ML20062E881
| ML20062E881 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/05/1978 |
| From: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| To: | Speis T Office of Nuclear Reactor Regulation |
| References | |
| P-78192, NUDOCS 7812130164 | |
| Download: ML20062E881 (10) | |
Text
'
?
s
.t t
P
\\\\
PUBLIC SERVICE COMPANY OF COLORADO
- o. B o x 64o DENVER, CoLoRAOo So2o1 C. K. mu.EN December 5, 1978 semoa vice..cs.oc r Fort St. Vrain Unit No. 1 P-78192 Mr. Themis P. Speis, Chief Advanced Reactor Branch Division of Project Management.
Office of Nuclear Reactor Regulation Washington, D.C. 20555 Docket No. 50-267
(
SUBJECT:
Review of Technical Specification Setpoints REF:
- 1) Letter Speis to Fuller, August 28, 1978
- 2) P-77196 September 20, 1977
- 3) P-77092 March 29,1977
- 4) P-77176 August 17, 1977
- 5) P-77228 November 16, 1977
- 6) P-77221 November 1, 1977
Dear Mr. Speis:
Pursuant to your letter (Reference 1), we are proceeding with our plan of action for identifying the instrument trip settings and the absolute limiting values as outlined in Reference 2.
You should note, however, that our plan of action set forth in Reference 2 was predicated on your approval of the proposal action pl'an by October 3, 1977. Based on your recent approval our plan of action has necessarily been delayed. This letter shall serve to establish a new sche-dule for our action plan as well as set forth the present status of the program.
We have completed our ' valuation, with a few exceptions that are identified e
below, for the Category I instruments of Table 3.3.1 of LSSS 3.3 and Tables 4.4-1 thru 4.4-4 of LCO 4.4.1.
Our evaluation has been based on overall channel accuracy utilizing manufacturers published data and the least squares method for determining accumulated accuracy. The results of this evaluation are indicated on the attached revised tables as follows:
CATECORY I A.
Table 3.3.1 of LSSS 3.3 The attached Table 3.3.1 reflects the absolute trip value and the corresponding instrument, trip settings with the following exceptions:
I
'\\ k j s
l 7812230164
[o
,..n f
t
}
l i
Mr. Themis Speis I
t Page 2 la) High Neutron Flux - The High Neutron Flux scram is presently undergoing L
further evaluation and will be addressed under separate correspondence along with the Category II instrument trip settings.
B.
Table 4.4-1 of LCO 4.4.1 f
The attached Table 4.4-1 has been revised to reflect the absolute trip values k
and the instrument trip settings with the following exception and/or notes of clarification:
3a) Linear Channels - High channels 3 through 8 are presently undergoing 3b) further evaluation and will be addressed under separate correspondence along with Category II instrument trip settings.
[
- 8) Hot Reheat Header Press-Low - A request for change of the Technical
[
Specifications concerning this item was submitted to the NRC on November 16, 1977, via P-77228 (Reference 5).
The attached Table reflects the changes requested by P-77228.
(
C.
Table 4.4-2 of LCO 4.4.1 The attached Table 4.4-2 has been revised to reflect the absolute trip values and the corresponding instrument trip settings. As addressed in P-77092 (Reference 3), the absolute trip values and instrument trip settings for l
Items 2b. and 2d. of the table are the same. Any attempt to adjust the instrument trip settings for these two items will bring us into the normal operating range of temperature expected in areas being monitored. The abso-a lute trip value of 130*F is presently being evaluated to determine if this
[
value can be adjusted upward to allow a margin for instrument inaccuracy.
i l,
(
This item will be addressed by separate correspondence along with other
[
i Category II items.
1 D.
Table 4.4-3 of LCO 4.4.1 The attached Table 4.4-3 has been revised to reflect the absolute trip values and the instrument trip settings with the following clarification:
}
2a) Loop I and Loop II Fixed Feedwater Flow - A Technical Specification
[
2b) change was submitted to the NRC on September 7,1977, via P-77188, which requested a change in the absolute trip value to 0% with an instrument trip setting of 10% of full rated load. The attached Table 4.4-3 reflects the values requested by this correspondence.
{
b F
i t
i t
i t
I Mr. Themis Speis Page 3 e
E.
Table 4.4-4 of LCO 4.4.1 Items in Table 4.4-4 are presently under evaluation consistent with changes that are being evaluated in Table 4.4-1, which were previously identified.
Changes in this table will be addressed by separate correspondence as defined above for Items 3a and 3b of Table 4.4-1.
