ML20117L166
| ML20117L166 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/10/1996 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9606140031 | |
| Download: ML20117L166 (6) | |
Text
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y Beaver Vdey Power Station Shippingport, PA 15077 0004
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n P esident June 10, 1996 raxh!lN$$$
Nuclear Power DMalon U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No.1 i
BV-1 Docket No. 50-334, License No. DPR-66 Response to NRC Bulletin No. 96-01:
~
Control Rod Insertion Problems Attached is the Duquesne Light Company report summarizing the data and documenting the results for Beaver Valley Power Station Unit No.1 Fuel Cycle 12 beginning of life 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-Oli Control Rod Insertion Problems.
Based on the evaluation of the data obtained for control rod testing at the beginning of Cycle 12 at Beaver Valley Power Station Unit No.1, no difficulties were encountered with control rods failing to insert completely on a scram signal. In our April 24,1996, 1
submittal to you on this issue, we reported the results of the testing performed at Beaver i
Valley Power Station Unit No.1 (BV-1) at the end of Cycle 11.
That testing i
demonstrated the operability of the control rods in fuel assemblies with maximum burnup of 44,399 MWD /MTU. The projected maximum fuel assembly burnup in rodded fuel assemblies at the end of BV-1 Cycle 12 is 46,743 MWD /MTU. This represents an additional burnup ofless than 2,500 MWD /MTU. The successful testing completed for BV-1 Cycle 12 at the beginning oflife demonstrates operability of the control rods at the start of the fuel cycle.
Throughout BV-1 Cycle 12 lifetime the normal Technical Specification surveillance testing of the control rods will be performed. This testing will i
demonstrate operability of the control rods in accordance with Technical Specification surveillance requirements. According to information which was presented to the NRC at a Westinghouse Owners Group / Westinghouse /NRC meeting on May 15,1996, at the NRC offices in Rockville, MD, concerning NRC Bulletin 96-01, there have been over 9606140031 960610 DEllVERING PDR ADOCK 05000334 gggg;7y G
PDR ENERGV
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l Beaver.Vclicy Power Station, Unit No.1 Response to NRC Bulletin No. 96-01:
Control Rod Insedion Problems Page 2 l
540 successful control rod insertions in fuel assemblies with burnup greater than 42,500 MWD /MTU.
This includes 87 successful control rod insenions in fuel assemblies with burnup in the range of 47,500 to 52,500 MWD /MTU. As noted earlier the projected maximum burnup of rodded fuel assemblies for BV-1 Cycle 12 is 46,743 l
MWD /MTU. Thus it is expected, based on the available data, that full insertion of the l
control rods will occur should a reactor trip be required during BV-1 Cycle 12 lifetime.
\\
l If you have any questions concerning this response, please contact Mr. Roy K.
l Brosi at (412) 393-5210.
Sincerely, l
Sushil C. Jain Attachment c:
Mr. L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager i
COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNTY OF BEAVER
)
Subject:
Beaver Valley Power Station, Unit No.1 BV-1 Docket No. 50-334, License No. DPR-66 l
Response to NRC Bulletin No. 96-01:
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 President, Nuclear Services of the Nuclear Power Division, Duquesne Light Company, 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 j
his knowledge, information and belief.
Sushil C. Jain Subscribed and swom to before me on this/
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V ALud b ao>eb Notfrly Pubtfc mmdsses Beo w m aw t h
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1 DUQUESNE LIGHT COMPANY Nuclear Power Division
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l ATTACHMENT 1 l
Beaver Valley Power Station Unit 1 Cycle 12 Beginning of Life Control Rod Testing l
l l
Rod Drop Testing Between May 8,1996, and May 10,1996, Control Rod Drop Time measurements were performed for all 48 rods in the core.
Drop times were measured from the l
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 l
rod bottom recoil to ensure all rods reached the rod bottom position. All drop times to i
dashpot entry were within the Technical Specification limit of 2.7 seconds and all rods demonstrated positive evidence of recoil (greater than 4 bounces). A smnmary of the l
Beginning of Life (BOL) drop tests for Cycle 11 and 12 are listed below.
j 1
l Time to dashpot Time to rod bottom
.l l
BOL Test Average Fastest Slowest Average Fastest Slowest Cycle 11 1.22 1.18 1.35 1.74 1.68 1.83 Cycle 12 1.22 1.18 1.35 1.75 1.69 1.95 All rod drop times for the Cycle 12.BOL test with the conesponding BOL assembly burnups are listed in Table 1.
