ML20196G829

Forwards Request for Addl Info Re Util 871109 Tech Spec Change Request Reflecting Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation Described in GE Topical Rept NEDO-31399

ML20196G829
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/07/1988
From:	Scott W Office of Nuclear Reactor Regulation
To:	Berry K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TAC-66655, NUDOCS 8803100002
Download: ML20196G829 (3)

Text

O O Docket No. 50-155 E 7 1988 Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON POWER RANGE MONITORING INSTRUMENTATION - BIG ROCK POINT (TAC 66655)

Consumers Power Company submitted a Technical Specification Change Request for the Power Range Monitoring Instrumentation on November 9, 1987. The changes reflect the features and terminology used with new out-of-core power range nuclear instrumentation as described in GE topical report NE00-31399, the Nuclear Measurement Analysis and Control DC Wide Range Monitor (NUMAC-DCWRM).

Based on the staff review of your submittal, which includes the above topical report, the staff has concluded that there is not sufficient information available to complete its rev:ew of the change request for the power range monitoring instrumentation. As a result, the staff has enclosed a request for additional information related to this submittal. To facilitate completion of our evaluation, we request that you give this matter appropriate priority.

The request in this letter affects fewer than ten respondents; therefore OMB clearance is not required under PL 96-511.

Sincerely, Orit ic:l s?;nd by Wayne E Scott Jr., Project Manager Project Directorate III-1 Division of Reactor Projects, III, IV, V

& Special Projects

Enclosure:

As stated cc/w enclosure:

See next page

DRSP p, N

0RSP

' SCOTT MV}1:

IRGILIO 3/[/88 3/ 'it/88 DISTRIBUTION Docket. File. EJordan PD31 Gray File JPartlow NRC & Local PDRs ACRS (10)

GHolahan RIngram W5cott OGC 8803100004 080307 PDR ADOCK 05000155 P PDR

1. p %q\ UNITED STATES

! NUCLEAR REGULATORY COMMISSION

{ waswiwovow o.c.rosos N e ...e*

REQUEST FOR ADDfTIONAL INFORMATION ON THE NUCLEAR MEASUREMENT ANALYSIS AND CONTROL DC WIDE RANGE MONITOR (NUMAC-DCWRM)

BIG ROCK POINT PLANT DOCKET NO. 50-155 We have reviewed the reactor protection system modernization as discussed in the licensee's submittal dated November 9, 1987 for the Big Rock Point Plant. As a result of our review of the documentation provided thus far, the following questions have been identified which require a formal response in order for our review to be completed.

1. New instrument racks and indicators in the control room have been installed. New cables have been installed from the sensors to the new instrument racks and to the new indicators in the control room. Provide a detailed description of the separation criterion for the new cables and equipment and its conformance to Regulatory Guide 1.75 and IEEE-STD-384.

Compare this separation criterion to that currently utilized in the plant.

2. After reviewing the NUMAC-LRH System (Topical Report NEGO-30883), it is the staff's understanding that the NUMAC-LRM is a single-channel instrument designed to be an exact replacement for Log Rad Monitors in existing systems.

However, when used for safety related system application, it should conform to IEEE Standard 279-1971. Describe the conformance of the NUMAC-DCWRM system to IEEE Standard 279-1971 requirements for a protection system application. Although the mechanical design of this instrument permits it to replace several other neutron flux monitoring instruments in a single I chassis, it should not compromise the channel separation requirements.

3. Provide a detailed description of the isolation devices used between separation groups and between safety and non-safety system. Provide a l detailed description of design criteria, tests performed and test results I for all isolation devices utilized.

4. Provide a description of the design prccess and the design verification and validation steps utilized in the development of the software utilized i for the updated neutron monitoring system.

5. Identify any major difference in hardware and software development between NUMAC-DCWRM system and NUMAC-LRM system (Topical Report NEDO-30883).

6. The NUMAC-DCVRH system was designed for use in control room or similar environments, not in "harsh" environments. Provide plant specific infonnation that will assure that the NUMAC-DCWRM instrument will be operating within the environmental qualification limit.

L_------_-----__--__--

1 4

7. Provide equipment qualification information on the detectors (gamma l

' compensated ion chamber) and the interface requirements with the  !

NUMAC-DCWRM system. l

.i

8. As described in the licensee's submittal Attachment 2 (Power Range Monitor System Description), Power Range Monitor trip contacts are connected to Reactor Protection System Channel 1 and Channel 2. Provide 1 an electrical schematic diagram that illustrates that the channel separation and channel independence are preserved in this arrangement. ,

f l

4 I

i

I t

1 l i

i l t I i t

t a  :

i

. t j i

i j t i

[

l l

4  !

I t l I 1 i t