CATEGORY II and III Based on our original plan of action as set forth in P-77196 (Reference 2) and your recent approval, the schedule for completing our evaluation of Category II i
and III items is revised as follows:
A.
Category II items will be evaluated with the intent of defining absolute f
tr.?.p values and instrument trip settings for submittal to the NRC by May 1,1979.
B.
Category III items will be addressed within thirty (30) days of receiving NRC approval for Category II items.
l.
Again, the schedules set forth above assume concurrence by the NRC with our approach for evaluating the absolute trip values and instrument trip settings that are being transmitted herewith for Category I items. Category II and III items are presently being evaluated utilizing the same basic approach that we have taken for Category I items; and obviously, any changes to this basic approach will necessarily delay our evaluation.
Very truly yours,
\\
C. K. Millen Senior Vice President 9
CKM/sb l
i
3.3-2 c
f;i.ec t ricat.lon I.SSS 3.1 - I.lai t t nit finfety System Set tint'I TAN E 1.1.1 Absolute instrument Parameter Function Trip Settlet S ye13 1.
Reactor Core Limitirig Safety Systasa Settings a) High 18eutron Flum Scram g 110% of rated Presently helen ev.sluateil. Serpe %7 est a to be m.I nf e r ed 1.y Kay 1,19/9.
thersial gover b) tilgh Behcat Stemas Scram i 1075*>
1059 1 4*F Temperature c) Low Primary Coolant Scram
< 50 Pal below rated, CateRasy 18 ta l>e submitted Pr essure progreened with load by Key 1, 1979.
2.
Reactor Vessel Pressure 1.imiting Safety System Settings a) liigh Primary Coolant Scram and Preselected i 53 pst above rated.
Category Il to be submitted Pressure Loop Shutdown and progras med with load.
by Kay 1,1979.
Steam / Water thimp Upper programned limit met to produce trip at i 775 palm 1 7'P dewpoint temp-Category III to be submitted following 6
b) lijgh Hols.ture in the Scram,I. cop Shistilown and Steam / Water Inamp crature (corresponds to approval of Category II Items.
I rimary Cunlant-1 SOO pyny liph &
100 psia pressare) c) 11;HV Pressure Pressure Itallef Itupture Disc (Low 820 psig 812 psig
- 1 Set Safety Valve) 1.uw Set Safety Valve 804 psig 796 psig i 12 Dupture Disc (High R40 pelg 812 psig i 12 Set Safety Valve) tilgh Get Safety Valve 8510 Pste R12 psig i II d) llelium Circulator Pressure Bellef i
l*cne tra ti on Interspawe l're a sure H2% psig i 22 Itupture Disc (2 per 842 p::gg 1.ca.c tra t ion) e 4
- - - - - - - +
.r---..
~. - -. - - - -., - - -,
--...,.-w-
-.s
,-.4,
3.3-3
^
TABLE 3.3 1 (continued)
Abnolute ins t rimiesit Pararneter Function Trio Settin:(
setting _
Safety Valve (2 per 821 pata 805 1 >x penetration) e) Steam Generntor Pressure 'telier Penetration Interspace Pressure Rupture Disc (2 for 842 psig 825 + 2%
each steam generator) i Safety Valve (2 for 485 psig 475 + 22 each steam generator)
\\
1 P
S M
=
$ 9
,v
---3
,a%-r~rr-,
e--,,.#-
,---r-r-
,- -,---- - - -----:,es
,--w-ew-,
-v--
r
-gr,r,.-~r
.-,r--+
- * ~, = - -,
-,-,,,e-
N
- b.b-3 Speelflestion Ir0 L.b-1 TAinf.E li.b-1 J.frQKiEt.T OP!3ATitS R53IREL_'kT3_rtyt Pt A;f7 Ps>n_TICTIyr 577:31, Kraf*!
AM204. lift H ggp3rg gegygtmyg p[pyggS!!PLE I NSTRiltil'N T TRIP OP12AELE Pir.REE Or DiPMS 1Hir MO.
FUNCf!OllAl, II:llT
$!Tflld Cr.A ;14.I I.S BMI.ii4:!CT CO.T.I'i 4 0.'~e
,J m ( Ng,,,,,,,,,,,, _ __,,,,, _
la.
Hanuel (Control Roo1) 1 0
Eme lb Hanual (fhersency Board) 2 (f) 1 None 5 -
2.
Startup Channel-Elsh 1 10 egs 2
1 Resetcr Ihte Category 118 an he g.shmitted following 1.w. In "RUS:"
appsoval of thiscr.ory 18 Items.
3a.
Linear Channel-High.
e IbOf power 2 (f) 1 Mone Prese utly l *Ing ev.sinatcJ.
