ML19257D225
| ML19257D225 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/23/1980 |
| From: | Karrasch B BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML19257D211 | List: |
| References | |
| NUDOCS 8002010548 | |
| Download: ML19257D225 (7) | |
Text
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January 23, 1980 UNITED oTATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFFj AND LICENSING BOARD In the Matter of
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SACRAMENTO MUNICIPAL UTILITY DISTRICT
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Docket No. 50-312
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(Rancho Seco Nuclear Generating Station)
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AFFIDAVIT OF BRUCE A.
KARRASCH City of Lynchburg
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)
Bruce A.
Karrash, being duly sworn according to law, deposes and says as follows:
1.
I am Manager, Plant Integration, in the Nuclear Power Generation Division of the Babcock and Wilcox Company, the nuclear steam system supplier for the Rancho Seco Nuclear Generating Station.
I give this affidavit in support of the Licensee's Motion for Summary Disposition of Contentions by Intervenors Richard Castro ar.d Gary Hursh.
I have personal knowledge of the matters set forth herein, and believe them to be true and correct.
A summary of my professional quali-fications and experience is attached as Exhibit "A"
hereto.
2.
Contention 21 advanced by intervencrs Gary Hursh and Richard Castro alleges that Rancho Seco "has a pressurizer tank and quench tank which are of inadequate size to accommo-date the volume of gas or liquid that may be required to be stored in the event of a loss of feedwater transient."
In my 1857 129
. g,j p
opinion this contention is unfounded.
For a loss of feedwater transient, the pressurizer relief systems are not expected to actuate; primary pressure and pressurizer level are maintained within proper bounds and no steam or liquid is released to tae quench tank.
3.
The pressurizer is an integral part of the Reactor Coolant System.
Its function is to maintain the primary system pressure within system design values and to absorb system fluid volume changes during normal and anticipated transients.
The presserizer capacity was sized by considering changes in liquid volume of the Reactor Coolant System resulting from normal oper-ation and anticipated transients such as turbine trip and reactor trip.
4.
The basic criteria for pressurizer capacity is that the pressurizer will not empty nor go solid during normal oper-ation or following anticipated transients.
The steps in achieving this design goal are:
A.
The minimum pressurizer volume to be maintained following a reactor trip is established.
B.
The maximum expected reduction in Reactor Coolant System volume due to a reactor trip from full power is determined.
The magnitude cf this volume change, added to the previously established minimum post-trip pressurizer volume, establishes the minimum pressurizer volume for normal operation.
C.
The minimum normal pressurizer volume is increased by the volume change associated with potential 1857 130 variations in reactor coolant temperature during operation to establish a maximum pressurizer volume for normal operation.
D.
The maximum expected increase in Reactor Coolant System volume due to closure of the turbine stop valves at full power is determined.
This volume change is added to the maximum normal pressurizer volume to establish a maximum pressurizer volume.
E.
The resulting maximum pressurizer volume is increased by an appropriately conservative engineering factor to arrive at the total design pressurizer volume.
5.
At Rancho Seco, the pressurizer has a total capacity of 1500 ft3, or about 13% of the total volume of the Reactor Coolant System (11,500 ft3).
Consistent with the above design discussion, this volume results in the pressurizer neither filling nor emptying during an anticipated loss of feedwater transient.
6.
Also, with the currently installed anticipatory reactor trip on loss of feedwater, lowered reactor coolant high pressure trip and increased pressurizer PORV set point, no pressurizer discharge to the quench tank is expected during a loss of feed-water event.
The quench tank, although not a part of the Reactor Coolant System pressure boundary, is, however, designed to quench (subcool) steam which could be released due to off-normal transients resulting in primary system pressures which exceed the pressurizer power operated relief valve (PORV) or safety valve setpoints.
Tne i857 131
size of the quench tank is based upon accommodating the total steam discharge and discharge rate from the worst case design basis czerheating transient, a rod withdrawal accident.
