ML19351D747
| ML19351D747 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/10/1974 |
| From: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19351D746 | List: |
| References | |
| NUDOCS 8011170835 | |
| Download: ML19351D747 (7) | |
Text
.
_,, _ 1
- e UNITED STATES ATOMIC ENERGY COMMISSION 5
'_.J 1*
WASHINGTON, D.C. 20545 l *I 1!L >p 7
YANKEE ATOMIC POWER COMPANY f
DOCKET No. 50-29 YANKEE-ROWE ATOMIC POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. DPR-3 1.
The Atomic Energy Commission ("the Commission") has found that:
A.
The application for amendment by Yankee Atomic Power Company
("the licensee") dated September 21, 1973, and supplements dated November 26, 1973, and February 20, 1974, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended
("the Act"), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; C.
The facility will operate in conformity with the license, the provisions of the Act, and the rules and regulations of the Commission; D.
There is reasonable assurance (i) 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; and E.
Prior public notice of this amendment is not requie d since the amendment does not involve a significant hazards consideration.
2.
Accordingly, Paragraph 3.A.(2) of Facility License No. DPR-3 is hereby amended to read as follows:
"(2) Technical Specifications The Technical Specifications contained in Appendix A, attached to Facility Operating License No. DPR-3 are i
revised as indicated in the attachment to this license amendment. The Technical Specifications, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised."
l 80111zo D 5 j
~^
- 2'-
4 3.
This ikcense amendment is effective 'as of the date of its issuance.
FOR THE ATOMIC ENERGY COMMISSION 2
4 Karl R. Goller, Assistant Director for Operating Reactors Directorate of Licensing
Attachment:
Change No. 112 to Appendix A Technical Specifications Date of Issuance: July 10, 1974 f
i ATTACHMENT TO LICENSE AMENDMENT NO. 7 CHANGE NO. 112 TO TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO. 50-29 Replace pages 214:5, 214:6 and 214:7 and Table 1 in the Technical Specifications with the attached revised pages and the revised Table I.
Change specification D.2.d. (1) of Appendix A to read as follows:
1 (1) The reactor shall be scrammed automatically by a low primary pressure trip signal at 1800 psig whenever the reactor is critical.
a i
h 214 5 cain control. board. The source range and intemediate range signals actuate the 1.1 decade per minute circuit, but only _the intermediate range signals operate the 1.5 decades per minute circuit.,
The startup rate scram is nomally set to trip at 5.2 decades per minute and is adjustabic from 3 to 10 decades per minute. The sourco range and intermediate range signals can actuate individual channel bistable mag-netic cmplifiers to initiate the scram.
In addition to these signals, there exists from each one of the log microammeter units in the intermediate range channels an automatic sig-nal, which disconnects the high voltage from the BF3 Proportionalgounters when the reactor neutron flux is increasing between 5 x 10' and 10 nv and ccecc::3 cts the high voltage on decreasing flux at approxi=stely the same level. The infomation that this signal is initiated is obtained by the source range high voltage light mounted on the nuclear section of the main control board. The light is off when the high voltage is off. A manual switch disconnecting the BF3 source range high voltage is also available at the nuclear instrumentation cabinets.
The coincidence feature makes it secessary for two out of six power range channels to initiate high neutron flux level signals in order to cause the scram amplifiers to trip.
The high neutron flux level trip set point is adjustable for various reactor operation conditions.
For reactor 100% full powerloperation, (i.e., 600 buit), with four loops in service, the level trip set point is set at 108%.
For rea'ctor operation between 0 and 15% of full power, the IcVel trip set point is manually adjusted to 35% of full power.
A power range coincidence single switch is provided to allow for coincidence scram or any singic channel scram. The low power scram set switch is located on the nuclear section of the main control board.
Signals not fed through the coincidence circuit but operating on the scram amplifiers through the alarm and scram panel are those initiated from low main coolant pressure, low pressurizer pressure, low steam generator Provision is made in Icvel, high pressurizer level, and high startup rate.
the alarm and scram panel to accommodate additional signals for memory light
~
indication only.
A praissive relay circuit, shown on page 214:6, is provided which is operated cy two pressure switches activated from the turbine No. I nozzle Operation of the circuit occurs at a turbine steam pressure pressure.
equivalent to 15bufe output. This circuitry provides for an optional manual by-pass for the low steam generator level scram, low flow scram and turbine-At 15 MNe and above, generator scram signals when the power is below 15 MNe.
the scram bypass is automatically removed and the system is available for automatic rods-in motion of the control rods. The high startup rate scram signal is automatically connected at 15 MWe and below and automatically bypassed above 15 MWe.
