ML20153H081
| ML20153H081 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/11/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-1.D.2, TASK-TM TAC-51257, NUDOCS 8602280603 | |
| Download: ML20153H081 (4) | |
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$ 1 Docket No. 50-336 February 11, 1986 Mr. John F. Opeka, Senior dic'e President Nuclear Engineering and Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE SAFETY PARAMETER DISPLAY SYSTEM FOR MILLSTONE 2 We have reviewed your March 25, 1985 submittal concerning the Safety Parameter Display System (SPDS) and concluded that insufficient infortnation was provided to complete the evaluation. The enclosure requests specific information needed to complete the evaluation.
In order to preserve our present review schedule, the staff needs to have this information within 60 days from your receipt of this letter.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincer'ely, -
/S/
Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B I
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Enclosure:
As stated cc w/ enclosure:
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Mrs John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:
Gerald Garfield, Esq.
Mr. Wayne D. Romberg Day, Berry & Howard Superintendent Counselors at Law-Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczka U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations ~
Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. John Shedlosky Resident Inspector / Millstone Box 811 Niantic, Connecticut 06357 Office of Policy & Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106
REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE MILLSTONE 2 NUCLEAR POWER STATION SAFETY PARAMETER DISPLAY SYSTEM Each operating reactor shall be provided with a Safety Parameter Display System (SPDS). The Comission approved requirements for an SPDS are defined 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.
The staff reviewed the SPDS safety analysis and supplemental documents provided by Northeast Nuclear Energy Company (Reference 1). The staff was unable to complete the review because of insufficient infonnation.
The following additional infonnation is required to continue and complete the review:
INSTRUMENTATION AND CONTROL SYSTEMS BRANCH
~
~ Isolation Devices Provide the following:
For the type of device used to accomplish electrical isolation, describe a.
the specific testing perfonned to demonstrate that the device is accept-l able for its application (s). This description should include elementary diagrams when necessary to indicate the test configuration and how the l
maximun credible faults were applied to the devices.
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b'. ' Data to verify that the maxima 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 detennined.
Data to verify that the maxima credible fault was applied to the output c.
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.
Provide a comitment that the isolation devices comply with the environ-e.
men't 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 Crosstalkf that may be generated by the SPDS.
g.
Provide infonnation to verify that the Class IE isoaltor is powered from a Class IE power source.
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REFERENCE:
l 1.
Letter from W. G. Counsil (NNEC) to J. R. Miller (NRC), dated 3-25-85.
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