ML20117H343
| ML20117H343 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/22/1996 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, VPNPD-96-033, VPNPD-96-33, NUDOCS 9605280166 | |
| Download: ML20117H343 (6) | |
Text
,
l Wisconsin f
'Electnc POWER COMPANY l
231 w Micnican. PO Box 2046. Milwaukee.WI 53201 2046 (414)221-2345 VPNPD-96-033 10 CFR 50.54(f)
May 22,1996 i
Document Control Desk US NUCLEAR REGULATORY COMMISSION Mail Station PI-137 I
Washington, DC 20555-0001 Gentlemen:
DOCKETS 50-266 AND 50-301 RESPONSE TO NRC BULLETIN 96-01 CONTROL ROD TEST DATA FROM UNIT 1 OUTAGE UIR23 POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 In response to Bulletin 96-01, we subinit the following control rod data from tests conducted during Unit 1 outage j
UIR23. As discussed in nur April 3,1996, response to the Bulletin, we committed to submit this data within 30 days of completing the control rod testing conducted during the outage. Refueling outage UIR23 was completed April 23,1996. Completed tests included:
(1)
End-of-Cycle (EOC) Rod Drop Testing of Unit I rodded fuel assemblies was completed on March 30. The drop time for each control rod was less than the maximum limit of 2.2 seconds established in Technical Specification 15.3.10.E.1.
Recoil was esident on all control rods. (Note that these results were generally reported to the NRC in our letter, VPNPD-96-019, dated April 3,1996. Specific test data was not included.)
(2)
Beginning-of-Cycle (BOC) Control Rod Drag Force Testing of Unit I was performed on April 11.
This is the routine test conducted on the rodded fuel assemblies of the refueled core. Drag force testing is conducted over the vessel with the drive shafts latched. Test results for all assemblies in the core were acceptable. This data is reported in Attachment 1,"PBNP Drag Test Results" One fuel assembly (#BB-11) was close to the Westinghouse guideline for maximum drag force in the thimble tube region. This assembly has relatively low burnup, and would not be considered susceptible to high burnup rod insertion problems.
Westinghouse was consulted concerning this fuel assembly. They advised us that it is not unusual to occasionally observe low burnup fuct assemblies with drag forces comparable to those measured in BB-11. The assembly was therefore considered acceptable, pending results of the BOC control rod drop tests.
(3)
BOC Control Rod Drop Tests. Cold rod drop testing was performed April 20 and hot rod drop testing was performed April 22. The drop time for each control rod was less than the maximum limit of 2.2 seconds established in Technical Specification 15.3.10.E.1. This data is reported in Attachment 2, " Point Beach Unit I Cycle 24", Recoil was esident on all control rods.
(4)
EOC Drag Force Tests on Discharged Assemblies. On May 4, a crew of Westinghouse technicians performed l
drag force tests in the Spent Fuel Pool (SFP) on the five high burnup discharge fuel assemblics from U1C23.
Eight other high burnup assemblies were selected by Westinghouse and also tested in the l
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Document. Control Desk May 22,1996 Page 2 t
SFP. The results of the five UIC23 discharge assembly tests are included with the BOC drag force test results in Attachment 2. Three of the five fuel assemblies (# Y-11, Z-ll, and Z-12) had thimble tube drag forces in excess of Westinghouse guidelit es. Westinghouse will be evaluating these and the other tests they performed as part of their investigation and Westinghouse Owners Group (WOG) investigation of the incomplete rod insertions identified in the Bulletin.
We also enclose a core map of rodded fuel assemblies for Unit 1 Cycle 24 (Attachment 3), as requested in the Bulletin.
We continue to evaluate the operability of all rodded fuel assemblies using this information and that made available to us from the WOG. To date, all rodded fuel assemblies installed in our operating cores meet our existing test acceptance criteria, and therefore are considered operable. Our evaluation of test data does not indicate any basis for revising the existing acceptance criteria or developing new criteria. We look forward to the evaluation and guidance that may result from your review of data and the continuing WOG investigation.
. Please contact us if there are any questions.
Sincerely, J
B Lin Vice President Nuclear Power GDA Attachments cc:
NRC Resident Inspector NRC Regional Administrator Public Service Commission of Wisconsin (Attn: Paul Kitzenbel)
Subscribed and sworn to before me on this 22nd day of May,1996.
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[JNdtarfPublic, State of Wisconsin My Commission expires /U-Ml(.
