ML20212N862
| ML20212N862 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/22/1986 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 2002K, NUDOCS 8609020005 | |
| Download: ML20212N862 (9) | |
Text
%) co
/
=
- % One First National Plaza. Chica00, libro_s
/ Addra)s Reply to: Poet Omco Box 767
'd Chcago, Illiros 60600 - 0767
~
August 22, 1986 L
Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC. 20555
Subject:
Byron Station Units 1 & 2 Submittal of Revised Heatup and Cooldown Curves and LT Value for Byron Unit 2 NRC Docket Nos. 50-454 and 50-455
Dear Mr. Denton:
Enclosed are three attachments which include information to be incorporated in the Byron Station Technical Specifications. and 2 are the revised heatup and cooldown curves, respectively for. Byron Unit 2.
These curves replace Figures 3.4-2b and 3.4 3-b currently found in the Byron Technical Specifications, Section 3/4.4.9 (Reactor Coolant System, s
Pressure / Temperature Limits).
The curves were revised for two reasons.
The current Unit 2 heatup curve is applicable for heatup rates of 600F/hr, which is inconsistent with the 1000F/hr maximum limiting condition for operation.
Additionally, the original heatup and cooldown curves are also based on an analy. sis assuming copper content of 0.05 wt.%
in the controlling material.
The revised curves were made in order to conform to Regulatory Guide 1.99, Rev. I which requires analyses to use the actual weight percent of copper, or 0.08 wt.%, whichever is higher.
The Byron Unit 1 heatup and cooldown curves are correct and l
require no further action.
i provides the Byron Unit 2 specific value for l
the maximum allowable containment test leakage rate, LT, at pressure Pt.
Based on the results of the Byron Unit 2 i
preoperational containment integrated leak rate test, LT was determined to be 0.07%.
This number has been reviewed and approved I
in accordance with Commonwealth Edison Company procedures and should be included in Section 3/4.6, Containment Systems (page 3/4 6-2) of the Byron Technical Specifications, Or1 n
8609020005 860822 PDR ADOCK 050004S5
/
g j A
PDR j
l
% In accordance with the requirements of 10 CFR 50 Appendix Section V, a summary technical report of the Byron Unit 2 Reactor J,containment _ building integrated leak rate test will be submitted in a separate transmittal.
Please direct any questions you may have regarding this matter to this office.
One signed original and fifteen (15) copies of this transmittal and its attachments-are provided for your use.
Very truly yours, I. M. Johnson Nuclear Licensing Administrator
/klj :
Figure 3.4-2b, Byron Unit 2 Reactor Coolant System Heatup Limitations Applicable up to 16EFPY 2:
Figure 3.4-2b, Byron Unit 2 Reactor
~
Coolant System Cooldown Limitations Applicable up to 16EFPY 3:
Proposed Changed to Appendix A Technical Specifications for Byron Stetion Units 1 and 2 Facility Operating License, NPF-37 cc:
L. Olshan 2002K t
i
. -,., -, - _. _ _ ~
ATTACHMENT 1 Figure 3.4-2b, Byron Unit 2 Reactor Coolant System Heatup Limitations Applicable up to 16 EPPY Revised Pace:
3/4 4-34 d
4
MATERIAL PROPERTY RASI4 2 Controlling Material : Weld Metal Copper Content
- Conservatively assuned to be 0.08 WT5 (actual content = 0.06 WTS)
Phosphorus Content 0.009 WIS j
Initial RT
- Conservatively assumed to,,,40*h g
(actual itial RT a1
)
j RT After 16 UPY
- 1/47, 82 E
WT j
WW, 5 Curve applicable for heatup rates up to'100*F/hg for the service period up to 16 EFPT and contains margins of 107 and 60 psig for i
possible instrunent errors I IIII I I I IIII
'A
' t I
II I I I I II I II I I
I I
i 1
1 LEAK TEST LIMIT 2250
/
I E
E I
I i
1 I
r 2000 I
I i
1
}
- 973, i
1 f
1 f
I
, HEATUP R[TES UP J
l a
isoo TO 100T/HR %
ACCEPTABLE j
N f f
OPERATION l
3 isso
. UNACCEPTABLE
/
1 3
- OPERATION i
2 2
l1000
/
I a
i yse -
1 1
2 g
/
CRITICALITY LIMIT RASG ON IN5ERH 2 300 HYDROSTATIC TEST TeeERATUm (226*n i
POR TE SERUM PERIOD tso UP TO 16 IFP!
l 0
SG 140 130 300 280 300 380 400 430 See j
enescasas tsessmatwas (ese.r) i FIGURE Byron Unit 2 Reactor Coolant System Heatup Limitations Applicable 3.4 --g UP to 16 EFPY 3/4 t-s'l 1
v-,-,--_--
,,--,a.r,.,--
,-s
4 ATTACHMENT 2 Figure 3.4-2b, Byron Unit 2 Reactor Coolant System Cooldown Limitations Applicable Up to 16EFPY Revised Pace:
3/4 4-36 l
i A
_ =-
l*
MATERIAL PROPER'IT RASLS t l
Controlling Material : Weld Metal Copper Content
- Conserystively asmaned to be 0.08 W 5' (actual content a 0.06 M 5) i Phosphorus Centent
- 0.009 WS Conservatively assumed to ke'40%
Initial E g
, (actus1 itial RTg a 107)
NT# 'After 16 EFPY
- V4T, 82 j
- 3/47, 59 Curves applicable for cooldown rates up to 100T/hr for the service period up to 16 EFPI and contains margins of 10 7 and 60 psig for possible inst:wient errors 2500 I
s l
I j
2250 f
i I
2000 f
~
i i
i.
I l
I 1
i 1750 UNACCEPTABLE j
2 l
OPERATION
/
g 1900
/
l 2
1180 j
r i
I ACCEPTABLE r
l geog j
OPERATION 8
'm "N RATES j
7so,.9/HR 3
1 u
9 1
0%
F
_? po
- m s
900 3 40 f U f7 60 -
100-
- f 150 Oe se toe 1se too aw ase ano 4eo 4so soo
'susicarse treessatums (ste.r)
FIGURE Byron Unit 2 Reactor Coolant System Cooldown Limitations y,y_3g Applicable up to 16 EFPY N
4Ub
.... = -..
ATTACHMENT 3 Proposed Change to Appendix A Technical Specifications for Byron Station Units 1 and 2 Facility Operating License, NPF-37 Revised Pace:
3/4 6-2 9
e 5
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1)
Less than or equal to L,, 0.10% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,
44.4 psig, or o.oq )
2)
Less than or equal to L, 0.07% by weight of the containment t
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 1 (Later % by weight of the contain-ment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 2) at P 22.2 'psig.
t b.
A ccmbined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With either the measured overall integrated containment leakage rate exceeding O.75 L, or 0.75 L, as applicable, or the measured combined leakage rate for t
all penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable, and the combined leakage rate for all penetrations t
subject to Type B and C tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in confomance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 210 month intervais during shutdown at a pressure not less than P,, 44.4 psig, or P, 22.2 psig, during t
each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection; BYRON - UNITS 1 & 2 3/4 6-2
Summary of Chances The changes being made to the Byron Station Technical Specifications result from including the Unit 2 specific maximum allowable leakage rate, LT-1.
Page 3/4, 6-2, Containment Systems, Containment Leakage, Limiting Condition for Operation.
3.6.1.2a.2)
Delete the word "Later" and in its place insert the number 0.07 so the phrase now reads, "O.07% by weight of the containment air..."
t 1
4
.