ML20117N589

Submits Rev to Response to NRC Bulletin 96-001

ML20117N589
Person / Time
Site:	Vogtle
Issue date:	09/13/1996
From:	Woodard J GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-001, IEB-96-1, LCV-0788-E, LCV-788-E, NUDOCS 9609190301
Download: ML20117N589 (4)

Text

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,i monIA enu 333 i Atlanta, Georgia 30308 Telephone 404 526 3195 l

Mathng Address 40 inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 i

Telephone 205 868-5086 i

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dresident e io i September 13, 1996 Docket Nos. 50-424 LCV-0788-E 50-425 i

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk j

j Washington, D. C, 20555 Gentlemen:

I VOGTLE ELECTRIC GENERATING PLANT REVISION TO RESPONSE TO NRC BULLETIN 96-01 t

l By letter LCV-0788 dated April 4,1996, Georgia Power Company (GPC) responded to NRC Bulletin 96-01. This response included commitments for testing control rods following the March 3,1996 refueling outage of Vogtle Electric Generating Plant (VEGP)

Unit 1 and the September outage of VEGP Unit 2. The testing for Unit I was completed

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and the results were summarized in LCV-0788. The data from the tests was submitted to the NRC by letter LCV-0788-D, dated September 4,1996. The commitments made for VEGP Unit 2 included rod drop time measurements and drag testing.

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l On' August 22,1996 the Westinghouse Owner's Group proposed a relaxation of the testing proposed by NRC Bulletin 96-01. In response to this request, the NRC's letter dated September 4,1996, stated that the staff continued to consider the rod drop time tests to be essential but that if sufficient data is available, the staff would consider relief j

from the drag test commitment. Georgia Power has successfully conducted end of cycle drop time test for VEGP Unit 2. In accordance with our commitments, all of the control rods inserted well within their Technical Specification limits. The results from these tests l

are attached along with the results from the rod drop time tests that were conducted at the beginning of the operating cycle.

9609190301 960913

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gDR ADOCK 05000424 I

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.e GeoigiaPower d U. S. Nuclear Regulatory Commission Page 2 l-Based on our discussions with Westinghouse, the additional data from drag testing is not i

required for their root cause evaluation. The successful rod drop time tests indicate that l

the drag testing will exhibit results that are within normal parameters. The Unit 2 fuel is l

of the same type as was tested during the previous outage on Unit 1. In addition, the burnups and power history of the fuel being discharged with this cycle on Unit 2 have been enveloped by the exposure of the fuel tested at the previous Unit 1 outage. This is shown by the burnup and history of the rodded fuel assemblies from Unit 1 Cycle 6 and Unit 2 Cycle 5 which are also attached to this letter.

The results of the Westinghouse Owner's group investigation indicated that the incomplete rod insertions that have been experienced by other plants have occurred in rodded fuel assemblies during their third cycle. Neither of the VEGP Units have control i

rods in third cycle fuel, and there are no plans to design cycles with control rods in third l

cycle fuel. Therefore, the existing data for VEGP is sufficient for demonstrating l-confidence that the control rods will function properly during the next fuel cycle and the l

additional data is not required to complete the root cause analysis. Extensive fuel sipping is expected to be required during this refueling outage. The need for this activity had not

. been realized at the time GPC committed to the drag testing. In order to reduce the activities in the spent fuel pool and for the reasons described above, Georgia Power requests relief from its commitment to perform drag testing in the spent fuel pool during the current outage of Unit 2.

I Sincerely j

-A 1

. Woodard i

JDW/HWM

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Enclosures.

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1. Vogtle -1 Cycle-6 Drag Tests Results During Refueling Outage

2. History of Unit 2 Cycle 5 Rodded Fuel Assemblies And Drop Times c(w): Georgia Power Company Mr. J. B. Beasley, Jr.

Mr M. Sheibani NORMS U. S. Nuclear Regulatory Commission

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Mr. S. D. Ebneter, Regional Administrator Mr. L. L. Wheeler, Licensing Project Manager, NRR j.

