ML17264A489
| ML17264A489 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/11/1996 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9605170524 | |
| Download: ML17264A489 (7) | |
Text
CATEGORY 1.
REGULA)RY ZNFORMRTZON DZSTRZBUTZIN SYSTEM (RZDS) k.
ACCESSION Ng :9605170524 DOC.DATE: 96/05/11 NOTARIZED:
NO DOCKET FACIL:50"244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester' 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas a Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Forwards control rod drag testing results from spent fuel pool testing conducted between 960410 a ll,per NRC Bulletin 96-001.
DISTRIBUTION CODE:
IE57D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: NRC Bulletin 96-01 Control Rod Inserts.on Problems NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 G
RECIPIENT ID CODE/NAME PDl-1 PD VISS ING F G.
INTERNAL: AEOD NRR/DSSA/SRXB EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD4-2/THOMAS,K
~m~TRZZYMa MLE CENTER NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 D
E NOTE TO ALL "RIDSN RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl
, TOTAL 'NUMBER OF COPIES REQUIRED:
LTTR' ENCL
" '9
D
~
~
ZZIt IIIIII
'III >>g zuzzz zest I ursus I
5't*'lE ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 May 11, 1996 T5 1. E P N0 N E AREA CODE. 715 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Submittal of Control Rod Drag Testing Results NRC Bulletin 96-01 "Control Rod Insertion Problems" R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Reference:
(a)
Letter from R.C. Mecredy (RG&E) to A.R.
Johnson (NRC),
Subject:
Response
to NRC Bulletin 96-01, dated March 28, 1996 (b)
Letter from R.C. Mecredy (RG&E) to A.R.
Johnson (NRC),
Subject:
30-day Response to NRC Bulletin 96-01, dated April 8, 1996 (c)
Letter from R.C. Mecredy (RG&E) to A.R.
Johnson (NRC),
Subject:
Response
to NRC Bulletin 96-01, dated-March 29, 1996 Dear Mr. Vissing; In accordance with our commitment made in Reference (a) under our response to Requested Action 3, and repeated in our 30-day response to NRC Bulletin 96-01, Reference (b), enclosed are "the control rod drag testing results from spent fuel pool testing conducted between 4/10/96 and 4/11/96.
Relative to the test results the following information is provided.
The ability of the RCCAs to fully insert was verified during an unplanned trip on March 7, 1996 (See Reference c), prior to the plant shutdown on April 1, 1996.
After the shutdown the core was unloaded and all fuel assemblies containing a
RCCA were drag tested in the spent fuel pool.
The purpose of this testing was to determine the condition of the thimble tubes related to RCCA drag. It should be pointed out that Westinghouse Specification F-5.1 criteria is intended to identify assemblies that require additional review, from those that are, of no concern relative to RCCA drag.
The criteria are not intended to reject fuel assemblies.
3 7Atl'70 6
551 027605560515 PDR ADQCK 05000244 8
The results of the drag tests are shown on the enclosed table.
The strip chart data shows that all assemblies meet the dashpot criteria in Westinghouse Specification F-5.1.
This compares favorably to the anomalous (high drag) assemblies observed at Wolf Creek.
All of the Wolf Creek assemblies that failed to fully insert, also failed to meet this dashpot criterion (typically by a substantial amount) when tested in core.
For two fuel assemblies, strip chart data did not meet the criteria in F-5.1 for the upper guide thimbles.
Both assemblies (C52 and A62) exceeded the criteria by one pound.
Westinghouse experience is that 14x14 and 15x15 fuel assemblies normally show a higher drag than 17x17 fuel assemblies.
RCCA insertion anomalies have not been observed when only one criteria (dashpot, thimble) has been exceeded.
After a review of the attached drag test data, it is concluded that the behavior of the assemblies at Ginna is not similar to that of the anomalous assemblies at Wolf Creek.
All of the Ginna assemblies (even the highest burned) passed the dashpot criteria in F-5.1.
The two assemblies that exceed the drag criteria for the major diameter of the guide thimble are moderate
- burnup, and still fully inserted during the trip.
Based on the review of the attached test results, it has been concluded by both Westinghouse and RG&E that there is no concern for RCCA insertion anomalies at burnups tested for Ginna.
Very Truly Yours, Robert C. Mecredy Enclosure NRC51427 xc:
Mr. Guy S. Vissing (Mail Stop 14B2)
Project.Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King, of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector
~I I,
ASSEMBLY ¹ BURNUP RCCA ¹ GINNA STATION EOC 25 DRAG TESTING STRIP CHART READINGS Dashpot ((100 Ibs Max)
Guide Thimble (40 Ibs Max)
(MWD/MTU)
Withdrawal Insertion Withdrawal Insertion A65 F62 C50 C53 C52 C51 E76 E54 ESO E78 E51 E57 E81 E77 D75 E50 D72 E56 DSO D69 E55 D60 E53 D52 E52 D50 D61 E75 E74
'79 A62 43706 0
38259 37944 38006 38058 13523 15271 13497 13485 14981 15171 13314 13127 29153 15124 29387 14876 28922 29316 14981 28371 14741 28259 15152 28471 28394 13091 13035 13458 33558 R76 R76 RSO R74 R59 R56 R63 R79 R78 R64 R77 R81 R65 R82 R71 R75 R60 R67 R62 R68 R57 R61 R72 R73 R69 R58 R70 R83 R66 R84 R66 60 24 62 39 51 49 36 33 46 36 30 30 39 29 32 20 30 37 28 34 28 35 28 50 34 26 24 17 21 84 78 60 72 67 47 51 55 54 45 46 41 53 37 52 43 53 42 42 45 41 58 45 55 50 44 46 33 23 31 35 40 30 31 40 29 20 19 34 24 19 22 28 23 21 40 18 21 21 20 26 34 29 24 19 14 27 39 31 37 29 29 35 24 26 27 34 33 31 29 28 32 27 38 28 36 25 24 28 27 37 26 35 37 30 27 31 NEW ASSEMBLY TESTED FOR COMPARISON ONLY CENTER ASSEMBLY FOR CYCLE 26 CORE { NOT RODDED IN CYCLE 25I TABLE 1 Enclosur'e to RGB'etter dated May 11, 1996
r I
t