ML19323G311
| ML19323G311 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/27/1980 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8006020149 | |
| Download: ML19323G311 (10) | |
Text
e BALTIMORE GAS AND ELECTRIC COMPANY P. O. B OX 147 5 B A LTI M O R E. M ARYLAN D 21203 May 27, 1980 ARTHun E. LusovaLL.Ja.
V ct Passierme so.o Office of Nuclear Reactor Rerulation U. S. Nuclear Pegulatory Comnission Washington, D. C.
20555 Attn:
Mr. Robert A. Clark. Chief Oterating Reactors Branch #3 Division of Licensing
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318 Partial-Loon Oneration
References:
(a) BGLE letter dated h/5/79 from A. E. Lundvall, Jr.
to H. R. Denton, Application for Amendment (b) NRC letter (undated), received 1/28/80 from R. W. Reid to A. E. Lundvall, Jr., Request for Additional Information.
Gentlemen:
Reference (b) requested additicnal information concerning our application for an amendnent to the Calvert Cliffs Units 1. and 2 operating licenses to allow operation with less than four reactor coolant pumps operating, Reference (a).
Enclosure (1) to this letter provides the requested information.
We have determined that this constitutes supplenentary information to a previous request and that, pursuant to 10 CFR Part 170, no additional fee i
is required.
Very truly yours, T-
/
e L.y>cums (. Pg'~v$ M,
.c- - -er.
^-
cc:
J. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. E. L. Conner, Jr. - NRC Mr. P. W. Kruse - CE 8 0 0 6 0 2 0/fg M
L..
a
< s RESP 0tlSE T0 fiRC DATA REQUEST The requested flRC information is listed in Reference 1.
The response to this request is presented below.
_QUESTI0tl#1:
"The analysis used a review of large break sizes to determine the limiting blowdown period. The staff assumes that this study was performed for the standard C-E geometry. Justify that partial-loop operation will not impact the blowdown, refill and safety iiijection times. Also, provide the i
blowdown and safety injection times as a function of break size and the break size used in the present analysis".
i RESP 0ftSE:
l Specific part-loop blowdown thermal hydraulic calculations were not performed.
Instead, rod heatup during the " blowdown" period was considered to be adiabatic.
There was no clad to coolant heat transfer during this period. This approach i
is the most conservative.
Without any thermal hydraulic calculations I
having been perfomed, no specific break size is modeled. The analysis was, however, i
performed in this manner so as to represent "a large break". The length of time for this adiabatic period was taken from consideration of partial loop operztion on the length of the blowdown period. For the Calvert Cliffs plants the typical large break four-loop blowdown time is 21 seconds. We have perfomed three-loop calculations in the past and have found the blowdown time lengthened by a second.
Extrapolation of this trend would lead to the value of 23 seconds used in our two-loop analysis for the blowdown period. Similar differences were found in the safety injection and refill times. A safety injection time of 19.0 seconds and a contat.t time of 36 seconds were selectea as conservative values.
_QtlESTI0t1 #2:
I "A constant heat transfer coefficient of 5 BTU /hr-ft -0F to represent steam 2
cooling and a rod-to-rod radiation contribution was used in this analysis.
Justify that this constant is a minimum value for this case; that is, a e epe., em.
e.
quasi-pool boiling and thermal radiation to steam condition at reduced power.
Also, provide the following time dependent data in plot fona for the ruptured and peak clad temperature nodes:
a.
The sink temperature, T for the steam cooling heat transfer.
gg, b.
The surface heat flux due to steam cooling.
The surface heat flux due to rod-to-rod radiation."
c.
RESPONSE
The justification of the value of 5.0 BTV/hr ft2 *F as the steam cooling heat transfer coefficient is explained in Section S.III.D.6.b of Supplement I to CENPD-132. This model has been examined and approved by the NRC in Reference 2.
This value is employed in all C-E ECCS calculations to represent a conservative lower limit for rod to coolant heat transfer during the reflood period.
i The time dependent data requested is listed in Table 1 for the peak clad temperature node and Table 2 for the rupture node.
QUESTION #3:
" Provide the follouing additional infonnation:
a.
the hot pin axial power profile b.
the power decay curve in tabular form the time varying inlet core reflood rate in plot form c.
d.
the time varying core outlet mass flow in plot form and, the time varying core mixture level in plot form."
e.
RESPONSE
The hot pin axial power shape is described in Section IV.A.4.b of CENPD-132.
4 The decay heat power is given in Table 3.
The time varying reflood rate, outlet mass flow, and mixture level are given in Figures 1, 2 and 3, respectively.
REFEREl4CES:
1.
Letter from R. W. Reid (f1RC) to A. E. Lundvall (BG&E) received 2/7/80.
2.
Letter from Olan D. Parr (tiRC) to F. M. Stern (C-E) dated 6/13/75.
h
0 AI.i J l CALVERT CLIFFS I Afl0 !! PART -l.00P OPI. RAT 10fl PEAK CLAD TEf:PERATURE fiODE
-(===
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Steam Cooling Steam Cooling
,Thennal Radiation Si k-Tempera'ture-- Surface lleat Flux Time
{ F) l l (BTU /hr ft )
!_(IleatFlux i
2 BTU /hr f t )
2
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j 34LE2 CALVERT CLIFFS I AllD II PART-LOOP OPERATI0tl RUPTURE tt00E O
n-
-- -=-
Steam Cooling Steam Cooling
-Sink-Temperature-Surface float Flux ~ l;Thennal Radiation
' ~ ~
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lleat Flux Time I ( F)
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TABLE 3 CALVERT CLIFFS I AND II PART-LOOP OPERATION DECAY HEAT TRANSIENT Time Normalized Decay Heat Fraction
- 0.1 0.085 4.0 0.070 10.0 0.063 50.0 0.053 100.0 0.049 200.0 0.044 500.0 0.039 1000.0 0.020
- Fraction of 1377 Mwt
FIGURE 1 MASS ADDED TO CORE DURING REFLOOD 120000.
4 100000,.
80000.
/
S0000.
/
40000.
TIME (SEC)
REFLOOD RATE (IN/SEC) 0-11.8 2.51 11 9-92.4 1.24 20000.
92.4-400.0 0.77
/
a
=
e 9
J
=
2 S
m e
a cu m
+
TIME AFTER CONTACT 3 SEC
FIGURE _2 CORE OUTLET HASS FL0liRATE F
900,00 i
750.00 600.00 o
DJ m
450.00 s
i CD
_J 300.00 150.00 8
6 i
i i
e
~
J 8
S 8
o
=
a cu m
+
TIME AFTER CONTnCT3 SEC
FIGURE 3 MIXTURE LEVEL
- 12. 000 TOP (;F ACTIVE C ORE 10.000 lZ q
E 8.000 8
A C
wa n/
f /
6.000 5
[F E
's 5g 4.000 y
5 p
w
- 2. 000 j 0.000 5
8 8
8 o
e a
w m
TIME AFTER CONTACTS SEC
,7
_