ML032470060
| ML032470060 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/03/2003 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Clifford J NRC/NRR/DLPM/LPD1 |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| TAC MB8137 | |
| Download: ML032470060 (3) | |
Text
September 3, 2003 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Victor Nerses, Sr. Project Manager, Section 2
/RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB8137)
The attached draft RAI was transmitted by facsimile on September 3, 2003, to Mr. Ravi Joshi, Dominion Nuclear Connecticut, Inc. (licensee). This draft RAI was transmitted to facilitate the technical review being conducted by Office of Nuclear Reactor Regulation (NRR) and to support a conference call with the licensee to discuss the RAI. The RAI was related to the licensees submittal dated March 4, 2003, concerning the Fuel Handling Accident using a selective implementation of the Alternate Source Term. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRR staff position regarding the licensees request.
Docket No. 50-423
Attachment:
Draft RAI
September 3, 2003 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Victor Nerses, Sr. Project Manager, Section 2
/RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB8137)
The attached draft RAI was transmitted by facsimile on September 3, 2003, to Mr. Ravi Joshi, Dominion Nuclear Connecticut, Inc. (licensee). This draft RAI was transmitted to facilitate the technical review being conducted by Office of Nuclear Reactor Regulation (NRR) and to support a conference call with the licensee to discuss the RAI. The RAI was related to the licensees submittal dated March 4, 2003, concerning the Fuel Handling Accident using a selective implementation of the Alternate Source Term. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRR staff position regarding the licensees request.
Docket No. 50-423
Attachment:
Draft RAI DISTRIBUTION PUBLIC J. Clifford V. Nerses H. Li PDI-2 Reading Accession Number: ML032470060 OFFICE PDI-2/PM EEIB/SC NAME VNerses EMarinos DATE 09/03/03 09/03/03 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 (TAC NO. MB8137)
By letter dated March 4, 2003, Dominion Nuclear Connecticut, Inc. (the licensee) submitted a proposed amendment to the Technical Specifications (TS) for Millstone Unit 3. The proposed amendment would selectively implement the Alternate Source Term for the Fuel Handling Accident Analyses. The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed changes to the TS. In order for the staff to complete its evaluation, the following additional information is requested:
In the licensees submittal, a request was made to delete technical specifications (TS) 3.3.2, Engineered Safety Features Actuation System Instrumentation, functional unit 3.c, Containment Isolation, Purge Isolation and the related Surveillance Requirements, Instrumentation Trip Setpoints, and notes related to that functional unit. The licensee states that the proposed changes under re-analyses of the FHA, allow plant operation without the capability for an automatic purge valve closure during core alterations and during movement of irradiated fuel. The staff considers that this deletion from TS should be treated as a relocation of selected TS requirements and as such the licensee should follow the guidance provided in NRC Generic Letter 95-10, Relocation of Selected Technical Specifications Requirements Related to Instrumentation. Therefore, the licensee is requested to justify why this deleted item no longer meets the four criteria in 10 CFR 50.36(c)(2)(ii), regarding TS limiting condition for operation.