ML20058H250
| ML20058H250 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/26/1982 |
| From: | Parker W DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20058H254 | List: |
| References | |
| NUDOCS 8208030524 | |
| Download: ML20058H250 (3) | |
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Duxn POWEH COMPANY Powra Burwswo 4ra Sourn Cnuncu Sturer, CHAHl.Orf E, N. C. 26242 WILLI AM O. PAR KER, J R.
Vice Parssoruv TcLep oNt; ARCA 704 dyly 26, l982 Strane PnODUCTIO*e 373-4083 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Conmission 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:
Elinor G. Adensam's letter of December 9,1981 transmitted question 440.T.5 from the Reactor Systems Branch. This question requested justification for bypassing the anticipatory reactor trip on turbine trip at low power levels.
i provides an analysis of the feasibility of deletion of reactor I
trip on turbine trip below 70 percent power. Attachment 2 provides an analysis of the radiological doses from the steam potentially released from the steam generator safety valves.
From these analyses it is concluded that the plant design permits a turbine trip without a direct or immediate reactor trip with no hazard to the integrity of the Reactor Coolant System or the main steam system. Pressure relieving devices incorporated in the two systems are adequate to limit the maximum pressures to within the design limits. The analyses also demonstrate that for a complete loss of forced reactor coolant flow initiated from the most adverse preconditions of a turbine trip, the departure from nucleate boiling ratio does not decrease below the limit value during the trensient. Thus, no fuel or clad damage is predicted, and all applicable acceptance criteria are met.
l For normal plant operation with all normal control systems assumed oper.aional, l
pressurizer pressure does not reach the point of pressurizer PORV actuation.
Therefore, the deletion of reactor trip on turbine trip below 70 percent power j
is not expected to significantly increase the probability of a small break i
LOCA due to a stuck-open PORV.
Ve y truly yours,
)i
$._ _d, William 0. Parker, Jr.
ROS/php Attachment 8208030524 820726 PDR ADOCK 05000 A
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Mr. Harold R. Denton, Director July 26, 1982 Page 2 cc: Mr. James P. O'Reilly, Regional Administrator d
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
Attorney-at-Law 314 Pall Mall Columbia, South Carolina 29201 Palmetto Alliance 2135 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group i
854 Henley Place Charlotte, North Carolina 29207 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207 i
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