ML20078A286
| ML20078A286 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/18/1995 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-93-04, GL-93-4, NUDOCS 9501240347 | |
| Download: ML20078A286 (2) | |
Text
.-
- ~
e' A
' ghg 107 Selden Street, Berlin, CT 06037 t
Utilities System so,a,em s,+ c,m,.ny P.O. Box 270 Hsetford, CT 06141-0270 (203) 665-$000 January 18, 1995-Docket No. 50-423 B15089 Re:
Generic Letter 93-04 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Resnonse to Recuest for Additional Information-Generic Letter 93-04 The purpose of this letter is for Northeast Nuclear Energy Company (NNECO) to respond to a
request for additional information transmitted by [[letter::B14971, Application for Amend to License NPF-49,incorporating Changes Recommended in GL 93-05 Re DG SR & Other DG SR Concerning Cold Starts|letter dated December 9, 1994]],f and to document its commitment to implement the current order timing modification and the new current order surveillance test for resolution of Generic Letter 93-04 at Milistone Unit No. 3 during our next refueling outage, scheduled to begin in April 1995.
By lettsrs dated August 4, 1993,
- and September 20, 1993, m NNECO provided the required 45 and 90 day responses to Generic Letter t
93-04.
These respontes summarized the compensatory actions taken by NNECO in response to the Salem rod control failure event, stated continued compliance to Generic Design Criterion (GDC) 25, and provided the status for potential long-term enhancements related to this issue.
In these letters, NNECO stated that while the assessment indicates that the licensing basis is currently satisfied, there are measures that can be taken to clarify compliance with GDC 25.
These measures developed by the Westinghouse Owner's Group (WOG) include a combination of rod control system logic cabinet changes (current order timing adjustments) and an additional plant surveillance.
(1)
V.
L.
Rooney letter to J.
F.
Opeka, " Request for Additional Information (RAI) Regarding Generic Letter 93-04, ' Rod Control System Failure and Withdrawal of Rod Cluster Control Assemblies, 10CFR50. 54 (f) '
(TAC No.
M86855), "
dated December 9, 1994.
(2)
J.
F. Opeka letter to the U.S. Nuclear Regulatory Commission,
" Response to Generic Letter 93-04," dated August 4, 1993.
(3)
J.
F. Opeka letter to the U.S. Nuclear Regulatory Commission,
" Response to Generic Letter 93-04," dated September 20, 1993.
o g (; O /
wa nna%
9501240347 950118 0
PDR ADOCK 05000423 Og P
fg G 1
J1 U.S. Nuclear Regulatory Commission B15089/Page 2 January 18, 1995 NNECO indicated that implementation of these activities was contingent upon NRC Staff review and acceptance of the WOG initiatives.
The NRC Staff's letter of December 9, 1994, indicated that the Staff, by letter dated November 10, 1994, to the WOG approved the following documents:
- 1) WCAP-13864 Revision 1,
" Rod Control System Evaluation Program";
2)
Westinghouse Technical Bulletin NSD-TB-94-05-RO, " Rod Control CRDM Timing Change," and 3)
"WOG Recommended Rod Control System Surveillance Test".
Since the WOG recommended actions have been approved by the NRC Staff, NNECO commits to modify the rod control system current order timing to prevent any uncontrolled asymmetric rod withdrawal in the event of the failure identified at Salem.
If corrupted current orders are
- present, none of the rods will move (with e high degree of certainty) once the current order timing adjustments are made.
NNECO will also implement a new current order surveillance (such as current order traces from each group following each refueling outage) to ensure detectability.
These modifications will be implemented during the upcoming Millstone Unit No.
3 refueling outage.
As requested by the NRC Staff, NNECO will inform the Staff in writing after implementing the current order timing modification and the new current order surveillance test.
If you should have any questions on the above, please contact Mr.
T. G. Cleary at (203) 267-3934.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY F
J.
F.
Opekd U
Executive Vice President cc:
T.
T.
Martin, Region I Administrator V.
L.
Rooney, NRC Project Manager, Millstone Unit No.3 P. D. Swetland, Senior Resident Inspector, Millstone Unit No.3