ML20236J857
| ML20236J857 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/28/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20236J860 | List: |
| References | |
| DPR-66-A-111 NUDOCS 8708060314 | |
| Download: ML20236J857 (7) | |
Text
.
jo t,..iTED STATES g
[
g NUCLEAR REGULATORY COMMISSION To
- j WASHINGTON, D. C. 20555
%,.....,/
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET-NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee), dated February 11, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, j
the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
8708060314 870728 PDR ADOCK 05000334 P
PDR 4
m
1 4 (2) Technical Specifications The Technical Specifications contained in Appendices A, as revised through Amendment No.111, are hereby incorporated in the license. The licensee shall. operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented no later than 30 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\
F Stolz Director l
J ect Directorate I-4 ision of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 28, 1987 l
l I
_-_______- _=__-_- _ - -
l ATTACHMENT TO LICENSE AMENDMENT N0.111 l
FACILITY OPERATING LICENSE NO. fiPR-66
)
j DOCKET NO. 50-334 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages~ are identified.by Amendment number and contain vertical lines indicating the area of change.
Remove Page Insert Page 3/4'4-24 3/4 4-24 l
3/4 4-25 3/4 4-25 i
B 3/4 4-6 B 3/4 4-6
.1 B 3/4 4-6a B 3/4 4-6a I
i l
l i
l
E I
MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: WELD METAL COPPER CONTENT:
0.31 WT5 PHOSPHORUS CONTENT.
0.015 WT1 RT INITIAL-0*F NDT RT AN 9.5Em 1/47,2744 NOT 3/47,137'F CURVE APPLICABLE FOR HEATUP RATES UP TO 60*F/HR FOR THE SERVICE PERIOD UP TO 9.5 EFPY AND CONTAINS MARGINS OF 10*F AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS 3000 i
I!
j I
l
,' i'
- I
t l
' l lj II:
ll i
j.i i i
l 16.
i l
l t
j'j l l 1,,
t i
j iji LEAK --
~; ',
TEST
'II I
I I' ITN LIMIT L
l
/
- if lil ii i!Ii j'!
I ~'i '---
- :i1 i
Iti i
', *4 l'/!
5 '/ i i
~"
I /;
f i,U !
,i i
l
/
ilili;
- iiill, ic
!J 1
i.
- i.
,i!
eij If
/
l fiI 2000 1; ;
i I
/!
l /,1 !
2 g
.i !l.ji j
. /
l /l i
'il'!'il i
/
/
,ii; i.
!I
'l
/
)
[
~
.:'.ii, I
l i
i E
6 f
}
l.;!is, i
/
/'
i.
j,i j j UNACCEPTABLE
/
./
i.j f
OPERATING REGION e
/
/
I l.1 ACCEPTABLE i
iiI 1I i
W
_5,
- i i ii i
/
I I
OPERATING REGION j
b,!
1000 ia I
/
I 6
- j.i
/
HEATUP -
,e RATES
_ /
I e
UP TO II!
'I
' CRITICALITY t.IMIT 60*F/HR
- jil, j
l 1,f j.-
i
'l i
V BASED ON INSERVICE
~
HYDROSTATIC TEST
- i i
jj!
,-- TEMPERATURE (414*F)
'2 II f
~"
~~
FOR THE SERVICE l
J.~. i
,' 3 PERIOD UP TO 9.5 EFPS 7...,,_. l,;
.i i
r q..
0 0
100 200 300 400 500 INDICATED TEMPERATURE (*F)
FIGURE 3.4-2 BEAVER VAL' LEY UNIT NO. 1 REACTOR COOLANT SYSTEM HEATUP
' LIMITATIONS APPLICABLE FOR THE FIRST 9.5 EFPY 3/4 4-24 Amendment No.% 111 N
~_
MATERIAL PROPERTY BASTS CONTROLLING MATERIAL:
U.31 WT%
PHOSPHORUS CONTENT:
0.015 WT:
RT INITIAL:
0*F RT AFTER 9.5 EFPY:
1/4T, 274*F q
3/4T,137'F CURVE APPLICABLE FOR C00LDOWN RATES UP TO 100'F/HR FOR THE SERVICE PERIOD UP TO 9.5 EFPY AND CONTAINS MARGINS OF 10*F AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS 3000
,3, i
,Iii i
l 1
I i
l l
i I
il iil i
i i
,I I
i il!
i.
