ML20247P767
| ML20247P767 | |
| Person / Time | |
|---|---|
| Site: | Palisades  (DPR-20-A-129) |
| Issue date: | 09/15/1989 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247P768 | List: |
| References | |
| NUDOCS 8909280002 | |
| Download: ML20247P767 (7) | |
Text
_ - _ _ _
- h o
UNITED STATES.
[
NUCLEAR REGULATORY COMMISSION g
- y WASHINGTON. D. C. 20555
%,*.**+p$
c.
CONSUMERS POWER COMPANY DOCKET NO. 50-255 NLISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE AmendmentNo.k90 License No. DP 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The appitcation for amendment by Consumers Power Company (the licensee) dated August 4, 1988, 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, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this emendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will ba conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to rcad as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.129, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8909280002 890915 PDR ADDCK 05000255 P
PNU
l-a-2..
1 l
3.
This license amendment is effective as of the date of its: issuance and.
shall'be implemented not later than October 30, 1989.
FOR THE NUCLEAR REGULATORY COMMISSIONS 9
h.
John 0. Thoma, Acting Director -
/.
Project Directorate-111-1 Division of Reactor Projects - III,.
IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to.the Technical Specifications Date of Issuance: September 15, 1939 i\\
ATTACHMENT TO LICENSE AMENDMENT NO.129 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below 'and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3-81a 3-81a 3-81b 3-81b 3-82 82 4-11a 4-11a l
l l
@9 c.
m
[
[,'
Table 3.17.4 (Cont'd) h
^
Minimum.
Minimum Permissible ~
__No Functional ~ Unit -
. Operable' Degree of-Bypass 1 7o Channels Redundancy Conditions
'8.
Pressurizer Wide' 2 - (m, P, 9)-
None-Not required in
/.'
' Range Water Level Cold or Refueling L
Indication Shutdown 9.-
Pressurizer' Code,
1 per None-Not Required Safety Relief Valves Valve below 325'F Position Indication (Acoustic Monitor or Temperature Indication)
- 10..
Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Temperature is closed and its Indication) indication system is operable-II.
PORV Isolation' Valves-1 per.
None Not required when Position Indication Valve reactor is depressurized and vented through a vent it!'.3 sq.in.
12.
Subcooling Margin 1
None Not required Monitor ^
below 325'F
//
-13.
Auxiliary Feed Flow 1 per flow (h)
None Not required Rate Indication Control below 325'F Valve
.14.
Auxiliary Feedwater 2persteg 1
Not required
- Actuation System generator below 325'F Sensor Channels 15.
Auxiliary Feedwater 2(I) 1 Not required Actuation System below 325'F Actuation Channels 16.
Excore Detector 1(8)
None Not Required Below Deviation Alarms 25% of Rated Power 17.
Axial Shape Index 2(I) 1 Not Required Below Alarm' 25% of Rated Power U'
'I'")
None Not Reaniied
/
18.
Reactor Vessel 2
Water Level Belce 325'F
/
3-81a Amendment No. #1, #5, 96, JJ5,
- 175, 129
I t.
-Table 3.17.4 (Cont'd) 4 (e) Auxiliary'Feedwater System Actuation System Sensor Channels contain pump auto initiation circuitry.
If two sensor channels for one steam generator are inoperable, one of the steam generator low level bistable modules in one of the inoperable channels must be in the tripped condition.
(f) With one Auxiliary Feedwater Actuation System Actuation Channel inoperable, in lieu of the requirement of 3.17.2, provide a second licensed operator in the control room within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. With both inoperable, in lieu of following the requirements of 3.17.2, start and maintain in operation the turbine driven auxiliary feed pump.
(g) Calculate the Quadrant Power Tilt using'the excore_ readings at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the execre detectors deviation alarms are inoperable, or at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> using symmetric incore detectors when the difference between the excore and the incore measured Quadrant Power Tilt exceeds 2%.
(h) With two flow rate indicators inoperable for a given control valve,.the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply.
(i) A0 operability requirements are given in Specification 3.11.2.
(j) A level channel consists Sf eight sensors in a probe. A channel
/
is OPERABLE if four or more sensors, two or more of the upper
/
four and two or more of the lower four, are OPERABLE. There
/
are two channels.
/
(k) With the number of OPERABLE Channels one less than the minimum
/
channels operable requirement, in lieu of the requirement of
/
3.17.2, either restore the system to OPERABLE status within 7 days,
/
if repairs are feasible without shutting down, or prepare and
/
submit a Special Report to the Commission within 30 days,
/
following the event, outlining the action taken, the cause of the
/
inoperability and the plans and schedule for restoring the systems
/
to OPERABLE status.
