ML18092A443
| ML18092A443 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/07/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Uderitz R Public Service Enterprise Group |
| References | |
| NUDOCS 8412190446 | |
| Download: ML18092A443 (5) | |
Text
I Docket Nos. 50-272 and 50-311
- December 7, 1984 Mr. Richard A. Uderitz, Vice President -
Nuclear Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. Uderitz:
DISTR_IB_UT:ION,..
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L PDR ORB#l Rdg DFi scher DEisenhut EJordan PMcKee NRC PDR Gray File CParrish ACRS 10 OELD JPartlow
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE SAFETY PARAMETER DISPLAY SYSTEM FOR SALEM UNITS 1 AND 2 The staff has reviewed your January 30, 1984 submittal "Safety Parameter Display System, Safety Analysis and Implementation Plan" and concluded that insufficient information was provided for us to complete our evaluation.
The additional information required is discussed in the enclosure.
Please respond to this request for information within 60 days from receipt of this letter.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required Under P.L.96-511.
o~
DFischer;ps 12/c.,/84 8412190446841207 PDR ADOCK 05000272 F
PDR Sincerely,
/s/SVarga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
Mr. R. A. Uderitz Public Service Electric & Gas Company cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric & Gas Company P. 0. Box 570 - Mail Code T5E Newark, New Jersey 07101 Gene Fisher~ Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. John M. Zupko, Jr.
General Manager - Salem Operations Public Service Electric & Gas Company Post Office Box E Hancock Bridge, New Jersey 08038 Mr. Dale Bridenbaugh M.H.B. Technical Associates 1723 Hamilton Avenue San Jose, California 95125 James Linville, Resident Inspector Salem ~uclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancock Bridge, New Jersey 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, New Jersey 08625 Richard B. McGlynn,.Commission Department of Public Utilities State of New Jersey 101 Commerce Street Newark, New Jersey 07102 Salem Nu~ar Generating Station Units 1 ana 2 Regional Radiation Representative EPA Region II 26 Federal Plaza New York, New York 10007 Mr. R. L. Mittl, General Manager Nuclear Assurance and Regulation Public Service Electric & Gas Co.
Mail Code T16D - P. 0. Box 570 Newark, New Jersey 07101 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancock Bridge, NJ 08038 Mr. Alfred C. Coleman, Jr.
Mrs. Eleanor G. Coleman 35 K Drive Pennsville, New Jersey 08070 Carl Valore, Jr., Esquire Valore, McAllister, Aron and Westmoreland, P.A.
535 Tilton Road Northfield, NJ 08225 June D. MacArtor, Esquire Deputy Attorney General Tatnall Building Post Office B6x 1401 Dover, Delaware 19901 Harry M. Coleman, Mayor Lower Alloways Creek Township Municipal Hall Hancock Bridge, New ~ersey 08038
Salem Nuclear Generating Station Units 1 and 2 cc:
Mr. Edwin A. Liden, Manager Nuclear Licensing & Regulation Public Service Electric & Gas Company Post Office Box 236 Hancock Bridge, New Jersey 08038 Mr. Charles P. Johnson Assistant to Vice President~ Nuclear Public Service Electric & Gas Company Post Office Box 570 80 Park Plaza - 15A Newark, New Jersey 07101 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Frank Casolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628
REQUEST FOR ADDITIONAL INFORMATIOM.
CONCERNING THE SALEM UNITS 1 AND 2 SAFETY PARAMETER DISPLAY SYSTEM Ea~h operating reactor shall be provided with*a Safety Parameter Display*
System (SPDS).
- The CoITUTiission approved requirements for an SPDS dre defir1ed in"NUREG-0737~ Supplement 1.
In the.Regional Workshops on Generic Letter 82-33.held during March '1983, the NRC discussed these requirernents and the staff's review of* the SPDS..
Pro~pt implementation of t~e SPDS in operating reacto~s is a design goal of prime importance.
The staff's review ofSPDS documentation for operating reeictors 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 ~or compliance wfth the
~equirements of Supplement 1 of NUREG-0737 prior to i1~ple~entatibn uoless a preimplementation review has been specifically requested by licensees.
The licer.see'.s Safety Analysis and SPDS Implementation Plan will be revie\\ved by the f*IRC staff only to deterrnir1e if a serious safety question is posed or if the analysis is seriously inadequate.
The f~RC staff review to accomplish this ~iil be directed at:
(a) confirming the adequacy of the parameters sel~cted to be displayed to d~tect critical safety functions, (b) confirming that ~e~ns are provided to assure that the data displayed are valid, (c) confirming that the licensee has committed to a human factors program to ensure that the displayed information can be readily perc~ived and comprsh~nd2d so as not to mislt:ad the operator, and (d) confirr:-:ing that S?DS wi11 be suitably isolated frcm electrical and electronic int~rference with equipment and sensors that are usea in safety sys:2~s. If bc~2d on this review the staff identifies a serious safety ~uestion or seriously inadequate analysis, the Director of IE or the Directur of NRR may require or di~ect the licensee to cease implementation.
The staff has reviewed the SPDS safety analysis and implementation plan provided in your subrPit+::~ riateci,:c:.r:t:i!'.'Y 30, 1984.
In order to complete our evaluation the follnwing additional information is requried:
- a.
For each type of device used to accomplish electrical isolation, describe the specific testing perforr:;ed to demonstrate that the device is acceptable for its application(s).
This description should include eler,;entJry diagrams when 1:ecessary to indicate the test configuration and how the r:1ax~r.iur:i credible faults 1.,.e1*t:: c:nilied to the ct.:v1ces.
~*. (
- 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 (bet\\veen 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, Common Mode and Crosstalk) that
~ay be generated by the SPDS.
- . HUM~N FACTORS PROGRAM Provide a description of the display system, its human factored desian, 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 validate data displayed in the SPDS.
Also, describe how invalid data is defined to the operator.
PARAMETER SELECTION Provide the rational which justifies parameter selection and relates the parameters selected for display on the SPDS to the critic. *:;afety functions stated in NUREG-0737, Supplement 1.
erov1de conclusions regarding unreviewed safety questions and changes to technical specifications.