ML032020002
| ML032020002 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/21/2003 |
| From: | Mozafari B NRC/NRR/DLPM/LPD2 |
| To: | Keenan J Carolina Power & Light Co |
| mozafari B, NRR/DLPM, 415-2020 | |
| References | |
| TAC MB6692, TAC MB6693 | |
| Download: ML032020002 (5) | |
Text
July 21, 2003 Mr. J. S. Keenan Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION ON AMENDMENT REQUEST TO EXPAND THE CORE FLOW OPERATING RANGE (MELLLA+) (TAC NOS. MB6692 AND MB6693)
Dear Mr. Keenan:
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the subject amendment request as submitted by your letter dated November 12, 2002. In a teleconference on July 8, 2003, we discussed our need for additional information with members your staff. The draft request for additional information (RAI) had been e-mailed to your licensing staff on June 16, 2003. The enclosed RAI formalizes the NRC staffs information request.
As we discussed during the July 8 teleconference, we will need a timely response. Please respond within 45 days to meet the schedule established for this review. If more time is needed, or you need clarification of this RAI, feel free to contact me at 301-415-2020 or blm@nrc.gov.
Sincerely,
/RA by Chandu Patel for/
Brenda L. Mozafari, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosure:
RAI cc w/encl: See next page
ML032020002 OFFICE PDII-2/PM PDII-2/LA DSSA/SRXB/SC PD-II-2/SC NAME CPP for BMozafari EDunnington ZA for FAkstulewicz BLM for AHowe DATE 7/18/03 7/18/03 7/18/03 7/ /03
REQUEST FOR ADDITIONAL INFORMATION FOR AMENDMENT TO EXPAND THE CORE FLOW OPERATING RANGE (MELLLA+)
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 (TAC NOS. MB6692 AND MB6693)
On November 12, 2002, Carolina Power & Light Company (CP&L), the licensee for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, submitted a request to revise the Technical Specifications, as necessary, to support an expansion of the core flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+) following the extended power uprate (EPU). The MELLLA+ application (NEDC-33063P) states that the anticipated transient without scram (ATWS) suppression pool temperature limit is 207.7F (See table in Section 9.3.1 of NEDC-33063P). NEDC-33063P also indicates that the suppression pool design limit is 220F. However, page 20 of the CP&L emergency operating procedure (EOP) document (0EOP-01NL, Rev. 12) shows the Heat Capacity Temperature Limit (HCTL) plot as a function of pressure. For a pressure of 1150 psig, the HCTL is between 120F and 168F, depending on the assumed suppression pool water level. In addition, page 109 of 0EOP-01-NL, Rev. 12, states that the suppression pool temperature requiring reactor depressurization is 120F. It appears that the safety limits stated by NEDC-33063P and 0EOP-01-NL, Rev. 12, are contradictory. The following questions address the capability of BSEP, Units 1 and 2, to maintain containment integrity during ATWS for the EPU/MELLLA+
operation.
(1)
Justify the use of the 207.7F ATWS suppression pool temperature limit for the EPU/MELLLA+ ATWS analysis. Specifically, justify why the suppression pool temperature limit is higher than the temperature limit requiring reactor depressurization.
(2)
Provide the basis for the ATWS suppression pool design limit of 220F quoted in NEDC-33063P.
(3)
The peak suppression pool temperature for EPU/MELLLA+ reported in NEDC-33063P is 197.7F. While this number is below the 207.7F loss-of-coolant accident (LOCA) limit, the reactor is still at full pressure. Thus, the reported 197.7F is not the peak temperature but the initial condition prior to the reactor depressurization. Following a depressurization (which is required by the EOP for a temperature of 197.7F), the suppression pool temperature would be greater than 207.7F. Provide the actual peak suppression pool temperature when the ATWS transient is followed to completion according to the EOPs.
(4)
Provide the assumptions used in the ATWS analysis for the EPU/MELLLA+ specific calculations reported in NEDC-33063P. Specifically, identify which ATWS transient is limiting in terms of each ATWS acceptance limit. Describe the initial conditions, including power, flow, and suppression pool level used. Identify the operator actions that are assumed. Provide the ATWS mitigation actions that are implemented during the transient. Provide the values that are used for the EOP variables (e.g., HCTL, HSBW, etc).
(5)
Provide a plot of suppression pool temperature versus time (short-term and long-term).
(6)
Provide a plot of reactor pressure and power versus time during the event.
(7)
Provide a table showing the sequence of events (system and component actuations and operator actions) during the pressure regulator failure to open (PRFO) and Main Steam Isolation Valve Closure (MSIVC) ATWS events analyzed. Show the safety/relief valve actuation setpoints and indicate the time each safety/relief valve group first actuates.
Mr. J. S. Keenan Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:
Steven R. Carr Associate General Counsel - Legal Department Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551 Mr. David R. Sandifer, Chairperson Brunswick County Board of Commissioners Post Office Box 249 Bolivia, North Carolina 28422 Resident Inspector U. S. Nuclear Regulatory Commission 8470 River Road Southport, North Carolina 28461 Mr. John H. ONeill, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street NW.
Washington, DC 20037-1128 Ms. Beverly Hall, Section Chief Division of Radiation Protection N.C. Department of Environment and Natural Resources 3825 Barrett Dr.
Raleigh, North Carolina 27609-7721 Mr. W. C. Noll Plant Manager Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10429 Southport, North Carolina 28461 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211 Ms. Margaret A. Force Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, North Carolina 27602 Mr. Robert P. Gruber Executive Director Public Staff - NCUC 4326 Mail Service Center Raleigh, North Carolina 27699-4326 Mr. C. J. Gannon Director - Site Operations Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10429 Southport, North Carolina 28461-0429 Mr. Norman R. Holden, Mayor City of Southport 201 East Moore Street Southport, North Carolina 28461 Mr. Dan E. Summers Emergency Management Coordinator New Hanover County Department of Emergency Management Post Office Box 1525 Wilmington, North Carolina 28402 Mr. James W. Holt, Manager Performance Evaluation and Regulatory Affairs PEB 7 Progress Energy Post Office Box 1551 Raleigh, North Carolina 27602-1551 Mr. Edward T. ONeil Manager - Support Services Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10249 Southport, North Carolina 28461