ML20030A472

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Informs That Startup Neutron Sources to Be Replaced & Cobalt Rods in F-type to Be Replaced W/Nonfueled Test Rods During Mar Outage
ML20030A472
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/26/1974
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Oleary J
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101090605
Download: ML20030A472 (9)


Text

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Docket 50-155 Mr. John F. O' Leary c'

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',k ' 4 d Director of Licensing 42 Big Rock Point US Atomic Energy Commission ' 6 Washington, DC 20545

Dear Mr. O' Leary:

This letter has been written to inform you of two reactor components to be changed during the March outage at Big Rock Point.

The start-up neutron sources will be replaced by neutron sources of essentially the same design; and eight (8) cobalt rods in the F-type fuel vill be replaced with nonfueled test rods.

A layer of light gray crud was found lying on the baffle plate next to the reactor vall during the March 1973 refueling outage.

A sample weighing approximately two grams was sent to General Electric Vallecitos Laboratory for analysis. A crud sample was analyzed to be 99% beryllium oxide with traces of titanium, iron and copper.

Since no failure of the pin type sources was noted during fuel inspection and no antimony was present in the crud sample, it was concluded that beryllium was leaking from at least one of the beryllium cylinders of the start-up neutron sources. As both neutron sources were manufactured at the same time from the same materials, it was decided to replace both start-up neutron sources.

The new neutron sources were manufactured by Battelle Memorial Laboratories in Columbus, Ohio. The neutron source design is shown in the attached Battelle Drawing 785-001. Tv; unirradiated antimony pins (gamma sources) are being procured at the same time.

It is planned to replace both neutron sources and reinstall the activated antimony pins from the original neutron sources. The gamma source hold-down device has been modified to provide a means of irradiating a new antimony pin while utilizing the new neutron sources.

(See Drawings 785-012 and 785-014.) One of the original antimony pins vill be removed from the reactor and a new antimony pin will be inserted into the neutron source during the July-August 1974 refueling outage. The second antimony pin vill be replaced during the succeeding refueling outage. This course of action vill ensure adequate neutron source strength throughout the changeover from the original neutron sources to the new neutron sources.

CG00 SLd24070604~

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Mr. J'ohn F. O' Leary 2

- Big Rock' Point March 26, 197h

' The cobalt corner rods of sixteen (16) F-type (9 x 9) fuel assemblies will be replaced by nonfueled corner rods. The cobalt is being

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removed primarily from.the peripheral fuel assemblies to increase the power generation in that region. _ As a result, an overall power flattening is expected which will improve the response of the Big Rock Point Plant

' to a Loss of Coolant Accident.

The corner rod test program will begin when eight (8) advance corner rods replace eight (8) cobalt rods during Cycle 12.

The remain--

ing fifty-six (56) corner test ' rods will be utilized when appropriate while maintaining Technical Specifications limits.

The infinite multi-plication factor (k.) of irradiated F-type fuel assemblies after the

.eplacement of the cobalt corner rods will not exceed the peak k. (1.155 assuming equilibrium xenon and samarium) that occurs at approximately 3500 mwd /T exposure.

The nonfueled corner rods will contain experiments developed by The General Electric Company to improve fuel performance.

All re-placement corner rods will be filled with either test capsules, solid 2ircaloy bars or mandrels which will prevent the Zircaloy cladding from collapsing beyond tolerable limits to prevent coolant channel blockage and local flux peaking. A brief description of each test rod type follows:

1.

Oxidation Rati test rods will contain several sealed capsules to obtain data on the oxidation rate of Zircaloy-2 at low partial pressure.

3.

Coating Stability test rods will contain several sealed capsules to obtain data on the irradiation stability of various tubing,

'd, surface coatings.

3 Mechanical Test specimen Carrier test rods will be similar to those previously irradiated in B-type fuel assemblies and in the corner pon'.tions of E-and E-G-type fuel assemblies.

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Creep test rods will be sealed tubes containing a stlid Zircaloy-2 mandrel to provide support in case of collapse of the outer tubing.

Calculations and previous irradiation experience indicate that the creep collapse strains will be in S 2-3 mils after three years of reactar exposure.

5 Corrosion test -rods manufactured from tubing of differing chemistries within Zircaloy-2 specification limits with nominal 0 563 in OD.

These test rods will contain a solid Zircaloy-2 bar for support of the external cladding to prevent collapse.

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Mr. John F. O' Leary 3

Big Rock Point March 26, 1974-6.

Irradiation Growth test rods will be nominally 0 563 in OD Zircaloy-2 tubing. Holes will be drilled through the cladding wall at the top and bottom of the rods to allow water accesc to

~ the inside of the rods. An internal mandrel vill oe provided displacing the coolant to limit local peaking.

The thermal hydraulic characteristics of the Reload-F fuel with cobalt rods replaced by corner test rods are essentially identical to standard Reload-F fuel. The only differences are the differences in local power distribution which will be limited to a local peak-to-average ratio of less than 1.23 (Attachment 1).

