05000254/LER-1987-025, Forwards Addl Info Re Control Room Habitability to Support Narrative Contained in LER 87-025 (Rev 1),including Control Room Habitability Study,Updated FSAR (Rev 88),inplace Charcoal Absorber Leak Rate Testing & Calculations

Forwards Addl Info Re Control Room Habitability to Support Narrative Contained in LER 87-025 (Rev 1),including Control Room Habitability Study,Updated FSAR (Rev 88),inplace Charcoal Absorber Leak Rate Testing & Calculations

ML20247M275
Person / Time
Site:	Quad Cities
Issue date:	05/19/1989
From:	Stols R COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20247M280	List: 05000254/LER-1987-025, Forwards Addl Info Re Control Room Habitability to Support Narrative Contained in LER 87-025 (Rev 1),including Control Room Habitability Study,Updated FSAR (Rev 88),inplace Charcoal Absorber Leak Rate Testing & Calculations ML20247M283 ML20247M289 ML20247M319 ML20247M327
References
0136T-5-6, 136T-5-6, NUDOCS 8906050011
Download: ML20247M275 (2)

LER-2087-025, Forwards Addl Info Re Control Room Habitability to Support Narrative Contained in LER 87-025 (Rev 1),including Control Room Habitability Study,Updated FSAR (Rev 88),inplace Charcoal Absorber Leak Rate Testing & Calculations

Event date:
Report date:
2542087025R00 - NRC Website

text

.-

Y Commonwealth Edison j

' f _.

'72 West Adams Street, Chicago, Illinois (V N ddress Reply to: Post OTfEBoi~7BT .

Chicago, Illinois 60690 - 0767 -

May 19, 1989-

'\

i

Dr. Thomas E. Murley, Director

'Of fice of Nuclear Reactor: Regulation

.U.S. Nuclear Regulatory Commission Washington, DC' 20555 Subjects- Quad. Cities Station Units 1 and 2 Request for Additional Information Control Room. Habitability NRC Docket Nos. 50-254 and 50-265 ,

.I Dr. - Murley

• The attached information was requested by Mr. T. Ross, Quad Cities Project Manager. 'The information supports the narrative contained in the  ;

' Licensee Event Report 87-025 (Revision 1). l (1) Control' Room Habitability Study for Quad Cities Units l'and 2 'l prepared by Bechtel Power Corporation,. Final Report dated l November, 1981 with update pages . 5 -1, 5-2, 5-3 and Figure 1 '!

dated June 14, 1982. .{

l (2) Updated Final Safety Analysis Report (UFSAR), . Revision 88 .j l

(a) 1.5.5 Inter-plant Effects of Accident i (b) 5.3.3.4 Standby Gas Treatment System (c) 5.3.5 SBGTS Inspection and Testing 3 (d)- Table 8.2.3 )

(e) 10.10.4 Control Room Air Conditioning System 'f (f) 14.2.2.5 Radiological Effects -l (g) 14.2.4.2 Fission Product Release from Fuel 'l (h) 14.2.4.7 Site Dose Rates I

{

(3) Proposed UFSAR Section changes ]

(a) 14.2.4.8 Control Room Dose Rates (b) Section 14 References fBD

/ I w

l ib 8906050011 890519 R ADOCK 0 % 2 4 e - _ - - _ - _ _ _ . _ _ _ - _ _ _ - - - _ _ _-_ _ - - _ - _ _ _ _

c Dr. T.E. Murley May 19, 1989 (4) Inplace Charcoal Absorber Leak Rate Testing, Methyl Iodine Analysis of Charcoal Absorber Test Cannisters and Inplace DOP Leak Testing of the HEPA Filters conducted on the Standby Gas Treatment System (SGTS) and Control Room Emergency Filtration System (CREFS) since December, 1984.

The following tests are enclosed:

1/2 A SGTS: 12/84, 12/85, 4/87, 9/88 1/2 B SGTS: 12/84, 12/85, 5/87, 6/87, 10/88 CREFS: 12/85, 12/86, 11/87 (5) NUS Corporation Engineering Calculation, 546Y-M-012, Revision 0, dated 1-08-88.

(6) NUS Corporation Engineering Calculation, 54 6Y-M -0 2, dated 4-01-87.

(7) NUS Corporation Engineering Calculation, 546Y-M-07, dated 6-25-87.

(8) NUS Corporation Engineering Calculation, 546Y-M-07/S1, dated 10-05-87.

Please direct any questions you may have regarding this issue to this j office.

Very truly yours,

f. '

Rita Stols ,

Nuclear Licensing Administrator ,

i Im l

cc T.M. Ross - Project Manager, NRR l k

4

\ l 0136T/5-6