ML15264A458
| ML15264A458 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/27/1987 |
| From: | Pastis H Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| GL-83-28, TAC-52860, TAC-52861, TAC-52862, TAC-53695, TAC-53696, TAC-53697, NUDOCS 8705010149 | |
| Download: ML15264A458 (5) | |
Text
Docket Nos.:
50-269, 50-270 and 50-287 Mr. H. B. Tucker, Vice President APR 27 1987 Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
Subject:
Request for Additional Information - Items 2.1 and 2.2 (Part 1) of Generic Letter 83-28 (TACS 52860/52861/52862 for Item 2.1)
(TACS 53695/53696/53697 for Item 2.2)
Re:
Oconee Nuclear Station, Units 1, 2, and 3 We have reviewed your letters dated November 4, 1983, January 17, 984 and August 30, 1985. To complete our reveiw, we need the additional information identified in the enclosure.
We request that you respond to this request for additional information within 45 days of the date of this letter.
Sincerely, Helen N. Pastis, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II
Enclosure:
As stated cc:
See next page Distribution:
Docket File NRC PDR Local PDR PD#II-2 Reading MDuncan HPastis BJYoungblood Reading ACRS (10)
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Mr. H. B..Tucker Oconee Nuclear Station Duke Power Company Units Nos. 1, 2 and 3 cc:
Mr. A. V. Carr, Esa.
Duke Power Company Duke Power Company P. 0. Box 33189 Post Office Rox 331.89 422 South Church Street 422 South Church Street Charlotte, North Carolina 28242 Charlotte, North Carolina 222 J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Washington, D.C.
20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Reoional Administrator U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 3100 Atlanta, Georgia 30303 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Pull Street Columbia, South Carolina 29201 Office of Intergovernmpntal Relations 116 West Jones Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621
REQUEST FOR ADDITIONAl INFORMATION ITEM 2.1 AND 2.2 (PART 1) OF GENERIC LETTER 83-28 "EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE" OCONEE NUCLEAR STATION, UNITS 1,2,3 Review of the licensee's.responses dated November 4, 1983; January 17, 1984; and August 30, 1985 for Items 2.1 and 2.2 (Part 1) of Generic Letter 83-28, discloses the need for additional information as follows:
A.
Item 2.1 (Part 1) "Equipment Classification (Reactor Trip System Components)"
The licensee's submittal of August 30, 1985 stated that the identification and listing of reactor trip system components had been completed and identified as safety-related in plant procedures to control and execute safety-related activities.
However, the process to identify these components in other related documents was continuing and would be completed by July 31, 1986.
The licensee should confirm that the identification process has been completed.
P.
Item 2.1 (Part 2) "Vendor Interface (Reactor. Trip System Components'"
Our review of the licensee's submittals indicates that the licensee has identified an interface with their nuclear steam supply system vendor. However, we are unable to determine that the licensee's vendor interface program encompasses a periodic and continuing feedback mechanism. Item 2.1 (Part 2) states that the vendor interface program shall include periodic communication with vendors to assure that all applicable information has been received. The licensee should describe how their program assures that all relevant material is received, properly evaluated, implemented and maintained during the life of the plant.
-2 C.
Item 2.2 (Part 1) Equipment Classification (Programs For All Safety-Related Components)
- 1.
Item 2.2.1 -
Program The licensee's response does not confirm that all safety-related components are designated as safety-related on plant documents such as procedures, system descriptions, test and maintenance instructions, operating procedures, and in information handling systems so that personnel performing activities that affect such safety-related components are aware that they are working on safety-related components and are guided by safety-related procedures and constraints.
The licensee should make the above described confirmation. If all
.safety-related components are not designated as safety-related on the relevant documents, the licensee should specifically describe the exceptions and provide a justification for such exceptions for staff review.
- 2.
Item 2.2.1.2 - Information Handling System The licensee's responses do not confirm that the information handling system includes a list of safety-related equipment and that procedures exist which govern its development and validation.
The licensee should make the above confirmation.
- 3.
Item 2.2.1.4 -
Management Controls The licensee's response has not confirmed that manacement controls are utilized to verify that the procedures for preparation, validation and routine utilization of the information system have been followed.
The licensee should make the above confirmation.
- 4.
Item 2.2.1.5 -
Design Verification and Procurement The licensee's response does not confirm that their procurement specifications require thatthe appropriate desian verification and qualification testing be provided by the supplier.
The licensee should make the above confirmation.