ML20246E528

Forwards Plant Boraflex Surveillance Program Rept,For Info. W/Certificate of Svc

ML20246E528
Person / Time
Site:	Saint Lucie
Issue date:	08/22/1989
From:	Bauser M FLORIDA POWER & LIGHT CO., NEWMAN & HOLTZINGER
To:	Moore T, Rosenthakl A, Wilber H NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
CON-#389-9085 OLA, NUDOCS 8908290163
Download: ML20246E528 (26)

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= ora MrrvEo oc Thomas S. Moore, Chairman' Howard A. Wilber LAtomic Safety'and Licensing

. Atomic Safety and Licensing Appeal Board _

Appeal Panel Atomic. Safety and Licensing U.S. Nuclear Regulatory Appeal' Panel-Commission l

'U.S.. Nuclear Regulatory Washington, D.C.

20555 Commission.

Washington, D.C.'

20555_

i Alan S'. Rosenthal Atomic.' Safety'and-Licensing

' Appeal Panel U.S. Nuclear Regulatory Commission

. Washington, D.C.

20555 Re:

In the Mctter of Florida Power and Light Company (St. Lucie Plant, Unit No. 1)

Docket No. 50-335-OLA

. Dear Members of the Appeal Boards Enclosed, for your information, is a copy of the first St. Lucie 1 Boraflex surveillance progre.m report (without Appendix).

The Boraflex' surveillance program is discussed at

pages'22-25 of.the Licensing Board's May 9, 1989 " INITIAL DECISION'(Authorizing Spent Fuel Pool Reracking)," below.

As summarized on page two of the July 28, 1989 letter to Mr. Weinkam

'from Dr. Turner, forwarding the report: " Based upon the measurements made, no significant degradation or change in j

gB290163890822 b-

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ADOCK 05000335 (7

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PDR J

4-NewxAw & HoLTztworn, P. C.

Atomic Safety and' Liceas!.r.g Appeal Board August 22~, 1989 Page 2 physical properties of the surveillance coupon were observed other than the expected shrinkage and increase in density and hardness."'

Sincerely, Michael A. Bauser Enclosure ec:

Service List l

l.'

. nh.

b-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMM3SSION BEFORE THE ATOMIC SAFETY AND LICEMSING BOARD

)

In the Matter of

)

Docket No. 50-335-OLA

)

FLORIDA POWER'AND LIGHT COMPANY

)

)

l (St.-Lucie Plant, Unit No. 1)

)

(Spent Fuel Pool Expansion)

)

CERTIFICATE OF SERVICE j

I hereby certify that copies of the Letter dated August 22,.1989, to Members of the Appeal Board from Michael A.

Bauser, and Enclosure, were served on the following by deposit in the United States mail, postage prepaid and properly addressed,'

on the date shown below:

Thomas S. Moore, Chairman Atomic Safety and Licensing Appeal Board

. Atomic Safety and Lt. censing Appeal Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Alan S. Rosenthal Atomic Safety and Licensing Appeal Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Howard A. Wilbur Atomic Safety and Licensing Appeal Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555 B. Paul Cotter, Jr. Chairman Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Glenn O. Bright Atomic Safety and Licensing Doard Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555

p

/ry Revision 1 Revision 2 4

4

1.0 INTRODUCTION

AND CONCLUSIONS Efght Boraflex surveillance coupons removed from the St. Lucie Unit i spent fuel pool were removed and physical measurements made, including the followings o Physical Observations and Photographs, o Weight and Dimensional Checks, o Neutron Transmission Tests, o Neutron Radiography, and o Shore A Hardness Tests.

All tests'were performed in accordance with the requirements of FPL Operating Procedure No. 1-0010144, Revision 1 and NUSURTEC Measurement Procedures NPP-92419-1 attached as Appendix A.

l These coupons are the first of the long-term surveillance coupons removed from the St. Lucie Unit 1 spent fuel storage pool.

Two replicate coupons were removed from each of the two regions of the storage racks at two irradiation periods.

