ML20027D611
| ML20027D611 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/04/1982 |
| From: | Sun S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20027D609 | List: |
| References | |
| ISSUANCES-OL, NUDOCS 8211080157 | |
| Download: ML20027D611 (7) | |
Text
.
.1-i UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the, Matter of
)
CLEVELA D ELECTRIC ILLUMINdTING Docket tio. 50-4'40 OL C011PANY, ET AL.
)
50-441 OL
)
(Perry Nuclear Power Plant,
)
Units 1 and 2)
)
AFFIDAVIT OF S.B. SUN IN SUFPORT OF
SUMMARY
DISPOSITION OF ISSUE #4 I, S.B. Sun, state under oath that:
1.
I am a Nuclear Engineer in the Core Performance Branch, Division of Systems Integration, Office of Nuclear Reactor Regulation, U.S.
!;uclear Regulatory Commission.
I have knowledge of the matters set forth herein and believe them to be true and correct.' A statement of my professional qualifications is attached.
2.
Issue #4 states that:
The safety of Applicant's emergency core cooling system has not been demonstrated with appropriate experimental data because a full scale 30 degree sector steam test has not been
~
performed.
3.
I understand that the Licensing Board admitted Issue #4 because of its view that a full-scale 30-degree-sector steam test " appears to be required by 10 CFR 50, Appendix K, Part I, i D.6" and because Applicants' FSAR indicated that no such test had been performed.
LBP-81-24, 14 NRC 175, 215-216 (1981).
ym -
8211080157 821105 PDR ADOCK 05000 G
1 s
p
..e 4.
Full-scale 30-degree-sector steam tests are not specifically mandated by Appendix K to 10 CFR 50.
Section I.D.6 of Appendix K requires only that during spray cooling following the blowdown p~eriod in a loss-of-coolant accident convective heat transfer for BWR feel rods be. calculated using coefficients based on appropriate experimental, data.
5.
Section I.D.6 also specifies acceptable heat transfer coefficients for reactors with jet pumps and 7 x 7 fuel assembly arrays. The BWR/6 employs an 8 x 8 fuel assembly array.
6.
General Electric has confirmed by test that if the flow rate through a BWR fuel assembly is approximately 1 gallon per minute;a convective 2
heat transfer coefficienti of 1.5 Btu /hr-ft - F, the value employed
^
in the GE ECCS Evaluation Model, will be achieved.
7.
GE also has conducted full-scale s' pray distribution' tests in air at atmospheric pressure for the'BWR/2 and later designs, including the BWR/6 design, to confirm that the necessary minimum coolant flow will be provided to each fuel assembly. Those tests were performed ia a full-scale test facility that used the actual core spray nozzle geometry to spray water over a mockup of the top cf the reactor core.
8.
However, later tests conducted in Europe (the results of which were confirmed in tests conducted by GE) indicated that the presence of c
l steam and/or increased pressure in and above the upper core region could adversely affect the distribution of flow from certain types o,f core spray nozzles.
l 9.
To assess these effects GE developed a methodology for determining the distribution of BUR spray flow in a steam environment.
Using l
l
p s
v 3
S that methodology GE predicted core spray system performance for a full-scale 30-degree-sector of a simulated BWR. Tests in a steam environment were conducted by GE on the configuration for which performance was predicted using the GE methodology.
10.
Tlie test configuration was designed to be representative of'a
~
reference BWR/6 with a 218-inch diameter core.
Prototypical hardware was used, and the upper plenum of the test apparatus was a full-scale mockup of a 30-degree sector of the reference upper plenum with accurate simulat' ion of its geometry.
- 11. The results of these tests confirmed GE's capability to, predict with its methodology spray distribution performance-in a steam environment-of multiple-nozzle core spray systems similar to that of the BWR/6 design tested.
Pre-t'est predictions compared well with the test results.
12.
The data from these full-scale 30-degree-sector steam tests, together with data from the 360-degree-sector air-water tests and tests on other variously sized sector test cor. figurations 'uve confirmed the core spray cooling convective heat transfer coefficient assumptions in the GE ECCS Evaluation Model.
13.
Moreover, because other data show that even without any of the core spray water flowing through the 8x8 fuel assembly array steam cooling alone would result in a significantly greater convective heat transfer 2
coefficient than the 1.5 Btu /hr-ft - F assumed in the GE ECCS Evaluation Model for a BWR/6, the Staff has concluded that the core spray
s
)
,v
.4-a distribution for Perry is of no safety concern.
