ML20064B356
| ML20064B356 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 09/25/1990 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-90-098, CON-NRC-90-98 VPNPD-90-423, NUDOCS 9010160240 | |
| Download: ML20064B356 (2) | |
Text
,
+y v
4 Om
^
Wisconsin:
1 E?Ienctric
\\
POWER COMPANY 231 W Mcwon PO ika 2045. Mho.*oe WI 53201
. (414)221234$
VPNPD-90 42 3 '
September 25, 1990
(
Document Control Desk.
U.'S. Nuclear Regulatory' Commission Mail Station P1-137-Washington, D. C; 20555 Gentlemen:
DOCKETS 50-266 AND 50-301 POTENTIAL FOR EXPOSURE OF ENVIRONMENTALLY OUALIFIED EQUIPMENT TO HIGH PH CONTAINMENT SPRAY.
POINT BEACH NUCLEAR PLANT.-UNITS l' AND 2 Nuclear Power' Department Nonconformance: Report 1(NCR)_N-89-275 identified the potential-for a containment spray pH which:is. higher than that for which our in-containment Environmentally-Qualified (EQ) equipment'was qualified.
A recent calculation has: determined that during Emergency-Core Cooling System--(ECCS) recirculation of containment sump water, following a, postulated'large-break Loss of:
Coolant Accident, continuedcaddition;of Sodium-Hydroxide (NaOH) spray additive could' result-in a containment. spray =pH-as high'as-12.87.
This high pH is a result of continued additionLof NaOH into the containment spray system.while~ circulating containment sump fluid, which already has an elevated pH. 'The EQ equipment-located-inside containment at Point Beach'is: typically l qualified'to a pH of 10 to 10.5.
An-evaluation of materials was performed in order.to~
determine the operability.of the'EQ equipment;inside containment that are required to operate-during the recirculation phase.
As a result of this analysis, it was determined that-the ability of this equipment to perfore its safety. function in the mitigation;of a design basis event would not"be'affected by the higher pH._ _Since the higher pH spray condition would:not have impacted.the~
operability of the required equipment,'a potential for the degradation of a safety function did not exist.
Thus NCR N-89-275>
was determined to be not reportable under:10CFR50.73.
As a-result of NCR N-89-275, the Emergency Operating-Procedures (EOP 1.3) have now been changed such that.NaOH flow from the spray additive tank to the containment spray system will be terminated-just prior to the switch-over of ECCS from-injection to containment sump recirculation. -This will limit containment spray to a pH of 9.0 to 10.0 during the injection phase and 7.5 to 9.0 during n
s--
9010I6024d 300925 0\\
i PDR ADOCK 05000266 1
0 P
PDC l
il subskkg ofIlin mshi Energy (19watim
^l
. oA U.
S. Nuclear Regulatory Commission q
September 25,.1990 j
Page 2 j
1 l
- s recirculation.
These containment spray pH levels are less than'the j
pH levels to which EQ equipment inside containment was~ qualified.
The EQ Summary Sheets for in-containment.EQ equipment currently.
H lists a containment spray pH value of 7.9 to 10.
These sheets will~
L be updated to reflect the new pH range of 7.5 to 10.0.
Also,Jit l
was determined that.the new containment sump fluid and' containment spray pH levels would remove a sufficient amount of~ iodine from the-containment' atmosphere to meet the off-site dose requirements of-10CFR100.
t We would be pleased to answer any questions you may havelregarding the above information.
very truly
- ours, j
[
C. W.
ay Vic Pre den N
lear Power SWO/pok Copy to:
NRC Resident Inspector NRC Regional Administrator, Region III f
k n
a