The two irradiation periods (92 and 186 days) represent an accumu-lated radiation dose estimated to be 1.4 x 108 and 2.3 x 10' rada respectively.

l The most important measurements characterizing the performance of Boraflex in the storage racks are the length and width (to characterize shrinkage) and neutron attenuation tests (to assure the continued presence of the Boron-10).

Other tests serve a

supporting role to assure that there are no l

previously-unrecognized mechanisms for degradation and to reveal any possible long-term synergistic effects.

i l

Page 1 of 17 l

l 1

Acceptance criteria for performance of the coupons ares o

Shrinkage in length and width equal to or less than

'2c5%,

o Shore A hardness greater than 90%

(once the material.

has become hard), and o

Neutron attenuation indicative of the original B-10 content within 5%.

i None of the-coupons examined showed changes beyond those l

expected and no evidence of degradation was observed.

Neutron attenuation tests were consistent with those of archive samples, confirming there was no loss in boron and no abnor-malities were evident on the neutron radiographs.

Shrinkage was of the order of 1% or less and hardness asasurements showed that the coupons were fully hard (shore A of 100).

Results of the measurements are well within the acceptance criteria and it I

is concluded that the Boraflex absorber in the storage racks have retained their neutron absorption properties (B-10 loading) and are capable of continuing to perform their intended function of controlling reactivity.

The surveillance coupon data are summarized on the following Data Sheets from OP 1-001-144. Rev. 1 and detailed date is presented in Appendix B.

Page 2 of 17

'/

ST. IDC3E UNIT 1 OPERATDG PR03IXJRE NO. 1-0010144, REVISICH 1 ENIT 1 SURVPTTIANCE 'fTRT PROCS* PGt wel.FrFX NI!Dm3i AMMTC

[

Mk2ERIAL CIEEhINED IN THE SPENP FIEL RACES rb i

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Data Data (bal asumamblies Installed O i 1 'd B Regyved Date Data RemCNed coupcm ID bI~I~YI

/4 M A 7!/7!fP9 signature

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Data Dimensions: medS

/4.768

4. F4 6 0.o79 langth wicitn

'I!u.cKness

@ yes lZjno Alternation:

4 7. O +

Acceptable E yes lZ l no 4

Hardness 99 Acceptable @ yes lZl no

% shore A Coupon dry weight 162.92 mmw-ific gravity

/,796 M wtaY.sa - d Ihysical a p mnoe:

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/ % 779 4.886

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amen wuren nucxn s yes I

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Attenuation:

_97.I3 Acceptable Syes lZj no a

Ph 99 W i.able @ yes lZl no t snore A W

mTeri dry weight

/6 6, O / g Specific gravity I.804 Physical appearance:

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Specific gravity

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Data Dimensions: ItJcH E5 14,77/

4.F93 C. O 31 Lengtn wlatn niic* ness

@ yes lZl re Attenuation:

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M+

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Date l'

Di:nensions: J tac 6Es 14,,734

% F66 o.o 78 Imrgtn wicrtn unckness S yes lZl no Attenuation:

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OPDATDC PROCEDURE NO. 1-0010144, REVISICH 1

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UNIT 1 SURVEIIIANCE 'ITST PBCGRAM KR BTAFIZX NEI7IH2i ABEGBDQ MmRIAL Q;NIAINED IN 'IHE SPWT FUEL RACKS 6

4 Jl DATA SHEET 3 INDIVIDUAL C00PCN DA2A SHEEP I

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mte Accep*& le Dimensions: i N e +4 E5

14. 7 b,

1. /.f 6 9 Length wlath h ckness

@ yes lZlno Attenuation:

81.66 Acceptable @ yes lZ l no 4

Hart! ness 9O Acceptable @ yes lZl no t snore A

/* TIf Ceupon dry weight M. 4 5 specific gravity Ma4Y, <m a M u -a 5 L - M.

Physical appearance:

1

%~ K da%wJ.an Ux155 tr Y.s - 2.3 x15 R 24 ya gmy x

UNIT 1 M~dPf0 GRAM PGt BWAFIEX NEITIRN ABSCREDC 9

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mte 18 Dimensions: sucHE5

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0,0 31*

Length wictn m

@ yes lZl no Attenuation:

6l.94 Acceptable @ yes lZ j no 4

Hardness 4%

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hfad.