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4Hachmen/ 1 PBNP Drag Tost Rcsults Fuel
- Cycle, Burnup, Static wt. Guidetube Guidetube Dashpot Dashpot Guidetube Dashpot Assembly BOC or EOC MWD /MTU lbs out drag in drag out drag in drag avg. drag avg. drag 88-09 24, BOC 17140 474.6 17.1 34.1 13.7 34.1 25.6 23.9 BB-10 24, BCC 17195 471.2 6.8 17.1 6.4 29.7 12.0 18.1 BB-11 24, BOC 17130 478.0 23.9 54.6 27.3 61.4 39.3 44.4 BB-12 24, BOC 17164 474.6 6.9 30.7 14.7 41.0 18.8 27.9 BB-21 24, BOC 14249 471.2 4.7 18.0 13.7 29.9 11.4 21.8 BB-24 24, BOC 14117 471.2 13.4 27.3 12.8 34.3 20.4 23.6 BB-25 24, BOC 14108 471.2 6.6 23.4 3.4 27.3 15.1 15.4 88-28 24, BOC 14092 471.2 11.3 23.9 13.7 27.3 17.6 20.5 BB-29 24, BOC 15330 471.2 6.8 16.4 18.7 27.3 11.6 23.0 BB-30 24 BOC 15324 471.2 5.9 16.2 0.0 24.1 11.1 12.1 BB-31 24, BOC 15455 471.2 13.7 22.3 6.8 30.7 18.0 18.8 BB-32 24, BOC 15404 471.2 13.7 23.9 13.7 36.1 18.8 24.9 CC-01 24, BOC 0
471.2 6.8 13.7 3.4 27.3
,10.3 15.4 CC-02 24, BOC 0
471.2 8.0 13.7 3.0 27.2 10.9 15.1 CC-03 24, BOC 0
471.2 6.9 17.1 3.4 24.6 12.0 14.0 CC-04 24, BOC 0
471.2 6.8 16.1 3.4 23.9 11.5 13.7 CC-05 24, BOC 0
474.4 13.9 18.8 2.2 30.5 16.4 16.4 CC-06 24, BOC 0
474.6 9.0 17.7
-3.4 24.6 13.4 10.6 CC-07 24, BOC 0
471.2 6.8 15.9 2.9 27.3 11.4 15.1 CC-08 24, BOC 0
471.2 3.9 10.2 6.8 29.8 7.1 18.3 CC-09 24, BOC 0
471.2 6.8 21.9 16.7 23.9 14.4 20.3 CC-11 24, BOC 0
464.4 13.6 7.6 6.8 17.1 10.6 12.0 CC-12 24, BOC 0
471.2 6.8 13.7 3.4 23.9 10.3 13.7 CC-14 24, BOC 0
476.5 1.5 22.4
-5.3 29.2 12.0 12.0 CC-19 24 BOC 0
464.4 25.4 23.9 23.2 20.5 24.7 21.9 CC-20 24, BOC 0
471.2 6.8 16.3 6.8 23.9 11.6 15.4 CC-21 24, BOC 0
474.1 8.7 13.1 0.5 26.8 10.9 13.7 CC-24 24, BOC 0
464.4 12.7 7.9 13.6 20.5 10.3 17.1 Y-11 23, EOC 51957 not avail.
70.0 70.0 90.0 90.0 70.0 90.0 Y-14 24, BOC 42806 464.4 13.6 10.5 9.2 17.1 12.1 13.2 Z-09 23, EOC 42146 not avail.
10.0 30.0 42.0 45.0 20.0 43.5 Z-10 23, EOC 42415 not avail.
5.0 8.0 22.0 25.0 6.5 23.5 Z-11 23, EOC 42005 not avail.
66.0 70.0 75.0 78.0 68.0 76.5 Z-12 23, EOC 42344 not avail.
42.0 45.0 55.0 75.0 43.5 65.0 Z-13 24, BOC 40583 464.4 37.5 31.6 30.7 37.7 34.6 34.2 Z-18 24 BOC 40265 471.2 13.7 30.5 17.1 40.4 22.1 28.8 Z-24
- 24. BOC 40484 468.0 19.7 23.6 23.7 27.5 21.7 25.6 Z-28 24, BOC 40382 474.6 20.3 47.5 17.1 47.8 33.9 32.5 L
h4med 2 POINT BEACH UNIT 1 CYCLE 24 Fuel Type:
Westinghouse OFA PWR 14X14 Control rod Type:
AG(80)/IN(15)/CD(5)
PB1 - CYCLE 24 (-4 23-96 thru 3 29-97)
CORE BANK"*
F/A RCCA CURRENT PROJECTED BOL COLD ROD BOL HOT ROD LOCATION LOCATION ID ID BURNUP' EOL BURNUP' DROP TIMES" DROP TIMES" B6 SDA CC11 R86 182 13,916 1.499 1.510 B8 SDA CC14 R129 173 13,792 1.559 1.570 C5 CBA CCO2 R136 215 16.224 1.512 1.550 C7 CBD BB32 R104 15,622 27,709 1.755 1.740 C9 CBA CC04 R147 221 16,277 1.663 1.610 D4 CBC 8810 R146 17,384 33.452 1.495 1.570 D10 CBC B809 R89 17,333 33,465 1 327 1.570 E3 CBA CC05 R84 212 16.217 1.583 1.570 E5 SBB 8825 R100 14,335 29,814 1.520 1.570 E9 SBB BB24 R140 14.343 29.848 1.624 1.610 E11 CBA CC06 R504*
