ML20004F382

Forwards Request for Addl Info on SEP Topics VII-1.A & VII-2 Re Isolation of Reactor Protection & Engineered Safety Features Sys

ML20004F382
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/12/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Counsil W CONNECTICUT YANKEE ATOMIC POWER CO.
References
TASK-07-01.A, TASK-07-02, TASK-7-1.A, TASK-7-2, TASK-RR LSO5-81-06-048, LSO5-81-6-48, NUDOCS 8106180271
Download: ML20004F382 (3)

Text

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'M June 12,1981 Docket No. 50-213 e

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Mr. W. G. C;uns11, Vice President 44 Nuclear Engineering and Operations

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7A Connecticut Yankee Atomic Power Co.

g Post Office Box 270 1>

d Hartford, Connecticut 06101

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SUBJECT:

SE' TOPICS VII-1.A ISOLATION OF REACTCR PROTECTION SYSTEM FROM NON-SAFFTY SYSTEMS, INCLUDING QUALIFICATION OF ISOLA-TION DEVICES !AD VII-2 ENGINEERED SAFETY FEATURES (EST)

SYSTEM CONTROL LOGIC AND DESIGN - REQUEST FOR ADDITIONAL INFORMATION(HADOAMNECK) j 1

The enclosed request for additional infomation has been prepared as part of our evaluation of the subject matters at Haddam Neck.

Because these concems are parts of SEP Topics, response within 30 days is requested so that we,mair)tair the present 3EP review schedule.

l Sincerely, l

Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

As stated t

cc w/ enclosure:

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i Docket No. 50 213 LS05-81 06-045 t

Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Connecticut Yankel Atomic Power Co.

Post Office Box 270 Hartford, Connecticut 06101

SUBJECT:

SEP TOPICS VII-1.A. ISOLATION OF REACTOR PROTECTION SYSTEM FROM tDN-h FETY SYSTEMS, INCLUDING QUALIFICATION OF ISOLA-TION DEVICES AND VII-2, ENGINEERED SAFETY FEATURES (ESF)

SYSTEM CONTROL LOGIC AND DESIGN - REQUEST FOR ADDITIONAL INFORMATION (Hf.DDAM NECK) l The enclosed req:.est for additional infomation has been prepared as part of our evaluation of the subject matters at Haddam Neck.

Because these co,cerns are parts of SEP Topics, response within 30 days is requested so th,at we maintain the present SEP review schedule.

Sincerely, lls A s

Dennis M. Crutchfield, ief Operating Rcactors Branch No. 5 Division of Licensing

Enclosure:

As ' stated' cc w/ enclosure:

See next page I

i

er Mr. W. G. Counsil CC Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region I Office Hartford, Connecticut 06103 ATIN: EIS C00RDINATOR JFK Federal Building Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RfD #1 Resident Inspector Post Office Box 127E Haddam Neck Nuclear Power Station East Hampton, Connecticut 06424 c/o U. S. NRC l

East Haddam Post Office i

Mr. James R. Himmelwright East Haddam, Connecticut 06423 Northeast Utilities Service Cocpany P. O. Box 270 Hartford, Connecticut 06101 I

Russell Library 119 Broad Street t

Middletown, Connecticut 06457 l

Board of Selectmen Town Hall Haddam, Connecticut 06103 l

Connecticut Energ Agency ATTN: Assistant Director Research and Policy i

Development Department of Planning and Energ Policy 20 Grand Street j

Hartford, Connecticut 06106 Director, Criteria and Standards

Division, i

Office of Radiation Programs (ANR-460) 7 U. S. Environmental Protection Agency Washington, D. C.

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6 REQUEST FOR ADDITIONAL INFORMATION ON HADDAM NECK FOR SEP TOPICS VII-1.A AND VII-2 ISOLATION OF REACTOR PROTECTION AND ENGINEERED SAFETY SYSTEMS The FDSAR and available drawings do not centain sufficient information for us to adequately review the degree of isolation between the Reactor Trip and ESF systems from control and non-safety systems. Therefore please provide the following additional information and drawings:

1.

Current schematics or elementary diagrams of the Reactor Trip System and I

the ESF Systems and their interface with Shared Control Systems.

2.

P&ID's of the ESF systems.

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Identify by make s d model the isolation buffers installed in the Nuclear 3.

a Power Range channels to obtain isolated indication of the detector ion currents.

(Plant Design Change #198.) Describe how they meet the I

reqLirements of IEEE Standard 279-1971 Sect. 4.7.2 and GDC 24.

4.

Identify locatior.s and describe any other isolation buffers currently

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in use in the reactor trip and ESF systems to isolate these systems from control, computer, recorders and non-safety systems. Describe how they comply with the requirements of IEEE Standard 279 and GDC 24.

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