ML20107M413
| ML20107M413 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/24/1996 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9604300379 | |
| Download: ML20107M413 (6) | |
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ver Valley Power Station Shippingport PA 15077 0004 1
April 24, 1996 uc e
s Nuclear Power Division U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No.1 l
BV-1 Docket No. 50-334, License No. DPR-66 Response to NRC Bulletin No. 96-01:
j Control Rod Insertion Problems Attached is the Duquesne Light Company report summarizing the data and i
documenting the results for Beaver Valley Power Station Unit No.1 Fuel Cycle 11 end i
oflife measurements of the control rod drop times and drag forces for all rodded fuel assemblies. This report is being submitted to satisfy the Required Response (3) of NRC Bulletin 96-01: Control Rod Insertion Problems.
i Based on the evaluation of the data obtained for control rod testing at the end of Cycle 11 at Beaver Valley Power Station Unit No.1, no difficulties were encountered with control rods failing to insett completely on a scram signal. Operability of control rods in fuel assemblies with burnup of 44399 MWD /MTU was demonstrated.
If you have any questions concerning this response, please contact Mr. Roy K.
l Brosi at (412) 393-5210.
Sincerely, Sushil C. Jain 300105 Attachment c:
Mr. L. W. Rossbach, Sr. Resident inspector Mr. T. T. Martin, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager DillViRING QUALITY 57 ' /
iniiGv 9604300379 960424 PDR ADOCK 05000334 G
PDR l
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AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNTY OF BEAVER
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l l
Subject:
Beaver Valley Power Station, Unit No.1 BV-1 Docket No. 50-334, License No. DPR-66 Response to NRC Bulletin No. 96-01:
l Control Rod Insertion Problems Before me, the undersigned notary public, in and for the County and Commonwealth aforesaid, this day personally appeared Sushil C. Jain, to me known, who being duly sworn according to law, deposes and says that he is Division Vice l
President, Nuclear Services of the Nuclear Power Division, Duquesne Light Company,
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l he is duly authorized to execute and file the foregoing submittal on behalf of said Company, and the statements set forth in the submittal are true and correct to the best of his knowledge, information and belief.
Sushil C. Jain Subscribed and sworn to before me on this8 day of G
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l
e DUQUESNE LIGHT COMPANY Nuclear Power Division ij-ATTACHMENT 1 Beaver Valley Power Station Unit 1 Cycle 11 End of Life Control Rod Testing l
Rod Drop Testing l
l On March 23,1996, Control Rod Drop Time measurements were performed for all 48 rods in the core. Drop times were measured from the beginning of voltage decay on the stationary gripper coil to entry into the dashpot region and from entry into the dashpot region to rod bottom. Each trace was also checked for rod bottom recoil to l
ensure all rods reached the rod bottom position. All drop times to dashpot entry were j
within the Technical Specification limit of 2.7 seconds and all rods demonstrated varymg i
degrees of recoil (2 to 6 bounces).
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During the test the dashpot entry time could not be exactly determined for four rods in Control Bank D (core location B8, K6, F10, and K10). The dashpot entry time l
could not be measured due to an electrical anomaly in the RPI coil stack. This anomaly did not prevent the determination of total rod drop time. The total rod drop time for each rod was measured and found to be less than the Technical Specification limit. All rods demonstrated rod bottom recoil to varying degrees. The rods with the least number of bounces (2) were in core locations M10, J9, and G9. Rods J9 and G9 were located in assemblies with a burnup of approximately 44399 MWD /MTU and their rod drop times to rod bottom increased 0.02 seconds from the Beginning of Life (BOL) test. Rod M10 q
was located in an assembly with a bumup of approximately 35128 MWD /MTU. Its rod drop time to rod bottom increased 0.03 seconds from the BOL test. The assemblies in
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l core locations M10, J9, and G9 were not reloaded into the core for Cycle 12. A summary of the BOL and End of Life (EOL) drop tests are listed below.
l Time to dashpot Time to rod bottom Test Average Fastest Slowest Average Fastest Slowest BOL 1.22 1.18 1.35 1.74 1.68 1.83 EOL 1.25 1.17 1.38 1.73 1.67 1.86 All rod drop times for the EOL test with the corresponding assembly burnups are listed in Table 1.
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1 Response to NRC Bulletin 96-01 l
Page 2-Control Rod Drag Test i
Control rod drag tests were performed from April 1 through April 2,1996. All 48 rods were drag tested by withdrawing the control rod approximately ten feet out of the assembly and reinserting it. During this time the initial dead weight, maximum weight l
during withdrawal, and minimum weight during insertion were measured using a spring scale and recorded.