These bundles will be placed in core positions having low radial power factors to compen-sate for the higher local peaking. C.,nsequently, the bundle steam quality will be reduced, resulting in greater thermal margins to the MCHFR limits established in BRP Technical Specifications.

Physics and thermal hydraulic analysis will be performed on the reactor core to insure that all license limits are met.

We have concluded that the use of the Reload-F fuel assemblies utilizing corner test rods or the replacement of the neutron sources in the manner described does not involve any change in hazards considera-tion. We have further concluded that neither the replacement of the cobalt corner rods with the test rods as described above nor the replace-ment of the original neutron sources as described above do not require a change in the Big Rock Point Technical Specifications.

Yours very truly, l

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RBS/mel Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler USAEC l

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TABLE 1-

' Local Power Listribution-(Approximately 10,000 mwd /T Exposure)

(Octant-Symmetry)

- With Cobalt 1.149 0.894 0 903 0.819 0 798 1

- Without Cobalt 1.124 0.869 0.869 0.782

- 0.760 4-With Cobalt 1.168 0.914 0 926 0.840

- Without Cobalt 1.15h 0.896 0.896 0.805

- With' Cobalt 1.041 0 982 1.011

. Without Cobalt 1.064 0 988 0 995 With Cobalt 1.127

-1.118 Without Cobalt !

- 1.226 1.167 With Cobalt 0

Without Cobalt 0

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AEC DIi IBUTION FOR PART 50 DOCKET MAT iAL 2660 (TEMPORARY FORM)

CONTROL NO:

FILE: DTC).

FROM:

DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Co sumers Power Company Jackson, Mich. 49201 Mr. R.B. Sewell 3-26-74 3-29-74 X

TO:

ORIG CC OTHER SENT AEC PDR XXX J.F. O' Leary 1 signed CLASS UNCLASS PROP INFO INPUT NO CIS REC'D DOCKET NO:

XXX 40 50-155 DESd.. 'YTION :

ENCLOSURES:

Ltr furn information concern two reactor Table 1 - Local Power Distribution components to be changed during the March Drawing #785-001 outcge......trans the following.....

  1. 785-012
  1. 785-014 Sheet 1 of 2 Sheet 2 of 2 PLANT NAME:

Big Rock Point (40 cys es enc 1 ree'd)

FOR ACTION /INF0FJ'ATION 3-29-74 JB BUTLER (L)

SCWENCER(L)

VZIDIANN(L)

REGAN(2)

W/ Copies W/ Copies W/TCopies W/ Copies CLARK (L)

STOLZ(L)

DICKER (E)

ACKNOWLT rD W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)

VASSALLO(L)

KNIGHTON(E) g y { { 'j {,i(I ]

W/ Copies W/ Copies W/ Copics W/ Copies KNIEL(L)

SCHD:EL(L)

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INTER':AL DISTRIBUTION I C @ G FILIP TECH REVIEW DENTON A/T IrD AEC PDR HENDRIE CRIMES LIC ASST BRAITMAN

' d GC, ROOM P-506A SCHROEDER GAMMILL

/DIGGS (L)

SALTZMAN B. N MUNTZING/ STAFF MACCARY KASTNER GEARIN (L)

CASE KNIGHT BALLARD COULBOURNE (L)

PLANS GIAMBUSSO PAWLICKI SPANGLER LEE (L)

MCDONALD BOYD SHAO MAIGRET (L)

DUBE w/ Input N00RE (L)(BWR)

STELLO ENVIRO REED (E)

FO DEYOUNG(L)(PWR)

HOUSTON MULLER SERVICE (L) d KOVHOLT (L)

NOVAK DICKER SHEPPARD (L)

C. M M S B. KEG P. COLLINS ROSS KNIGHTON SLATER (E)

DENISE IPPOLITO YOUNGBLOOD SMITH (L)

A EG OPR TEDESCO REGAN TEETS (L)

FILE & REGION (3)

LONG PROJECT LDR WADE (E)

WILLIAMS (E)hh

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MORRIS LAINAS kr l

STEELE BENAROYA HARLESS WILSON (L) g y VOLIEER U I fl I_

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EXTERNAL DISTRIEUTION

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  1. 1 - LOCAL PDR_.'.Charlevn_fw-'

(1)(2X10). NATIONAL LAB'S 1-PDR-SAN /LA/NY Mieh-4 - DTIE(ABERNATHY)

/1'- NSIC(BUCHANAN) 1-ASLBP(E/W Bldg,Rm 529')

1-GERALD LELLOUCHE 1 - ASLB(YORE l-W. PENNINGTON, Pan E-201 GT BROOKHAVEN NAT. LAB 1-CONSULTANT' S 1-AGMED(Ruth Cussran)

/16 - CYS ACRS 312Dl$ Sent to Diggs NEWMARK/BLUME/AGBABIAN RM-B-127, CT.

3-29-74 1-CERALD ULRIKSON...ORNL 1-RD.. MULLER..F-309 T