ML20072G121
| ML20072G121 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/18/1994 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20072G123 | List: |
| References | |
| NUDOCS 9408240207 | |
| Download: ML20072G121 (2) | |
Text
R C:mmonwstith Edisen 1
Draidwood Nuclear Power Station
- ;~1 Houte #1, Box B4
' v',
Braceville, Illinois 60407 Telephono 815/458 2801 August 18, 1994 Mr. William Russell, Director Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn:
Document Contrcl Desk
Subject:
Braidwood Station Un1L 1 Supplement to Request to Amend Facility Operating License NPF-72 Technical Specifications 3/4.4.5 and 3/4.4.8 NRC Docket No. 50-456
References:
1)
Teleconference between Commonwealth Edison Company and the Nuclear Regulatory Commission dated August 18, 1994, regarding the requested Technical Specification Amendment pertaining to Steam Generator Tube Interim Plugging Criteria 2)
D. Saccomando letter to W. Russell dated June 20, 1994, transmitting request to amend Technical Specifications 3/4.4.5 and 3/4.4.8
Dear Mr. Russell,
The reference letter 2 transmitted Commonwealth Edison Company's (Comed) request to amend Technical Specifications 3/4.4.5 and 3/4.4.8 for Braidwood Unit 1.
This amendment requested a revision which would:
remove the condition of limiting operation of Braidwood Unit 1 to 100 days, as imposed by Amendment 50, restore the reactor coolant dose equivalent iodine limit to 1 microcurie / gram from the 0.35 limit which was imposed for the first 100 calendar days of operation with Tsg greater than 500'F for Unit 1 Cycle 5, and contained editorial changes.
Per the reference teleconference with the NRC, Comed agreed that rather than delete the footnote applicable to Technical Specification 3.4.8 as requested la reference letter 2, the footnote should be revised to maintain the dose equivalent iodine at 0.35 microcurie / gram for the remainder of Cycle 5.
This revision will provide additional conservatism by limiting offsite dose in the event of a Main Steam Line Break accident.
Therefore, the footnote pertaining to Tecnnical Specification 3.4.8 should read,
"**For Unit 1 Cycle 5, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0.35 microcuries per gram."
See Attachment.
9408240207 940018 PDR ADOCK 05000456 g8 P
PDR I
t
Mr. Russell August 18, 1994 i
Comed believes that the NRC should find this change acceptable.
Please address any comments or questions regarding this matter to this office.
Sincerely, xmb
., m~)&
L Denise M. Saccomando Nuclear Licensing Administrator Attachment cc:
R. Assa, Braidwood Projects Manager-NRR S. Dupont, Senior Resident Inspector-Braidwood J. Martin, Regional Administrator-Region III Office of Nuclear Facility Safety-IDNS f
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