ML13016A013
| ML13016A013 | |
| Person / Time | |
|---|---|
| Site: | Boiling Water Reactor Owners Group |
| Issue date: | 02/25/2013 |
| From: | Anthony Mendiola Licensing Processes Branch (DPR) |
| To: | Schiffley F Hitachi-GE Nuclear Energy, Ltd |
| Golla J | |
| Shared Package | |
| ML13017A463 | List: |
| References | |
| Download: ML13016A013 (4) | |
Text
February 25, 2013 Frederick P. Ted Schiffley, II BWROG, Chairman c/o GE Hitachi Nuclear Energy, P.O. Box 780, 3901 Castle Hayne Road, M/C A-70, Wilmington, NC 28402
SUBJECT:
USE OF CONTAINMENT ACCIDENT PRESSURE IN DEMONSTRATING ACCEPTABLE OPERATION OF EMERGENCY CORE COOLING SYSTEM AND CONTAINMENT HEAT REMOVAL PUMPS DURING POSTULATED ACCIDENTS
Dear Mr. Schiffley:
U.S. Nuclear Regulatory Commission (NRC) licensees, including many licensees operating Boiling Water Reactors (BWRs), have included the use of containment accident pressure (CAP) in demonstrating acceptable operation of the emergency core cooling system (ECCS) and containment heat removal pumps during postulated accidents.
The NRC staff undertook a review of this issue and issued a draft guidance document for your review by letter dated March 1, 2010, Agencywide Documents Access and Management System (ADAMS) Accession No. ML100550903. The draft guidance document is available in ADAMS under the Accession No. ML100550869.
The NRC staff has revised the draft guidance document to provide additional clarifications, including the addition of a flow chart entitled Flow Chart for LOCA Containment and NPSH Analyses and its accompanying sketches Figure a, and Figure b. This flow chart along with the sketches provide a snapshot summary of the required analyses to be performed to support power uprate and other license amendment applications to demonstrate adequate net positive suction head (NPSH) to the ECCS and containment heat removal pumps. The flow chart clarifies the guidance for the analyses to be performed and does not reflect changes in the guidance from the previous version of the draft guidance document.
We have enclosed the revised draft guidance document, entitled Nuclear Regulatory Commission Draft Guidance for the Use of Containment Accident Pressure in Determining the Net Positive Suction Head Margin for Emergency Core Cooling System and Containment Heat Removal Pumps in Boiling Water and Pressurized Water Reactors, and ask that you share it with interested members of the BWR community. The document is also available in ADAMS under Accession No. ML13015A437. The NRC staff intends to use this draft guidance in engaging stakeholders and issue an Interim Guidance Document in the near future.
F. Schiffley If you have any questions regarding this matter, please contact Joseph Golla at (301) 415-1002.
Sincerely,
/RA/
Anthony J. Mendiola, Chief Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 691
Enclosure:
As stated cc w/encl: See next page
(Package) ML13017A463; (Cover Letter) ML13016A013; (Enclosure) ML13015A437 NRR-106 OFFICE PLPB/PM PLPB/LA SCVB/BC DSS/D PLPB/BC NAME JGolla (GLappert for)
DBaxley RDennig TMcGinty AMendiola DATE 02/14/2013 02/05/2013 02/14/2013 02/14/2013 02/25/2013
BWR Owners Group Project No. 691 cc:
Mr. Frederick Schiffley BWROG Chairman c/o GE Hitachi Nuclear Energy, P.O. Box 780, 3901 Castle Hayne Road, M/C A-70, Wilmington, NC 28402 frederick.schiffley@exeloncorp.com Mr. Kenneth McCall BWROG, Program Manager GE-Hitachi Nuclear Energy PO Box 780 M/C F12 3901 Castle Hayne Road Wilmington, NC 28402 kenneth.mccall@ge.com