ML15223A665

Forwards Request for Addl Info in Order to Complete Review of Standby Shutdown Facility.Response Due in 30 Days

ML15223A665
Person / Time
Site:	Oconee
Issue date:	10/27/1980
From:	Reid R Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 8011040609
Download: ML15223A665 (4)

Text

OCTOBER 27 L

NSIC MFair ile NRC PDR ORB#4 Rdg RIngram L PDR NRR Rda OELD TER -3 DEisenhut AEOD Dockets Nos.

0-269 50-270 RPurple Gray File and 59-287

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-TNovak EBlackwood Mr. William 0. Parker, Jr.

RReid Vice President - Steam Production osnak Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242.

Dear Mr. Parker:

In order to complete our review of the DPC Standby Shutdown Facility at the Oconee Nuclear Station we find that we need additional information..

It is possible that you may receive additional requet§ts.

Kindly respond within 30 days'of receipt of this letter with three signed originals and 37 additional-copies.

Sincerely, Origial signed bY Robert W. Reid Robert W. Reid, Chief Operating,bactors Branch #4 Division of Licensing

Enclosure:

Request -for Additional Information cc w/enclosurg:

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GOVERNMENT PRINTING OFFICE: 1979-289-369

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 October 27, 1980 Dockets Nos. 50-269, 50-270 and 50-287 Mr. William 0. Parker, Jr.

Vice President - Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242

Dear Mr. Parker:

In order to complete our review of the DPC Standby Shutdown Facility at the Oconee Nuclear Station we find that we need additional information.

It is possible that you may receive additional requests.

Kindly respond within 30 days of receipt of this letter with three signed originals and 37 additional copies.

Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing

Enclosure:

Request for Additional Information cc w/enclosure:

See next page 01

Duke Power Company cc w/enclosure(s):

Mr. William L. Porter Duke Power Company P. 0. Box 2178 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)

U. S. Environmental Protection Agency Washington, D. C. 20460 U. S. Environmental Protection Agency Region IV Office ATTN:

EIS COORDINATOR 345 Courtland Street, N.E.

Atlanta, Georgia 30308 Mr. Francis Jape U.S. Nuclear Regulatory Commission P. 0. Box 7 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III,.Esq.

DeBevoise &,Liberman 1200 17th Street, N.W.

Washington, D. C'. 20036 IrI

Enclosure REQUEST FOR ADDITIONAL IIFORMATION OCONEE NUCLEAR STATION DUKE POWER COMPANY DOCKET NOS. 50-269, 50-270, 50-287

1. Provide a summary in sufficient detail to demonstrate that the proposed Standby Shutdown Facility Reactor Coolant Makeup System and Auxiliary Service Water System have been designed in accordance with the rules of the ASME codes,Section III, class 2 and class 3. Specifically, include justification of the design loading combinations considered in the analysis and design of the above systems.

'2. As required by the NRC letter of December 29, 1978, from R. W. Reid to W. 0. Parker, Jr., which provided conceptual approval of the proposed system, we request that you identify and justify those portions of the design not meeting NUREG 75-087. Specifically, with respect to the information presented in the system design criteria for the proposed Standby Shutdown Facility, identify any deviations from applicable portions of the following NRC Standard Review Plans:

a. SRP Section 3.7.3, "Seismic Subsystem Analysis".

b. SRP Section 3.9.2, "Dynamic Testing and Analysis of Mechanical Components".

c. SRP Section 3.9.3, "ASME Code Class 1, 2, & 3 Components, Component Supports and Core Support Structures".

d. SRP Section 3.9.6, "Inservice Testing of Pumps and Valves".