/
(1) With both channels inoperable, in lieu of the requirement of 3.17.2,
/
either restore the inoperable channel (s) to OPERABLE status within
/
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:
/
1.
Initiate an alternate method of monitoring the reactor vessel
/
inventory; and
/
2.
Prepare and submit a Special Report to the Commission within
/
30 days following the event outlining the action taken, the
/
cause of the inoperability and the plans and schedule for
/
restoring the system to OPERABLE status; and
/
3-81b Amendment No. PE, 95, 115, JJE, 129
~
Tdle 3.17.4 (Cont'd)-
/
=3.
Restore the system to OPERABLE status at the next scheduled
/.
refueling.
/
(m) The provisions of Specification 3.0.4 are not applicable.
/
(n, o).
Blank
/
(p) With one OPERABLE Pressurizer Wide Range Water Level Channel in lieu of the requirement of 3.17.2, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(q) With no OPERABLE Pressurizer Wide Range Water Level Channels in lieu of the requirements of 3.17.2, either restore at least one of the inoperable channels to OPERABLE status enthin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.18 (Deleted) 3-82 Amendment No. 29, JJp,129
f lll s
/////
s 9
l 2
e 1
n,
ns
(
ae r
N
)
hl e
d 4 cp p
n o
o
(
u o
a t
t todr he 7
d Dt ncep e
5 o
d d
D Tu aot mr h
e e
T Rp dmae oh t
i i
R n nrev ot o
e l
l rI ueh r r
N M
p p
r o
dh e
a p
p o
fe etos l
t e
A A
f l
r r tb on n
c a
du r
o ri e
n e
e e
n es mot t
n m
a r
r t
g ts of n d nh o
d l
u u
u i
ue r en oc i
n l
s s
t S
t r fera ct t
e i
s s
i iP gr i
i m
e e
e ts t st saus ew d
A v
r r
sl s l sn gt c e hs n
r P
P be e ebw nl l
t o
u un T nuo iorp y
c S
l l
Sn nSn dveu me a
a a d a K a t o ok n
i i
eh e he enac r-w t
t cC t Cch rweo ft o
n n
n a
nt ohm s
d e
e af r fai fn r
pe t
r r
tob otW ok e e mt u
e e
s i
s sh u
h f
f in l
nit neat pp s
m f
f so a osn ote i
i es C see surne ru d
Ds Ds Ri iRd itcos ep l
r h r
r t r i ri n i n t
o no cno na c anc atito ae c
ws tws wp e pwn ps cp wh on i on omj moi mbd n s dt e
)
ne wne no n ono ounue e
h d
KS SKS KC I
CKC CSajr em t
t fo n
r g
yf n
o C
a ab ab a ab ab r
i
(
ad r
i n u
l a d
3 yc
)
i n
5 x) g 1
uy n
e
(
. 4 u
)
al i
a q
3 p
t 1
E e
(
gp s
1 L
r nu e
B F
4 A
t T
rm
.d aa e
t e
- 1. f i
st e
e e
e e
e s
- 1. i e
t t
t t
t t
e c
c a
a a
a a
a de 4e nn r
r r
r r
r ut p
ao b
b bk b kb kb l a es li i
ti ic i ci ci cn l
lt l
sl l e l
el el nr be i c a
ea ah a ha ha i e ah en C
Tt vu ol rF ta
,m u
) r S
a ab ab a ab ab dr bo eo (f
s t(
4r e
a e
v nr mp rl re e
fea ek t o ezV t a it n
p p
ii n
r l e o
m m
l rf o o
ar hy i
u u
euei t
n b
t r t
P P
Rsit i i e
i a p
n sl a n g be ws i
do d deec e o r l
h s
r ei e erRi r M a e
ot ne c
et e tP d u M
s t
.oc s
Fa F a
yn t c
sl mdi e e
c rdtI a i g ee dootn D
yi y
ene r
t n Vv o ri c rd r pafn e s i e
hfrnt l
an a O
ao p u l r rL t
euo e
iI i
sSi m
o oo o
e,pjn n
l lt re t
e c ot tr mh n
n iwir evei T A ci ce chos a
xo xa wlds bn at tttci h
ul ut oaoo
. uo ea sin C
AF AS PVCP a b SM RW ewont TsmII
)
))
5 6
7 8
9 3
45 1
1 1
1 1
(
((
b l\\ll llI