ML20010B830
| ML20010B830 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/07/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| NUDOCS 8108180205 | |
| Download: ML20010B830 (4) | |
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Docket No. 50-336 1
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Mr. W. G. Counsil. Vice President 9.**Mg S
L Nuclear Engineering & Operations Northeast fluclear Energy Company P. O. Box 270 l-Hartford, Connecticut 06101 (b
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Dear Mr. Counsil:
In our review of the thermal hydraulic section of the Westinghouse Basic Safety Report (BSR) to be used at Millstone Nuclear Power Station Unit No. 2, we find that additional information, as delineated in the encicsure, is necessary to complete our review.
i Please provide this additional information at your earliest convenience to correspond with your need for our Safety Evaluation of the BSR.
Sincerely, Original signed by, Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing l
Enclpsure: As stated DISTRIBUTION:
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Northeast Nuclear Energy Company CC:
William H. Cuddy, Esquire Mr. John Shedlosky Day, Berry & Howard Reside'nt Insp~ector/ Millstone Counselors at Law c/o U.S.N.R.C.
One Constitution Plaza P. O. Drawer KK Hartford, Connecticut 06103 Niantic, CT 06357 Mr. Charles Brinkman Natural Resources Defense Council Manager - Washington Nuclear 917 15th Street, N.W.
Operations Washington, D. C.
20005 C-E Power Systems Combustion Engineering, Inc.
, Mr. Lawrence Bettencourt, Ff'st Selectman 4853 Cordell Aven., Suite A-1 r
Town of Waterford Bethesda, MD 20014 Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Nuclear Energy Company ATTN:
Superintendent Millstone Plant Connecticut Energy Agency Post Office Box 128 ATTN:
Assistant Director, Research Waterford, Connecticut 06385 and Policy Development Department of Planning and Energy Qaterford Public Library Policy Rope Ferry Road, Route 156 20 Grand Street Waterford, Connecticut 06385 Hartford, CT 06106 U. S. Environmental Protection Agnecy Regicn I Office ATIN:
EIS C00RDINAIOR John F. Kennedy Feceral Building Boston, Massachusetts 02203 Northeast Utilities Service Company -
ATTN:
Mr. James R. Himmelwright Nuclear Engineering and Operations P. 0. Box 270 Hartford, Connecticut,06101 4
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Request for Additional Information Northeast Nuclear Energy Company Millstone Nuclear Power Station, Unit 2 Docket No. 50-336 By letter dated October 6, 1980,, we requested that you provide a justification of the Cycle 4 measurement uncertainty values for axial shape index, pressure, temperature, flow, power (LCO) and power (LSSS). This was in relation to
,Section 2.3.2.1, Critical Hegt F, lux, of the B5R.
While our review of measurement uncertainties continued, LC0 and LSSS limits were to be maintained at the values for Cycle 3 based on the more conservative Cycle 3 analysis results.
This has the effect of limiting the partial credit for statistical combination of uncertainties to 1.2% on LC0 and 2.1% on LSSS compared to the 3% credit proposed.
Your January 8, 1981. response to our request for the justification of measurement uncertainty values was not totally satis'actory.
Your staff is aware that this response needs to be,similar to the response provided on the D.C. Cook cocket to justify the use of " Improved Thermal Design Procedure", WCAP 8567/8568.
Although Millstone Unit 2, Cycle 4 does not take full advantage of the " Improved Design Procedure", it does take partial advantage by use of the proposed 3%
credit subtracted from the equivalent sum of combined ur. certainties. Therefore, provide responses to the following questions:
1.
Provide a block diagram depicting sensor, process equipment, computer and devices for each parameter channel used in the uncertainty analysis. With-in each element of the block d;iagram, identify the overall accuracy of, each channel transmitter to final output and specify the minimum acceptable ac-curacy for use with.the new proceJure. Also identify the overall accuracy of the final output value and maximum accuracy requirements for each input channel of this final output device.
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Discuss the method (s) for incorporating environmental effects (e.g.,
l noise, EMI) on instrument channels into the i1 certainty analysis.
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Provide data to verify that the plant instruments will perform with l
a high degree of confidence, within their design accuracies. This i -,
information may be obtained from the operating history of Millstone l
Unit 2 and identical instrumen,ts installed in other plants. This l
request pertains to the instruments affecting the uncertainties in the i
. design procedure (as identified in question 1 above), the overtem-I perature T trip, the high flow trip and the pump voltage trip.
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- 4. ~ Provide the ranges of applicability of sensitivity factors.
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