Inatrimunt Channels 3. 4. 5 Ts)
.% t enint-i n he
..d mi t t ed 6 et.y i. 1979.
lb0% power 2 (f) 1 Eone
[.,
Pre ;cnt ly 1.clun evaluated. Ing t r.emen t
' 3b.
Eineer Channel-Righ.
4 Channels 6, 7, 8 Ts) set rainen to 1.
nhei s te.i hy et., I. i9is.
Primary Cnolant Holsture g,,
Nigh Level Monitor 167'F Deypoint 1(f,t) 1 (c)
None CateRary HI to be nulemitted inlinwing No' Imp Honttor 127'F Taemeint 2/Inop(f tl 1/Ico.7 IhI arproval of eLategory Il faces.
g3 5'.
Delient Steam Temperature 110T5*r (a')
2 (b) (f) 1 some ling
- g 4,*r.
- Illgh (b) 6.
Primary Coolant Pressure 1 50 psie below 2 (f) (k) 1 Less than 33:
cater.ory Is. Instrimment Set pointa en he
- - Low normal, load rated power submitted by ttiy 1, 1979, prograssed (a) i 7 Primary Coolmat Pressure 1 7 5% ebove 2 (f) (k) 1 Ncane Catenary II. Instrument set painta en he
- Migh siomal rated, subaltre11.y May 1. 1979.
Jend programmed (a) 8.
Rot Behest fleeder 10 psic 2 (f) 1 Less thari 30T 135 ents (Heq.icnt to change thtm value Pressure - Low rated g<wer submitted Navesul.cr 16, 19 78, P-7 772R, 9 Main Steam Pressure g 1500 psig 2 (f) 1 Less thwa 305 l(.15 1 25 psig
. Low rated po.er
- 10. Flaat Electrical.
(d) 2 (c) (f) 1 None System-Loss i
- 11. Two I. cop Trouble 2
1 Reactor mode
~ -----
switch in
'Tuel Loading" 8
- 12. Ilklt Reactor Bisi,1 ding 5 325*F 2 (f) 1 1:ona 175 1 5*F Te mperature (Fig.e Cavity) i a
.~
8 m-m y
c r
m j
4.4-4 e-Specification LCO 4.4-1 TABLE 4.4-2 INSTRifMElff CPERATItE REgillFHFtrtS FOR Pl.Attr PROTECTIVE SYSTDi, If10P SituTOOV.4 A hSol.IITE HilfDRIH HINDfUH PERMISSIBLE INSTRilHFNT TitlP OPERABLE D'f.REE OF BYPASS TRIP e
No.
PONCTIONA1. UNIf SITT1tC CitAffMEl.S REDUNDANCY CONnlTintlS S F.TT i tN.
la.
Steam Pipe Rupture Under i 9 v. de, 2 (f)(a) 1 None 8.7 i.02 v.
PCRV. Loop 1 (1) lb.
Stees Fjpe Rupt are Under PCRV, Loop 2 (j) 19 v. dc.
2 (f)(s) 1 None 8.71 02 v.
Ic.
Steen Pipe Rupture, North Pipe Cavity loop 1 (j) i 9 v. dc.
2 (f) 1 None 8.7 1 02 v.
IJ.
Steen Pipe Rupture, South Pipe Cavity Loop 1 (j) i 9 v. dc.
2 (f) 1 None 8.7 1 42 v.
le.
Steam Papa Rupture, North Pipe cavity Loop 2 (j) i 9 v. dc.
2 (f) 1 lione 8.7 1 02 v.
If.
Steen Pipe Itupture, South Pipe Cavity Loop 2 (J) i 9 v. dc.
2 (f) 1 Hone
- 8. 71 02 v.
2a.
litsh Pressure, Pipe 1 2.5" w.g.
2 (f) 1 Ilone 1.5"-2.0" Il o f
Cavity (j)
- 21..
tilsh T.:mperature, Pipe i 130*F 2 (f) 1 lione Category 18. as Indic.ited in P-77092, Cavity (j)
Absolute Trip Value und Set point must lie flee s.uw arit il further evaluat ion la made.
2c.
liigle Pres.ure. Under 1 2.5" w.g.
2 (f) 1 florea Cassnnry lli to lac submitted folloutng PCRV (3) e approval of r.aterury 11 2J.
liigh Tempere w.,
Under i 130*P 2 (f) 1 Hone c.eterory II, as indtrated in P-7/092, PCRV ())
Ahmoluter Teip V.alue and Set point must lac slae same eine il f ur t her ev.aluat f an In m.ede.
3a.