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2.0 PHYSICAL OBSERVATIONS AND PHOTOGRAPHY l

The surveillance coupons were identified as follows:

I l

Coupon I.D.(18 Exposure time Radiation Dose (2)

R1-1-T1 92 days 1.4 x 109 R1-2-T1 92 days 1.4 x 109 R2-1-T1 92 days 1.4 x 109 R2-2-T1 92 days 1.4 x 109 R1-3-T1 6 Months 2.3 x 109 R1-4-T1 6 Months 2.3 x 109 R2-3-T1 6 Honths 2.3 x 109 R2-4-T1 6 Honths 2.3 x 109 Tree No.

Coupon No.

(23 Region No.

(2)

Calculated from exposure history, power levels and storage i

l time of surrounding fuel assembles.

The samples were mounted in steel casings, spot welded together.

When the welds were carefully cut away and the covers

removed, the exposed coupons were found to be intact f

with no sign of degradation.

Water marks were visible (as expected) but are not considered significant (residue remaining when the water evaporates).

Except for the water marks, the coupons had retained their original black color and the edges were still sharp and well defined.

Photographs of the coupons are attached documenting the observations described above.

Radiation measurements (approximate) showed very low radiation

]

levels (maximum of about 0.1 mR/hr gamma on contact).

l l

Page 11 of 17 j

a 3.0 NEUTRON ATTENUATION AND RADIOGRAPHY Nautron attenuation measurements were made at three locations on all eight

coupons, using a

collinated thermal neutron beam from the University of Florida Test Reactor.

The counting intervals used were sufficiently long to assure that normal counting statistics are essentially negligible (<0.3% at the lowest counting rate).

Archive samples of the original St.

Lucio Boraflex were available for comparison.

A number of Boraflex samples of known B-10 content had previously been used to establish a

calibration

curve, enabling the attenuation measurements to be used for B-10 analysis (See Figure 1).

The nominal design basis loadings of the St.

Lucie Unit i storage racks were 0.0238 grams B-10/cm* in Region 1 and 0.0097 grams /cm8 in Region 2.

Results of the neutron attenuation sensurements, given in Table 1, show an average B-10 loading in the surveillance coupons of 0.0246

• O.0003 grams /ca8(Region 1) and 0.0098 t 0.0001 grams /ca* (Region 2).

These values may be compared with measured loadings in the archive samples of 0.0242 2

0.0006 grams /ca*

(Region 1) and 0.0098

• O.0001 grams /ca* (Region 2).

These data are well within the accep-tance criteria for attenuation measurements and confirm that there has been no loss in boron.

The slightly greater absorp-tion of the irradiated Boraflex coupon is expected.

This phenomenon has been observed previously and is attributed to the increased B-10 loading due to coupon shrinkage with perhaps some contribution from the water absozbed within the open porosity of the Boraflex coupon.

Attached are radiographs of each of the two series of surveillance coupons, taken with a thermal neutron beam from the graphite thermal column of the University of Florida Test l

Reactor (UFTR).

These radiographs do not reveal any areas of significant non-uniformity in the B-10 distribution.

Page 12 of 17 l

i

L.

4.0 WEIGHT AND DIMENSIONAL CHECKS Length 'and width dimensions for the surveillance coupons l

are listed in Table 2 Shrinkage in the length appears, on the average, to be somewhat greater than in the width direction, although this may be an consequence of the difference in measurement accuracy in the two directions.

All shrinkage values are small, but the "3" and "4"

coupons in both regions, at the higher radiation dose, appear to exhibit slightly higher values.

However, all of the shrinkage data are all well within the 2.Li acceptance criteria, averaging less than it.

Thickness measurements generally did not show a change, as expected, since a 1% or 2% shrinkage in thickness would be less than the measurement accuracy.

In any event, the thickness itself is not an important parameter as long as the attenuation measurements confirm that B-10 has not been lost.

5.0 WEIGHT AND DENSITY MEASUREMENTS Irradiation of Boraflex usually results in a weight gain and an increase in open porosity with an attendant gain in density.

