ML20133B575
| ML20133B575 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/20/1996 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9701060029 | |
| Download: ML20133B575 (7) | |
Text
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O, v Valley Power station Stdppingport. PA 15077-0004 W n Vbe eskient Fax 412) 8 3 owYo*maion December 20, 1996 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to NRC Bulletin No. 96-01:
Control Rod Insertion Problems Attached is the Duquesne Light Company (DLC) report summarizing the data and documenting the results for Beaver Valley Power Station Unit No. 2 Fuel Cycle 7 beginning 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 Insenion Problems.
Based on the evaluation of the data obtained for control rod testing at the beginning j
of Cycle 7 at Beaver Valley Power Station Unit No. 2, no difficulties were encountered with control rods failing to insert completely on a scram signal. Additional data is included in the attached report.
The DLC response to Bulletin 96-01 dated July 18, 1996, provided a core esp showing the projected end-of-life burnup for rodded fuel assemblies in Beaver Valley Power Station Unit No. 2 Cycle 7. Due to cladding defects which were identified in some fuel assemblies during the 6th refueling outage, the originally planned core loading scheme was modified so the fuel assemblies with leaking fuel rods would not be reloaded into the core. The revised projected burnup values for the as-loaded Unit No. 2 Cycle 7 core are shown as Attachment 2 to this letter. The maximum projected burnup for any rodded fuel assembly decreased slightly from the values originally reported (41,071 MWD /MTU versus 41,108 MWD /MTU). Thus it is still expected that full insenion of the control rods will occur should a reactor trip be required during Unit No. 2 Cycle 7 lifetime. All rodded assemblies in Unit No. 2 Cycle 7 are Westinghouse Vantage 5 Hybrid fuel assemblies.
dD9 l DEllVERillG 4
9701060029 961220 PDR ADOCK 05000412 0UALITY 0
E 11 E R G Y
C Beaver Valley Power Station, Unit No. 2 Response to NRC Bulletin No. 96-01:
Control Rod Insertion Problems Page 2 If you have any questions concerning this response, please contact Mr. Roy K.
Brosi at (412) 393-5210.
Sincerely, i
Sushil C. Jain Attachment i
c:
Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Mar.ager 4
e A
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B,e:ver Valley Pcwer Stati:n, Unit No. 2 Response to NRC Bulletin No. 96-01:
Control Rod Insertion Problems Page 3 bc: Mr. M. L. Bowling (VEPCO)
Mr. John Duran (Westinghouse) 4 l
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4 W
l
i AFFIDAVIT i
COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNTY OF BEAVER
)
Subject:
Beaver Valley Power Station, Unit.No. 2 Docket No. 50-412, License No. NPF-73 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, i
who being duly swom according to law, deposes and says that he is Division Vice President, Nuclear Services of the Nuclear Power Division, Duquesne Light Company, 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.
1 Sushil C. Jain i
Subscribed and sworn to before me on thisAd-kay ofOJ'dt/LN4 L&La [bk.n?N Wotary Public retv: w Tramy A Bace.,daryPubhc Eh My
_.e -am
e Attachm:nt 1 Response to NRC Bulletin 96-01 3
l Unit 2 Cycle 7 Beginning of Life Control Rod Testing 7
Rod Drop Testing On November 29,1996, Control Rod Drop Time measurements were performed for all 48 control rods in the core. Drop times were measured from the opening of the 1
i reactor trip breakers to rod entry into the dashpot region and from rod entry into the dashpot region to rod bottom. Each trace was also checked for rod bottom recoil to ensure all rods reached the rod bottom position. All drop times to dashpot entry were i
within the Technical Specification limit of 2.7 seconds and all rods demonstrated positive evidence ofrecoil(3 to 5 bounces). A summary of the Beginning of Life (BOL)
{
drop tests for Cycles 6 and 7 is listed below.
1 l
Time to dashpot (sec).
Time to rod bottom (sec) i Test Average Fastest Slowest Average Fastest Slowest l
Cycle 6 1.40 1.35 1.50 1.86 1.79 1.99 Cycle 7 1.39 1.34 1.50 1.84 1.78 1.93 t
l All control rod drop times from the BOL test for Cycle 7 with the corresponding j
fuel assembly BOL burnups are listed in Table 1.
J i
l Control Rod Drag Test i
Control rod drag tests in the reactor vessel were performed on November 18, i
1996.
All 48 control 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 during withdrawal, and minimum weight during insertion were measured using a spring scale and recorded.
i Maximum drag measurements in the dashpot or non-dashpot region for all control j
rods were between 10 and 40 pounds. These values are within the acceptance criteria of l
40 pounds in the non-dashpot region and 100 pounds in the dashpot region. Maximum j
drag measurements in the non-dashpot region for all control rods are listed in Table 1.
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Table 1.
