ML18087A946

Comments on NRC 820722 Draft Safety Evaluation of SEP Topic VI-10.A, Testing of Reactor Trip Sys & Esfs,Including Response Time Testing. Tables Showing Reactor & ESF Trip Parameters Encl

ML18087A946
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/08/1982
From:	Cagnetta J, Counsil W CONNECTICUT YANKEE ATOMIC POWER CO.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-06-10.A, TASK-6-10.A, TASK-RR A02679, A2679, NUDOCS 8211160422
Download: ML18087A946 (2)

Text

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• CiNNECTICUT YANKEE ATOMIC POWER COMPANY

• Tst.&PMONI 2os-eee-e1m B E R. L I N , . C 0 N N EC T I C UT P.O. *OX Z70 HAltTl"OIU). CONNECTICUT oetOI Nov.ember 8~ 1982 Docket No* .50-213 A02679 Director of Nuclear Reactor Regulation Attn: Mr. Dennis M. Crutchfield, Chief

. Operating Reactors ~ranch 115 ....

U.S. Nuclear Regulatory Commission

, Washington, D.C. 20555

References:

- (1) D. M. Crutchfield letter to W. G. Counsil, dated

. July 22, 1982.

(2) W. G. Counsil lette'r to D. M. Crutchfield, dated February 1, 1982.

Gentlemen:

Haddam Neck Plant SEP Topic VI-IO.A, Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing Referenc;:e (1) forwarded" the Staff's draft Safety _Evaluation Report for SEP

. Topic Vl-10.A, Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing, for the Haddam Neck Plant. Connecticut Yankee Atomic Power Company (CYAPCO) ~as reviewed Reference (1) and offers the following comments.

Section 3.1, "Description" The table listing the Reactor Trip System parameters and their channel logic is incomplete. Table A, attached, identifies all Reactor Trip System parameters and the required trip logic at various power levels.

Section 3.2, "Evaluation", Item 1 The Staff states that the Haddam Neck RPS is not tested for automatic or manual actuation during reactor operation. This is incorrect, as the main': ~

protective device in the RPS, the variable low pressure tr,!p calculator, is tested' . p , o *

• 91. .

every six weeks coincident with the six week pressurizer surveillance test. The ~

automatic and manual reactor trip systems are tested during refueling and start-

. up, respectively.

Section 3.2, "Evaluation", Item 2 Section 4.1 of the Haddam Neck Technical Specifications states the purpose of 9211160422 821108 PDR ADOCK 05000213 p PDR

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surveillance requirements and the basis for surveillance frequencies for two categories of systems (i.e. - systems in continuous operational use and systems infrequently used). Section 4.1 does not provide the surveillance frequencies

• themselves.

• The surveillance requirements for all il'.IStJ:"Ument channels in*

continuous operational use are specified in table 4.2-1 of *the Technical Specifications. This information was provided to the Staff in Table 1 of Reference (2).

Section 3.2, Evaluation", Item 3 Testing of the manual trip circuitry during J:"eactor .operation would result in a

reactor. t~ip. Therefore, this test is only conducted during start-up in accordance with operating procedures. :

The* pressurizer pressure channel° is included in Table 4.2-1 of the Technical Specifications, although this is not listed in Table. 4.2.1 as "Pressurizer L9w.

Pressure", .but rather as "Pressurizer Pressure". This channel is required to 'be checked, calibrate9, and functionally tested as stated in Table 1 of Reference (2).

A channel check, <:~libration, and functiofla.L test for the high steam flow isolation valve trip (also referred to as the main steam line isplation valve trip) are not required by the Technical Specifications, however these tests are conducted in accordance with plant operating procedures as stated in Table 1 of Reference (2).

Section 3.2, "Evaluation", item 5 The Standard Technical Specifications (STS) for Westinghouse reactors refers to

• a "Loss of Flow" trip in Table 3.3-1. This is equivalent to the "Reactor Coolant Flow" trip listed in Table 4.2-1 of the Haddam* Neck Technical Specifications, and the "Loss of Flow" trip listed in Table 1 of Reference (2). . .

' . . . t Section 3.2, "Evaluation", Item 6 '

No functional test is performed on the Steam-Feedwater Flow Mismatch and Low Steam Generator Water Level channels since these are arranged in a "

matrix. A functional test would, therefore, result in a reac~or trlp.

Table 1 The Overtemperature /:AT and Overpower A.T trips do not exist at the Haddam.-'.

Neck Plant. Also, as noted above, Table 4.2-1 of the Hcuidam Neck Technical '

Specifications gives requirements for the calibration, channel check, and functional test of the "Loss of Flow" trip.