Measurement of the density of the surveillance coupons by the immersion technique (ASTM D-297, Section 15.1.2) gave the dry weights and density values listed in Table 3.

f Measured densities are consistent with expected density increases at the accumulated radiation dose.

The weight measurements, however, show a slight weight loss which may be a consequence of the pre-and post-irradiation measurements having been made in different laboratories.

In any event, the

)

differences are small (less than about it) and are not thought to be of any consequence.

Some earlier experimental data had previously shown a small weight loss at low radiation levels increasing with further irradiation to a weight gain at higher accumulated doses.

Page 13 of 17

l O'

I 1

l 6.0 HARDNESS TESTS Heasuretents of the coupon hardness were made with a Shore A Durometer in accorCance with ASTM D2240-85.

All of the samples were fully hard (checked against a glass surface with a*

hardness of 100 as one of the calibration points).

These data are consistent with the expected increase in hardness of Boraflex irradiktsd to 108 rads or more and does not indicate degradation.

Page 14 of 17 l

l l'

Table 1 NEUTRON ATTENUATION MEASUREMENTS

~

% TRANSMISSION B-10 LOADING COUPON

_191__

MIDDLE BOTTOM Grams /en R1-1-T1 2.99.

2.82 3.06 0.0245 R1-2-T1 2.96 2.75 2.91 0.0247 R1-3-T1 2.89 2.92 2.94 0.0246 R1-4-T1 2.84 2.78 2.99 0.0248 Archive Region 1 3.04 0.0242 R2-1-T1 18.21 18.26 18.86 0.0098 R2-2-71 18.13 18.52 19.17 0.0097 R2-3-T1 18.54 18.47 18.05

0. 00f'.

R2-4-T1 18.33 17.65 18.20 0.0099 Archive Region 2 18.33 0.0098 i

Page 15 of 17

l I

l l

l

' J

.. Table 2 LENGTH AND WIDTH MEASUREMENTS Coupon R1-1-T1 R1-2-T1 R2-1-T1 R2-2-T1 Lenath, inches Pre-irrad.

14.867 14.866 14.894 14.824 Post-irrad.

14.768 14.779 14.739 14.771

% Shrinkage 0.65 0.59 1.04 0.36 Width. inches i

Pre-irrad.

4.879 4.903 4.899 4.915 Post-irrad.

4.865 4.886 4.893 4.893

% Shrinkage 0.28 0.35 0.12 0.45 Coupon R1-3-T1 R1-4-T1 R2-3-T1 R2-4-T1 Lenath, inches Pre-irrad.

14.842 14.870 14.886 14.888 q

Post-irrad.

14.712 14.739 14.736 14.725

% Shrinkage 0.88 0.88 1.01 1.09 i

i l

i Width. inches f

1 Pre-irrad.

4.900 4.873 4.902 4.920 l

I Post-irrad.

4.866 4.856 4.869 4.876 j

% Shrinkage 0.69 0.35 0.67 0.89 l

Page 16 of 17 1

_______________ _ _ J

E_-

I-lr..

Table 3 WEIGHT AND DENSITY VALUES Weight in Air, g Pre-Post-i Coupon Irradiation Density, c/cetal R1-1-T1 163.4 162.92 1.796 R1-2-T1 166.4 166.01 1.804 R2-1-T1 65.0 64.52 1.808 R2-2-T1 64.8 64.62 1.796 i

R1-3-T1 163.4 162.83 1.818 R1-4-T1 164.7 164.05 1.817 R2-3-T1 64.7 64.45 1.815 R2-4-T1 65.8 65.54 1.820 (2)

Initial density averages 1.775 g.cc, per Bisco Products measurements on a large number of quality control samples.

l l

I

)

l 1

Page 17 of 17 i

I w--_._.___-

0.045,

4 k

O.040

\\

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N i

3 0.035 s

2 U

8 0.030 s.

}

e 0.025

-e E

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0.020 1

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9 s

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d 0.015 0.010 0.005 0.000 3

10 10

• PERCENT NEUTRON TRANSMISSION FIGURE 1 CAUBRATION CURVE FOR B-10 LOADNG

.