I i
I II'!!
l I
I I
i l/ijtii I
!/i!'i G
.'i l
lfil i
s Ii l
' ' /, 1 I
i-i
l I
lilli'il
~
g 2000 m
,)
il i
E
/
lilii
! Ii l
l 5
i !
/
ti 5
. /
i; I
~
i UNACCEPTABLE
'l i:!'.:
3 i; OPERATING REGION
/
j!;
,i l
f j: t i
[
I 1000
]
lit il g
]
i S
ACCEPTABLC C00LDOWN ij JV/
OPERATING REGION t
RATES *F/HR i,
yrp
/
W7 I!'
2-l d' II-40
-~
60 -
i
,j 100-l j
- j I
0
'l i
O 100 200 300 400 500 INDICATED TEMPERATURE (*F)
FIGURE 3.4-3 BEAVER VALLEY UNIT NO.1 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE FOR THE FIRST 9.5 EFPY 3/4 4-25 Amendment No.M,lll
j 0
]
l BASES 1
I The heatup analysis also covers the determination of pressure-temperature limitations for the case in which the outer wall 2
i of the vessel becomes the controlling location.
The thermal gradients established during.heatup produce tensile stresses at the outer wall of the vessel.
These stresses are additive to the i
pressure induced tensile stresses which are already present.
The thermal induced stresses at the outer wall of the vessel are tensile and are dependent on both the rate of heatup and the time along the i
heatup ramp; therefore, a lower bound curve similar to that described I
for the heatup of the inner wall cannot he defined.
Subsequently, for the cases in which the outer wall of the vessel becomes the I
stress controlling
- location, each heatup rate of interest must be analyzed on an individual basis.
l The heatup limit curve, Figure 3.4-2, is a comporite curve which was prepared by determining the most conservative case, with either 1
~
the inside or outside-wall controlling, for any heatup rate up to
)
60*F per hour.
The cooldown limit curves, Figure 3.4-3 are composite curves which were prepared based upon the same type analysis with the exception that the controlling location is always the inside wall where the cooldown thermal gradients tend to produce tensile stresses whi3e producing compressive stresses at the outside i
wall.
The heatup and cooldown curves were prepared based upon the most limiting value of the predicted adjusted reference temperature at the end of 9.5 EFPY.
l The reactor vessel materials have been tested to determine their initial RTgg; the results of these tests are shown in Table B 3/4.4-1.
Reactor operation and resultant fast neutron (E > 1 Mev) irradiation will cause an increase in the RT m.
Therefore, an N
adjusted reference temperature, based upon the fluence and copper content of the material in question, can be predicted using Figures,B 3/4.4-1 and B 3/4.4-2.
The heatup and cooldown limit curves, Figures 3.4-2 and 3.4-3 include predicted adjustments for this shift in RTNTD as well as adjustments for possible errors in the pressure and temperature sensing instruments.
BEAVER VALLEY - UNIT 1 B 3/4 4-6 Amendment No. 'NL111
e E
C A
F r
T R
4 4
U
/
/
S 1
3 i
5 3
)
Y PF E
(
EF 0
I I
3 L
E C
e I
VR E
S 5
R E
/
2 W
O P
L
)
L Y
U P
F F
F 4
0E O
X 2(
NO E
I F
T I
C L
N U
F E
5C A
, /
/
1 I S
V A
R
)
E V
S e
M l>
0 E
/
1
(
E CN E
/
U L
/
F, r
N 5
O j
R
/
T U
/
E
/
N 7
/
7 I
I T
/
/
S AF c
0 9
8 7
2 1
1 1
g o
o 0
=
i t
i 1
1 4
r N=4 CV w x 3: 55aWI 4/
3 B
E R
U G
I F
c},b" F ~ o.2% ! WH m
3 <
m
, E-n
?
3