See fiUREG-2229 (Vol. 1), "BWR Large Break Simulation Tests - BWR Blowdown / Emergency Core Cooling Program," dated April 1982.
- 14. Thus convective heat transfer from fuel rods in the Perry reactor cdre is calculated using coefficients that are based on appr.opriat'e experimental data as required by Section I.D.6 of Appendix K to 10 CFR 50.
See Perry SER, flVREG-0887, pp. 6-27 and 6-28.
s S.B. Sun T
Subscribed d sworn to before me this day of flovember, 1982.
0)$LLOW A }s12C llotary Public
!)y commission expires:
7!/
d e
s e
s
.a n
Summer B. K. Sun Core Performance Branch Division of Systems Integration U.S. Nuclear Regulatory Commission PROFESSIONAL QUALIFICATIONS 9
I am ernployed as a nuclear engineer of the Thermal-Hydraulics Section in the Core Performance Branch of the Division of Systems Integration.
I received a BS degree with Chemical Engineering Major from f[ational Taiwan University in 1967 and a Ph.D degree with Chemical Engineering Major from University of Missouri of Columbia, Missouri, in 1974.
I am a registered Professional Engineer, Certificate Number 11309, in the state of Connecticut.
In my present work assignment at the NRC, I have technical responsibility.
for the review of the reactor core thermal-hydraulics design submitted in BWR reactor construction permit and operating license applications.
In addition, I participate in the review of analytical models used in licensing evaluation of the core thermal-hydraulic behavior under various operating and postulated accident and transient conditions'. The latter responsibility includes technical review of the core spray issue and the instrumentation for monitoring inadequate core cooling to comply with the Commission requirements.
Prior to joining the NRC staff in August 1980 I was employed by Combustion Engineering Company, as a consulting engineer.
I was responsible for the development and application of computer codes and methods for the analysis of transients for PWRs. My, tenure at CE was from 1974 through 1980.
P s.
a s
s
?
-1.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
CLEVELAND ELECTRIC ILLUMINATING
)
Docket Nos. 50-440 OL COMPANY, ET AL.
)
50-441'0L
).
~
(Perry Nuclear Power Plant,
)
Units 1and2)
)
CERTIFICATE OF SERVICE I hereby certify that copies'of "NRC STAFF'S MOTION FOR SUMTARY DISPOSITION OF ISSUE NO. 4" in the above-captioned proceeding have been ' served on the following by deposit in the United States mail, first class, or, as indicated by an asterisk, by deposit in the Nuclear Regulatory Commission's internal mail system, this 5th day of November, 1982:
- Feter B. Bloch, Esq., Chairman Donald T. Ezzone, Esq.
Administrative Judge Assistant Prosec,uting Attorney Atomic Safety and Licensing Board 105 Main Street U.S. Nuclear Regulatory Commission Lake County Administration Cent'er Washington, DC 20555 Painesville, Ohio 44077
- Dr. Jerry R. Kline Susan Hiatt Administrative Judge 8275 Munson Avenue-Atomic Safety and Licensing Board Mentor, Ohio ~ 44060 U.S. Nuclear Regulatory Commission Washington, DC 20555 Daniel D. Wilt, Esq.
2 P. O. Box 08159
- Mr. Frederick J. Shon Cleveland, Ohio 44108 Administrative Judge Atomic Safety and Licensing Board Terry Lodge, Esq.
U.S. Nuclear Regulatory Commission Attorney for Intervenors Washington, DC 20555 915 Spitzer Building Toledo, Ohio 43604 Jay Silberg, Esq.
Shaw, Pittman, Potts and Trowbridge John G. Cardinal, Esq.
1800 M Street, NW Prosecuting Attorney Washing ~ ton, DC 20036 Ashtabula County Courthouse Jefferson, Ohio 44047
?
/
?
4 e'
s
[
e-
- A U
- Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Cosnission Wash'ington, DC 20555
- Atcmic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory Connission Washington, DC 20555
- Docketing and Service Section
~
Office of the Secretary U.S. Nuclear Regulatory Connission Washington, DC 20555 m:%w
~
James M. Cutchin,'IV N
Counsel for liRC Staff
=i l
t '
r s (
/