ML20086S056
| ML20086S056 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/22/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8403010335 | |
| Download: ML20086S056 (2) | |
Text
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DUKE Powr.n GOMPANY P.O. HOX 33180 CHAMLOTTE. N.C. 28242 HAL H. TUCKER Tetrersown tus *mmessent (704) 37M538 February 22, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Section 13.5.3 of the Catawba Safety Evaluation Report discusses License Condition 26, Modifications to Emergency Operating Instructions.
It is requested that this license condition be revised to reflect the changed circumstances since the Catawba SER was issued.
On April 14, 1983, Duke Power Company provided a response to Supplement 1 to NUREG-0737 which included a description of the Emergency Procedure Upgrade Program for Catawba. Section 6.2.1 of that response described Duke's plans for incorporating the Westinghouse Emergency Response Guidelines (ERGS) into the Catawba emergency procedures.
On June 1, 1983 the NRC Staff's Safety Evaluation of Emergency Response Guidelines was transmitted 'to Mr. J. J. Sheppard, Chairman, Westinghouse by Darrell G. Eisenhut, NRC/0NRR. The guideline set listed Owners Group (pp. 5-10 through 5-12) of the SER served as the starting point in Table 2 for the development of the Catawba Plant Specific Technical Gjidelines.
Duke's review of further modifications to the guidelines, made by Westinghouse as they developed Revision 1 to the ERG set, resulted in changes to this guideline set. These modi.'ications can be briefly summarized in three groups:
Group 1 (E-0, E-1, E-2 and associated subprocedures)
These guidelines have been maintained as the framework for their counterparts
.in the Catawba Plant Specific Technical Guidelines. Certain modifications have been made on a guideline-by-geideline basis to incorporate later guidance in Revision 1 or to reflect changes made by Duke Power for plant-specific or other technical reasons.
Group 2 (E-3, ECA-1, ECA-2 and associated subprocedures)
The structure of these Catawba Plant Specific Technical Guidelines has been changed 'to more nearly reflect the corresponding Revision 1 guidelines.
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8403010335 840222
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Mr. Harold R. Denton, Director February 22, 1984
.Page 2
. Group 3 (FRGs)
For FRGs there are fewer differences between the NRC-approved ERG version referenced above and Revision 1 than for ORGs. Therefore, the Catav:ba Plant Specific Technical Guidelines are similar to the NRC-approved version,
-yet have incorporated later guidance from Revision 1.
Very truly yours,
&b.w Hal B. Tucker ROS/php cc: ~Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region ~II.
'101 Marietta Street, NW, Suite 2900
. Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
. Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street Columbia, South. Carolina 29205
~
Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 t-
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