Luop i Shutdown logic 2
1 None 3b.
Loop 2 Shutdown Logic 2
1 Hone 4a.
Circut.stor 1A and IE Circ. LA & 18 2
1 tloc e ShutJuun -Loop Shutdown SinatJoun logic 4 t3.
Circulator 1C and ID Circ. 18: & 10 2
1 None Shutilown -luup Shutdown SipstJouis Ingle e
e g
t
- l.. le-5 Specification LCO !..le-1 TABLE Is.I-2 (continued) 6 A11501,IITE l-fINIl4JH HINIMUM PDC 4ISSII:LE INSTHilMENT TRIP OETRABl.E DIEREE OF DYPASS TRIP No.
FIRlCTIONAL UNIT SFTPING CHANy_ELS REDtnfDANCY CONDITIO83 SETTINGS ____..._.
Sa.
Steam Generator 1 010 psig 2 (f) 1 none 75'7 + 5 pata Penetration Overpressure Loop 1 Sb.
Steam cenerator 1 810 psig 2 (r) 1 None 757 + 5 pstg Penetration Overpressure Loop 2 6e.
High Reheat Header 1 5 mr/hr Above 2 (f) 1 None Category TII to be siihmit ted following Activity. Loop 1
Background
approval of Category iI.
6b.
liigh Reheat Hender 1 5 mr/hr Above ~
2 (f) 1 None Category itI to be submitted following Activity. Loop 2
Background
approval of Category 11.
J 00*F 2 (f) 1 Less thsn 30%
Category III presently being evaluate 1.
8 Ta.
Low Superheat Header Temperature, Loop 1 (p)
Rated Power Tb.
Low Superheat Header
> 800*F 2 (f) 1 Less than 30%
Category III presently being evaluateel.
Temperature. Loop 2 (p)
Rated Power Tc.
High Dirrerential Temp.
1 50*F 2 (r) 1 None Category III presently being evaluateil.
Between Loop 1 and Loop 2 (p)
-s, e
e a
e e
l I
I r
I i
~ \\
k k
6
=
=
2 G
=
"U T
=
4 6
4 4
.e
-en 6e.
8 L
N K
- g
{
EP E
?.
- r. e J-w 4=
e.
w$
}
.h h l
- se e
s
.2 a C
=*
E o
Q r
.n' c
= m a
EL2 b
- 2 m
E M.=
EE
== %
-C W..=
==-
b
==-d 4
- e r=
= "T
=N
==3N h at, W'
L&
b N.
6 e%
- 3. C Z
=
=C 5
e E
=.E "3.
e
=
a g
EL "g
"4" b
.===
O OO p
- a.
i
>4
?=
W-c 4
% as e
E E D.=.
+,.
q E D E D w
I m E w ar een I
1 2 j
0 h t t
f.
G ac s C u
- u ec 6
+1 8
a
-N
+\\
e 1
.&. 4 I
+!*?
C C
=
b4 C-t GC N
N C w
N E'.{ >
==C.g.
C2
- C e
e.
g C
I C ee c
w
.= 4
.s
N
==
4 4 **
e0 I
L DC O
t=
.&..M s
a.
3=
I um L'
- a M
M N
C.
4 en W Me C
C.
O C
e M
U ra n.
es e.
O t.1
=.b.
Pf -*
laa.
M t.
==
J M
b 4
b O
s
- s
d Ol = 3 U 0 4
E E
C 3 C y C 3 e
6 C 0. =es C
C' at C er 0 e C C'
M "f -
A S.
4L
L a.=
2 b
e 6='
fa 3 g ug g 4
- =
T.
C i=
ew i
=*
EMC E "W"
-r1
3 C=.
5 C==
"6 3
1 4
7 c
J W G W 4 4
4 0
0 Ce vw C e C
y W
C ul U
E EC M w R
m=
C C
U
. =,
e C.
C C
L=
m-C e
so e
w
=1 w
3
- 9. a 2
a
=
x a
c.5 doe i c v.; a am m
r.
Uf C
3 C
J wt
.e.
aL 5
b e.e u
=i.-
sc d
C
-c.
t
- = =$.
C i
He'
=
t 9
0
- =,
- e..a k.M;
.a 4
C
- e M
se 3
==
me a.
s=
.=
a=
w w
u
{- l = J. G l
=
w W
G.
O z.'
G e
5
. =.
{
\\
e U.
w
.c. *I r
.a 3
e W
e.
w m
- g
.M.:;
,=
a w
w
=
=
=
=
w w
s
.,3 c
s =.. w w
w w
w w
w w
s C
v = $m C
0
=. ri a
n ce c.
ce a
ce N
m n
= a e,
e e
wl 2
- aC I V
4
-u-T 3
h w
r a.
