ML20114B637

Forwards Revised Version of FSAR Table 14.2-82, Power Reactivity Coefficient Measurement & Corresponding Revs to App a Writeup on Extent of Compliance W/Reg Guide 1.68. Approval of Changes Requested by 850124

ML20114B637
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	01/21/1985
From:	Tramm T COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
9660N, NUDOCS 8501290384
Download: ML20114B637 (4)

Text

.[ 'N Commonwealth Edison

/ ) one First Hitional Plaza. Chicago. Illinois (O 7 Address Reply to: Post Office Box 767 q,/ Chicago, Illinois 60690 January 21, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission

. Washington, DC 20555

Subject:

Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Start-Up Tests NRC Docket Nos. 50-454/455 and 50-456/457

Dear Mr. Denton:

This letter provides advance copies of revised pages for the Byron /Braidwood FSAR. These pages describe modifications to the initial test program. It appears that NRC review of these changes is required by Condition C(3) of the Byron 1 Operating License, NPF-23. Approval of these changes is needed by January 24, 1985 to support the current pre-test review schedule dictated by Condition B in Attachment 1 to the Operating License.

Enclosed is a revised version of FSAR Table 14.2-82, " Power Reactivity Coefficient Measurement " and the corresponding revisions to the Ap endix A writeup on the ex, tent of compliance with Regulatory Guide 1.68. Th'ese changes reflect vendor-recommended changes in the testing methodology. The power reactivity coefficient verification factor will be checked because that is the only parameter available.

These revised pages will be incorporated into the FSAR at the earliest opportunity. Advance copies were telecopied to the NRC on January 15, 1985. Please contact this office if there are questions regarding this matter.

One signed original and fifteen copies of this letter and the attachment are provided for NRC review.

Very truly yours, f /Zefvfdhw%

T. R. Tramm Nuclear Licensing Administrator 1m Enclosure 8501290384 850121 PDR ADOCK 05000454 s P PDR, T 9660N g

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TABLE 14.2-82 POWER REACTIVITY COEFFICIENT MEASUREMENT (Startup Test)

Plant Condition or Prereauisites During power level changes at approximately 30%, 50%, 75%,

and 90% reactor power.

Test Objective vwi99 To actermine the power coe f ficient of reactivity. and-p<wn d;fcet, Test Summary During power level changes when the reactivity effects of xenon can be adequately accounted for, measurements will be made of reac* : power and associated reactivity changes as follows:

Reactor thermal power will be determined using calo-rimetric data. Associated reactivity changes will be measured by reestivity computer-resperise er.d the

. response of Tavg and delta T. recorders, The power coefficient of reactivity :.d power defect will be determ)ined vwift<. from these measurements.

Acceptance Criteria .g hof The power reactivity coef ficient 41s within values-ased-in. limds d 17 Sub ceticr. 4. 3. 2. 3. 5 cr.d - in--agr4ement-wi-th '

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REGULATORY GUIDE 1.68 Revision 2, August 1978 INITIAL TEST PROGRAMS FOR WATER-COOLED REACTOR POWER PLANTS The Applicant complies with this regulatory guide, as described in Chapter 14.0, with the following exceptions: ,

Appendix A.4.t, states " Performance of natural circulation tests of the reactor coolant system to confirm that the design heat removal capability exists or to verify that flow (without pumps) or temperature data are compatable to prototype designs for which equivalent tests have been successfully completed (PWR)."

As described in the Byron SER the Applicant will be referencing the natural circulation testing which will be performed at Diablo Canyon. A preliminary assessment of differences between Byron and Diablo Canyon that may affect boron mixing under natural circulation has been provided and indicates that the Diablo Canyon test results and supporting analysis would satisfy the necessary requirements for Byron. If the tests at Diablo Canyon are not completed or the test results are unsatisfactory, the Applicant will perform such tests prior to startup after the first refueling for Byron. Additionally, simulator training for Byron reactor

((pgogk operators includes natural circulation procedures training.

Ahb4U Appendix A.S.h states " Check rod scram times from data recorded y

-]((ypd[#1duringscramsthatoccurduringthestartuptestphasetodeter-mine that the scram times remain within allowable limits."

f,Mi During power ascension testing, the Applicant does not intend to formally instrument the rod position indication system for reactor trip review purposes because this would require reiaoval of the rod position indication from service. This would be a violation of Technical Specifications. For this reason the Appli-cant believes that this requirement applies to BWR's only.

Appendix A.5.j states " Verify that plant performance is as expected for rod runback and partial scram."

The Applicant asserts that these particular events are applicable to BWRs only, and therefore will not be performed at Byron.

Appendix A.S.gg states "If appropriate for the facility design, conduct tests to determine operability of equipment provided for anticipated transient without scram (ATWS), if not previously done (25%) . "

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