ML17223A934

Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl

ML17223A934
Person / Time
Site:	Saint Lucie
Issue date:	09/10/1990
From:	Sager D FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-323, NUDOCS 9009140036
Download: ML17223A934 (16)

Text

ACCELERATED DIS BUTION DEMONST TION SYSTEiVI

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9009140036 DOC. DATE: 90/09/10 NOTARIZED: NO DOCKET., 0 FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION SAGER,D.A. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards addi info re generic implications & resolution of CEA failure at Maine Yankee.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution I ENCL L SIZE:

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 2 2 INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB SE 1 1 NUDOCS-ABSTRACT 1 1 1 0 OGC/HDS2 1 0 RE@ FIL Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,i ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 21

P.O. Box14000, Juno Beach, FL 33408-0420 SEP I 0 IBX L-90-323 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Re: St. Lucie Unit 1 Docket 50-335 Generic Implications and Resolution of CEA Failure at Maine Yankee By letter dated July 6, 1990, the Nuclear Regulatory Commission (NRC) staff requested additional information from Florida Power and Light (FPL) regarding the Combustion Engineering Regulatory Response Group (CERRG)

Action Program for addressing the issue of irradiation assisted stress corrosion cracking (IASCC) in Control Element Assemblies (CEAs).

L-90-272, dated July 17, 1990, FPL confirmed its intent to follow By'etter the CERRG Action Program as well as committing to provide the results of the completed eddy current test (ECT) and visual inspections. FPL also committed to utilize the data taken during the ECT to update the CERRG Action Program. The revised Action Program and ECT results were submitted to the staff on August 16, 1990 FPL letter L-90-301.

In subsequent conversations, the staff requested FPL provide additional information to facilitate its review of the revised Action Program.

Attachment One to this letter provides a description of the testing program for the old style CEAs in the Unit 1 core. Attachment Two provides other additional materials requested by the staff which FPL committed to furnish as a part of this submittal'hould you have any questions, please contact us.

Very truly yours, 5A D. A. ger Vice r sident St. L ie Plant DAS:JMP:kw Attachments (2)

CC: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC DAS/PSL 4252 9009140036 900910 ADOCK 05000335 PDR PDC an FPL Group company

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Attachment One ST. LUCIE UNIT ONE OLD STYLE CEA TESTING PROGRAM By letter L-90-301, dated August 16, 1990, Florida Power and Light (FPL) stated its intention to verify the structural integrity of the seventeen high exposure, old style CEAs in the Unit 1 core on a quarterly basis. In order to assess the FPL Action Program, the NRC staff requested that FPL describe its procedure for exercising the subject CEAs.

The FPL program for the verification of the structural integrity of the old style CEAs in the St.

Lucie Unit 1'core consists of the following elements:

1. EAR i i nin The 17 high exposure old-design CEAs willbe maintained in the fullest withdrawn position (i.e. - monthly CEA wear exercising will be discontinued for those CEAs).

2. emi-weekl Inc r Fl ix M ni rin Neutron flux maps will be taken on a semi-weekly basis for the remainder of the cycle or until the old design CEAs have been replaced.

Ex rci,in aft r I, hi wn A full insertion/withdrawal exercise of the 17 high exposure old design CEAs will be performed after each cold shutdown and reactor trip. This exercise program will stay in place until the end of the current cycle unless CEAs have been replaced prior to that time.

rl Fx i in A quarterly full insertion/withdrawal exercise of the 17 high exposure old design CEAs will be performed in Hot Standby, or Mode 3 (exercising performed after cold shutdowns and/or trips will be considered as a quarterly exercise). This exercise will stay in place until the end of the current cycle unless CEAs have been replaced prior to that time, or ifexercising (or other anomalous CEA movement restrictions) shows evidence of a stuck old style CEA. If the sticking of the CEA is determined to be attributable to a loss of structural integrity, the CEA will be immediately replaced prior to returning to power operation.

