ML19305A744
| ML19305A744 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/29/1980 |
| From: | Birkel R Office of Nuclear Reactor Regulation |
| To: | Case E, Ross D, Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002130136 | |
| Download: ML19305A744 (13) | |
Text
e jar 20 1980 o
Meeting Summaryv Docket File 4--~*-ECI
. Murphy flRC PDR
- 1. Knight local POR
- 5. Hanauer TIC-R. Tedesco flRR Reading R. Bosnak LWR #2 File S. Pawlicki E. Case F. Schauer D. F. Ross K. Kniel D. B. Vassallo T. Novak S. A. Varga Z. Rosztoczy D. Skovholt W. Butler W. Ganmill V. Benaroya J. Stolz R. Satterfield R. Baer V. Moore
- 0. Parr M. Ernst L. Rubenstein F. Rosa C. Heltemes R. P. Denise W. Haass EP Branch Chief R. Houston G. Chipman L. Crocker J. Collins F. J. Williams W. Kreger R. J. Ma ttson G. Lear R. DeYoung B. Youngblood Project Manager R. A. Birkel L. Hulman Attorney, ELD -
NRC
Participants:
J. Lee F. Orr IE(3)
M. E. Zeftawy ACRS(16)
J. C. Glynn P. R. Matthews V. Leung L. W. Bell R. W. Stevens, Jr.
R. A. Birkel s
8 0 0 213 0 t*Jo
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JAN 2 91980 l
DOCKET N05. 50-369/370 i
I APPLICANT:
DUKE POWER COMPANY FACILITY:
MCGUIRE NUCLEAR STATION, UNITS 1 & 2 l
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SUBJECT:
SUtMARY OF MEETING HELD ON JANUARY 9,1980
)
A meeting was held with the applicant on January 9,1980 in Bethesda, j
Maryland to discuss design changes to the auxiliary feedwater system.
A list of attendees is provided in Enclosure No.1.
Paview of the Auxiliary Feedwater System by the applicant resulted in the 1ssuance of Significant Deficiency Report SD 369-370/79-07, September 7 1979 (See Enclosure No. 2). Subsequently SD 369-370/79-10 was issued i
on November 8,1979 (See Enclosure No. 3). The applicant described i
the results of the AFS review which revealed (1) certain pump suction prublems during postulated multiple steam generator depressurization and (2) pimp runout problems during a feedline break with a second i
depressurized steam generator. Enclosure No. 4 describes the previous f
AFS design, the associated problems and the design changes being j
implemented to correct the deficiencies. Schematic diagrams of both the previous and present AFS system are also included in the enclosure.
The applicant anticipates that all changes will be completed by May 1980.
The FSAR will be revised to reflect these changes.
Original signed hv:
Ralph A. Birkel LWR Branch #2 Division of Project Management l
Enclosures:
As stated cc: w/enclosurr see next page I
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20555
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JAN 2 91980 DOCKET NOS. 50-369/370 APPLICANT:
DUKE POWER COMPANY FACILITY:
MCGUIRE NUCLEAR STATION, UNITS 1 & 2
SUBJECT:
SU MARY OF MEETING HELD ON JANUARY 9, 1980 A meeting was held with the applicant on January 9, 1980 in Bethesda, Maryland to discuss design changes to the auxiliary feedwater system.
A list of attendees is provided in Enclosum No.1.
Review of the Auxiliary Feedwater System by the applicant resulted in the issuance of Significant Deficiency Report SD 369-370/79-07, September 7, 1979 (See Enclosure No. 2). Subsequently SD 369-370/79-10 was issued on November 8,1979 (See Enclosure No. 3).
The applicant described the results of the AFS review which revealed (1) certain pump suction problems during postulated multiple steam generator depressurization and (2) pump runout problems during a feedline break with a second depressurized steam generator.
Enclosure No. 4 describes the previous AFS design, the associated problems and the design changes being implemented to correct the deficiencies. Schematic diagrams of both the previous and present AFS system are also included in the enclosure.
The applicant anticipates that all changes will be completed by May 1980.
The FSAR will be revised to reflect these changes.
ft. k, Ll Ralph A. Birkel LWR Branch #2 Division of Project Management
Enclosures:
As stated cc: w/ enclosure see next page L
i 5
Mr. William O. Parker, Jr.
Vice President, Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 i
cc: Mr. W. L. Porter Duke Power Company 4
f P. O. Box 2178 2
422 South Church Street Charlotte, North Carolina 28242 4
Mr. R. S. Howa rd Power Systems Division i
Westinghouse Electric Corporation l
P.-0. Box 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incorporated i'
220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 4
Mr. Jesse L. Riley, President t
The Carolina Environmental Study Group 854 Henley Place i
Charlotte, North Carolina 28207 4
J. Michael McGarry, III, Esq.
Debevoise & Liberman 1200 Seventeenth Street, N. W.
Washington, D. C.
20036 i
Robert M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Connission Washington, D. C.
