ML20002C820
| ML20002C820 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/26/1977 |
| From: | Bilby C, Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101120071 | |
| Download: ML20002C820 (7) | |
Text
-
t
). -.
w
~
~
CORSumBIS 7
POVlBr Company c.n.r.i ome..: 2 2 w..e uien.9en Avenue, Jack.on. Ma nigan 49201. A.ea Code 517 788, SSO September 26, 1977
,.. ~,
j 9,
' ~.'l.
, <. VJ,
~
j
'd Ditector of Nuclear Reactor Regulation Att: Mr Don K Davis, Acting Branch Chief
" D.')
Operating Reactor Branch No 2
.f1*-[w.,/
US Nuclear Regulatory Cocsission Washington, DC 20555 j
' h,. f) 'l'
=*/
-DOCKET 50-155, LICENSE DPR BIG ROCK POINT PLANT - T/S CFJJiGE REQUEST - DRY OUT TIME LIM ~,,TS Transmitted herewith are three (3) original and thirty-seven (37) conformed copies of a proposed change to the Technical Specifications for the Big Rock Point Plant, Docket 5C-155, License DPR-6.
The purpose of this change is to provide specifications on the assembly averaged power-void relation to ensure that dry out times in the event of a Loss of Coolant Accident (assuring actual core operating conditions) vill be conservative when compared to the dry out times used in the LCCA analysis.
This, in turn, vill ensure the applicability of the Technical Specifications MAPLHGR limits.
- j David A Bixel Huclear Licensing Ad=inistrator CC: JGKeppler, USNRC I
(
h, W$
MJtJ**fb w
[]
CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter Jet forth, it is requested that the Technical
' Specifications contained in Facility Operating License DPR-6, Docket 50-155, be changed as described in Section I, below:
I.
Changes A.
Add to botto= of Table 1:
" Mini =u= Bundle Dr:r Out Ti=e****
Figure 1 Figure 2 Figure 2 Tip= e 2" B.
Add footnote to Table 1:
"**** Based on the General Electric Bundle Dry Out Correlation for Non-jet Pu=p Boiling Water Reactors (NEDE-20566)."
C.
Add new Figures 1 and 2 after Table 2.
NOTE: Corrected Technical Specifications pages and new figures are attached.
i, These pages also reflect the Technical Specifications change request dated
~
April 15, 1977 II.
Discussion The Big Rock Point ECCS model utilizes an e=pirical correlation to determine the duration of nucleate boiling heat transfer in the early period folleving the postulated pipe break. This correlation for ti=e to dry out is found to be proportional to the ratio of asse=bly water volume to power.
Dry out time is a significant parameter in determining the extent of nucleate and transition boiling heat transfer, and consequently the peak cladding temperature.
During power operation, the asse=bly average void fraction and asse=bly power for ENC 11 x 11 and GE 9 x 9 fuel shall be such that the following relationship is satisfied:
Actual Dry Out Time > T(Q) where the actual dry out time is a functic of asse=bly pcver and asse=bly-average voids, which in turn are conputed (utilizing the GE dry out corre-(=
lation for nonjet pu=p plants) on the basis of real ti=e 1:i c'ere =easurenents involving the. total bundle power, the axial power distributien, the inlet 1
i r
l' subcooling and the coolant flow rate. 'The parameter T(Q) is the dry out time used in:the ECCS heatup. analysis as a function of total bundle peak linear heat generation rate Q.
Q is equal to the MAPLHGB limit times the number of active fuel rods in the assembly. The function T(Q) is given in Figure 1 for ENC fuel and in Figure 2 for GE fuel.
The specification on the assembly averaged power-void relation provides assurance that dry out times in the event of a LOCA for actual core oper-ating conlitions (considering such factors as inlet subcooling, radial power distribution, axial power distribution) vill be conservative relative to the dry out times used in the LOCA analysis; hence, assuring applicability 4
of the MAPLEGR limits. The power-void relation is intended for.cperations at normal core pressure (1350 psia) but is otherwise applicable without restr$ tion on either core power or flow. The factor'of 1.02 conservatism in MAPLEGR limits is retained in the power-void relationship since dry out l
times actually used in utablishing MAPLH3R limits are based on 25 higher radial powers than those associated with the Q values in the power-void
~
relation.
III. Conclusion Based on the foregoing, both the Bir Rock Point Plant Review CoHttee and the Safety and Audit Review Board have concluded that this change does not involve an unreviewed safety question.