Control Rod Drag Tests Control rod drag tests were performed from April 20'through April 21,1996. All 48 rods were drag tested by withdrawing the control rod approximately ten feet out of I
the assembly and reinserting it. During this time the initial dead weight, maximum l
weight during withdrawal, and minimum weight during insertion were measured using a sprmg scale.
l Drag measurements for all rods were between 20 and 30 pounds. These values are well within the acceptance criteria of 45 pounds in the non-dashpot region and 100 pounds in the dashpot region. Drag measurements are listed in Table 1.
Table 1.
Response to NRC Bulletin 96-01 Beaver Valley Power Station Unit 1 Cycle 12 BOL 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)
F6 M25 32523 1.22 0.52 1.74 460 490 30 K6 M12 32523 1.20 0.54 1.74 460 480 20 F10 M24 32523 1.22 0.49 1.71 460 490 30 K10 '
M02 32523 1.22 0.52 1.74 460 480 20 H6 M14 31488 1.22 0.56 1.78 450 480 30 F8 M22 31488 1.22 0.48 1.70 460 490 30 K8 M17 31488 1.22 0.53 1.75 450 480 30 H10 M13 31488 1.22 0.52 1.74 450 480 30 D6 M56 27801 1.21 0.50 1.71 450 480 30 M6 M44 27801 1.20 0.62 1.82 450 480 30 D10 M59 27801 1.20 0.56 1.76 450 480 30 M10 M34 27801 1.20 0.50 1.70 460 480 20 F4 M58 27065 1.20 0.52 1.72 460 480 20 K4 M38 27065 1.22 0.54 1.76 460 480 20 F12 M36 27065 1.20 0.53 1.73 450 480 30 l
K12 M37 27065 1.18 0.51 1.69 450 480 30 D4 N48 15234 1.22 0.59 1.81 450 480 30 M4 N38 15234 1.22 0.56 1.78 460 480 20 D12 N43 15234 1.20 0.52 1.72 450 480 30 j
M12 N37 15234 1.22 0.50 1.72 460 480 20 F2 N40 14954 1.22 0.56 1.78 460 400 30 i
K2 N41 14954 1.23 0.52 1.75 460 490 30 F14 N45 14954 1.23 0.56 1.79 450 480 30 j
K14 N42 14954 1.30 0.55 1.85 460 490 30 Page 2
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Table 1.
j Response to NRC Bulletin 96-01 Beaver Valley Power Station Unit 1 Cycle 12 BOL Rod Drop and Drag Test ResuP.s 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)
B6 N44 14921 1.35 0.60 1.95 450
-480 30 P6 N39 14921 1.22 0.58 1.80 460 490 30 B10 N47 14921 1.28 0.53 1.81 450 470 20 N46 14921 1.21 0.53 1.74 450 480 30 P10 G7 N02 14349 1.20 0.53 1.73 460 490 30 J7 N01 14349 1.20 0.51 1.71 460 480 20 G9 N04 14349 1.18 0.55 1.73 450 480 30 J9 NO3 14349 1.24 0.46 1.70 450 480 30
~
G3 N28 0
1.20 0.50 1.70 460 480 20 J3 N26 0
1.20 0.54 1.74 450 480 30 G13 N31 0
1.20 0.53 1.73 460 480 20 J13 N30 0
1.22 0.51 1.73 460 490 30 C7 N25 0
1.20 0.49 1.69 450 480 30 N7 N35 0
1.20 0.50 1.70 460 480 20 C9 N27 0
1.20 0.56 1.76 450 480 30 N9 N36 0
1.20 0.50 1.70 450 480 30 ES N34 0
1.20 0.51 1.71 450 480 30 LS N29 0
1.20 0.51-1.71 450 480 30 E11 N33 0
1.20 0.52 1.72 450 480 30 L11 N32 0
1.22 0.51 1.73 450 480 30 H2 P41 0
1.20 0.52 1.72 450 480 30 B8 P43 0
1.28 0.59 1.87 450 480 30 P8 P42 0
1.20 0.49 1.69 460 490 30 H14 P44 0
1.22 0.51 1.73 460 480 20 Page 3
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