A second pcmissive relay circuit is activated at the 30 MWe power IcVel, which provides for automatic cut-in of a manual rods out reset circuit.
At power levels of 30 MWe and above, the reset circuit requires the control switch to be returned to the neutral or reset position before making each additional rods out step.
Selow 30 MWe output, the reset circuit becomes P00RDR31NAL 1
^
~(
^
^ '
'~
~
l'OS. NO. 2 Battery
'AT PO*;l:R SUR TRIP TRIP
\\
/
\\
'/
,;f Trip PS423.
PS420' A
On>15 A
On<15 se a
/ Close,
MWe Open K3-2 q Bypass
=
j o
<l5 }rde
<15
~
gy_1 -
We
~~
- K5-1
[
K4-4 K5-2 K1 K2 K3 K4 K5 g
pf j
~
NEG.
S.C. Level
'High SUR Memory Light
\\
/
m 1
l
'M.C. Flow
/
\\
Tripped r
v K2-1 K4-1 K4-2 KS-3 K3-1 y signal Y
y.
To Scram Amplifiers No. 2 Battery POS.
\\
N
/
Turb.-Gen.
Turb.-Gen.
A-A Trips Trips M.C.
M.C.
/
g
.f s
Flow Flow N
Trip Trip p
Ki-2 pdKl-2 l
r Manual and Nuclear Trips BK-1 K-2 s
NEG.
PERMISSIVE RELAY CIRCUIT l
P90R GRIGINAL l
[
(
W.
7.a 214:7 7.f ;
ineffective and thus a controlled but continuous rods out motion may be uffected.
Alarm and Scram Panci The six scram signals, low pressurizer pressure, low main coolant pressure, lov steam generator icvel, high pressurizer, high startup rate, and hig!. neutron flux levels are connected to the magnetic amplifier alarm and scram panel that acts as the control center for indicating the individual signals that may have caused the scram and for operating the scram amplifiers directly.
Low main coolant flow and Turbine Trip signals are connected to g,r, the alarm and scram panel for indication only.
~
i Scram Amplifiers The two magnetic scram amplifiers operate individual scram relays whose contacts are connected to the trip coil circuitry of the rod scram cir-
'3
'i[f ~
cuit breakers. The scram relays are energized at all times except when a scram.
signal is sent to the scram amplifiers.
When the scram amplifier outpats are zero, the scram relays are de-energized and the contacts in the trip coil cir-cuits close causing both breakers to operr. *The circuit is such that any one scram relay actuates both circuit. breakers.
Meter and Test Panel Two meter and tes' panels provide local indication at the nuclear instrumentation cabinets and the necessary calibratini; signals to completely and accurately check out all the channels for normal operation and energizing conditions.
Auxiliary Meter Panel The auxiliary meter panel contains three meters which were us3d during early plant life to measure the uncompensated signal from the three intermediate range ion chambers. They have been short circuited because intermediate power range channels now measure this signal with greater accuracy.
' Recorder The recorder used with the nuclear instrumentation is a large, 2-pen, multi-speed instrument with two decade switching circuits.
The speeds of the paper are 4 and 240 inches per hour. The decade switching allows for full scale deficction for one decade change in reactor flux.
This recorder is mounted on the front of the nuclear section of the main control board.
7*
O q
v e
s m.
M
_4g
% L Mf).-W gu RW
~
r
~
u E
r L
%gp h a
f 2
a"
{
d m-J 3
t P r.
5 e
a (*W
/k f n
t.
n r
3 x.
Lk r
g ef i
a r
i n
r i a. t 4
o t
i f
L.
ni t
1 r*/
t i
c nhn o!
- e n
C t
c na ar r.
t pot
=
eW s
i r
oi I
4 o
c5
- r
.h d
p;.
ur ot e t
a1 r
c*
oe l ard u
o c
c 5
r d. c b
n
- rol -
A e
a se s1 ni d e c o ;.
e.
1 r e
v t
ye ia ep cg S.
t s : r.
o r
ne e
~
er t
t os o cmc 8t b
r) si sn a
2 i ed a
r c e
- r. e eo t
eo l o
- cr ea r
r cb n
vc ot r
ee t
pe o
cr a
oy l
snrhe ree er f
so p
in ar ii u rj e
t ie t a vo tip a;n t r 4 r b
ps rc e
p y' d a h e sai o
ir ti ct pa ner i c rd ff e
re b
ja iv i.
a e e n t.
t e.
o c
t n rr n
r c p a. v c
d il e
ou iy t n s]
r
=er me va sg t t l
i t pcL
- t e
ur rc n
a yl s
n t
- r. t w
ut xi ci ie rs t a es eg rl i en iu
=t bp ap eu sc vipea nri q
i ri ni fn on ol ow ke nr ur cr aa li r e o on s
! 22 Mr I c Tt Ct S u.