CONSUERS POWER COMPA'IY 7
9 C R Bilby, Vice Prgiffdent -
Production & Transirission Sworn and subscribed to before me this 2cth day of September 1977 i
Lt trta j
S$1vi B 3all, Notary Public Jackson County, Michigan Ib cct::nission expires April 13, 1980.
l
)
i 2
i 1
1 TABLE l' Reload E-G and Modified E-G Reload Relcad F & J-2 Reload G G-1U G-3 Minimum Core Burnout Ratio at Overpower 1.5*
1 5**
1.5"*
1 5**
Transient Minimu= Burnout Ratio in Event cf Loss of Recirculation Pumps From Rnted Power 1.5 1.5 1.5 1.5 Maximum Heat Flux at Ove,rpower, Btu /h-ft 500,000 395,000 h07,000 392,900 Maximum Steady State Eeat Flux, Btu /h-ft h10,000 32h,000 333,600 322,100 Maxi =un Average Planar Linear Heat Generation Rate, Steady State, kW/ft Stability Criterion: Maximus Measured Z:ro-to-Peak Flux A=plitude, Percent of Average Operating Flux 20 20 20 20 2h0 2h0 2h0 Maximum Steady State Power Level, MW 2h0 t
i aximum Value of Average Core Power Density @ 2h0 IG, kW/L h6 h6 h6 h6 t
No=inal Reactor Pressure During Steady State Power Operatien, psig 1335 1335 1335 1335 Minimus Recirculation Flow Rate, Lb/h (Except During Pump Trip Tests er Natural Circulation Tests as Outlined in 6
6 6
6 Stetion 8) 6 x 10 6 x 10 6 x 10 6 x 10 Minimum Bundle Dry Out Time *****
Figure 1 Figure 2 Figure 2 Figure 2 Rate-of-Change-of-Reactor Pover During Power Operation:
Control rod withdraval during power operation shall be such that the average rate-of-change-of-reactor power is less than 50 We per minute when power is less than 120 !N,
t 1sss than 20 MUt per =inute when power is between 120 and 200 !N, and 10 int per =inute g
whnn power is between 200 and 2h0 !G
- t CBased on correlation given in " Design Basis for Critical Heat Flux Conditien in Eciling Yater Reactors," by J M Healzer, J E Hench, E Janssen and S Levy, September 1966 (APED 5286 and APED 5266, Part 2).
OcBased on F2xon Nuclear Corporation Synthesized Hench Levy.
CCCTo be determined by linear extrapolation from Table 2 attached.
~3ased on the General Electric Eundle-Dry Out Correlatien for Non, jet Pu=p Sciling ' dater
-O k
dsactors (NEDE-20566).
h3
1 i
i k
2.5 2.0 8
o z
O M
m i
O 4
I 1.5 g
O a
O m
d Q = M APLHGR LIMIT
- NUMBER OF ACTIVE FUEL RODS 1.0
/
N 700 800 900 TOTAL BUNDLE PEAK LINEAR HEAT GENERATION RATE. Q (KW / FT) j
(
Figure 1 FUNCTION TCQ) FOR ENC 11X11 FUEL POWER VOID RELATION
6 i
~
i t
2.5 2.0 oz O
M,.
a i
N g
s ur 3
1.5
(
o O
a 0
0 U
Q = MAPLHGR LIMIT
- NUMBER OF
~
ACTIVE FUEL RODS 1.0
/
A 600 700 800 TOTAL BUNDLE PEAK LINEAR HEAT GENERATION RATE. Q ( KW/ FT)
(
Figure 2 FUNCTION TCQ) FOR GE 9 X 9 FUEL POWER VOID RELATION
- ~
U.2. NUCLE \\R REGULATOMY COMA ICN OOCKET NU4"En NRC sv Ru 195 86-/((
12 7si.
WRC DISTRIBUTION rOn PART 50 DOCKET MATERIAL TO:
FROM:
OATE OF OCCUMENT Consumers Power Co.
09/26/77 Mr. Don K Davis Jackson, Michigan 49201
- I/2Y[7Y David A. Bixel 0(
ETTER h0TORIZEO PROP INPUT FORM NUMBER OF COPIES RECEIVED h-'lGIN AL g NC LASSIFIE O aCO,y 3.s l g co 37 cc, j
DESCRIPTION ENCLOSU RE i
License No. DPR-6 Appl for Amend:
tech specs proposed change concerning providing specifications on the assembly averaged power-void relation' to ensure that dry out times in the J
enent of a LOCA (assuming actual core operating conditions) will be conservative when compared to the dry out times used in the LOCA analysis...
]
Notorized 09/26/77...
1p 5p PLANT NA'4E:
BIG ROCK POINT jcm 09/29/77 YO fYb
&fL ECL I
SAFETY FOR ACTION /INFORMATION BRANCH CHIEF: (7)
M Adi$
I i
,(
INTERNAL DISTRIBUTION
{ JFG FILE j
'MRC FDR I C E (2) l OELD HANAUER C:!ECK i
STELLO i
EISENHUT l
SHA0 BAER BUTLER GRIMES I
J J. COLLINS i
I l
EXTERN AL DISTRIBUTION CONTROL NUMBE R,i
///jl LPOR: d.h A E Le u s VJ M1.*C.Jr.
J t
I 16 CYS ACRS SENT CATEb0F,Y M s
a m