20555 i
Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. 0.~ Box 24 7 Bodega Bay, California 94923 t
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Mr. William 0. Parker, Jr.
cc: Anthony Z. Roisman, Esq.
Natural Resources Defense Council 917 - 15th Street, N. W.
Washington, D. C.
20555 Richard P. Wilson, Esq.
Assistant Attorney General State of South Carolina 2600 Bull Street Columbia, South Carolina 29201 a
2 k
9
ENCLOSURE No. 1 Attendance List Meeting With Duke Power Company January 9,1980 Duke Power Company G. A. Copp D. L. Canup S. D. Alexander Westinghouse Electric Corp.
C. L. Sturla G. Lang NRC Staff R. A. Birkel R. W. Stevens, Jr.
L. W. Bell V. Leung P. R. flatthews J. C. Glynn Med El Zeftawy F ank Orr 7
M*
y ENCLOSURE No. 2 Duke Power Company McGuire Nuclear Station Units 1 & 2 Recort Number: SD 369-370/79-07 Report Date: Septent>er 7,1979 Facility: McGuire Nuclear Station, Units 1 & 2 Description of Deficiency:
The prasent Auxiliary Feeckater System (AFS) is a safety related ASME Section III Class 3 system with the exception of the non-safety related condensate quality suction sources which are ANSI B31.1. The AFS pumps are normally aligned to the condensate quality sources with automatic switchover to the safety related Nuclear Service Water (NSW) source.
Recent review of the Auxiliary Feedwater System has identified depressurization cases of multiple steam generators which combined with the most limiting single failure will cause AFS flow increases to the extent that pump runout occurs.
The increased flow creates negative suction pressures in the pump suction headers which could lead to air inaestion from the normal non-safety grade source of water.
Analysis of Safety Imolications:
Worst case safety consequence is the loss of all AFS Pumps following a multiple steam generator depressurization event combined with the most limiting single.
failure. This, in combination with loss of nomal feedwater, would result in loss ci all fec6 eater.
Corrective Action:
Travel stops will be set on flow control valves to prevent unacceptable pump run-out with all steam generators completely depressurized.
The turbine driven AFS pump, rated at 200% design, will be throttled to supply 1/3 design flow to each of three intact steam generators at lowest safety valve set pressure plus 3% accumu-lation with the fourth steam generator conpletely depressurized. The two motor driven AFS pumps, rated at 100% design each, together will be throttled to supply 3/8 design flow to each of two stean generators and remaining 1/4 design flow to the third steam generator at lowest safety valve set pressure plus 3% accumulation with the fourth steam generator completely depressurized.
Tc prevent negative suction pressures, the suction piping will be revised to allow each motor driven AFS pu7 to be supplied from the corresponding train of NSW with the turbine driven AFS pump supplied from either train.
Adequate suction pressure will be available under the most limiting cases of multiple steam generator de-pressurization and single failure.
Potential AFS pump runout problems resulting from multiple steam generator de-pressurization will be considered in the design of future plants. -
A O ENCLOSURE No. 3 i
Duke Power Company l
McGuire Nuclear Station Units 1 & 2
(
Report No:
SD 369-370/79-10 Report Date:
November 8, 1979 l
Facility: McGuire Nuclear Station, Units 1 and 2 i
I Der.cription of Deficiency:
[
Some safety related mechanical and electrical equipment in the doghouse area
[
outside containment is not qualified f or the final environment resulting f rom a feedwater or steamline break, in addition, some safety related equipment is below the flood level caused by a feedwater line break.
l The following safety related equipment and corresponding controls are affected by the adverse environment.
[
1.
(
2.
Main Steam Power Operated Relief Valves I
3.
Auxiliary Feedwater Pump Turbine Steam Supply Isolation Valves i
4.
Feedwater Isolation Valves l
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Analysis of Safety Implications l
Worst case safety consequence following an auxiliary f eedwater line break in a doghouse would be reduction of effective auxiliary feedwater flow
)
from the required 450 gpm to 100 gpm.
This worst case assumes the failure of both auxiliary feedwater pump turbine steam supply isolation valves to open as a result of the break environment.
Additionally, a single failure of one motor driven auxiliary feedwater pump is assumed. The operating motor driven auxiliary feedwater pump would previde 100 gpm ficw to only one intact steam generator, with the remainder of its flow spilling from the broken auxiliary feedwater line.
i Worst case safety consequence following a steam line break inside a doghouse is reduction of auxiliary feedwater flow from the required 450 gpm to 340 gpm.
This worst case assumes the failure of both auxiliary feedwater pump turbine steam supply isolation valves to open as a result of the break environment.
Additionally, a single failure of one motor driven auxiliary feedwater pump is assumed.
The operating motor driven auxiliary feedwater pump would provide 170 gpm have been successfully iso DUPI.ICATE DOCUMENT Corrective Actiot Entire document previously All safety relat' entered into system unde fr-ove will, eithat be qualif.
gg f)
- ase steam i
line or feedwate.
table location outside M
N o.
of pages:
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