Cl P b l3i en
.i tl n
ae x
l r a
ou m
x os a
cs m
e s
e*
nr e
t v
l$
i p r
s n
c
)
a g.
u l
S t
T o
n ~
i 2
mr xx s
a.
o*
e 5
e aa s
i I
t t
a p
b 1
ns mm e
t H
n v
oi r*
n 1
s a
p,
W "-
s e
r p
e v"
l.
L d.
e e
gu r
nx on t
s h
o" i s se r
e T
oa oi c
c b
es yy e
f N
pm cm s
p n
a pe ll n
f I
a i
i
'e r
aa i
i S
O c-n-
. e p
r l
0p vy a
d T
P x
r i
. m a
T 5 e m
0 t
ap x
N s
rr T
m oe n
mo s
.i r
1v i
7 e 12 n
e t
t r
e t*
1s o
r 0
E cw i
o a
o nl i
c u
r S
o m
ll y
e t
a y
no oo t
xp a
n n
a hr n
aN NN r
a T
n u
my a.
a r
t e a
h o
r i
ld rn s*
b c
t t r p
e g
oa e
e n
ra e
o S
m f e
- 3. as a-p
/
t i
n h
l u
e ew l
u v
m
. n c
na s
n c
b T
C k
b sl
= T.#
ss e
io~
o or p
fi n
a ol a
ce pp g
t d
r o
i l
t l
l a l
1 n i
t%
0 w
i s
a m
i n
50 s
T 2
u8 0
Zo
.i a
u u'
t r a
'c a 86 p
t
= r e0 8
0l v
s s
oo v
oh 45
'0 5
N1 1
Ef A
u U
Nn A
Hc 22 5
3 T'
r't
~
t t" "
- r. '
CA r
s s
s e
s s
t e
se s e se se se eM pW cW a
sW aW a
p pM pW p :4 SA u:
y y
y y
y P
f5 b5 b5 b5 b5 b5 Y
y1 1
1 1
1 1
B b
l l
l l
l l
l e
aw a
av aw aw aw a
e uo u
e u o uo uo uo u
e e
e ov.
c t o n
n nl n
n nl nl nl nl n
n n
n ub o
o ae a
o ac ae rae ae a
o o
o' t
AA N
N IB M
N M Te HB tB MB H
N M
N' SP L
6
)
E. I R
c e
e e
e e
e n
l l
l l
l l
sT r i tJ o
.C a
b b
b b
b b
t O n
h a
a a
a a
t 2
t43 1
c c
c 43 c
2 c
2 c
O T-2 5
is i
i i
i i
i D-f f
(
f eff f
l l
l ff l
f l
f l
o roo o
p p
p oo p
o p
o p
FT o
o Ok 4
o p
p p
p p
p I
t t
t mt t t
a a-a tt a
t a
t a*
u u
f u
uu u
uu u
u r,
o o
o o
to ~c o o
t t
t oo t
o t
o t
- 0. I o
o o
o o
o 1
1 N21 1
N N
N 22 N
1 N
1 N
. t' I
2 1
e r
us e
s p
e t
e t
r n
.i v
r l
N t r n
e rl o
rT n a
nP a
z p
oe p
i e
o V
t vm
- e. i u i
.c-
=.
r.
a s
l n
i - Q m
is
- m. p 8
t nei i-p na l rm o
e r
s a
ra aea 1 rs c
e int t
,n o
r oea o
r ul r Ii r Tr rL r bTt e
rv aia n
C-T s
t c rl c
.ozr C
e s ec
- r c c
o c
r c
j cl tLr a
S. T S rS nrO urS nn zan n : o lk l
r *-
t eS CiM S
svS r
n ee o
ee To I o iVo c: p oc
.Wta uv n ;.
i r
rL r r e r t r Ct r t r i
r i
C n C.
oo r
e c. r
.i sr a-e P
o 1
n n o.
aa t e N1 o
.o iao
)t yt i
Cl wt aso M
t rt t.
., U t rt s
ei t
t srt t a s
ro r
- e hxc Het wc
.h e c nnb ogn u
e se c
uec er aer ne rc wo -
gt J
- g e.
r s nm eu nna f e cf e ptl i t
- ua wPe ol e 1
c 3
f ua ee t
a
- a. R IATR Cc S!
e aee ap rap aua an 1 1 e o
s tFR
- 1 1 0
. L 6 F.
1 z
',