ML20041F693
| ML20041F693 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/05/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| Shared Package | |
| ML20041F694 | List: |
| References | |
| TASK-07-01.A, TASK-7-1.A, TASK-RR LSO5-82-03-036, LSO5-82-3-36, NUDOCS 8203170306 | |
| Download: ML20041F693 (4) | |
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e March 5[1982
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Docket No. 50-213 C
LS05-82-03-036 e
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MAR 1719825 3 Mr. W. G. Counsil. Vice President
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Nuclear Engineering and Operations s
um Connecticut Yankee Atomic Power Company Post Office Box 270 t
6 Hartford, Connecticut 06101 d
Dear Mr. Counsil:
SUBJECT:
SEP TOPIC VII-1.A. ISOLATION OF REACTOR PROTECTION SYSTEM FROM NON-SAFETY SYSTEMS, INCLUDING QUALIFICATION OF ISOLATION DEVICES, DRAFT SAFETY EVALUATION FOR HADDAM NECK is our contractor's draft technical evaluation of the sub. ject for your plant. is the staff's draft safety evaluation and it is based on Enclosure 1.
Both documents recommend that suitable isolation devices be provided be-tween the process instrumentation system and the process recorders, data logger and the plant pmcess computer.
We also recommend isolation between the variable low pressure and flow mismatch computers and the rod contml and feedwater control systems.
The need to actually implement these changes will be determined during the integrated safety assessment. This topic assessment may be revised in the
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future if your facility design is changed or if NRC criteria relating to this tppic are modified before the integrated assessment is completed.
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J Sincerely, I
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l Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
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Enclosures:
As stated cc w/ enclosures:
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e - =- - -. = _ Mr. W. G. Counsil CC Day, Berry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Superintendent Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424 Mr. Richard R. Laudenat Manager, Generation Facilities Licensing Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 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 06115 U. S. Environmental Protection Agency Region I Office ATIN: Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203 i Resident Inspector Haddam Neck Nuclear Power Station c/o U. S. NRC East Haddam Post Office East Haddam, Connecticut 06423 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I Office cf Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406
ENCLOSURE 2 SYSTEMATIC EVALUATION PROGRAM TOPIC VII-1.A HADDAM NECK TOPIC: VII-1. A, Isolation of Reactor Protection System From Non-Safety Systems, Including Qualification of Isolation Devices I. INTRODUCTION Non-safety systems generally receive control signals from the-reactor protection system (RPS) sensor current loops. The non-safety circuits are required to have isolation devices to insure the independence of the RPS channels. Requirements for the design and qualification of isolation devices are quite specific. Recent operating experience has shown that some of the earlier isolation devices or arrangements at operating plants may not be effective. The objective of our review was to verify that - operating reactors have RPS designs which provide effective and qualified isolation of non-safety systems from safety systems to assure that safety systems will function as required. II. REVIEW CRITERIA The review criteria are presented in Section 2 of EG&G Report 0045J, " Isolation of Reactor Protection System from Non-Safety Systems." III. RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid duplication of effort since some aspects of the review were performed under related topics. The related topics and the subject matter are identified below. Each of the related topic reports contain the acceptance criteria and review guid-ance for its subject matter. VI-7.C.1 Independence of Onsite Sources VIII-1.A Degraded Grid IX-6 Fire Protection There are no safety topics dependent on the present topic information because proper isolation has been assumed. IV. ' REVIEW GUIDELINES The review guidelines are presented in Section 3 of Report 0045J. V. EVALUATION Based on current licensing criteria and review guidelines, the plant reactor protection system complies with all current licensing criteria listed in Section 2.0 of this report except f6r the following:
... -. ~.... = = - - -.... .a 1. Isolation of RPS monitoring channels from remote meters, the data logger, and/or process recorders does not meet current licensing criteria in the following subsystems: a. Pressurizer pressure b. High Pressurizer Level c. Steam-Flow d. Feedwater Flow ~ e. Steam Generator Level 2. Isolation between the RPS and the following control circuits does not meet current licensing criteria: a. The computer which provides setpoints for reactor trip for variable low pressure also provides output signals to the rod control systems without isolation. b. The Steam-Feedwater Flow Mismatch System provides analog signals to the' steam flow controller, the feedwater flow controller and the steam generator leve: controller without isolation. VI. CONCLUSION The staff's position is that suitably qualified isolators should be provided for exceptions 1 and 2 noted above. 0 + r-. ,a, w, -}}