ML20237L726

Forwards Util to NRC Submitting Addl Info Re Mfg & Design Process for Installation of Boraflex Plates in Storage Racks of Quad Cities.Certificate of Svc Encl.Related Correspondence

ML20237L726
Person / Time
Site:	Turkey Point
Issue date:	08/31/1987
From:	Frantz S FLORIDA POWER & LIGHT CO., NEWMAN & HOLTZINGER
To:	Cole R, Lazo R, Luebke E Atomic Safety and Licensing Board Panel
References
CON-#387-4302 OLA-2, NUDOCS 8709090050
Download: ML20237L726 (9)

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~ ,TE.D ms . co.aBL_syunM NEwMAN & HOLTZINOEH, P.Cr.3tKrirrt JACn R. NEwMAN . 1615 L STRE ET, N, W,- WILuAM E. BAER, JR JOHN E. MOLTZINGER,JR, DOUGL AS L. BERESFORD D REIS WASHINGTON, D.C. 20036 ADE A EATON g

. J. A .Ou N,G T, Ja 87 SEP -1 Pi2 :59 {wea nN ELSTE,N-G RGkLEDGAR' J1LL . OR N '

MATHLEEN H SME A ' ANDREW N. GREENE*

DOUGLAS G. GREEN ,,py , PAMELA A. L ACEY MAROL LYN NEWMAN L..- s .

FRANM R LINDH JOHN T. STOUGM, JR. Jlb t I

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MEVIN J UPSON JAMES S VASILE .

d 1l KATHLEEN M. MCDERMOTT MiCuaEtA. Austa August 31, 1987 sErra" B+u'Maa' ALVIN H. GUTTERMAN - ERROL M PATTERSON K CDWARD J. TWOMEY JANE 1.RYAN JAMES S WILCOX.JR. PAUL J. SAVfDGE' KCVIN P. GALLEN JACOLYN A. SIMMONS TMOMAS A SCHMUT2 ROBERT H. SOLOMON MICHAEL F. HEALY CHARLES C.THEBAUD, JR.

ROBERT ). WHITE NANCY A. WHITE

• CCOTT A. HARMAN ROBJN T. WiGGINS' STEVEN P. FRANTZ

- DAVIO S. RASKIN -

, DONALD J SILVERMAN HERSERT 5 COMN -

ERNEST C. SAYNARD.111

.J01EPHC.STUSS$ orCouwsto

. CouwstL W ADeetTTED IN O C Dr. Robert.M. Lazo, Chairman Dr'.. Emmeth A. Luebke-

'Dr. Richard F.~ Cole Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555' In the Matter of FLORIDA POWER AND LIGHT COMPANY (Turkey Point Plant, Unit Nos. 3 and 4)

Docket Nos. 50-250,.50-251-OLA-2

Dear Licensing Board Members:

Enclosed is a letter dated August 25, 1987, from-Florida Power & Light Company to.'the NRC. This letter provides additional.

information regarding the manufacturing and design process for installation of the Boraflex plates in the storage racks of Quad Cities, based upon.information recently provided to FPL by the Quad Cities rack vendor. As this letter indicates, there are significant differences in the fabrication and design of the Quad' Cities.and Turkey Point racks, and FPL believes that the experiences of the racks-at Quad Cities are not applicable to Turkey Point.

l Also enclosed is a letter dated August 27, 1987, from FPL l to NRC. This letter states that Turkey Point will not store  !

l. fuel with an enrichment of 4.1% prior to the completion of the

.next surveillance and testing of the Boraflex in approximately

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Ne'wwAw & Hot.rztween, P. C.

1 August 31, 1987 Page Two I

three years. A sensitivity analysis has indicated that the Turkey Point spent fuel pools will remain within their 0.95 K-effective limits assuming each storage cell in the racks contains a fuel assembly with an enrichment of 4.1% and each Boraflex plate in the cells has a gap of 3.5 inches.

Sincerely, N

Steven P. Frantz Co-Counsel for Florida Power

& Light Company cc: Service List i

t L_.______________

P. o. Box 100CD, Juko LE ACH, FL 33408 0420 s=pt AUGUST 2 5 1987 L-87-355 10 CFR 50.73 U. S. Nuclear Regulatory Commission  !

Atin: Document Control Desk )

Washington, D. C. 20555 Centlemen:

Re: Turkey Point Units 3 and 4 l Docket Nos. 50-250 omd 50-251 Request for AdditionalInformation*

Boroflex Usooe at Turkey Point On June 9,1987, NRC requested additonal information from Florida Power &

Light Company (FPL) regarding the use of Boroflex in the spent fuel storage rocks at Turkey Point, including justification for the continued use of Boroflex in light of the experience at Ovod Cities. FPL responded to this request on July 10,1987, explaining that there are differences between the storage rocks of Guad Cities and Turkey Point and that the experience of Ovod Cities mcy not be relevant to Turkey Point.

