ML20070J607
| ML20070J607 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/21/1994 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19304C405 | List: |
| References | |
| NUDOCS 9407250220 | |
| Download: ML20070J607 (2) | |
Text
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Commonwealth Edison
_I 1400 Opus Pir.ce V,~ Downers Grove, litinois 60515 July 21,1994 Mr. William T. Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
Subject:
Response to Request for Additional Information - Questions 2.a and 2.b pertaining to the TRANFLO model Braidwood Station Unit 1 N_PF-72: NRC Docket No. 50-456
References:
1)
J. A Bauer letter to W. T. Russell, dated July 14,1994, transmitting Comed's response to an NRC Request for Additional Information 2)
D. M. Saccomando letter to W. T. Russell, dated July 13,1994, transmitting Comed's response to an NRC Request for j
Additional Information
/
3)
NRR and Comed teleconference on July 12,-1994, regarding the Request for Additional Information pertaining to Braidwood Unit 1 Steam Generators 4)
R. Assa letter to D. Farrar dated July 7,1994, transmitting a Request for Additional Information 4
5)
D. Saccomando letter to W. Russell, dated June 20,1994, transmitting a request to amend Technical Specification Section 3/4.4.5, " Steam Generators"
Dear Mr. Russell:
.In the reference letter 5, Commonwealth Edison Company (Comed) requested to amend Technical Specification Section 3/4.4.5, " Steam Generators" for Braidwood Unit 1. As a result of that request the Nuclear Regulatory Commission (NRC) issued a Request for Additional Information (RAI) which was transmitted in the.
reference. letter 4. Subsequent to that letter, and during the referenced tele (odferdnee,-Comed detailed how Braidwood Station would respond to the RAI.
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Mr. Russell July 21,1994 Reference 2 transmitted Braidwood's response to RAI questions 1.a through 1.e, and 2.b through 2.g. In reference 1, Comed provided the dRC infor.mation regarding RAI question 2.a, and specified that Comed would forward the results of the TRANFLO test case 1 to the Staff by July 21,1994. Attached you will find the results of test case 1. Case 1 involves calculating the tube support plate pressure drops that occur during a postulated steam line break event when Braidwood Unit 1 is in a hot standby condition. Additionally, the attachment also contains supplemental infbrmation to RAI question 2.b. This information addresses the applicability of the Model F sensitivity study to determine the relative pressure drop across the uppermost tube support plate as a function of secondary side water level to the Model D4 steam generators at Braidwood Unit 1.
Please note that the Westinghouse attachment contain proprietary information as specified in the attached Westinghouse letter (NTD-NRC-94-4210) dated July 20, 1994. This letter defines how Westinghouse Corporation will comply with the requirements of 10 CFR 2.790. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure.
Correspondence with respect to the proprietary aspects of the Westinghouse attachment should be addressed to N. J. Liparulo, Manager of Nuclear Safety &
Regulatory Activities, Westinghouse Electric Corporation, P.O. Box %5, Pittsburgh, Pennsylvania 15230-0355.
If you have any questions concerning this correspondence please contact this office.
Sincerely, S khd Denise M. Saccomando Nuclear Licensing Administrator Attachments cc:
R. Assa, Braidwood Project Manager-NRR S. Dupont, Senior Resident Inspector-Braidwood B. Clayton, Branch Chief-Region III Office of Nuclear Facility Safety-IDNS kinla W duperaicl\\2