Quarterly exercising willbe performed as follows:

~ the reactor willbe placed in Mode 3

k

~ each CEA to be exercised willbe raised from the fully inserted position to the fully withdrawn position, using the Control Element Drive Mechanism (CEDM)

~ the CEA will then be returned to the fully inserted position using the'CEDM

~ each CEA will be exercised individually in this manner until all seventeen old style, high exposure CEAs have been exercised.

ATTACHME'NT TWO Records Search Results Summary CEA ECT Inspection Results Summary CEA Exposure Comparison St. Lucie Unit 1 Cycle 10 CEA Reactivity Worth Core Map

4 RECORDS SEARCH RESULTS

SUMMARY

As stated in Florida Power and Light (FPL) letter L-90-272, dated July 17, 1990, a manufacturing record search/comparison has been conducted by FPL personnel. The intent of the review was to identify and document verifiable differences in the material, configuration, and manufacturing processes for the old style CEAs in place at St. Lucie Unit 1 compared to similar CEAs.

The review, which was conducted by the FPL Quality Assurance Department, investigated such items as tubing, endcaps, weld material, B4C pellets, material manufacturing, and component manufacturing. Differences were encountered in the materials used for the tubes for St. Lucie Unit 1 CEAs in the areas of yield values, tensile strength, percent elongation and heat numbers.

The values of these parameters were somewhat higher for the St. Lucie Unit 1 tube materials.

However, all materials used were determined to be within the specifications of ASTM B444-66.

Overall, the review showed that the St. Lucie Unit 1 CEAs were manufactured in accordance with approved design and manufacturing specifications and processes. No objective evidence was uncovered that would indicate a problem or defect in the design, materials or manufacturing processes used to construct the St. Lucie Unit 1 CEAs.

e t ST. LUCIE UNIT 1 EDDY CURRENT TEST RESULTS JEAN FPD i 'nD ri 'n 3836 Axial crack, 0.2" in length 12 4340 Axial crack, 0.2" in length 19 3855 Axial crack, 3.4" in length 71 3979 Axial crack, 0.2" in length; not through wall 73 3986 Axial crack, 0.2" in length Note: no evidence of circumferential cracking was detected

EXPOSURE COMPARISON in EFPD SPENT FUEL POOL CEAs and EOC 10 CEAs F F.I P Y IF FANim r Fx FPD x s> F Q."FP~D 75 1241 76 1482 77 1777 4 3836 41 3853 19 3855 47 3863 5 3867 61 3868 25 3874 70 3965 72 3978 71 3979 73 3986 23 4048 21 4054 45 4054 43 4062 4072 9 4075 8 4077 27 4082 30 4086 57 4087 36 4088 58 4089 39 4090 52 4105 74 4105 6 4109 14 4109 55 4114 63 4122 1 4124 34 4128 22 4129 32 4132 4135 29 4136 38 4139 28 4141 40 4142

SPFNT F7JF>>L POOL CF>>.AS Y I F>>. I RF F EANim er Ex s> FPD Ex s >re E Q~FPD 37 4143 11 4149 26 4149 35 4149 64 4149 31 4155 65 4229 7 4237 15 4251 18 4260 48 4262 10 4267 56i 4267 51 4275 59 4277 17 4335 24 4336 13 4337 16 4338 20 4339 12 4340 50 4344 42 4344 54'9 4345 4349 53 4350 46 4359 62 4524

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b . Lucie Unit 1 Cycle 10 BOC HFP Reactivity Worth of 20 B4C Center Finger Design CEAs and Associated Duals N

YXWVTSRPNML.KJHQFE D C B A 21 65 64 '

58 58 63 6g 19 129 83 129 18 55 52 17 129 129 16

'l6 75 74 14 83 98 13 40 35 12 58 58 11 76 10 74 9

8 31 58 26 58 7 A 14 11 129 129 '

3 129 129 2 1 58 58 Legend CEA I.D.

3i ~i ili ax'c 14 Worth (pcm)

Dual C~

FORM 3013 hKV. 4/7

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