ML20112B911
| ML20112B911 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/20/1996 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9605240079 | |
| Download: ML20112B911 (4) | |
Text
3 Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 May 20,1996 Bulletin 96-01 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Summary Report for Prairie Island Rod Drop Data (requested b.y Bulletin 96-01) from Unit 2 Reactor Trio of Aoril 18.1996 i
This letter is to summarize results of Rod Drop testing performed at Prairie Island Nuclear Generating Plant following a Unit 2 Reactor Trip which occurred on April 18, 1996. This testing was performed per requested action #3 of NRC Bulletin 96-01 Control Rod Insertion Problems.
Testing was performed identically to the normal refueling test by simultaneously dropping all rods from a full out position at hot (547 F) full pressure (2235 psig) full flow (100%) condition. The results of this test were essentially identical to testing previously reported on April 18,1996 (within i30 msec). Of the 29 rods tested the highest exposure rod was approximately 42,938 MWD /MTU. All of the rods tested met the technical specification drop time requirements. No abnormalities were detected in rod drop time (rod full out to entry to dash pot region) nor in total rod drop time (full out to rod bottom). All rods experienced recoil upon rod bottom similar to normal refue:!ng rod drop testing. In comparisors of rod drop times to data submitted April 18,1996, no degradation in drop time nor rod recoil was evident.
The testing performed verified operability of each of the control rode and did not require any corrective actions.
9605240079 960520 PDR ADOCK 0500 2
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.USNRd NORTHERN STATES POWER COMPANY May 20,1996 Page 2 in addition attached to this letter is a corrected Unit 2 burnup table from our April 8, 1996 original response letter showing the correct current" date of 2/29/96 rather than 2/29/95 in the column header.
In this letter we have made no new Nuclear Regulatory Commission commitments.
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions related to this letter.
ON~Y 0lt l
I Michael D Wadley l
Plant Manager Prairie Island Nuclear Generating Plant l
1 c:
Regional Administrator - Region Ill, NRC Senior Resident inspector, NRC i
NRR Project Manager, NRC 4
J E Silberg Attachments-
- 1. Affidavit
- 2. Fuel Burnup Data for Unit Two Cycle Seventeen i
e J
BU9601-2. DOC
l 4
UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 BULLETIN 96-01, CONTROL ROD INSERTION PROBLEMS Northem States Power Company, a Minnesota corporation, with this letter is submitting information requested by NRC Bulletin 96-01.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY BY
/14E ~
Michael D Wadley Plant Manager Prairie Island Nuclear Generating Plant On this O
ay of M
before me a notary public in and for said County, pdrsonally appeared Mi@ledged that he is authorized to execute this docum aef D Wadley, Plant Manager, Prairie Island Nuclear Generating Plant; and being first duly swom acknow Northem States Power Company, that he knows the conte ts thereof, and that to the best of his knowledge, information, and be ief the s ments made in i are true and that it is not interposed for delay.
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MARCIA K. LaCORE NOTARY PUBUC-MlNNESOTA D L'y Commission Expres hn.31,2000 hl HENNEPIN COUNTY l
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1 Unit Two Cyclo Ssvantsen Control Burnup At Rod BOC Timing Burnup on Projected EOC Fuel Core Control Bank Test 2/29/96
. Exposure Assembly Location Rod-Group (MWD /MTU) (MWD /MTU)
(MWD /MTU)
P-22 G07 R-148 C2 35775 41776 50490 T-51 D04 R-132 C2 23749 34301 47340 T-53 D10 R-147
~C1 24097 34762 47340 T-54 J10 R-138 C2 24222 34899 47340 T-56 J04 R-141 C1 24020 34788 47340 T-66 K07 R-158 D1 24381 35656 49020 T-67 C07 R-152 D1 24453 35677 49020 4
T-68 G03 R-151 D1 24387 35642 49020 T-69 G11 R-150 D1 25120 36395 49020 T-82 F08 R-145 B1 27669 37392 50100 T-83 F06 R-157 B1 27895 37828 50100 T-84 H06 R-134 B1 27960 37763 50100 T-85 H08 R-142 B1 27611 37372 50100 U-66 LO8 R-131 A2 0
11243 25720 U-67 F12 R-154 A2 0
11501 25720 U-68 B0G R-136 A2 0
11091 25720 U-69 H02 R-139 A2 0
11013 25720 U-70 H12 R-143 A1 0
11443 25720 U-71 B08 R-135 A1 0
10943 25720 U-72 F02 R-156 A1 0
11084 25720 U-73 LOG R-153 A1 0
11292 25720 U-90 K09 R-144 S.B1 0
11829 28070 U-91 E11 R-137 S.B1 0
11924 28070 U-92 C05 R-140 S.B1 0
11788 28070 U-93 10 3 R-133 S.B1 0
11820 28070 U-94 11 1 R-155 S.A1 0
11991 28070 U-95 C09 R-146 S.A2 0
11876 28070 U-96 E03 R-149 S.A1 0
11655 28070 U-97 K05 R-159 S.A2 0
11828 28070 Fuel Burnup Data
.