ML20003B095
| ML20003B095 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/05/1981 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.2, TASK-2.K.2.10, TASK-TM 1R-0281-01, 1R-281-1, NUDOCS 8102100348 | |
| Download: ML20003B095 (2) | |
Text
f r.
L'.
',1 7.
~
[s "" '
~:
r
~
~/'
L/
d o
ARKANSAS POWER & LIGHT COMPANY
{
POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 February 5, 1981 1R-0281-01 Director of Nuclear Reactor Regulation ATTN:
Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Comnission Washington, D.C.
20555
Subject:
Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Anticipatory Reactor Trip System (ARTS)
(File:
1511.1, 1510)
Gentlemen:
Your letter of January 21, 1981 requested information concerning the subject system. Responses to your concerns are given below.
Concern:
1.
For evaluation of the action statement of Paragraph 3.5.1.7/3 (Page 42A of the proposed changes to the Tech Spec), the following infor-mation should be provided (See Standard Tech Spec Table 3.3-1) for each of the two ARTS.
(a) Total No. of channels (b) Channels to trip (c) Minimum channel OPERABLE (d) Applicable modes
Response
ANO-1 does not utilize Standard Technical Specifications.
Because the ARTS can be bypassed during power operation, as discussed in response to Item 2 below, the ARTS cannot be included in present Technical Specifi-cation Table 3.5.1-1.
The total number of channels and channels to trip are given in AP&L's letter dated August 8, 1980, which described the ARTS. Technical Specifications 3.5.1.7.1 and 3.5.1.7.2 specify appli-cability.
AooL b
81021 o 03W
/o MEMBEF4 MiOOLE SOUTH UTIUTIES SYSTEM
1 Concern:
2.
Paragraph 3.5.1.7 (Page 42A) has trip bypass up to 10% reactor power whereas August 8,1980 submittal calls for up to 20% reactor power bypass. Correction should be made.
Response
4 The August 8,1980 submittal calls for a bypass up to 20% reactor power.
Because the discussion centers on the reactor trip on loss of Main Feedwater, the letter should call for a bypass up to 10% reactor power, as given in proposed Technical Specification 3.5.1.7.1.
The bypass up to 20% reactor power is still correct for the reactor trip on turbine trip, as given in proposed Technical Specification 3.5.1.7.2.
Concerni 3.
Surveillance requirement Table 4.1-1, Item 36 and 42 (ARTS) should have functional test every month and calibration test on refueling outage (See ANO-1 letter, dated August 8,1980).
Response
Proposed changes to the Technical Specification have been made and submitted to NRC by AP&L's letter dated January 29, 1981.
Very truly yours,
. i Uv'24YY-A David C. Trimble Manager, Licensing DCT: MAS:nak D
l l
l l
l t.