ML18153A468
| ML18153A468 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/13/1996 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18152A471 | List: |
| References | |
| 96-135A, IEB-96-001, IEB-96-1, NUDOCS 9606180351 | |
| Download: ML18153A468 (2) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 13, 1996 United States Nuclear fqegulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.
96-135A NL&OS/GDM RO Docket No.
50-280 50-281 License No.
DPR-32 DPR-37 NRC BULLETIN 96-01 ON CONTROL ROD INSERTION PROBLEMS CONTROL ROD PERFORMANCE TEST RESULTS On March 8, 1996, the NRC issued Bulletin 96-01, "Control Rod Insertion Problems,"
which requested licensees to complete several actions to determine whether control rod insertion problems were a concern at their facilities.
The bulletin requested licensees to *measure and evaluate control rod drop times and rod recoil data for all control rods during 1996 outages of sufficient duration.
Licensees were also requested to measure and evaluate drag forces for all rodded fuel assemblies for plant conditions where the reactor vessel head was removed.
We recently completed a refueling outage for Surry Power Station Unit 2, during which we performed the required control rod tests and evaluations. This information has been summarized and is provided in the attachment. We have also evaluated an additional ten fuel assemblies in support of the Westinghouse root cause efforts in this area. This data is also provided in the attachment for your information.
Based on the evaluation of the data presented in the attachment, the control rods in Surry Unit 2, Cycle 13, operated as designed without any incident of incomplete control rod insertion. The data in this report support the conclusion presented in of Virginia Power's response to NRG Bulletin 96-01 which states that the control rods in Surry Units 1 and 2 remain operable consistent with current information, and that operation of Surry Unit 1, Cycle 14, and Surry Unit 2, Cycle 14, to their respective design burnup limits is acceptable.
Should you have any questions or require additional information, please contact us.
Very truly yours,
~~l'.W'~
James P. O'Hanlon Senior Vice President - Nuclear Attachment
- --- 9606180351-960.613 -- --- - --
*,17 0 0 3 i1 PDR ADOCi( 05000280 I
~jL_-"----------- PDR __ ~ ___ ~--___ )
cc:
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station