.c a.
1 n,
m:C s
a
=
e e
i e-
=
a 2
=l e
a
- - -=
r.
i
.s.:
a C
a.
a
.J i
E g
6
- =
mi =
r x
=
=
c
=
y <
Or
- o e
m a
e O
u a -
.C H
an.
G a.
.L t
E h
me c
.=
l v
e n
e
-s ac r
..a
.=
s ae
.s e e
.C.
u,
-C
-i M
e ae e -s e.
3 c=I u
we
=o-e m
=4 e
~
3 mi W S.i At.=- r -e; a3 6.;.
oIwc o.
=.q.
e c
- w..q c.
c.
E.l
~
o e
c
=
b - c:
e s =
0 a
i O
14 os en.
s s.
I., a;= $
N r-
. o a
r e
c e aa es c
=
w a 8 8 3
e l s..;.n.
o i.m.
o 6.s.
='
--rr
- we N
alvl vi
-C c
. a el vf at vt v.
l en e <
w s
e.
=
n.
n
-e e,
o e
i.
E c.
d e
s e
i 6
i m
2 ee C
J he V
t
=l 3
g e
==
.ad
.C 4.,
a
=
c; 3
3 as "el1 9
.
e M'
=.
9 t
h W
9 4
E W
C^
h 6
C C
q M
5 t
e*
4.
w C
'3 4
C 2
3 G
G "6
E.t.
E.e.
L H
5 %s.
U -
= = ^
4
. =, =. =
4 C
U.
T
==
G J
K
==
C C. w 4
4 s g
g hs n
g g
Z cb Te 9 en 3 ne e
t c.
6 see 4
=
- e he '
h.
8" 3
M O^
=a te 4 b
2 M
M M
W Z
ME e E
he es S
C h=
tie
.M a.
- e. e.m W
.J n.
=.w
O i
0 W3 Cw C
- C O
la.
b.O
.e w i
-e a.
6s he O he t=
a'=
E O
O e=
0 e.n O =.
4 en
.0 3
.C u 3
e 3a 3 ee es
- es en b ee en C
=e C
H
=
D q
e e
w M C C 4 W qw S
q4 e6.q i.
=
s 3 s 3
==
32
= 3
= 8 st
== U 9 -
h e
o P'
O C
- = *== C e=
- =
C 4=
M
==
se m.
.* 3 W
he g6 w 3
&==
u1
=
ww wA 3 3 3
C.
to
- )
U u
C. 3 w
- c. 3 u..ew 4
C
-8 2
- * ^
b.O Is.
%) w al is.==
e(
he
-a. O.
W
y 44 3 Qd y=--
G
- J e.
h e c
=
4 C
h.
- a. as 3
=. b
.O
=*
e 1
= ee C
f.i
in. Q a as u >
0 1
E.
.J g
y l
=.
W C
2 C,
s.e g
A
=
as h4
=D.
f*
ee 84.
I e
-C 4
3 i
e a
e e
l aC l f't.
ee est -
e
==
3 a.
g l
e
" me
-e.
l'
-s l
-. s l
t k. le-7 Spec t rice t i on LCO la. la-l_
TABf2 Is.le-4
.LNymty,emr Orl2LATING R!n!!ftfprEE F0H REACTOR PROTECPIVE SYGTfJt. POD WITilij;AWAl. I'H0!!!!:IT (RVP)
AllSOI.f rl'E itIflIMilli F4INDitR1 PEIMISSil4LE INSTittlHENT TRIP OPDIAELE DEHEE OF BYPASS TitiP NO.
FUNCTIONAL tlMIT SETTING citannEI.S REmnnancy corforrio:f3 SETTING 1.
Startup Channel-Low
> 2.5 cps 2
1 Above 10 35 5 cps + 1 count rate
~
Batd Pwer 2a.
Linear Channel-Low Power RWP
> 5%'(m) 2 1
(g)
(Channels 3, b and 5) ro be acidressed 2b.
Linear Channel-Low power RWP
> 5% (m) 2 1
(g)
(Channels 6. T and 8) by separate correspondence 3a.
Linear Channel-High power RWP
~< 30% (n) 2 (f) 1 None consistent with (Channels 3. 4 and Si Items 3a and 3h of 3b.
Linear Channel-High Power RUP
< 30% (n) 2 (f) 1 None (Channels 6, 7 and 8)
Table 4.4-1.
+-
e y,.
.,y 1
.-.s-
..r..
m
-,m t.
~
,,__.