ML041590024

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Request for Additional Information to Be Discussed in an Upcoming Conference Call, TAC No. MC2533
ML041590024
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/03/2004
From: Dan Collins
NRC/NRR/DLPM/LPD1
To: Clifford J
NRC/NRR/DLPM/LPD1
Collins D S, NRR/DLPM, 415-1427
References
TAC MC2533
Download: ML041590024 (3)


Text

June 3, 2004 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Daniel S. Collins, Sr. Project Manager /RA/

Project Directorate I, Section 2 Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK NUCLEAR GENERATING STATION, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC2533)

The attached draft RAI was transmitted by facsimile on June 3, 2004, to Mr. Paul Duke, PSEG Nuclear, LLC. (PSEG). This draft RAI was transmitted to facilitate an upcoming conference call in order to clarify certain items in the licensees application dated March 31, 2004, regarding the licensees usage of their Oscillation Power Range Monitor system. Review of the RAI would allow PSEG to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-354

Enclosure:

Draft Request for Additional Information

June 3, 2004 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Daniel S. Collins, Sr. Project Manager /RA/

Project Directorate I, Section 2 Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK NUCLEAR GENERATING STATION, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC2533)

The attached draft RAI was transmitted by facsimile on June 3, 2004, to Mr. Paul Duke, PSEG Nuclear, LLC. (PSEG). This draft RAI was transmitted to facilitate an upcoming conference call in order to clarify certain items in the licensees application dated March 31, 2004, regarding the licensees usage of their Oscillation Power Range Monitor system. Review of the RAI would allow PSEG to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-354

Enclosure:

Draft Request for Additional Information DISTRIBUTION:

PDI-2 Rdg PUBLIC THuang, SRXB DCollins

  • Concurrence by Memorandum, no major changes made Accession No.: ML041590024 OFFICE PDI-2/PM RORP-A/SC NAME DCollins FAkstulewicz DATE 6/3/04 5/28/04*

DRAFT REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK NUCLEAR GENERATING STATION (TAC NO. MC2533)

1. Identify any difference in response to the plant-specific actions stated in CENPD-400-P-A, Rev 01, Generic Topical Report for the ABB Option III Oscillation Power Range Monitor (OPRM) with respect to the current BWROG position for the long-term stability Solution. Specifically, provide a detailed description of the methodology for calculation of the plant-specific DIVOM correlation. Please identify the methodologies used to support the OPRM setpoints for TS 3/4.3.11.
2. Please describe in detail the current implementation status of the OPRM system including system calibration and trip set-points based on the approach stated in NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, or based on a plant-specific data approach. Provide specific values for OPRM scram setpoints and the DIVOM correlation for the next cycle.
3. Provide detailed results of the system tests to support the accuracy and operability of the new OPRM instrumentation, especially, available data bases obtained during the shutdown and subsequent startup from refueling outage.
4. Provide a description of the actions taken by PSEG according to the BWROG letter, BWROG-03049, dated September 30, 2003, Utility Commitment to NRC for OPRM Operability at Option III Plants. Please identify any plant-specific differences from the generic values specified NEDO-32465-A such as Period Based Detection Algorithm (PBDA) period confirmation setpoints in Table 3-1, PBDA trip setpoints in Table 3-2, and generic DIVOM curve slope.
5. Please provide a detailed description of the procedure to generate the OPRM Period Based Algorithm Allowable Value and Confirmation Counts for future cycles.
6. Please describe the functional relationship between the Interim Corrective Actions (ICAs) and Actions stated in TS 3.3.11 for OPRM. Also, Provide the rationale to delete Figure 3.4.1-1 from the TS and identify any role of Figure 3.4.1-1 in the reactor operating manual.
7. Please provide a detailed description of the alternate method to detect and suppress thermal hydraulic instability oscillation stated in TS 3.3.11 Action b.
8. The proposed TS change to TS 6.9.1.9 Core Operating Limits to add TS 3/4.3.11 Oscillation Power Range Monitor (OPRM) is not consistent with the guidance specified in Generic Letter 88-16. TS 6.9.1.9 should list all the cycle-specific core operating limits in the proposed TS change not an OPRM system. Please provide justification for this proposed change.