Mr. C. R. Ogle, Senior Resident Inspector, Vogtle i

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i ENCLOSURE 1 l

VOGTLE 1 CYCLE 6 DRAG TESTS RESULTS DURING REFUELING OUTAGE Cycle 6 Assembly Bumup Insert Drag Avg Drag RCCA (MWD /MTU)

Bumup Sharing F/A ID (bs)

(bs)

BankID EOCS EOC6 EOCS EOC6 SG70 80 103.73 C

28824.8 50585.9 1.38 1.04 SG67 125 C

28761.7 50851.5 1.39 1.04 l

SG80 145 C

28686.3 50805.2 1.38 1.04 SG82 65 C

28560.9 50677.3 1.38 1.04 SH12 55 55 D

N/A 28350.9 N/A 1.34 SG56 45 45 D

26891.6 48908.7 1.30 1.04 SG63 50 D

26931.1 49270.3 1.30 1.05 l

5G58 40 D

27077.5 49406.2 1.31 1.05 l

SG55 45 D

27198.8 49493.0 1.31 1.05-SG02 35 43.75 SE 21635.8 42381.8 1.04 0.98 SG04 40 SE 21793.0 42524.4 1.05 0.98 SG03 60 SE 21760.1 42551.5 1.05 0.98 SG01 40 SE 21628.1 42390.3 1.04 0.98 5G43 40 37.5 SA 27571.9 40728.8 1.33 0.62 SG41 40 SA 28181.4 41223.2 1.36 0.61 SG47 30 SA 28086.5 41177.9 1.35 0.62 l

SG48 25 SA 28083.8 41159.9 1.35 0.62 SG40 45 SA 28075.5 41623.9 1.35 0.64 l

SG52 40 SA 27946.1 41502.7 1.35 0.64 l

5G50 35 SA 27854.3 41129.6 1.34 0.63 l

SG44 45 SA 28232.9 41631.8 1.36 0.63 5H52 35 36.5 SD N/A 29326.0 N/A 1.38 5H59 40 SC N/A 28924.3 N/A 1.36 SH73 50 SC N/A 28977.2 N/A 1.37 5H54 40 SD N/A 28927.7 N/A 1.36 l

5H53 35 SC N/A 28630.8 N/A 1.35 j,

5H75 30 SD N/A 30270.4 N/A 1.43 5H63 D

SC N/A 28851.9 N/A 1.36 5H77 27 SD N/A 29183.2 N/A 1.38 5H07 30 33.75 SR N/A 27993.9 N/A 1.32 5H10 15 SB N/A 27817.6 N/A 1.31 5H06 65 SB N/A 28251.7 N/A 1.33 5H08 20 SB N/A 28035.9 N/A 1.32 5H09 50 SB N/A 27842.3 N/A 1.31 5H05 35 SB N/A 27923.4 N/A 1.32 SH11 35 SB N/A 28125.3 N/A 1.33 SH13 20 SB N/A 27928.3 N/A 1.32 5H71 35 30.5 A

N/A 27562.7 N/A 1.30 SM81 30 A

N/A 27637.8 N/A 1.30 t

5H57 20 A

N/A 27677.7 N/A 1.31 SH64 37 A

N/A 27795.0 N/A 1.31 5H42 25 22.875 B

N/A 26465.1 N/A 1.25 i

5H38 23 B

N/A 26800.7 N/A 1.26 i

5H26 20 B

N/A 26864.6 N/A 1.27

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5H43 20 B

N/A 27256.3 N/A 1.29 5H39 30 B

N/A 26177.1 N/A 1.23 SH40 25 B

N/A 26069.7 N/A 1.23 5H28 25 B

N/A 26601.1 N/A 1.25 5H44 15 B

N/A 26290.9 N/A 1.24 i

5H04 19 18.5 C

N/A 25828.1 N/A 1.22 5H01 15 C

N/A 259440 N/A 1.22 i

j SH03 20 C

N/A 25823.6 N/A 1.22 SH02 20 C

N/A 25716.0 N/A 1.21 j

CYCLE BURNUP 20738.0 21207.6 4

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ENCLOSURE 2

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HISTORY OF UNIT 2 CYCLE 5 RODDED FUEL ASSEMBLIES AND DROP TIMES Cycle 5 RCCA Drop Times (msec)

