ML20004E831
| ML20004E831 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/10/1981 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20004E828 | List: |
| References | |
| NUDOCS 8106150349 | |
| Download: ML20004E831 (4) | |
Text
.
rD
\\ -
PLANT SYSTEM SECONDARY WATER CHEMISTRY UE LIMITING CONDITION FOR OPERATION
- E'.'
3. 7.1.
The secondary water chemistry shall be maintained within e
limits of le 3.7-3.
APPLICABILITY: tw rS 1, 2 and 3.
ACTION:
' ;;^.
.~ <.
(To be. determined in the manner t for in the bases in approximately six months after commercial opfgt1 and to be imposed by a change to this Specification.) 6@p SURVEILLANCE REQUIREMENTS 4.7.1.6 The s e ary wat.er chemistry shall be determi n'
be within the limits by analysi those parameters at equencies specified in Table 4.7-3.
t w',
F ARKANSAS - UNIT 2 3/4 7-11 810 615 0%$
-_-:...~:,,..._,.
-~:,- _
~;-
~ ~. -
~
~
l Tflt)LE 3.7-3 x
w 4.*
g 2,
SECONDARY WATER CHEMISTRY LIMITS y
o.
v>
s c
z Wa r Sample Pa rameters
~.'
Z L
tion ro i
\\
l
\\
- i I
w 2
?
- Sample locations, parameters and limits operation based upon test program describe (
s lished in approximately 6 months after commercial es.
l3 D
1 i
.s
\\
1 i
e i
i f
)
l El?
,.,,1-
- I?,,
.Yl,kb
'~
=r e
w,
~5:;
.(
i TABLE 4.7-3 SECONDARY WATER CHEMISTRY SURVEILLANCE REQUIREMENTS 5
't Water sample c
-Pa rameters Location s
=
q i
w b
\\
- Sample locations, param rs and frequencies to be established in a roximately 6 months after commercial w3 operation based upon st program described in bases.
?
C; r
P e,
v) ~
~'
'l( ~
(V)
((f. -
p.; i
.g y
a PLANT SYSTEMS BASES 5-yj 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the : team generator of the affected steam line and a concurrent loss of offsite electrical power.
These values are consistent
- l4.
with the assumptions used in the accident analyses.
3/4.7.1.5 MAIN STEAM ISOLATION VALVES The OPERABILITY of the main steam isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown 9:
associated with the blowdown, and 2) limit the pressure rise within containment in the 3 vent the steam line rupture occurs within contain-ment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the s
assumptions used in the accident analyses.
3/4.7.1.6 SECONDARY WATER CHEMISTRY A test program will be conducted during approximately the first 6 month f operation after initial criticality to establish the appropr' e
limits o he secondary water chemistry parameter. :nd the determi he appropriate equencies for monitoring these parameters. The r a ts of this test prog n will be submitted to the Commission for r ' 'ew.
The Commission will t.
issue a revision to this specificat' specifying the limits on the ch
'stry parameters and the f a u - ies for monitoring these parameters.
.ef b
-LN This test program will in an ysis of the chemicol con-stitutents of the condenser cool s+
The analysis shall identify the various traces of ions which u centration in the condenser may w% s corrosion in the steam have the potential for inducem for generator tubing. The test ogram shall alyze concentration phenomena and the concentration r s in t'ie steam gene tor and the secondary water system.
./
p.
N.
~~
F l
ARKANSAS - UNIT 2 B 3/4 7-3 l
l
.9.,,.
.~ - :..
~
r s
.