E4-885. Generic Safety Issue (GSI)-191, ``Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Sump Performance;'' Meeting

[Federal Register Volume 69, Number 76 (Tuesday, April 20, 2004)]
[Notices]
[Page 21166]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E4-885]


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NUCLEAR REGULATORY COMMISSION


Generic Safety Issue (GSI)-191, ``Assessment of Debris 
Accumulation on Pressurized Water Reactor (PWR) Sump Performance;'' 
Meeting

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of meeting.

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SUMMARY: Representatives from Nuclear Energy Institute (NEI), Electric 
Power Research Institute (EPRI), utility groups and stakeholders will 
meet with the staff of Nuclear Regulatory Commission (NRC) to discuss 
the chemical effects test plan and test facility that will be used to 
conduct the tests. This is a joint test program between the NRC and the 
industry (represented by NEI and EPRI). The meeting is a followup to a 
meeting in January 2004 on the same subject. The meeting is open to the 
public and all interested parties may attend.

DATES: April 28, 2004, from 9 a.m. to 11 a.m.

ADDRESSES: Nuclear Regulatory Commission, One White Flint North, 11555 
Rockville Pike, Conference Room O-10B4, Rockville, Maryland, 20852.

FOR FURTHER INFORMATION CONTACT: T.Y. Chang, Mail Stop T-10D20, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001. Telephone: 
[phone]; fax: [phone]; Internet: [email protected]

SUPPLEMENTARY INFORMATION: One of the remaining open GSI-191 issues to 
be resolved is the chemical effects for PWR Emergency Core Cooling 
System (ECCS) recirculation, which relates to possible chemical 
reactions between sump/spray fluids and materials in containment. The 
NRC Advisory Committee on Reactor Safeguards (ACRS) has asked if 
chemical reaction products or precipitates in post-loss of coolant 
accident (LOCA) sump fluid could be generated in sufficient quantity to 
significantly increase pressure drop (head loss) across ECCS 
recirculation sump screen debris beds. This test program will generate 
data needed by both NRC and the industry to address this question. NRC 
and industry will conduct data analysis and reach conclusions 
independently. These results will be made publicly available.
    Attendees are requested to notify T.Y. Chang at [phone] of 
their planned attendance if special services, such as for the hearing 
impaired, are necessary.
    The NRC is accessible to the White Flint Metro Station. Visitor 
parking near the NRC buildings is limited.

    Date in Rockville, Maryland, this 12th day of April, 2004.

For the Nuclear Regulatory Commission.
Anthony Hsia,
Acting Chief, Engineering Research Applications Branch, Division of 
Engineering Technology, Office of Nuclear Regulatory Research.
 [FR Doc. E4-885 Filed 4-19-04; 8:45 am]
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