ML041810465

Facsimile Transmission, Draft Request for Additional Information (RAI) to Be Discussed in an Upcoming Conference Call

ML041810465
Person / Time
Site:	Hope Creek
Issue date:	06/29/2004
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: ML041810465 (3)

Text

June 29, 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, Senior. Project Manager, Section 2 /RA/

Project Directorate I 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 25, 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. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-354

Attachment:

Draft Request for Additional Information

ML041810465 OFFICE PDI-2/PM SRXB-A/SC NAME DCollins FAkstulewicz DATE 6/28/04 6/25/04*

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

The staff has reviewed the March 31, 2004 TS amendment request and has identified the following questions to be addressed by the licensee in order to complete our evaluation.

1. Please describe the details of the confirmation process for the proposed OPRM system to meet the conditons stated in CENPD-400-P-A, Rev 01, Generic Topical Report for the ABB Option III Oscillation Power Range Monitor (OPRM), and identify any deviations.

2. Provide detailed procedures to verify the accuracy of trip set-points for the new OPRM instrumentation based on available data of the system calibration tests during normal operation as well as the shutdown and subsequent startup from refueling outage.

3. Please provide a detailed description of the methodology for calculation of the plant-specific DIVOM correlation and the OPRM setpoints for TS 3/4.3.11. Also, provide a detailed description of the procedure to generate the OPRM Period Based Algorithm Allowable Value and Confirmation Counts for future cycles. Please identify any plant-specific differences from the generic values specified in 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. Provide specific values for OPRM scram setpoints and the DIVOM correlation for the next cycle.

4. 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. Provide a detailed description of the alternate method to detect and suppress thermal hydraulic instability oscillation stated in TS 3.3.11 Action b.

5. 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) may not be 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.