The rod with the higl.est measured drag was rod M10 which had a drag of 65 pounds in the dashpot region and 45 pounds in the non-dashpot region. This rod would nave required further evaluation since it exceeded the acceptance criteria for reactor reassembly of 40 pounds in the non-dashpot region. As stated before, the assembly in position M10 was not reloaded into the core for Cycle 12. Rods G7 and F4 had the next highest values of 45 pounds in the dashpot region. These values were within the acceptance criteria of 100 pounds in the dashpot region. Drag measurements are listed in Table 1.
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Table 1.
Response to NRC Bulletin 96-01 Beaver Valley Power Station Unit 1 Cycle 11 EOL Rod Drop and Drag Test Results Core Assembly Assembly Drop Time Dashpot to Total Dead Maximum Drag Location ID Burnup to Dashpot Rod Bottom Drop Time Weight Weight (MWD /MTU)
(sec.)
(sec)
(sec)
(Ibs)
(Ibs)
(Ibs)
G7 L27 44399 1.26 0.43 1.69 440 485 45 J7 L23 44399 1.24 0.45 1.69 450 480 30 G9 L22 44399 1.25 0.45 1.70 440 475 35 J9 L26 44399 1.28 0.44 1.72 450 490 40 F2 J59 42046 1.24 0.51 1.75 450 465 15 K2 J57 42046 1.26 0.43 1.69 450 465 15 F14 J53 42046 1.26 0.53 1.7b 440 470 30 K14 J51 42046 1.34 0.48 1.82 450 470 20 B6 J56 41680 1.38 0.44 1.82 440 460 20 PS J54 41680 1.22 0.45 1.67 450 485 35 B10 J52 41680 1.29 0.46 1.75 440 470 30 P10 J58 41680 1.24 0.46 1.70 450 470 20 G3 L49 40540 1.22 0.49 1.71 440 470 30 J3 LS1 40540 1.26 0.43 1.69 450 470 20 G13 L50 40540 1.24 0.44 1.68 450 465 15 J13 L45 40540 1.22 0.51 1.73 455 470 15 C7 L47 40388 1.22 0.51 1.73 440 460 20 N7 L48 40388 1.17 0.53 1.70 450 480 30 C9 L52 40388 1.24 0.43 1.67 440 455 15 N9 L46 40388 1.22 0.46 1.68 445 470 25 H6 M57 35809 1.24 0.48 1.72 450 470 20 F8 M39 35809 1.25 0.48 1.73 445 470 25 K8 M33 35809 1.26 0.46 1.72 440 480 40 H10 M45 35809 1.25 0.48 1.73 450 480 30 F4 M21 35166 1.24 0.46 1.70 435 480 45 K4 M19 35166 1.21 0.49 1.70 450 470 20 Page 3
Table 1.
Response to NRC Bulletin 96-01 Beaver Valley Power Station Unit 1 Cycle 11 EOL Rod Drop and Drag Test Results Core Assembly Assembly Drop Time Dashpot to Total Dead Maximum Drag Location ID Bumup to Dashpot Rod Bottom Drop Time Weight Weight (MWD /MTU)
(sec.)
(sec)
(sec)
(Ibs)
(Ibs)
(Ibs)
F12 M16 35166 1.24 0.48 1.72 440 470 30 K12 M32 35166 1.24 0.48 1.72 440 470 30 D6 M28 35128 1.26 0.50 1.76 440 460 20 M6 M29 35128 1.24 0.45 1.69 445 475 30 D10 M27 35128 1.24 0.46 1.70 440 465 25 M10 M18 35128 1.24 0.62 1.86 455 520 65 F6 N06 17130 1.28 0.47 1.75 450 465 15 K6 N21 17130
<1.73*
N/A*
1.73 450 470 20 F10 N19 17130
<1.74*
N/A*
1.74 445 470 25 K10 N05 17130
<1.75*
N/A*
1.75 450 460 10 E5 N20 16669 1.24 0.48 1.72 440 465 25 L5 N14 16669 1.23 0.49 1.72 450 460 10 E11 N09 16669 1.24 0.50 1.74 445 475 30 L11 N10 16669 1.24 0.47 1.71 450 470 20 H2 N38 15051 1.26 0.48 1.74 450 460 10 B8 N48 15051
<1.79*
N/A*
1.79 440 470 30 P8 N37 15051 1.26 0.55 1.81 450 480 30 H14 N43 15051 1.26 0.47 1.73 450 470 20 D4 NO2 14274 1.26 0.50 1.76 440 470 30 M4 N01 14274 1.26 0.46 1.72 450 480 30 D12 N04 14274 1.24 0.58 1.82 440 470 30 M12 NO3 14274 1.24 0.52 1.76 450 480 30
[
- Unable to determine Dashpot entry time due to trace anomaly.
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