ML20033F119
| ML20033F119 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/14/1990 |
| From: | Eddy J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-101, REF-GTECI-NI, RTR-NUREG-CR-5112, TASK-101, TASK-OR GL-89-11, NUDOCS 9003160050 | |
| Download: ML20033F119 (5) | |
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,s Consumers Power rewmemE MKMEAWS NIOERES$
Generet offices: 1946 West Pernell Road, Jockeori, MI 49201. (617) 78s o550 February 14, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
RESPONSE TO GENERIC LETTER 89 B01 LING WATER RFACTOR WATER LEVEL REDUNDANCY Generic Letter 89-11 dated June 30, 1989 provided the staff's resolution of Generic Issue 101, " Boiling Water Reactor Water Level Redundancy". The attached document to the letter, NUREG/CR-5112. " Evaluation of Boiling Water Reactor Water-level Sensing Line Break and Single Failure", provided the staff's technical basis for their conclusions. As part_of the letter, the staff requested licensees to review the information to verify that the design of its facility had been correctly represented.
Consumers Power Company has reviewed NUREG/CR-5112 and the changes to the document contained in the Errata Sheet and is providing the following comments.
Section 3.2 of NUREG/CR-5112 describes the sensing line arrangement of Big Rock Point (BRP) as that shown in Figure 1 to that report, which is not correct. Although not exact, Figure 2 is more typical of the Big Rock Point arrangement.
It also must be noted that the reactor vessel instrumentation is not utilized for feedwater control. Big Rock Point utilizes a steam drum. Level instrumentation off the steam drum is used for feedwater control. The arrangement for the level instrumentation is shown on the attached drawing. Reactor vessel level is obtained from Level Elements LE-RE09 A, B, C, D and steam drum level, for purposes of feedwater control, from Level Elements LE-ID25B or LE-lD25A, Based upon arrangement errors discussed above, the evaluation summary in 3cetion 4.1 may also contain some inaccuracies.
Breaks in vessel level instrumentation have no effect on feedwater operation. However, breaks in either the reactor vessel or steam drum Icvel sensor lines combined with an additional single failure could prevent the ADS (RDS at BRP) from automatically actuating.
9003160050 900214 I
ADOCK 0 % Q5 o
DR OC0190-0251-NLO4
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Nutlear Reguist-iry Comunission 2
Big Rock Point Plant
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Response to Cle89-11 February J4, 1990 I
Although the Big Rock Point design does differ from the arrangements described in the NUREG, Consumers Power Company concludes that these differences would not affect,the conclusions of the evaluation. Due to the differences in level' detection schemes at BRP, it would be difficult to place BRP into any of the five ;;roups presented in the report.
i These comments are supplied to the NRC as information only and review or-response is not requested.
Nitkh e
J Daniel Eddy Plant Licensing Engineer j
CC.' Administrator, Region 111, USNRC NRC Resident inspector - Big Rock Point Attachment-I OC0190-0251-h104' c
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