The purpose of this letter is to provide additional information regarding the fabricotton of the Quod Cities storage rocks based upon the enclosed information recently provided to FPL by letter dated August 12, 1987 from Joseph Oct Corporation, the manufoeturer of the storage rocks for Quod Cities.

In our letter dated July 10, 1987, FPL stated that the Boroflex panels at Guad Cities were not constructed from a single sheet of Boroflex, resulting in pre-existing breaks in the Boroflex panels. This statement was based upon information provided to FPL. It is our understanding that the Boroflex in the Quod Cities rocks is sandwiched between two rock cell walls, and that the Boroflex was installed by (1) opplying Dow Silicone No. 999 in a strip approximately 2 to 3 inches wide along the full length of one cell wall, (2) placing the Boroflex on the cell wall and allowing the Dow Silicone No. 999 to dry without using clamps, and (3) placing this element in a fixture with the other cell wall for subsequent welding of the assembly. Dow has informed FPL that Dow Silicone No. 999 con be used as either a seolont or on adhesive. Joseph Oct has informed FPL that Dow Silicone No. 999 was used for the Quod Cities rocks os o seolont to hold the Boroflex in place during the subsequent assembly operations, and that Dow Silicone No. 999 was not intended to be used as a permanent ottochment or glue.

Joseph Oct hos informed FPL that the Ovod Cities rocks contain only one full length sheet of Boroflex per wall per cell and that splicing of the Boroflex was not used in any of the cells.

an FPL Group comcany RG3/053/l

t U. S. Nuclear Regulatory Commission L-87-355 Poge two FPL is not in a position to resolve this apparent inconsistency. Nevertheless, FPL continues to believe that there are significant differences in the fabricotton and design of the Quod Cities and Turkey Point rocks, and that the experiences of the rocks at Quod Cities is not applicable to Turkey Point. These differences S include: (1) the Boroflex of Guad Cities was placed between two cell walls, whereas the Boroflex of Turkey Point was placed in a wrapper with a several mil clearance between the Boroflex and the cell woll; (2) the adhesive or seolont was applied to the length of the cell wall at Quod Cities, whereas at Turkey Point the adhesive was applied to o Boroflex panel in short lengths (up to 2-1/2 inches long) of a maximum of 16 places (8 per side). Furthermore, unlike the Boroflex of Quod Cities, the results of Blackness Testing of Boroflex panels at Turkey Point did not indicate the existence of gops, voids, or other spatial distribution anomolies.

Should there be further questions, please contact us.

Very truly yours,

./

C. O. Wo Group ce resident Nuclear nergy COW /RG/gp Attachment ec: Dr. J. Nelson Grace, Regional Administrator, Region 11, USNRC Senior Resident inspector, USNRC, Turkey Point Plant RG3/053/2

8-n i

, JOSEPH OI[ RPOR ATIO N CHEMICAL ENGINEERS & FABRICATORS August 12, 1987 4

Florida Power & Light Co.

P.O. Box 14000 700 Universe Blvd.

3uno Beach, FL 33408 At t ent ion : Mr. 3. A. DeHast ry

Reference:

Letter dated 8/3/87 FPL #3NL-87-372 3.0.C. #3-2483 Dear Mr. DeHast ryt In response to your letter referenced above and it s att achment we are submitting the followings l

There are several areas in the NRC lett er dat e d 7/8/87 and the FP&L letter L-87-279 dat ed 7/10/87 which are not correct.

All racks t h at were ever fabricated cont ained only one full length sheet of Boraflex per wall per cell. There has never been splicing used in any cells at any time. Joseph Oat procures the Boraflex from Bisco to the Joseph Oat drawings and Bills of H at e rial requirement s. These document s specify the full length of each piece. Each piece supplied to Oat by Bisco is cut to its required length by Bit.co. Joseph O at QC verifles the poison length as being correct as ordered.

At the onset of init ial f abrication of the very first racks f abricat ed by Joseph O at , it was recognized that torn or damaged Boraflex was not accept sble for use and therefore never was.

Each piece was t re at ed as unaccept able if it was not of it s required size or it was damaged in any manner.

During the application of the Boraflex to the subassemblies the inst aller uses one roll of full length per loc at ion . Quality Cont rol monitors this act i v it y to assure that the Boraflex is inst alled properly and that no torn or damaged Boraflex is used.

