ML20206M508

Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation

ML20206M508
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/15/1986
From:	Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20206M505	List: ML20206M501 ML20206M508 ML20206M515
References
NUDOCS 8608210239
Download: ML20206M508 (4)

Text

-

CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in.the Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 1964, for the Big Rock Point Plant be changed as described in Section I below:

I. Changes A. Change specification 6.1.2.1 to read as follows:

" Source Range Monitor Channel - Channels.6 and 7 shall provide logarithmic neutron flux level and period information from source level to seven decades above source level, without moving detectors

-10 to 10-3% of rated power). The principal (approximately 10 components in each channel shall be a neutron detector, current pulse amplifier, source range monitor instrument, log count rate meter, log count rate recorder and period meter. Gas-filled Boron-10 lined proportional counters with a sensitivity of approximately 12 counts /nv shall be used as detectors. Provisions shall be made for remotely positioning the detectors. By moving the detectors away from the midplane of the core, their effective range may be extended. A short period on either channel shall be annunciated in the control room."

B. Change specification 6.1.5(c) to read as follows:

"Both source range monitor channels shall be OPERABLE and measuring <

flux from the core during reactor start-ups, prior to the power level at which the intermediate or power range channels become operative. However, if one of the two source range monitor channels become inoperative during the course of start-up and prior to the power level at which the intermediate or power range channels become operative, then it will be permissible to hold the i control rod pattern and power level attained until both channels i are again OPERABLE."

C. Change specification 6.1.5(f) to read as follows:

"During POWER OPERATION in-core flux monitors shall be operating to e insure that local heat flux limits specified in Section 5.2.1 are i not exceeded."

D. Change specification 6.1.5(h) to read as follows:

" Minimum .aclear instrumentation in operation during SHUTDOWN operation shall be tha same as that required for REFUELING 8605210239 86091S

! PDR ADOCK 05000155 p PDR

TSOB0786-0123-NLO4

2 OPERATION, except that only one source range monitor channel shall be required."

E. Change the first paragraph of specification 7.3.2(d) to read as follows:

"The source range monitor shall indicate a minimum of three counts per second with a eignal-to-noise ratio of 3 to 1. This will be accomplished by withdrawing the proportional counter to a region of lower flux and observing ti.e reduction in count rate."

F. Change the first sentence of specification 7.3.2(d)(i).to read as follows:

" Prior to the first start-up after development of the low source strength condition, a critical approach (es) with the reactor vessel head off shall be performed to evaluata the source range monitor response and the control rod withdrawal sequence."

G. Change specification 7.3.2(d)(ii) to read as follows:

" Evaluation of source range monitor responses during the head-off critical approach (es) shall demonstrate that, by the time the estimated k of the core reaches 0.995, each source range monitor isreadingIbleast3cpswitha3to1 signal-to-noiseratio."

H. Change the last sentence of specification 7.3.2(d)(iii) to read as follows:

" Normal start-up may continue any time source range monitor count rate is at least 3 counts per second with a minimum signal-to-noise ratio of 3 to 1."

-I. Change the first two sentences of specification 7.3.2(e) to read as follows:

" Critical approaches shall be monitored using source range monitors. The start-up rate shall be restricted to demonstrate that the CIC picosameters overlap the source range monitors at about 10-5% indicated full power on the picoammeters is normal and satisfactory for control and safety purposes before continuing further into the power range."

l J. Change the first sentence in specification 7.3.5(e) to read as follows:

"A minimum of one source range monitor channel and one power range l channel shall be left in operation."

K. Change specification 7.4(a) to read as follows:

i

! " Detailed written procedures shall be available prior to each refueling outage."

TS0B0786-0125-NLO4 2

3 l L. Change specification 7.4(b)(iii) and the paragraph following it to read as follows:

(iii) " Insertion of new bundles in vacant positions as desired.

Shutdown margin verifications and subcriticality checks shall be made as required by Section 5.2.5. Assembly replacement shall proceed as described above until the desired number of fuel

, assemblies have been changed."

M. Change the third paragraph of specification 7.4(c) to read as follows:

"In addition, both source range monitor channels shall be in service and measuring neutron flux during all REFUELING OPERATIONS."

II. Discussion Consumers Power Company is replacing the source range out-of-core neutron monitoring instrumentation during the next scheduled refueling outage at Big Rock Point. This instrumentation is being replaced because of the limited availability of replacement parts and the high expenditure of maintenance hours to keep the existing equipment in operation.

The new instrumentation is a member of the General Electric Company's NUMAC series of microprocessor based instrumentation. The Nuclear Regulatory Commission has been previously requested to review this series of instrumentation as a standard design on the lacrosse docket (No. 50-409) by their February 6, 1986 letter.

This instrumentation is functionally equivalent to the existing instrumentation. A system description and block diagram of the instrumentation is enclosed as attachments 2 and 3 respectively. This changeout will include replacement of the entire source range monitoring system with the exception of the detector. Consumers Power Company has performed a 10CFR50.59 review of this modification and has determined it not to be an unreviewed safety question.

As a result of this modification administrative type technical specification changes are required to reflect the features and terminology used with the new instrumentation. All of the proposed changes requested are in this category except proposed changes C., K.

and L. Proposed change C. corrects the reference to the section where local heat flux limits are specified. Proposed change K. replaces the word operation with the word outage to more explicitly identify when procedures are to be available. Proposed change L. deletes the redundant statement of the requirement to perform shutdown margin checks. Also, in all proposed changes where technical specification definitions have been used they have been capitalized as is the practice i in standard technical specifications.

i TS0B0786-0125-NLO4 l

l I

4 III. Analysis of No Significant Hazards Consideration All of these proposed changes are administrative in nature and neither add new requirements nor delete existing requirements. Most of these changes are being requested to reflect the features and terminology used because of the change out of existing out-of-core source range neutron monitoring instrumentation with functionally equivalent equipment which exhibit improved operating characteristics and availability of spare parts. Two of the proposed changes correct typographical errors and one proposed change clarifies intent by more explicitly identifying when refueling procedures are required to be available.

Because they are administrative in nature, these proposed changes do not increase the previously evaluated probability of occurrence or consequences of an accident or malfunction of equipment important to safety, do not create the possibility of an accident or malfunction of a different type than those previously evaluated, and do not reduce the margin of safety as defined in any technical specification basis.

Therefore, these proposed changes do not involve a significant hazards consideration.

IV. Conclusion The Big Rock Point Plant Review Committee has reviewed th's Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY l

By .

RMeWlt't,'Vice President Energy Supply Services r

Sworn and subscribed to before me this 15th day of August 1986.

Y Elaine E Buehrer,\ Notary Public l Jackson County, Michigan

! My commission expires October 31, 1989 l