ML20207T357
| ML20207T357 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire, 05000000 |
| Issue date: | 08/28/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| Shared Package | |
| ML20205H658 | List: |
| References | |
| FOIA-87-68 NUDOCS 8703230475 | |
| Download: ML20207T357 (4) | |
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,. s 4 August 28, 1984 DISTRIBUTION Docket File 50-369/370 NRC PDR Docket Nos: 50-369 Local PDR and 50-370 NSIC i
PRC System LB#4 Reading F0rr MDuncan Mr. H. B. Tucker, Vice President EAdensam Nuclear Production Department Attorney, OELD Duke Power Company NGrace 422 South Church Street EJordan Charlotte, North Carolina 28242 ACRS (16)
GLapinsky
Dear Mr. Tucker:
JJoyce
Subject:
Safety Parameter Display System - Request for Additional Information (McGuire Nuclear Station, Units 1 and 2)
As a result of our continuing review of the McGuire Safety Parameter Display
. System we find that we are in need of some additional information which is described in the enclosure. We request that you respond to these matters within 60 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer then ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Elinor Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Request for Additional Information, Dated August 9, 1984 cc: See next page 8703230475 870319 NG
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ll Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company
'I 422 South Church Street Charlotte, North Carolina 28242 cc: Mr. A. Carr Duke Power Company P. O. Box 33189 422 South Church Street Charlotte,-North Carolina 28242 Mr. F. J. Twogood Power Systems Division Westinghouse Electric Corp.
P. O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Robert Gill Duke Power Company Nuclear Production Department P. O. Box 33189 Charlotte, North Carolina 28242 J. Michael McGarr Bishop, Liberman,y, III, Esq.
Cook, Purcell and Reynolds-1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Mr. Wm. Orde'rs Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Route 4, Box 529 Hunterville, North Carolina 28078 4
James P. O'Reilly, Regional Administrator U.S. Nuclear Regulatory Commission.
Region II 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323' R. S. Howard Operating Plants Projects i
Regional Manager Westinghouse Electric Corporation - R&D 701 P. O. Box 2728 Pittsburgh, Pennsylvania 15230 I
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, 3, r,y ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION gjG S 196-1 CONCERNING THE MCGUIRE 1 AND 2
' SAFETY PARAMETER DISPLAY SYSTEM System (SPDS)g reactor.shall be provided with a Safety Parameter DisplayThe C Each operatin in NUREG-0737, Supplement 1.
In the Regional Workshops on Generic Letter 82-33 held during March 1983, the NRC discussed these requirements and the staff's review of the SPDS.
1 Prompt implementation of the SPDS in operating reactors is a design goal of prime importance. The staff's review of SPDS documentation for operating reactors called for in NUREG-0737, Supplement 1 is designed to avoid delays resulting from the time required for NRC staff review. The NRC staff will not review operating reactor SPDS designs for compliance with the l-requirements of Supplement 1 of NUREG-0737 prior to implementation unless a pre-implementation review has been specifically requested by licensees. The licensee's Safety Analysis and SPDS Implementation Plan will be reviewed by the NRC staff only to determine if a serious safety question is posed or if the analysis is seriously-inadequate. The NRC staff review to accomplish this will be directed at (a) confirming the adequacy of the parameters selected to be displayed to detect critical safety functions ~, (b) confirming that means are provided to assure that the data displayed are valid, (c) confiming that the licensee has connitted to a human factors program to ensure that the displayed information can be read'ily(perceived andd) confirming that t comprehended so as not to mislead the operator, and SPDS will be suitably isolated from electrical and electronic interference with equipment and sensors that are used in safety systems.
If, based on this review, the staff identifies a serious safety question or seriously inadequate analysis, the. Director of IE or the Director of NRR may require or direct the licensee to cease implementation.
The staff reviewed the SPDS Safety Analysis and Implementation Plan provided byDukePowerCompany(Reference 1). The staff was unable to complete its evaluation because of insufficient information. The following additional l
infomation is required to continue and complete the SPDS evaluation:.
I Isolation Devices For each type of device used to accomplish electrical isolation, i
a.
j describe the specific testing performed to demonstrate that the device is acceptable for its applifcation(s). This description should include elementary diagrams when necessary to indicate i
i the test configuration and how the maximum credible faults were applied to the devices, j
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i b.
Data to verify that the maximum credible faults applied during the test were the maximum voltage / current to which the device could be exposed, and define how the maximum voltage / current was determined.
c.
Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e., open and short circuits).
d.
Define the pass / fail acceptance criteria for each type of
- device, e.
Provide a commitment that the isolation devices comply with the environmental qualifications (10 CFR 50.49) and with the seismic qualifications which were the basis for plant licensing.
f.
Provide a description of the measures taken to protect the safety systems from electrical interference (i.e., Electrostatic Coupling, EMI, Comon Mode and Crosstalk) that may be generated by the SPDS.-
Human Factors Program Provide a description of the display system,Jits human factored design, and the methods used and results from a human factors program to ensure that the displayed information can be readily perceived and comprehended so as not to mislead the operator.
Data Validation Describe the method used to.valida.te data displayed in the SPDS. Also describe how invalid data are defined to the operator.
REFERENCES 1.
Letter from Duke Power Company to NRC, dated March 29, 1984, with enclosure.
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