ML19309D011

Proposed Changes to Tech Specs App A,Revising Operating Limit Max Average Planar Linear heat-generation Rate to Ensure LOCA Limits Will Not Be Exceeded

ML19309D011
Person / Time
Site:	Pilgrim
Issue date:	04/03/1980
From:	BOSTON EDISON CO.
To:
Shared Package
ML19309D008	List: ML19309D007 ML19309D011 ML19309D014
References
NUDOCS 8004090472
Download: ML19309D011 (8)

Text

., - - .-.-. . . - . _ ,

9 SURVEILLANCE REQUIRDENTS LIMITING CONDITIONS FOR OPERATION 3.11 REACTOR FUEL ASSDIBLY 4.11 REACTOR FUEL ASSEMBLY Applicability Applicability The Limiting Conditions for Operation The surveillance Requirements associated with the fuel rods apply apply to the parameters which to those parsmeters which monitor the the fuel rod operating condi-fuel rod operating conditions. tions.

Objective Objective The Objective of the Limiting Condi- The Objective of the Surveil-tions for Operation is to assure the lance Requirements is to performance of the fuel rods. specify the type and frequency of surveillance to be applied to the fuel rods.

Specifications Specifications Average Planar Linear Heat A. Average Planar Linear Heat A. Generation Rate (APLHGR)

Generation Rate (APLHGR)

The APLHGR for each type of During power operation with both fuel as a function of average recirculation pumps operating, the APLHGR for each type of fuel as a planar exposure shall be function of average planar exposure determined daily during shall not exceed the applicable reactor operation at j> 25%

rated dhermal power.

limiting value shown in Figures 3.11-1 through 3.11-5. The top curves are applicable for core flow greater than or equal to 90% of rated core flow. When core flow is less than 90% of rated core flow, the lower curves shall be limiting. If at any time during operation it is determined by normal surveillance that the limiting value for APLHGR is being exceeded, action shall be initiated within 15 minutes to re-store operation to within the prescribed limits. If the APLHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought i l

to the Cold Shutdown condition with-in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

205A 8004090 k [2__

~

l -- .- - -. -_ - . .-

BASES 3.11A Average Planar Linear Heat Generation Rate (AFLHGR)

This specifications assures that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the limit specified in the 10 CFR 50, Appendix K. i The peak cladding temperature (PCI) following a postulated loss-of-coolant accident la primarily a function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is only dependent, secondarily on the rod to rod power distribution within an assembly. ne peak clad temperature is calculated assuming a MGR for the highest powered rod which is equal to or less than the design IRGR.

This LHGk times 1.02 is used in the heat-up code along with the exposure dependent steady state gap conductance and ,

rod-to-rod local peaking factors. De limiting value for -

APLHGR is this LEGR of the highest powered rod divided by its local peaking factor.

The calculational procedure used to establish the APLEGR limit for each fuel type is based on a loss-of-coolant accident analysis.

The emergency core cooling system (ECCS) evaluation models which are employed to determine the ef fects of the loss of coolant accident (LOCA) in accordance with 10CFR50 and Appendix K are discussed in Reference 1. De models are identified as LAMB, >

SCAT, SAFE, REFLOOD, and CRASTE. De LAMB Code calculates the short term blowdown response and core flow, which are input into the SCAT code to calculate blowdown heat transfer coefficients.

The SAFE code is used to determine longer term system response and flows from the various ECC systems. Where appropriate, the ,

output of SAFE is used in the REFLOOD code to calculate liquid levels. The results of these codes are used in the CHASTE code to calculate fuel clad temperatures and maximum average planar linear heat generation rates (MAPLHGR) for each fuel type. ,

The significant plant input paraneters are given in Reference 2.

MAPLHGR's for the present fuel types were calculated by the above The curves in Figures procedure and are included in Reference 3. 1 3.11-1 through 3.11-5 were generated by multiplying the values in These nultipliers i Reference 4 by factors given in Reference 3. l were developed assuming no core spray heat transfer credit in the LOCA analysis.

I i I

\

i

\

l 9

205C ,

- ~ --, _. .. __ __.- .=.

-

• - "- -a WM- Aem a m- -aw-- w p-w ymyw w , .

