ML20210G813
| ML20210G813 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/24/1986 |
| From: | Frank Akstulewicz Office of Nuclear Reactor Regulation |
| To: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| NUDOCS 8609250474 | |
| Download: ML20210G813 (5) | |
Text
e-September 24, 1986 Docket No. 50-213 Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
SAFETY PARAMETER DISPLAY REPORT (ISAP TOPIC N0. 1.20)
Re:
Haddam Neck Plant By letter dated May 13, 1986, Connecticut Yankee Atomic Power Company submitted a safety analysis report on the safety parameter display system at the Haddam Neck Plant. We have performed a preliminary review and have concluded that additional information is necessary for us to complete our review. Our requests for additional information are enclosed.
In order for us to complete our review in a timely fashion, we request that your response be received within 45 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincerely, Original signed by:
F. M. Akstulewicz Francis M. Akstulewicz, Jr Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosure:
As Stated cc: See Next Page DISTRIBUTION
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/e September 24, 1986 Docket No. 50-213 Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
SAFETY PARAMETER DISPLAY REPORT (ISAP TOPIC N0. 1.20)
Re:
Haddam Neck Plant By letter dated May 13, 1986, Connecticut Yankee Atomic Power Company submitted a safety analysis report on the safety parameter display system at the Haddam Neck Plant. We have performed a preliminary review and have concluded that additional information is necessary for us to complete our review. Our requests for additional information are enclosed.
In order for us to complete our review in a timely fashion, we request that your response be received within 45 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincerely, Wd h-Francis M. Akstulewicz, J Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosure:
As Stated cc: See Next Page
Mr. John F. Opeka Connecticut Yankee Atomic Power Company Haddam Neck Plant cc:
Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit Counselors at Law Department of Environnental City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent Haddam Neck Plant Richard M. Kacich, Supervisor RDF #1 Operating Nuclear Plant Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Edward J. Mroczka Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 State of Connecticut Office of Policy and Management ATTN:
Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Nuclear Power Station c/o U.S. NRC East Haddam Post Office East Haddam, Connecticut 06423 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
REQUEST FOR ADDITIONAL INFORMATION SAFETY PARAMETER DISPLAY SYSTEM Each operating reactor shall be provided with a Safety Parameter Display System (SPDS). The Commission-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 (Ref. 2) and supplemental document (Ref. 1). The staff was unable to complete the review and concluded that the following additional information is required to continue and complete the review.
f Isolation Devices f
Please provide the following:
a.
A description of the specific testing performed to demonstrate that the device used to accomplish electrical isolation 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 device.
b.
The data to verify that the maximum credible faults applied during the tests were the maximum voltage at the maximum current to which the device could.be exposed, and define how the maximum voltage / current was determined.
c.
The data to verify that the maximum credible fault was applied to the l
output of the device in the transverse mode (between signal and return) and that other faults were considered (i.e., open and short circuits).
..__ ~ __-_ __ _-_.._,_,..__ __ _
d.
The' definition of the pass / fail acceptance criteria for each type of
- device, e.
A comitment that the isolation device complies with the environmental qualifications (10 CFR 50.49) and with the seismic qualifications which were the basis for plant licensing.
f.
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.
g.
The information to verify that the Class IE isolator is powered from a Class 1E source.
References 1.
Letter dated November 28, l'983 from W. G. Counsil (CYAPC0) to D. G. Eisenhut (NRC), "Haddam Neck Plant, Supplement 1 to NUREG-0737, Requirements for Emergency Response Capability."
2.
Letter dated May 13, 1986 from J. F. Opeka (CYAPC0) to C. I. Grimes (NRC), "Haddam Neck Plant, Supplement 1 to NUREG-0737, Safety Parameter Display System, Safety Analysis Report."
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