222 16.217 1.568 1.570 F2 SBA CC24 R25 181 13.784 1.544 1.570 F6 CBB Z28 R96 40,539 52,917 1.686 1.680 F8 CBB Z18 R125 40,416 52,777 1.631 1.610 F12 SBA CC12 R124 188 13.875 1.542 1.530 G3 CBD 8831 R105 15,677 27,761 1.502 1.570 G7 CBC Y14 R131 42,952 53,967 1.642 1.590 G11 CBD B830 R92 15.547 27.625 1.524 1.530 H2 SBA CC19 R137 176 13,679 1.542 1.570 H6 CBB Z13 R108 40,740
$3,162 1.692 1.630 H8 CBB Z24 R97 40.635 52,979 1.635 1.610 H12 SBA CC20 R91 182 13,922 1.534 1.550 13 CBA CC07 R99 220 16.251 1.566 1.570 15 SBB BB28 R85 14,325 29,870 1.603 1.610 19 SBB BB21 R106 14.482 29,965 1.581 1.590 11 1 CBA CC01 R95 228 16,237 1.574 1.570 J4 CBC 8812 R132 17,367 33,603 1.574 1.610 J10 CBC BB11 R94 17,332 33.363 1.571 1.590 K5 CBA CC08 R130 232 16.239 1.663 1.590 K7 CBD BB29 R87 15,555 27,575 1.781 1.700 K9 CBA CCO3 R102 221 16,149 1.522 1.550 L6 SBA CC09 R143 183 13.768 1.598 1.590 L8 SBA CC21 R101 181 13.853 1.505 1.530
- CHROME TIPPED
" TIME TO DASHPOT (SECONDS)
"*SB= SHUTDOWN BANK, CB= CONTROL BANK CURRENT BURNUP BASED ON APRIL,1996 PBBURN DATA.
2PROJECTED EOL BURNUP IS AN ESTIMATE CALCULATED BY USING U1C23 BURNUP DATA AT A GIVEN CORE LOCATION, AND COMPENSATING FOR THE LENGTH OF CYCLE 24, WHICH IS SCHEDULED TO BE 8 DAYS SHORTER THAN CYCLE 23.
10:17 05/10/96
A ae7med 3 a.
n 10/ 2 page P8NP UNIT 1 CYCLE 24 CURRENT AND PROJECTED EOL* SURNUP (FOR ROODED FtAs ONLY) 1 2
3 4
6 6
7 9
0 10 11 12 13 A
A CC1141e8 CC144t128 B
ist 173 3
11914 1L792 CCOR130 M
CC0%W147 C
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18.277 M1M144 Meemse D
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191 48,534 4dL414 tes F
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- * =
53 ss7 nrJan CC1em137 211m188 234rRt7 CCatme1 M
176 44,740 44838 1st M
11379 13.142 S2.076 11R22 CCOFNIOS M
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itsee CCOWR143 CC21tR101 L
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{yEL TYPE:
Y CtNuGMT BusssUP SASED ON E30 0F AMEL.1000 PSBUIWI DAT Al SEE ATT ACHED SHEET f
Pfl0JECTED ECL' SUIW8UP ICOLORB RAEED ON THIS NUeleERI 1
eeen j
eUEN, atbR aseM, m 6 stBN en
- PROJECTED EOL SUUUeUP as Als tsfieBATI CALCULAftD $7 UENeG UTC23 BufgeUP DATA Al A GivfN COFE LOCATIOII. AfsD COMPENSA7118G FOR THE LENGTH OF CVCLA 24.
undCN 16 SCHEDULED TO et e DAYS EHONTEst UTC24 FHIST PRDOttED POWER ON 4-2190.
ese a seen
Machmed 3 r
c page z d 2 POINT BEACH NUCLEAR PLANT : UNIT 1 AND 2 FUEL TYPE:
WESTINGHOUSE, PWR, RECONSTITUTABLE,14 X 14, OFA MATERIALS:
TOP NOZZLE 304 SST BOTTOM NOZZLE 304 SST SPRING SET INCONEL - 718 GUIDE THIMBLE ZIRCALOY - 4 INSTRUMENT TUBE ZIRCALOY - 4 GRID ASSEMBLY INCONEL - 718 (TOP AND BOTTOM GRIDS)
GRID ASSEMBLY ZIRCALOY - 4 (MIDDLE GRIDS)
ADAPTOR PLATE 304 SST NOZZLE INSERT 304 SST LOCK TUBE 304 SST GUIDE TUBE INNER DIAMETER:
ABOVE DASHPOT 0.492" BELOW DASHPOT 0.4465" l