ML20138P406
| ML20138P406 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 12/13/1985 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| TAC-59623, TAC-59624, NUDOCS 8512260089 | |
| Download: ML20138P406 (7) | |
Text
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DUKE POWER GOMPANY P.O. BOX 33189 CHARLOTTE. N.C. 28942 HAL B. TUCKER retarnown
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=UDLEAR P=Ont OTION -
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December 13, 1985
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Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 Washington, D.C.
20555' Attention: B.J.-Youngblood, Director PWR Project Directorate #4 Subject - McGuire Nuclear Station Docket Numbers 50-369/370 TurbineL0verspeed Protection System; Response to Request for Information On' August 30, 1985, Duke' Power Company proposed Technical Specification changes relative to Turbine Overspeed Protection. By letter of October 15, 1985 (E.G.
Adensam to H.B. Tucker) the NRC staff requested additional information. Attached are the staff questions and the Duke responses to those questions.
m.
Very truly yours, b
ff Hal B. Tucker 2O
.g SAC /jgm
~ Attachments
.cc:
Dr. J.-Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 3100 Atlanta, GA 30323 W.T. Orders Senior Resident Inspector I
McGuire Nuclear Station 1
Mr. Dayne Brown, Chief J c-Radiation Protection Branch
% D *.
Division of Facility Services
- Depart' ment of Iluman Resources P.O.. Box 12200 s
Raleigh, N.C.
27605 8512260089 851213 7
PDR ADOCK 05000069 P
PDR c:
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g-ATTACHMENT I QUESTION 1:
In Attachment 11 of your submittal, you state that a study has shown that McGuire Nuclear Station has the same or very similar equipment in the TOP system as those of the Farley Nuclear Plant. Provide the study (or a suita-ble reference if publically available). Clarify (a) whether you extrapolated results from the Westinghouse evaluation and applied them to the McGuire TOP.
. system assurance program accordingly; or (b) whether the study is an indepen-dent analysis of the-McGuire TOP syctem.
RESPONSE 1:
Attachment la is a interchangeability listing of style numbers (Part Numbers) for turbine components at different stations. As can be seen on the attach-ment the major components listed in the Overspeed Reliability Program i.e.,
Throttle valves, Governor valves, Intercept valves, Reheat Stop valves and mechanical overspeed trip device are identical at McGuire and Farley. The information listed on Attachment hwas taken from the Westinghouse Steam Turbine Division Interchangeability Data Southeastern Area Utilities book.
The electronic overspeed protection circuits are basically identical since both Farley and McGuire have the Westinghouse DEH control systems.
The answer to the second portion of question (1) is (a): DPCo. extrapolated the Westinghouse results of their Farley evaluation and applied them to McGuire knowing the virtual identica1 ness of the components and control system.
QUESTION 2:
You propose certain test performance periods which deviate from the Westinghouse recommendations for Faricy. For example, Westinghouse recommended a monthly test of turbine valves whereas you propose testing every 4 months (Section 4.4 of Appendix I).
You state that these deviations have been deemed appropriate for McGuire based on actual test results which indicate that the testing frequency does not need to be increased. Provide these test results and justify quantitatively the using of these test results in deriving longer periods of testing, calibration, and maintenance intervals.
RESPONSE 28 DPCo. wishes to clarify the sentence on Attachment II, page 2, paragraph I which stated:
"As indicated in Appendix I, Duke Power has deviated from certain test performance periods which Westinghouse recommended for Farley".
This should have been " Duke Power has deviated from certain maintenance periods which Westinghouse recommended for Farley". Duke Power is proposing the same maintenance periods on the throttle valves, governor valves and overspeed devices (electrical and mechanical) as Farley but are proposing more stringent maintenance periods on the intercept and reheat stop valves (40 month inspections vs. 60 month). As part of the program Duke Power will be disassembling and inspecting all turbine valves on a 40 month basis instead of
- just one (1) of each type valve every 40 months as is now required by Tech.
Spec, The deviation noted above is a deviation from the generic Westinghouse recommendations, not the approved Farley-Specific program.
Duke Power is deviating from the generic Westinghouse recommendations because the proposed inspection and maintenance schedule increases the reliability of the Overspeed Protection System.
Review of the testing history reveals no problems which would have prevented proper operation of the overspeed protec-tion system.
QUESTION 3:
You state in Attachment III that "The potential insignificant increase of catas-trophic turbine failure would not have any adverse impact on the power plant safety or safety related equipment." Provide quantitative results (e.g., failure probability per year) to substantiate this statement. Compare the failure probability of the TOP system with the proposed testing intervals to the failure probability of the TOP system with the testing intervals within the standard Technical Specification.
RESPONSE 3:
The proposed increased to'st interval for the Turbine Overspeed Protection System may result in an increased failure probability for the system; which, in turn, may result in an increased probability of catastrophic turbine failure in the event of a coincident overspeed event. The potential increases have not been quantitatively analyzed. The potential for, and effects of, turbine missile generation have been analyzed and are discussed in Final Safety Analysis Report (FSAR) Sections 3.5.2.7 and 10.2.3.
Safety-related equipment is protected from postulated turbine missiles by Category 1 structures. Therefore, no increase in the probability of catastrophic turbine failure will result in an adverse impact on plant safety. Turbine Overspeed Protection System failure probability as a function of test interval, like the probability of catastrophic turbine failure, is solely an economic issue not a safety issue. Therefore, a quanti-tative analysis of failure probability is not justified by any additional safety assurance.
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