2500 Broadway / Drawer 10 / Camden New Jersey 08104 / (609) 5412900

> 1 JOSEPH CAT CORPORAT12N CHEMICAL ENGINEEAS & FABMCATORS NUCLEAR POWER COWONENTS f

ESTABUSNED 1 ten 1

l1 Mr. 3.A. DeHast ry )

s j

Florida Power & Light j

August 12 1987 Page Two j

In the event that damaged or torn Boraflex is det ect e d by the installer or QC, it is placed on hold, removed from the assembly area and st ored in Quality Cont rol. When Quality Control detect s possible damage to Boraflex, a Deviation Notice is generat ed, the it em a f f ect ed placed on hold and the evaluation and disposition is performed by Oat Engineering. There has never been one l occasion where the use of torn or spliced Boraflex has been I permitted. .

During the inst allat ion of the Boraflex to the individual cell walls or subassemblies, Joseph Oat employed the practice of applying several small dabs of silicone sealant to the subassem-bly. This sealant was then smeared with a putty knife type tool to a thin tacky film and tiie Boraflex was then applied. The use of clamping was never employed. The purpose. of this practice was not to permanently att ach or " glue" the Boraflex to the assembly, ,

but r at he r a method of holding it in place during subsequent i assembly operat ions.

Joseph Oat design racks cont ained a self enclosure for the Bora-flex. In all design racks the cell walls acted as the enclos-ure. On the outer boundary of the rack there were doubler plates over the poison. In no areas is poison exposed on assembled racks.

Att ached is a summary of the inst ructions given to the shop per-sonnel that were employed on assembly of the racks.

If there are any further que st ion s , please cont act either Jay Murphy or the undersigned.

Very t ruly ours, br '

.x. f.1 John Benckert

/ QC Hanager 30:cd

P. O. box 14000, Juno BEACH, FL 33408-0420 4

AUGUST, 2 7 1987 L-87-363 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Request for Additional Information Boroflex Our letter L-87-279, dated July 10, 1987, provided the results of a sensitivity analysis performed for Turkey Point Units 3 and 4 spent fuel rocks. This analysis was performed to show the offect of postulated gaps on maintaining the 0.95 K ff shutdown criteria. The analysis shows that Florida Power & Light (FPL) will%e able to maintain the 0.95 K,gg shutdown criteria for future fuel cycles, assuming that each Boroflex plate has gaps of 3.5 inches and each storage cell in the fue! ,

rocks has on assembly with al enrichrnent of 4.1%. There are no indications of '

gaps os a result of the blackness testing at Turkey Point, and the enrichment of the new fuel currently used at Turkey Point ranges from 3.4% to 3.6%. Under FPL's fuel management program and the current limits on reactor operations, FPL will only be able to increase the maximum Turkey Point fuel enrichment in small increments (opproximatelf 0.2%) each cycle. Therefore, at the time of the next blockness testir'g and surve!!!ance of the Boroflex in approximately three years, the maximum fuel enrichment at Turkey Point will be less than 4.1%. Prior to completion of that surveillance, FPL will not store fuel with on enrichment greater than 4.1%.

Should there be any questions, please contact us.

Very truly yours, k.

C. O. ' Wood Group Vice President Nuclear Energy COW /RG/gp Attochment i L cc: Dr. J. Nelson Grace, Regional Administrator, Region 11, USNRC Senior Resident inspector, USNRC, Turkey Point Plant I an FPL Group company l

l RG3/054/l j

X nili:

UNITED STATES OF AMERICA U" NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 87 SEP -1 Pl2 59 U' 'c; DGCU pu m

)

In the Matter of )

} Docket Nos. 50-250 OLA-2 FLORIDA POWER & LIGHT COMPANY ) 50-251 OLA-2

)

(Turkey Point Nuclear Generating )

Units 3& 4) )

)

CERTIFICATE OF SERVICE I hereby certify that copies of the attached letter in the above captioned proceeding were served on the following by deposit in the United States mail, first class, properly l stamped and addressed, on the date shown below.

Dr. Robert M. Lazo, Chairman l Atomic Safety and Licensing Board Panel l U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Richard F. Cole Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commissi on Washington, D.C. 20555 Atomic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Office of Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Chief, Docketing and Service Section (Original plus two copies)

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2.

Joette Lorion 7210 Red Road #208 Miami, FL 33143 Colleen P. Woodhead Office of Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Norman A. Coll Coll, Davidson, Carter, Smith, Salter & Barkett 3200 Miami Center 100 Chopin Plaza

• Miami, FL 33131 An%

Steven P. Frantz Newman & Holtzinger, P.C.

1615 L Street, N.W.

Washington, D.C. 20036 Dated: August 31, 1987 L_--__ _ _  !