ML18141A253
| ML18141A253 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 11/23/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18141A254 | List: |
| References | |
| 657, NUDOCS 8312060314 | |
| Download: ML18141A253 (4) | |
Text
,,
VIRGINIA. ELECTRIC A.ND POWER COMPANY RICHM_QND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS November 23, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Requlation Attn:
Mr. D. G. Eisenhut, D~rector Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Serial No.:
PSE/JOE:vdu Docket Nos.:
License Nos.:
657 50-280 50-281 50-338 50-339 DPR-37 DPR-32 NPF-4 NPF-7 Gentlemen:
VEPCO ROD EJECTION TRANSIENT ANALYSIS CAPABILITY Enclosed for your review and approval are 22 copies of the Vepco Topical Report VEP-NFE-2, 11Vepco Evaluation of the Control Rod Ejection Transient.
11 Both proprietary (Attachment 1 - 3 copies) and non proprietary (Attachment 2 - 19 copies) versions are enclosed, as discussed below.
This report is one of a series of topical reports describing the nuclear reload licensing and core follow support capabilities which have been developed at Vepco.
Our general capabilities in the area of system transient analysis were described in our topical report VEP-FRD-41, 11Vepco Reactor System Tran-sient Analyses using the RETR.AN Computer Code," which was transmitted to you by letter from Mr. \\IJ. N. Thomas (Serial No. 215) on April 14, 1981.
Because of the particular.requirements for the control rod ejection analysis, the attached report has been prepared to supplement our April 14, 1981 submittal.
This report describes in detail the methodology, models and assumptions which we intend to use for this transient analysis.
Our intended use of this capa-bility is to perform licensing reanalysis of the rod ejection event which may be required as a result of future core reloads or other operational or design changes at our nuclear units.
Vepco 1s general methodology and assumptions are similar to those assumed in our current Rod Ejection licensing analyses, and in particular utilizes a Power or Doppler Weighting Factor to conservatively approximate Doppler re-activity feedback.
The Vepco Power \\tJeighting Factor development is similar to the Babcock and Wilcox (B&W) weighting factor methodology which was recently approved by the NRC as part of the B&W Rod Ejection Topical (BA~/ 10150).
As part of our development effort, Babcock and Wilcox was retained to perform a detailed review of our Doppler \\tJeighting Factor.methodology and calculations.
In addition, BM~ provided comments on our proposed development program.
The
. *C*" 8312060314 831123 PDR ADOCK 05000280 p
.(~
~oo\\
n.. o n ~J J," ~-~,~~
t1 '\\ ~ \\n~04'"*\\~ J ~* ~~. ~'t ~'S I t
~,,;,'*
'i) \\, * ~
l
r*~
r..
vrnorNIA ELEcTRic AND PoWER CoMPANY To Mr. Haro 1 d R. Denton report has also been reviewed by both the Surry and North Anna Station Nuclear Safety and Operating Committees and by the Safety Evaluation and Control Staff.
Further, it has been determined that the methodology and analysis capability described herein does not involve an unreviewed safety question as defined in 10CFR 50.59.
Since this submittal contains information proprietary to Westinghouse Electric Corporation (specifically Figures 4-18, 4-28, 4-38, 4-48, 4-58, 4-68, 4-17A and 4-178 of Attachment 1), it is supported by a previously submitted affidavit signed by Westinghouse, as the owner of the information (see to this letter). The affidavit sets forth the basis for which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of Section 2.790 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's Regulations.
Correspondence with respect to the proprietary aspect of this application for withholding or the supporting Westinghouse affidavit should reference CAW-83-90 and should be addressed to R. A. Wiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P. 0. Box 355, Pittsburgh, Pennsylvania 15230.
We are aware that a fee will be required for the topical report review and will transmit the assessed fee upon completion of the review.
If you have any questions on the material in this topical report, please contact us.
cc:
Mr. James P. O'Reilly Regional Administrator Region II Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC Very truly yours, V.1,fU W. L. Stewart
r---------------============-------------- - --
vrnarnIA ELECTRIC AND PowEH CoMPANY To Mr. Haro 1 d R. Denton Attachments:
- 1.
Proprietary version of VEP-NFE-2
- 2.
Non-proprietary version of VEP-NEE-2
- 3. Westinghouse Application for Withholding Proprietary Information from Public Disclosure - CAW-83-90.
ATTACHMENT 3,