ML063000325
| ML063000325 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/26/2006 |
| From: | Gerald Bichof Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-835 | |
| Download: ML063000325 (6) | |
Text
Dominion Nuclear Connecticut, Inc.
i000 Dominion Boulevard, Glen Allen, Virginia 23060 Web Address: www.dom.com October 26, 2006 U. S. Nuclear Regulatory Commission Serial No.06-835 Attention: Document Control Desk NSS&UDF R1 One White Flint North Docket No. 50-423 1 1555 Rockville Pike License No. NPF-49 Rockville, MD 20852-2738 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING POST MAlNTENANCE/MODlFlCATlON SURVEILLANCE REQUIREMENTS LICENSE AMENDMENT REQUEST In a letter dated March 28, 2006, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request deleting redundant surveillance requirements (SRs) from the Millstone Power Station Unit 3 (MPS3) Technical Specifications. These SRs pertain to post-maintenancelpost-modification testing. In a facsimile dated July 14, 2006, the NRC staff forwarded a request for additional information (RAI) in order to complete its review of DNC's request. A conference call between DNC personnel and NRC staff members to discuss the contents of the RAI was conducted on July 27, 2006. The response to the RAI for MPS3 is provided in Attachment 1 to this letter.
The additional information provided in this letter does not affect the conclusions of the significant hazards consideration discussion in the DNC letter dated March 28, 2006.
If you have any questions in regard to the responses provided, or require additional information, please contact Mr. Paul R. Willoughby at (804) 273-3572.
Very truly yours, Gerald T. Bischof u Vice President - Nuclear Engineering Commitments in this letter: None Attachments: (1)
Serial No.06-835 Docket No. 50-423 Response to Request for Additional Information Page 2 of 3 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No.06-835 Docket No. 50-423 Response to Request for Additional Information Page 3 of 3 COMMONWEALTH OF VIRGINIA )
1 COUNTY OF HENRICO 1 The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T. Bischof, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this ab* day of @ a ,2006.
f i My Commission Expires: & - 31,a 8 .
(SEAL)
Serial No.06-835 Docket No.05-423 ATTACHMENT 1 POST MAINTENANCE/MODIFICATlONSURVEILLANCE REQUIREMENTS LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
Serial No.06-835 Docket No. 50-423 Response to Request for Additional Information Attachment 1 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITION INFORMATION REGARDING POST MAlNTENANCElMODlFlCATlONSURVEILLANCE REQUIREMENTS LICENSE AMENDMENT REQUEST In a letter dated March 28, 2006, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for deleting redundant surveillance requirements (SRs) pertaining to post-maintenancelpost-modification testing, from the Millstone Power Station Unit 3 (MPS3) Technical Specifications. In a facsimile dated July 14, 2006, the NRC staff forwarded a request for additional information (RAI) in order to complete its review of DNC's request. A conference call between DNC personnel and NRC staff members to discuss the contents of the RAI was conducted on July 27, 2006. The response to the RAI for MPS3 is provided in the balance of this attachment.
NRC Question The licensee proposed to delete from the Technical Specifications the following post-maintenance SRs: SR 4.1.3.4.b, a portion of SR 4.5.2.9.1, and SR 4.5.2.h.
The licensee claimed that the removal of these portions of the SRs is adequate by citing SR 4.0.1, which states in the associated Bases section, in part, that "upon completion of maintenance, appropriate post-maintenance testing is required to declare the equipment operable." However, neither SR 4.0.1 nor the associated Bases section specify what post-maintenance testing must be completed to fulfill the deleted SRs. For example, SR 4.1.3.4 requires that the rod drop time be demonstrated. SR 4.5.2.g requires verification of the correct position of each electrical andlor mechanical stop for emergency core cooling system throttle valves. SR 4.5.2.h requires that flow balance testing be performed on the charging pump lines, and residual heat removal pump lines.
Identify specific post-maintenance testing requirements in the relevant maintenance procedure or documentation, and justify that the test requirements equivalent to the deleted SRs discussed above will be completed in accordance with SR 4.0.1.
With the exception of SR 4.5.2.h, the balance of the SRs proposed for deletion in DNC's March 28, 2006 submittal are included in existing system test procedures.
(See table below.) The "Frequency" section of those procedures contains language similar if not identical to that of the existing SR. While the specific TS SR references will be removed from the system test procedures and associated forms, the prescribed frequency (i.e. after maintenance or modification) will be
Serial No.06-835 Docket No. 50-423 Response to Request for Additional Information Attachment 1 Page 2 of 2 retained. The procedures are licensee-controlled documents and changes are made in accordance with 10 CFR 50.59.
Historically a unique procedure has been generated whenever TS SR 4.5.2.h was required to be performed. In order to preserve the fundamental requirement to perform ECCS flow balance testing to the specified acceptance criteria, the flow requirements for the centrifugal charging pump lines, safety injection pump lines, and RHR pump lines (TS SR 4.5.2.h.1, TS SR 4.5.2.h.2, TS SR 4.5.2.h.3) will be relocated to the MPS3 Technical Requirements Manual (TRM). The TRM will require the flow balance test to be performed following completion of modifications to the ECCS subsystems that adversely impact the flow rates described in the TRM. The TRM is a licensee-controlled document and changes to the TRM are made in accordance with 10 CFR 50.59.
SR Frequency (relevant to proposed Millstone procedure SR -proposed
. for for deletion deletion) 4.1.3.4.b SP 3451 N22, Multiple Rod Drop Time For specifically affected Test, Rev 006-02 individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those rods.
Portion of SP 37122, Setting Position of High Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, after 4.5.2.1 .g.1 Pressure Safety Injection Throttle valve(s) maintenance Valves, Rev 004-01 Portion of SP 36141.2, SLCRS Filter Bank After any structural 4.6.6.1 .b Testing, Rev. 005-02 maintenance on the HEPA filter or charcoal adsorber housings Portion of SP 3614F.2, Control Room After any structural 4.7.7.c Emergency Ventilation, Rev. 007-07 maintenance on the HEPA filter or charcoal adsorber housinas Portion of SP 3614A.2, Auxiliary Building Filter After any structural 4.7.9.b Testing, Rev. 007-03 maintenance on HEPA filter or charcoal adsorber housings Portion of SP 3646A.3, Diesel Generator After modifications which 4.8.1.1.2.h Independence Test, Rev. 006 could affect diesel generator