This event has been shown to bound other overheating conditions such as anticipated loss of feedwater and turbine trip transients.
While the design basis of the quench tank is not a required post-accident safety function, it does serve the operational purpose of providing an additional boundary, beyond the reactor coolant pressure boundary to prevent release of primary coolant to the reactor building.
If, in the event primary system steam discharge due to off-normal conditions exceeds the capacity of the quench tank, the containment building contains the discharged fluid.
7.
In summary, the Rancho Seco pressurizer is designed to accommodate a range of anticipated transients including feed-water upsets.
Pressurizer fluid volume will be maintained and no discharge to the quench tank is expected.
The quench tank is, however, sized to effectively handle various off-normal esents, including a loss of feedwater.
Therefore, the stated concern regarding pressurizer and quench tank sizing, expressed in Hursh-Castro Contention 21, is not valid.
W Bruce A.
Karrash Subscribed and sworn to before me this 23rd day of January, 1980.
BsioG M Notary Public My commission expires 1857 132 l%b 1,
/993 on Q
STATEMENT OF QUALIFICATIONS Name Bruce A.
Karrasch Business Babcock & Wilcox Company Address Nuclear Power Generation Division P O Box 1260 Lynchburg, Virginia 24 505 Education BS, Nuclear Engineering, The University of Wisconsin, 1967 MS Nuclear Physics, Lynchburg College, 1971 Exoerience June 1967-June 1969; Engineer, Thermal Hydraulics Group, Fuel Engineering, B&W: Performed fuel assembly fluid flow and heat transfer calculations June 19 69-June 19 71; Engineer, Nuclear Analysis Group, Fuel Engineering, B&W: Performed three-dimensional power peaking calculations June 1971-March 1974; Engineer and Supervisory Engineer, Control Analysis Unit, Plant Analysis Section, B&W; Assisted in NSS design and analysis March 1974-September 1975; Manager, Control Analysis Unit, B&W Responsible for transient and steady state NSS analysis September 1975-August 1976; Manager, Core Integration Unit, B&W; Responsible for defining and controlling analytical and hardware interf aces between fuel assembly and balance of NSS August 1976-Present; Manager, Plant Integration, B&W; Responsible for defining and controlling analy,tical and hardware interfaces among the various elements of the NSS 1857 133 L h.. a; D $ d [L
+: co
b UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
SACRAMENTO MUNICIPAL UTILITY DISTRICT
)
Docket No. 50-312
)
(Rancho Seco Nuclear Generating
)
Station)
)
CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing " Licensee's Motion For Summary Disposition Of Contentions By Intervenors Gary Hursh And Richard Castro", " Statement Of Material Facts as To Which there Is No Genuine Issue To Be Heard (Hursh-Castro Contentions)", " Licensee's Brief In Support Of Motion For Summary Disposition Of Contentions By Intervenors Gary Hursh And Richard Castro", " Affidavit Of Robert A.
Dieterich",
" Affidavit Of R.J.
Rodriguez", and " Affidavit Of Bruce A.
Karrasch" were served upon the parties identified on the attached Service List by deposit in the United States mail, postage prepaid, this 24th day of January, 1980.
A W Wre-JEy Matias F.
Travieso-Diaz/
1857 134
UNITED STATES OF AMERICA 1
NUCLEAR REGULATORY CO.W SSION BEFORE TEE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
SACRAMENTO MUNICIPAL UTILITY DISTRICT
)
Docket No. 50-312
)
(Rancho Seco Nuclear Generation
)
Station)
)
SERVICE LIST r'4 " % th S. Sca rs, Essaire Mr. Richard D. Cams Cbad 2231 K StM A+
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20036 Stephen E. Iawis, Esquire Docketing and Service Sec"c, C##4ce of the Dcecutive Iagal Director n###ce of the Secretary U.S. IP-i aa-Regulatr=y Cm4 "ic" U.S. No-laa-Pagulatory Camd.ssica Washington, D.C.
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