ML17258A494
| ML17258A494 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/21/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17258A495 | List: |
| References | |
| TASK-06-01, TASK-6-1, TASK-RR 820127, NUDOCS 8202040097 | |
| Download: ML17258A494 (7) | |
Text
1 REGULATORY ORMAT ION DISTRIBUTION SY M
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AOCQSSION NBR:8202040097 DOC ~ DA'TE: 82/Oi/21 NOTARIZED! NO, DOCKET FACIL:50"244 Robert Emmet Ginna Nuclear Pl ant'i Uni(t 1~ Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION MAIERgJ ~ E ~
Rochester Gas 8 Electric Corp'RECIP
~ NAMF-RECIPIENT AFFILIATION GRUTCHF IELDg D, Operating Reactors Branch "5
SUBJECT:
Forwards, "Analysis of Decompositi Insulation on 304
"'SST Facings In questions re SEP iTopic VI 1~
"Org Chemistry.,"
DISTRIBUTION 'CODE:
A035S "COPIES
'RECEIVED-'I'TLE:
SEP Topi cs NOTES: 1 copy:SEP Sect.
Ldr.
on Effects of, Yinylcel DBAp" in -response to 811116 anic Metis 8 ~Post Accident LTR.
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NRR/DSI/CS8 07 COPIES LTTR ENCL 7
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1 REC I'P IENT ID CODE/NAME NRR/DF/ADMQE 13 NRR/DL/DRAB 11 B
REG FI 04 COPIES LT!TR ENCL 1
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/////I///I ROCHESTER GAS AND ELECTRIC CORPORATION 0
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o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E.
MAIER VICE PRESIDENT TELEPHONE AREA CODE 7 lb 546.2700 January 27, 1982 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 S
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Subject:
SEP Topic VI-l, Organic Materials and Post-Accident Chemistry R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
During the initial Ginna Integrated, Assessment
- meeting, held in Bethesda from December 1 to December 3,
- 1981, a number of questions were raised relative to the subject topic assessment.,
transmitted to the NRC by letter dated November 6, 1981.
The attachment provides the requested information.
Very truly yours, J
n E.
aier Attachment i
- ---. pg27 i
040097 82 F44 8202 gcy pQoP pgg A
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Attachment:
Responses to questions raised on 11/16/81 RG&E assessment of SEP Topic VI-1, Organic Materials and Post;-Accident Chemistry Question 1:
What type of atmosphere is in the NaOH tank?
Response
1:
The atmosphere in the tank is nitrogen.
Question 2:
Is the.tank in a heated area?
Response
2:
Yes, the tank is in the basement of the auxiliary building.
Question 3:
Will RG&E commit to a periodic visual inspection of the exposed paint.'surfaces in containment?
Response
3:
- Yes, RG&E will commit to make a visual inspection of the exposed:paint surfaces in containment, on a schedule consistent with the performance of the Containment Spray System nozzle testing.
This testing is performed approxi-mately 3 times every ten years.
Question 4:
What effect could be expected from corrosion of the 0.019 inch stainless steel facing which covers the containment liner insulation.
Response
4:
This information can be determined from the attached
- report, Wyle Report 17490-2.
Some corrosion of the stainless steel panels could occur within 1.4 months.
This corrosion would not cause failure of the panels, however.
Panel failure due to corrosion could occur by one of,two methods:
either the panelcould corrode around, the bolt area, or the bolts themselves"could corrode.
- Both 'of these cases were examined.
Using an assumption of long-term,'containment temperature of
.150'F, it was calculated that through-wall panel corrosion around the bolts could occur at about 7.5 months.
Sufficient bolt corrosion to cause shear failure could occur at about 1.9 years.
A more realistic estimate of the long-term containment temperature would be about 100'F.
Using the resulting extrapolated corrosion rate of about 13 mils/year
[10 mils/yr(2 3
)=12.93] would change these estimates to 11.1 1.46 years and 8.38 years, respectively.
These estimates show that potential panel failure would not be expected to occur for a long time following a postulated LOCA.
At a time many months into the accident, the water in con-tainment would be quiescent.
Only a few hundred gallons per minute would be drawn through the sump for use in long-term post,-accident recirculation.
Any panels which might become disattached from the containment wall would simply sink to the floor.
Since the sump is about 20 feet from the contain-
0 P
'1 K
4
ment, wall, and the panels are 44" x 84", they would not fall near the sump.
There would be no forcing mechanism to draw the panels toward the containment, sump.
Any containment liner insulation which might become disattached, being of very light material (about 4 pcf),
and of low moisture absorptivity, would float.
Therefore, RG&E does not believe that there is any potential for sump clogging due to corrosion and dis-attachment of the containment liner insulation and facing.