ML20206A246
| ML20206A246 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/27/1987 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 2900K, NUDOCS 8704070456 | |
| Download: ML20206A246 (4) | |
Text
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c mm se One First Nabonel Plata Chicago. IEnoe Address Reply to: Post Omco son 76F i
Chicago. lilinois 60600 0767 l
[
i March 27, 1987 l
9 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation I
U.S. Nuclear Regulatory Commission Washington, DC 20555 j
Subject Braidwood Station Units 1 and 2 l
Interim Operation of HVAC Systems NRC Docket _Nos. 50-456 and 50-457 References (a): January 11, 1985 letter from T.R. Tramm to H. R. Denton (b): September 9, 1986 letter from A. D. Miosi to H.R. Denton i
(c): August 26, 1986 letter from A. D. Miosi to l
H.R. Denton Dear Mr. Denton*
l t
References (b) and (c) documented interim operation plans for the f
control room and auxiliary building ventilation systems during the startup of Braidwood Unit 1.
These interim operation plans were supported by dose calculations which demonstrated that control room habitability would be maintained in accordance with the requirements of General Design Criterion 19 l
without the auxiliary building ventilation system operational. These l
calculations assumed a 90% iodine removat efficiency for the control room i
l ventilation system recirculation charcoal filters.
l I
The control room ventilation (VC) recirculation charcoal filters were not designed in accordance with the requirements of ANSI-N509. However, we l
have committed to test these filters to the requirements of ANSI. At Byron 1
l Station, it was determined that some of the acceptance criteria of ANSI-N510 could not be met for these filters. Reference (a) described the capability of the recirculation charcoal filters at Byron Station. This letter included the i
results of filter tests for the VC A-train recirculation filters. The NRC l
reviewed these results and concluded the assumption in our dose calculations regarding 90% iodine removal efficiency was valid.
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2-March 27, 1987 Mr. H. R. Denton 4
i The filter test for the Braidwood Station VC recirculation charcoal
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filters have recently been completed. Attachment A of this letter summarizes j
the results. Although the acceptance criteria is not met for the air flow j
distribution and the air-aerosol mixing tests, the halide performance test results are much lower than the acceptance criteria of 1% total system bypass.
We believe these tests results indicate a 90% efficiency is appropriate for l
control room dose calculations.
Prompt NRC review and approval of this matter is requested so the I
Braidwood VC system can be declared operable.
Please direct any questions you may have concerning this matter to I
this office.
j i
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Very truly yours, 1
K. A. Ainger
~
Nuclear Licensing Administrator l
)
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l Attachments cc: Resident inspector - Braidwood j
Region III Office 1
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i a
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2900K i
e ANA CONTROL ROOM RECIRCULATION CARBON FILTER TRAIN A ANSI-N51Q
- tBST DATA Mounting Frame 0.1%
0.074%
Leak Test CONDITION CFM Air Flow Capacity 110% of Clean 49,131 Test design flow Dirty 47,351 (49,500 CFM) 1.25 Dirty 46,320 Air Flow Distribution 120% of
-44%
Test (126 Readings) average velocity
+7M Air Aerosol Mixing 120% of
-53%
Test (126 Readings) average
+114%
concentration Halide Test (Total System) 1.0%
0.55%
(Bank) 0.05%
0.0588%
2900K l
A l
ATTAC99mit 4 (Cont'd) f CONTROL ROOM RECIRCULATION CARBON FILTER TRAIN B
[
Est-N510 TEST DATA
[
Mounting Frame 0.1%
0.017%
Leak Test I
CONDITION grt!
Air Flow Capacity 110% of Clean 47,983 Test design flow Dirty 46,999 (49,500 CFM) 1.25 Dirty 44,332 Air Flow Distribution 120% of
-39%
Test (126 Readings) average velocity
+39%
Air Aerosol Mixing 120% of
-36%
Test (126 Readings) average
+59%
concentration Halide _ Test (Total System) 1.0%
0.17%
(Bank) 0.05%
0.042%
2900K
._.