ML20138N666
| ML20138N666 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/28/1985 |
| From: | Fee W, Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 A02959, A2959, NUDOCS 8511050280 | |
| Download: ML20138N666 (2) | |
Text
a.-..
N UTHJTIES cenerei Orrice. seiden street. Berlin. Connecticut UN
$iNc5=,
P.O. BOX 270
.aos.ma wa coa' HARTFORD. CONNECTICUT 06141-0270 L
t
- [
'gcg (203) 665-5000 October 28, 1985 Docket No. 50-423 A02959 Director of Nuclear Reactor Regulation Mr. B. 3. Youngblood, Chief Licensing Branch No.1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
References:
(1)
- 3. F. Opeka letter to B. 3. Youngblood, dated August 13, 1985.
(2)
~3. F. Opeka letter to B. 3. Youngblood, dated September 12, 1985.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 Supplement I to NUREG-0737 Control Room Design Review A meeting was conducted on October 17, 1985 between the NRC Staff and representatives of Northeast Nuclear Energy Company (NNECO) to discuss information previously provided to the NRC Staff in References (1) and (2) regarding the Millstone Unit No. 3 Control Room Design Review (CRDR).
Specifically, the manner by which the characteristics associated. with the information and control needs of the operator were dete"nined during the function and task anaysis portion of the CRDR required some clarification. The purpose of this submittal is to document the clarifications verbally provided to e
the NRC Staff during the meeting.
The Instrumentation Characteristics Review Program (ICRP) performed by the Westinghouse Electric Corporation was conducted independently of the existing instruments and controls on the Millstone Unit No. 3 control boards. The ICRP identified both generic and plant-specific characteristics relating to operator information and control needs based upon the Westinghouse Owners' Group (WOG) Emergency Response Guidelines (ERGS),
the ERG background documentation, and the Millstone Unit No. 3 Emergency Operating Procedures (EOPs), including the plant-specific portions of the EOPs. The Westinghouse Electric Corporation did not rely upon the lists of instruments and controls which we provided to them on the I&C Characteristic Requirements Form.
We included this information on these forms to expedite our subsequent review of 1
the required characteristics as compared to the existing instruments and controls. Any differences were identified as Human Engineering Discrepancies (HEDs) and were resolved in accordance with CRDR methodology.
o$
8511050280 851028 L
0 PDR ADOCK 05000423 l
F PDR
< :.., Another item requiring some clarification resulted from the incorrect statement in Attachment No. 2 in Reference (1) that the WOG ERGS were only reviewed to identify major. operation actions necessary to support the operator functions.
Actually, all ERG steps were reviewed by the Westinghouse Electric Corporation while conducting the ICRP. On a related matter, procedural steps referenced in a particular EOP were also included in the ICRP.
We trust that this information adequately resolves any NRC Staff concerns regarding the manner in which function and task analysis was performed for Millstone Unit No. 3.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY et. al.
BY NORTHEAST NUCLEAR ENERGY COMPANY Their Agent 3.QJOpeka Senior Vice President
/
w By: W. F. Fee Executive Vice President STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD
)
Then personally appeared before me W. F. Fee, who being duly sworn, did state that he is Executive Vice President of Northeast Nuclear Energy Company, an Applicant herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Applicants herein and that the statements contained in said information are true and correct to the best of his knowledge and belief, t
% J.
a
= -
otary Public m amuim i
-s
- --