G 4

9 (T111S PAGE INTENTIONALLY LEFT BLANK)

L 9

205C-1

,- _ _ - _ _ - - - - _ . ~ _ . _ _ _ _ _ - _ _ _ - _ -- - - - -

REFERENCES

1. General Electric BWR Generic Reload Fuel Application, NEDE-24011-P.

2. Loss of Coolant Accident Analysis Report for Pilgrim Nuclear Power Station, NEDO-21696, August 1977.

3. " Supplemental Reload Licensing Submittal for Pilgrim Nuclear Power Station Unit 1 Reload 4", NEDO-24224, November 1979.

4. " Supplement 1 to Supplemental Reload Licensing Submittal for Pilgrim Nuclear Power Station Unit 1 Reload 4" NEDO-24224-1 March 1980.

s 205C-2 L

,- 5' F IG U R E 3.11 'l MAXIMUM AV ERAGE PLANAR LINE AR HE AT GENER ATION RATE VERSUS PLANAR AVERAGE EXPOSURE FUEL TYPE BD B 219 L 7

0 12 m

ZE co R.E LOW si.4 3 907c tATED s

$z '33 "3 a9 u n.

WD 3$ $7 io.e ez eo s

'g so. t ie.3 e 10 lo.8 3, y E ct om .3,se CORG FLOW 4. 90% RATE D 9G a ct

1. $ 9

's 8.'t l B O 5,000 1QOOO 15000 20000 25,000 30,000 l

\

PLANAR AVERAGE EXPOSURE (mwd /t) l l

205E-1

b bsOhr

~

4 F IG U R E 3.11- 2 MAXIMUM AVERAGE PLANAR LINE AR HEAT GENERATION RATE VERSUS PLANAR AVERAGE EXPOSURE FUEL TYPE 8DB219 H 7

6 $g m"g ccRe Ptow 44 zc

/ >, ec% r4 A7tn ii.4 jZ 81 3 11. 3

'9 11 gg o.o oa

$# uos lo.s 's

=g

,c . , o.4 10 '4 r io o b

Er ee se os gg es coac now 4 eo7,cmen 2m z 9 8.7 B

o 5,000 1Q000 15,000 20,000 25,000 30,000

\

PLANAR AVERAGE EXPOSURE (mwd /t) 205E-2 i

F IG U R E 3.11- 3 MAXIMUM AV ERAGE PLAN AR LINE AR HE AT GENER ATION RATE VERSUS PLAN AR AVERAGE EXPOSURE FUEL.. TYPE 6DBZG?

7 b jg COR.E F Low > 907o RATED w

KH s C t 1. 5 J 2 O- l l ?.

1j Lij q 10.9 0E lo G G

$ '$ 10.S W W , o, 4 10.4 4 C g o, t 10.4 10.0 10.1 24 3* '

CORE F LOW 4 907c R ATED 3

• ax qq 96 2m z 9 9 2.

3 .

B o 5,000 10000 15,000 20,000 25,000 30,000

\

PLANAR AVERAGE EXPOSURE (MWgt) 205E-3

A F IG U R E 3.11- 4 MAXIMUM AV ERAGE PLANAR LINE AR HE AT GENERATION RATE VERSUS PLAN AR AVERAGE EXPOSURE FUEL TYPE P83RB 2G 5 L 7

17.

m 4k ZC CORE Flow >< 90% RATE D

$Z a F52 u me ,

w4 n .o "li o t i.o ox 4m (0 8 E Z is t 'O' W m n n Yo2 'oa 4f 30 2 <t

,c 2 io :

to o .

DW S1 <g 5y 91 Nh CORE F LOW 4 907o R AT EIl 2W z 9

3 .

B o 5,000 10000 15,000 29000 25,000 30,000

\

PLANAR AVERAGE EXPOSURE (MWft) 205E-4

F IG U R E 3.11- 6' MAXIMUM AVERAGE PLANAR LINE AR HE AT GENERATION RATE VERSUS PLAN AR AVERAGE EXPOSU RE FUEL TYPE P8D R B 282 7

1 12 m

K V-44 CORE Flow <,*Sc7e R A T E D ZC 3Z a o r -

~

H , (t o i t.1 0$

A tLJ lo 9 so.9 EZ W P% IO 3 io 4

<e p 10

,o. ,

sc z

,o ic 54 sc.o ic o

>< m

?95 u5 Co RC Flow 4 907c it ATib 90 M

<< 9. 4 Ew z 9 3 .

B o 5,000 10000 15,000 20,000 25,000 30,000

\

PLANAR AVE RAGE EXPOSURE (mwd t) 205E-S

-