ML20237F984
| ML20237F984 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/24/1987 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20237F913 | List: |
| References | |
| NUDOCS 8709020056 | |
| Download: ML20237F984 (9) | |
Text
_ _...
'0' i
REACTIVITY CONTROL SYSTEMS 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.1.5 Two standby liquid control subsystems shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 5*.
ACTION:
a.
In OPERATIONAL CONDITION 1 or 2-l 1.
With one subsystem inoperable, restore the inoperable subsystem i
to OPERABLE status within 7 days or be in at least HOT SHUTOOWN l
within'the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
With both subsystems inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 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 />.-
b.
In OPERATIONAL CONDITION 5*-
1.
With one subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days or insert all insertable con-trol rods within the next hour.
l 2.
With both subsystems inoperable, insert all insertable control rods within one hour.
SURVEILLANCE REQUIREMENTS l
4.1.5 Each standby liquid control subsystem shall be demonstrated OPERABLE:
i a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that; Insert 1.
1.
The temperature of the sodium pentaborate solution is "itS#- th:
M lia.it; of Ti m m 0.1. ; 1.
3 2.
The available volume of sodium pentaborate solution is _ithin i
Insert 2 y gg
,4_$g
- f re g.g 3,;,5-3 f;7 gg; p;7;;;;,;; gg; ;;,,;,,,;; 3 j
l Hen determined once per 31 days per Specification 4.1.5.b.2.
DELETE D '3.
Th; h;;t trocios Circuit i; OIEI,ACLC b.r dete d 6 ins the te wm > a tur: Of th: ? p ::t'^ pipir,; up t; th; fir;t ;turose ta;,k '
l
' cutlet v:he t: be gre:ter than er ; qual to 70"I.
b.
At least once per 31 days by; 1.
Verifying the continuity of the explosive charge.
i
- With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
I l
I 8709020056 870824 RIVER BEND - UNIT 1 PDR ADOCK 05000458 Page 1 of 6 P
' 1 l
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
b;t rai 'ng, by :h: 1 :1 :n:1y:i:*, th t t.'. : r.;fi; Lie.eight Insert 3 -
su
/"
f ::dier pent b:r:t: 1: ;rt:t:r th;n ;[ ; ;;1 :: :10 :;; end-th; p;r;:nt u:ight ::n::ntr:ti:n ;f ;;dia; ;;nt; tere;. in ;;la
.a...
- a... _a.. _u a.. u..,s.._.3.-
,- >. v o.,
3.
Verifying trat each valve, manual, power operated or automatic, in the flor path that is not locked, sealed, or otherwise secured ir position, is in its correct position.
sm Insert'4 Demonstrating that, when tested pursuant to Specification 4.0.5, the c.
minimum flow requirement of 41.2 gpa per pump at e pressure of greater than or equal to 1220 psig is set.
d.
At least once per 18 months during shutdown by;.
1.
Initiating one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by-pumping demineralized water into the reactor vessel.
The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has bee,n certified by having one of that batch success-fully fired.
Both injdction loops shall be tested in 36 months.
DELETE
- 0-- n:t : tin; th:t :1' 5::t tr:::d piping b;tu::n th; et;.;;;
's
?.
/
u-on.
............. on. ws n.u uy.
- )
?::?: ting the p - :::t':n :::::1 ::f-t:r.:n:; v;1v;; ;nd the '
__......-,.s...,.... _. _ _. _ _,.,, _ _
-......r y.,.....,
.m.
as n.. 4.,., - _ -. __ __.
.r_._.__
y -,........
..w
.w.,
.. u.... _
.._...m
_r...
.. h.==
[.. [
[
..h
^
wush sw v
ww
.w
..wrwn-eM4py
.py
>_...g u....
a..u.
s__,.,
.g-
--s
=.
u
- t. i.
s....
. r as
. sas.i.g.Ig W...
p 5 y,..J wa..
I)
..u
...... 2.. _.....>.
n.v vuun.vwwi~
........n
.--_.__.s.._.,_
m..u _.
.. <..... -... wr m.s. u wy....-
.u.
..,...u...--.,_____..,_.._m...
m..,.
.iu.
u
_2 on.
._.,-.a.._.
a.
..u
._.u...-._._-..,a._..
. u.
- u... _...... __ ___
"This test shall also be performed anytime water or boren is added to the solJtion or when the solution temperature Wops below 40AP: +- -- 4 5 F Insert 5
^
.u......- ' - '. u'...
y.....
.....nv.....'...'.....'..-..
r e..
2 u.
a._
u,
.W 5W
..F.