RCCA EOC4 EOC5 BOCS EOC5 Location ASSY BURNUP BU SHARE BURNUP BU SHARE Dashpot Turnaround Dashpot Turnaround F10 SS05 19800.5 1.01 43522.0 1.07 1566 2116 1642 2152 F6 SS08 19949.3 1.02 43918.9 1.08 1628 2148 1630 2210 K6 5S09 20095.4 1.03 44224.5 1.09 1566 2116 1638 2168 K10 SS10 19724.9 1.01 43758.8 1.08 1588 2158

'1622 2172 M4 SS13 23901.5 1.22 47234.3 1.05 1566 2136 1606 2156 I

D12 SS14 23730.1 1.21 47214.2 1.06 1574 2144 1598 2148 i

D4 SS27 24152.0 1.23 47577.9 1.05 1592 2132 1582 2152 M12 SS29 23707.5 1.21 46960.8 1.05 1650 2130 1602 2152 M2 SS35 26947.9 1.38 40182.8 0.60 1C20 2150 1660 2180 D14 SS37 26909.3 1.37 40483.5 0.61 1604 2134 1640 2140 D2 SS39 26752.2 1.37 39886.4 0.59 1646 2196 1598 2178 s

B12 5S40 26733.7 1.36 40055.6 0.60 1636 2176 1624 2124 P12 SS42 26852.7 1.37 40437.1 0.61 1596 2186 1648 2178 j

H8 SS44 27007.6 1.38 48241.1 0.96 1586 2126 1648 2168 M14 SS46 26819.2 1.37 40022.5 0.59 1658 2178 1648 2188 P4 SS47 26705.6 1.36 39889.9 0.59 1566 2146 1592 2152 B4 SS49 26801.1 1.37 40017.0 0.59 1662 2192 1620 2170 B10 ST13 25667.8 1.16 1616 2126 1618 2178 P6 ST14 25425.1 1.14 1556 2096 1592 2152 K2 ST15 25856.9 1.16 1602 2122 1612 2142 H14 ST17 26401.0 1,19 1574 2094 1580 2100 P10 ST21 26133.4 1.18 1540 2080 1598 2108 H2 ST22 26571.5 1.20 1568 2118 1602 2142 B8 ST23 26291.9 1.18 1654 2124 1632 2182 1

P8 ST26 26481.1 1.19 1574 2074 1572 2102 K14 ST27 25819.7 1.16 1570 2080 1604 2124 F2 ST29 25447.8 1.15 1568 2108 1624 2134 F14 ST30 26411.8 1.19 1594 2104 1592 2142 B6 ST32 25701.0 1.16 1572 2142 1600 2200 M8 ST33 29282.1 1.32 1576 2116 1636 2166 J3 ST34 29738.7 1.34 1G04 2154 1634 2224 N9 ST35 29599.3 1.33 1610 2110 1618 2188 G3 ST36 29593.4 1.33 1608 2148 1674 2234 H4 ST37 29228.1 1.32 1568 2118 1588 2198 J13 ST38 29485.8 1.33 1620 2140.

1640 2160 G13 ST39 29536.9 1.33 1594 2114 1590 2180 C9 ST40 29310,2 1.32 1620 2140 1626 2176 H12 ST41 29439.4 1.33 1584 2094 1644 2184 N7 ST42 29369.4 1.32 1586 2096 1600 2160 C7 ST43 29523.5 1.33 1602 2112 1608 2178 D8 ST44 29213.0 1.32 1628 2128 1612 2182 L3 ST55 29757.1 1.34 1622 2142 1706 2236 L13 ST56 29042.8 1.31 1602 2142 1572 2132 K8 ST60 29895.0 1.35 1636 2146 1636 2166 E3 ST63 29360.3 1.32 1540 2120 1612 2172 H6 ST69 29802.4 1.34 1624 2124 1648 2208 C5 ST72 29556.3 1.33 1544 2124 1582 2182 N5 ST77 29450.5 1.33 1596 2086 1612 2142 H10 ST79 29983.0 1.35 1634 2124 1656 2156 C11 ST81 29306.4 1.32 1582 2122 1602 2152 F8 ST82 29836.6 1.34 1578 2148 1622 2192 N11 ST84 30344.7 1.37 1578 2128 1604 2154 E13 ST86 30050.3 1.35 1622 2142 1644 2164 END OF CYCLE 4 BURNUP 19596.5 MWD /MTU END OF CYCLE 5 BURNUP 22214.4 MWD /MTU