ML17251A640
| ML17251A640 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/09/1986 |
| From: | Fairtile M Office of Nuclear Reactor Regulation |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-51243, NUDOCS 8604180318 | |
| Download: ML17251A640 (5) | |
Text
a Docket No. 50-244 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas In Electric Corp.
89 East Avenue Rochester, New York 14649
Dear Mr. Kober:
We are conducting our review of the Ginna Safety Parameter Display System.
Your submittal of November 30, 1984, in part, described the electrical isolation devices used for the system.
We require additional information in order to complete our review.
The information needed by the staff is provided in the enclosure to this letter.
We understand through discussions with Mr. Paul Wilkens of your staff, held with NRC staff members on March 27,
- 1986, by telephone, that this system is on schedule as directed by the NRC Order of June 12, 1984.
Kindly respond within 45 days of the date of this letter.
This review is being conducted under our TAC number 51243.
t 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.
cc w/o encl:
J.
Kramer R. Eckenrode Morton B. Fairtile, Project Manager Project Directorate ¹1 Division of PWR Licensing-A Office:
PM/PAD¹1)gg,p-PD/PAD¹1 Surname:
NFairtile/tg GLear M Date:
Oa/ 9/86 04/g /86 Bb04180318 Bb0409 PDR ADOCK'5000244 P
PDR e
Mr. Roger W. Kober Rochester Gas and Electric Corporation R.
E. Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Klimberg, Esquire General
- Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission
- 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Jay Dunkleberger Division of-Policy Analysis 8 Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223
REQUEST FOR ADDITIONAL INFORMATION C
NCERNING THE R.
E. RI~E PIP I S
METR DIS L
TM Each operating reactor shall be provided with a Safety Parameter Display System (SPDS).
The Commission approved requirements for an SPDS are defined in NURFG-0737, Supplement No. l.
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.
The staff reviewed the SPDS safety analysis and supplemental documents provided by Rochester Gas and Electric (Reference I).
The information did not address the isolation devices in the detail required by the staff.
The following addi-tional information is needed to continue and complete 'the review:
Isolation Devices a.
For the type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable for its application(s).
This description should include elementary diagrams when necessary to indicate the test configuration and how the maximum credible faults were applied to the devices.
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 e'ach type of device.
e.
Provide a commitment that the isolation devices comply with the environment 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
g.
Provide information to verify that the Class 1E isolator is powered from a Class 1E power source.
Reference No.
1:
Letter dated November 30, 1984 from R.
W. Kober (RARE) to il. A. Zwolinski (NRC).
APR'09 lg8g DISTRIBUTION:
NRC PDR Local PDR G. Lear M. Fairtile P. Shuttleworth L. Harmon E. Jordan B. Grimes J.
Partlow T. Barnhart (4)
ACRS (10)
OPA LFMB
'DPl r/f PDPl s/f