Response to NRC Bulletin 96-01 Beaver Valley Power Station Unit 2 Cycle 7 BOL Rod Drop and Drag Test Results Core Assembly Assembly Drop Time Dashpot to Drop Time Dead Max.or Min.
Max. Drag Location ID Bumup to Dashpot Rod Bottom Total Weight Weight Non-Dashpot (MWD /MTU)
(sec.)
(sec)
(sec)
(Ibs)
(Ibs)
(Ibs)
B6 G67 30708 1.50 0.43 1.93 415 430 15 B10 G68 30708 1.42 0.44 1.86 415 425 10 P6 G57 30708 1.39 0.43 1.82 420 430 10 P10 G59 30708 1.39 0.42 1.81 410 435 25 F2 G63 30641 1.40 0.44 1.84 415 425 10 F14 G60 30641 1.38 0.46 1.84 410 430 20 K2 G62 30641 1.43 0.46 1.89 415 425 10 K14 G58 30641 1.47 0.46 1.93 415 425 10 F4 H55 21674 1.39 0.49 1.88 415 430 15 F12 H49 21674 1.42 0.49 1.91 410 435 25 K4 H42 21674 1.37 0.47 1.84 _
415 425 10 K12 H50 21674 1.40 0.46 1E3 430 405 25 D6 H53 21654 1.38 0.50 1.87 410 435 25 D10 H54 21654 1.37 0.47 1.84 415 430 15 M6 H45 21654 1.40 0.46 1.86 405 445 40 M10 H43 21654 1.39 0.46 1.85 415 435 20 E5 H23 21421 1.38 0.47 1.85 415 430 15 E11 H07 21421 1.39 0.46 1.85 415 430 15 L5 H12 21421 1.37 0.43 1.80 415 430 15 L11 H05 21421 1.37 0.48 1.85 410 435 25 H6 H08 18216 1.35 0.44 1.79 420 430 10 H10 H16 18216 1.37 0.44 1.81 415 435 20 F8 H09 18216 1.37 0.44 1.81 415 430 15 K8 H11 18216 1.35 0.45 1.80 415 425 10 Page 2 N
Table 1.
Response to NRC Bulletin 96-01 Beaver Valley Power Staten Unit 2 Cycle 7 BOL Rod Drop and Drag Test Results Core Assembly Assembly Drop Time Dashpot to Drop Time Dead Max.or Min.
Max. Drag Location ID Bumup to Dashpot Rod Bottom Total Weight Weight Non-Dashpot (MWD /MTU)
(sec.)
(sec)
(sec)
(Ibs)
(Ibs)
(ibs)
F6 H10 17126 1.36 0.48 1.84 415 430 15 F10 H18 17126 1.38 0.42 1.80 415 435 20 K6 H14 17126 1.35 0.45 1.80 415 430 15 K10 H24 17126 1.38 0.44 1.82 415 430 15 G7 H15 17010 1.34 0.46 1.80 415 435 20 G9 H13 17010 1.37 0.45 1.82 410 430 20 J7 H03 17010 1.34 0.47 1.81 415 435 20 J9 H01 17010 1.34 0.44 1.78 415 435 20 H2 J02 0
1.41 0.45 1.86 415 430 15 B8 J12 0
1.44 0.44 1.88 415 425 10 P8 J01 0
1.38 0.44 1.82 415 430 15 H14 J07 0
1.40 0.42 1.82 420 430 10 C7 J52 0
1.39 0.44 1.83 415 430 15 C9 J58 0
1.38 0.42 1.80 415 425 10 N7 J63 0
1.36 0.44 1.80 415 430 15 N9 J59 0
1.38 0.44 1.82 415 430 15 G3 J54 0
1.41 0.43 1.84 415 430 15 G13 J61 0
1.36 0.46 1.82 415 425 10 J3 J51 0
1.36 0.46 1.82 415 435 20 J13 J49 0
1.34 0.46 1.80 410 430 20 D4 J22 0
1.44 0.45 1.89 415 425 10 D12 J35 0
1.37 0.46 1.83 415 430 15 M12 J21 0
1.39 0.48 1.87 410 430 20 M4 J37 0
1.39 0.49 1.88 415 430 15 Page 3
R;spons*eTo NRd Bulletin 96-01 Revised Unit 2 Cycle 7 EOL Burnups (MWD /MTU)
R P
N M
L K
J H
G F
E D
C B
A 1
2 41045 19851 41045 3
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4 20480 39360 39360 20480 5
38586 38588 6
41071 39274 35318 36357 35318 39274 41071 7
23253 34144 34144 23253 0
19851 36357 36357 19851 9
23253 34144 34144 23253 10 41071 39274 35318 36357 35318 39274 41071 11 38586 3858s 12 20480 39360 39360 20480 13 23375 23375 14 41045 19851 41045 15 i
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