ML18353B157
| ML18353B157 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/22/1977 |
| From: | Hoffman D Consumers Power Co |
| To: | James Keppler NRC/RGN-III |
| References | |
| IEB-77-004 | |
| Download: ML18353B157 (2) | |
Text
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 December 22, 1977 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -
LICEL~SE DPR PALISADES PLANT - IE BULLETIN 77-04 IE Bulletin 77-04 identified a potential problem of post-LOCA pH control of containment sump water.
The specific information requested was as follows:
"If your facility utilizes or plaris to utilize a system for pH control of containment sump post-LOCA solution, d~scribe what action you have taken or plan to take to assure that the system design specifications will be met for all operating conditions permitted by the Technical Specifications, as applicable to the containment sump water sources."
Response
The Palisades Plant currently utilizes NaOH injection for post-LOCA pH control of containment sump water.
As a result of Amendment 31 to our operating license we are reevaluating the predicted performance of the plant's iodine removal sys-tem.
To specifically address IE Bulletin 77-04, Consumers Power has evaluated pre-dicted pH variation associated with the addition of 23 weight percent NaOH (from T-103) to the containment sump water following a postulated LOCA.
Five sources of boric acid solution (Table 1) with maximum and minimum concentr~
tions were considered.
TABLE 1 Boric Acid Solution Sources Boric Acid (P12m B)
Source Volume Max Min Primary Coolant System 7,800 1,070 0
Two Half Full Clean Waste Receiver Tanks 8,130 2,000 0
Concentrated Boric Acid Tank 1,740 17,500 11,000 Four Safety Injection Bottles 4,000 2,000 1,720 SIRW Tank 34,ooo 2,000 1,720
/
,... 2*
The results of the evaluation are that the pH of the containment sump water can be easily maintained between 7 and 8 with the existing system.
As indicated in our December l, l977 letter to the Director of Nuclear Reactor Regulation, we will continue to evaluate the performance of the iodine removal system for pos-sible improvements.
This evaluation will be completed during the upcoming re-fueling outage.
In summary, the present system for pH control of the containment sump water will perform, as required (maintain pH between 7 and 8). If the NaOH system is re-placed with TSP, the new system will be adequately sized for the same type pH control.
David P Hoffman (Signed)
David P Hoffman Assistant Nuclear Licensing Administrator CC:
ASchwencer, USNRC