.WN u
.. _ n. u_n w
.2 2
u.
w -
---w M
M W
W5 g T W
WW5 5.W Wl
@w
_w.].l.l g
W.
l
-;h nh I.OIA IC p..
Op rd...; hb. r0
^ '... ^ bA. ;
ww y
RIVER BENO - UNIT 1 3/4 1-20 Page 2
ENCLOSURE 1 INSERTS Insert 1
"... greater than or equal to 45'F."
l l
Insert 2 greater than or equal to the minimum required available volume..."
i l
l Insert 3
" Determining *,
that the available weight of Boron-10 is I
greater than or equal to 143 lbs, the percent weight concentration of sodium pentaborate in solution.is equal to or less than 9.5% by weight, and the minimum required solution volume."
Insert 4 "4.
Determining that the Standby Liquid Control System satisfies the following equation:
'd (C)(E))413 Where:
l C=
sodium pentaborate concentration, in weight percent, as determined per specification 4.1.5.b.2 E=
Boron-10 enrichment, in atom percent **".
4
}
Insert 5
"**The Boron-10 enrichment of the solution shall be determined anytime boron is added to the solution.
j l
l I
1 Page 3 of 6 i
1 1
l i
e 1
DELETE
,s oo
/
\\
%0
~
STAND 9V LIQUID CONTROL
/
f ANm OPER AfiNG Lault f
110 to
/
\\
$0DauM P(NT AGORATl/ WATER go y
/
$0LUT ON 5ATURar ON CH ARACTERIST ec
[
^
i
/
I
/
y
~
70
/
\\
to 60 l
f l
i i
i l
0 30 5
to 15 M
75 30 36 40 45 CONCE NTR ATION f% $V W(IGHT) 1 a
i l
FIGURE 3.1.5-1 SATURATION TEMPERATURE OF SODIUM PENTABORATE SOLUTION Page 4 RIVER BEND - UNIT 1 3/4 1-21
i l
l DELETE 14 j
H h 13
\\
ACCEPTABLE OPERATING REGION it
/
%'N j
[I]
I
> 12 e
,h'%
TANK
/
h_
OVERFLOW f
{
' -LOW LEVEL 5150 f
11 ALARM 3574
'HIGH L VIi.
o ALARM 45264.
y 10 g
\\
)
' MIN. REQ'D d
9 CONCENTRATION LINE
$o 9
Zo A
\\
5
(
a 7
O
\\
m 6
l 5
3000 4000 5000 NET VOLUME OF SOLUTION IN TANK (G ALS) l FIGURE 3.1.5 2 SODIUM PENTABORATE SOLUTION VOLUME / CONCENTRATION REQUIREMENTS RIVER BEND - UNIT 1 3/4 1-22 Page 5
_.m_____
i l
INDEX l
j LIST OF FIGURES l
l FIGURE TITLE PAGE DELETESgh?_1.5-1 Saturatier Temp 0ratur Of S0dium Penteberate r,.m,__
,,u, e,
sv.uo.v.......
.m.
1 13. 1. S - 2 Sodium Pentabcrct: Sclution Volumc/ Concentration l
lkquircacnt;......
3/4 1 22 l
3.2.1-1 Maximum Average Planar Linear Heat Generation Rate (P8 SIB 071)....................................
3/4 2-2 3.2.1-2 Maximum Average Planar Linear Heat Generation Rate (P8 SIB 094)....................................
3/4 2-3 l
l 3.2.1-3 Maximum Average Planar Linear Heat Generation l
Rate (P8 SIB 163)....................................
3/4 2-4 1
3.2.1-4 Maximum Average Planar Linear Heat Generation Rate (P8 SIB 248)....................................
3/4 2-5 1
3.2.1-5 Maximum Average Planar Linear Heat Generattori i
Rate (P8 SIB 278)....................................
3/4 2-6 l
3.2.3-1 MCPR..............................................
3/4 2-9 f
3.2.3-2 MCPR..............................................
3/4 2-10 p
l 3.4.1.1-1 Thermal Power versus Core Flow.....................
3/4 4-3 3.4.6.1-1 Minimum Temperature Required Versus Reactor Pressure...........................................
3/4 4-23 l
4.7.4-1 Sample Plan for Snubber Functional Test............
3/4 7-15 8 3/4 2.3-1 Power Flow Operating Map...........................
B 3/4 2-6 B 3/4 3-1 Reactor Vessel Water Level.........................
B 3/4 3-8 8 3/4.4.6-1 Fast Neutron Fluence (E>1 MeV) at 1/4 T as a Function of Service Life...........................
