AND SMALL MOTOR LOADS 34.3 34.3 (2)
REACTOR BLDG FAN AHF-1A 61 61 (2)
DECAY HEAT CLOSED CYCLE COOLING FAN AHF-15A 2.8 2.8 (2)
FLUSH WATER PUMP DOP-2A 8.9 8.9 (2)
TRANSFORMER AND CABLE LOSSES 5.1 5.1 (2)
TOTAL LOAD ON EDG 3A 2833.4 2882.5 Manually connected loads applicable to both "A"_and "B"_ Diesel Generators.
EQUIPMENT KW 4
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SPENT FUEL COOLANT PUMP 41 CHILLED WATER SUPPLY PUMP 17 CONTROL COMPLEX WATER CHILLER 193 EFIC CONTROL COMPLEX FAN 13 CONTROL COMPLEX EMER DUTY SUPPLY FAN...................
50 CONTROL COMPLEX RETURN AIR FAN 17 EDG "A"_ loads that are tripped and must be reconnected by Operator action i
EQUIPMENT KW
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HEAT TRACING 40.9 BATTERY CHARGERS i
93.1
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6 EQUIPMENT KW ES MCC 3AB 91 1
I NOTES (1) TEST VALUES CORRECTED FOR KW INSTRUMENT ERROR.
(2) DURING SP-417 THESE LOADS TESTED AT 134.7 KW(ERROR CORRECTED).HOWEVER, THE MORE CONSERVATIVE CALCULATED VALUE OF 292.3 KW IS BEING USED TO CALCULATE THE TOTAL EDG "A" LOAD.
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EDG ROOM AIR TEMPERATURE
- The EDG is presently locd rated at a combustion air temperature of 105 F
- Detailed analyses has projected a room temperature of up to 106.6 F.
with an outside air temperature of 95 F
- An HVAC modification is being implemented which will provide outside air ( <105 F ) directly to the EDG blower inlet for combustion.
EMERGENCY DIESEL GENERATOR UPGRADE REPLACE / INSTALL
- Blower assemblies Blower flex drive gears (different ratio)
Turbocharger air inlet piping w/ straight flow pipe 1
Auxilliary blower air piping (and new air by pass valve)
Upper and lower pistons w/ new fixed, cooler design Cylinder liners ( and 0-rings )
Injection nozzles w/ new gaskelless nozzles Fuel / Air ratio control Scavenging air temperature controls
m BENEFITS OF UPGRADE
- Potential increase in horsepower rating with improved piston life and reduced ring wear l
- Increased equipment reliability:
- 1) Air inlet check valve above turbocharger and associated piping have been removed, thereby simpilfying maintenance
- 2) The Turbo-Blower series arrangement system provides 20% more air at all loads. This results in:
l A) Exhausi smoke and temperature are reduced B) Cylinder liner, piston and piston ring temperatures are reduced l
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AUXILIARY FEEDWATER PUMP DESIGN BASES NON-SAFETY RELATED NON-SEISMIC MOTOR DRIVEN /NON-CODE PUMP NOT TIED TO EDG/NON-1E MANUAL START / CONTROL FROM M.C.R.
NOT ON REMOTE SHUTDOWN PANEL NOT ENVIRONMENTALLY QUALIFIED NON-SAFETY RELATED SOURCE OF FW NOT TECH SPEC'D PIPING TO B31.1 CODE
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May 12,1989 i
i j ;
4 I
4 General j
j The licensee indicated that its resources are becoming strained as a l
result of the above efforts, their normat work load, the configuration l
management and design basis verification programs, and the SP!P program.
For its own use, the licensee has had an integrated schedule in place for 3
some time, and proposed to submit that schedule during May 1988 as a basis l
for discussion of its proposed schedule for all those efforts. A meeting 4
for this purpose will be arranged after receipt of that submittal.
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Harley Silver, Project Manager 1
Project Directorate 11-2 i
Division of Reactor Projects-I/II i
Office of Nuclear Reactor Regulations
Enclosures:
I As stated cc w/encis:
See next page
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NRC & l'ocal PDRs 1
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05/ /88 05/9/88 05/f/88 05/gpB8 i
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