B 3/4 4-8 1
5.1.1-1 Exclusion Area.....................................
5-2 5.1.2-1 Low Population Zone................................
5-3 5.1.3-1 Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents.......
5-4 6.2.1-1 RBNG Organization..................................
6-3 6.2.2-1 River Bend Station Organization....................
6-4 RIVER BEND - UNIT 1 xxii Page 6 of 6
BASES i
l ROD PATTERN CONTROL SYSTEM (Continued)
The RPCS provides automatic supervision to assure that out-of-sequence rods will not be withdrawn or inserted.
The analysis of the rod drop accident is presented in Section 15.4.9 of the FSAR and the techniques of the analysis are presented in a topical report (1) and two supplements (2, 3)
]
The RPCS is also designed to automatically prevent fuel damage, during higher power operation, in the event of erroneous rod withdrawal from locations of high power density.
A dual channel system is provided that, above the low power setpoint, restricts the withdrawal distances of all non peripheral control rods.
This restriction is greatest at highest power levels.
3/4.1.5 STANDBY LIQUID CONTROL SYSTEM The standby liquid control system provides a backup capability for bringing the reactor from full power to a cold, xenon-free shutdown, assuming that the withdrawn control rods remain fixed in the rated power pattern.
To meet this Joron-10 122 m objective it is necessary to inject a quantity of bepenW hich produces a concen-fration of7560 ppm in the reactor core and other piping systems connected to the reactor vessel.
This concentration is increased by 25% to allow for poten-Insert 1 tial leakage and imperfect mixing.
Therequiredconcentrationisachievedbyg having a minimum available quantity of 3542 ;21!cn: cf redi r pent:b r:t: ;;lu-
-tion centsining : minimum of 'a'4 peands of : dium p;nt bevate.
Thie quantity ef ;;lution is not : cunt which is above the pump suction, thus allowing for the portion that cannot be injected.
The pumping rate of 41.2 gallons per minute (gpm) per pump provides a negative reactivity insertion rate,':ver th PDELETE DELE g er-ft:fb!: pent:b rat: 0012tf0r V:!ur: r:ng:, which adequately compensates for the positive reactivity effects due to temperature and xenon decay during shut-down.
Me t 7 erature versus cencentretier aequiatrent it necettery te ensure M ELETE th:t th: cedi= pest:50 rate re :in: 7 : lution.
4 4
-Insert 2 With redundant pumps and explosive injection valves and with a highly reliable control rod scram system, operation of the reactor is permitted to continue for short periods of time with the system inoperable or for longor periods of time with one of the redundant components inoperable.
1.
C. J. Paone, R. C. Stirn and J. A. Woolley, " Rod Drop Accident Analysis for Large BW2's," G. E. Topical Report NED0-10527, March 1972 2.
C. J. Paone, R. C. Stirn and R. M. Young, Supplement 1 to NEDO-10527, July 1972 3.
J. M. Haun, C. J. Paone and R. C. Stirn, Addendum 2, " Exposed Cores,"
Supplement 2 to NED0-10527, January 1973
)
l' RIVER BEND - UNIT 1 B 3/4 1-4 Page 1 of 3
~
ENCLOSURE 2 INSERTS l
Insert 1.
143 pounds of Boron-10 contained in the net amount of solution.
Insert 2 "The Standby Liquid Control System is also required to meet the criteria of 10CFR50.62, " Requirements for reduction of risk from Anticipated Transients Without Scram (ATWS)
Pvents For Light-Water-Cooled Nuclear Power Plants" by having the equivalent control capacity of a 66 gpm system using 13 weight percent natural sodium pentaborate. The equivalency requirement is fulfilled by having a system which satisfies the equiation given in surveillance requirement 4.1.5.b.4.
i Each parameter is tested at an interval consistant with the potential for that parameter to vary and also to assure proper equipment performance where applicable.
Enrichment testing is only required when boron addition occurs since change cannot occur by any other process."
l Page 2 of 3
~q
'1 REACTOR COOLANT SYSTEMS BASES i
STANDBY LIQUID CONTROL SYSTEM (Continued)
Boron-10 Surveillance requirements are established on a frequency that assures a high reliability of the system.
Once the solution is established, be.e..
concentration will not vary unless more boron or water is added. Therefore, a.
check on the temperature and volume once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solu-tion is available for use.
4 Replacement of the explosive charges in the valves at regular intervals will assure that these valves will not fail due to deterioration of the j
charges.
]
\\
1 1
q I
i l
l i
I i
RIVER BEND - UNIT 1 B 3/4 1-5 Page 3 of 3
_ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _