ML19270H183
| ML19270H183 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/24/1979 |
| From: | Conner E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906250151 | |
| Download: ML19270H183 (4) | |
Text
s._
e TR%f MEETING
SUMMARY
DISTRIBUTION ORB #4 Mr. A. E. Lundvall, Jr.
Vice President - Supply Baltimore Gas & Electric Company P. O.
Box 1475 Baltimore, Maryland 21203 Dopet File R. Reid W C PDR V. Noonan L PDR P. Check ORB #4 Rdg G. Lainas NRR Rdg G. Knighton H. Denton Project Manager E. G. Case OELD V. Stello Ol&E (3)
D. Eisenhut R. Ingram R. Vollmer R. Fraley, ACRS (16)
W. Russell Program Support Branch B. Grimes TERA T. J. Carter J. R. Buchanan A. Schwencer Meeting Summary File D. Ziemann NRC Participants T. Ippolito M. Cunningham R. Giardina 2237 2C11 79062506\\.,
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION
~f.- E WASHINGTON, D. C. 20555 s
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May 24, 1979 Docket No. 50-317 and 50-318 LICENSEE:
BALTIM0REGASANDELECTRICCOMPANY(BG&E)
FACILITY:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS NOS. 1 AND 2
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 17, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEMS AND RELATED AREAS On May 17,1979 representatives of BG&E met with the Regulatory Staff to discuss the auxiliary feedwater system and related station areas. The purpose of the meetina was to assemble information for an NRC report. The areas discussed are listed in Enclosure 1.
The attendees are listed in.
BG&E provided a simplified drawing of the system (Enclosure 3).
The meeting began at 8:30 a.m. with the discussion of the material listed in Enclosure 1.
A review with the licensee of the information written as a result of the morning session was completed. All questions in Enclosure 1 were answered.
E. L. Conner, Jr., Project Manager Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
Areas Discussed 2.
List of Attendees 3.
Sketch of Auxiliary Feedwater System cc w/ enclosures:
qqt7 g See attached list LL>'
As part nf its on-going review of.the Three Mile Island L' nit 2 accident, the staff finds that it needs additional information regarding the auxiliary j
feedwater systems (AFWS). This information as outlined below, is recuired I
to evaluate AFWS reliability for Combustion Engineering (CE) and Westinghouse (W) designed pressurized water reactors.
The requested infonnation is in addition to that requested in the IE Bulletins, and should be brought to the meeting scheduled with the staff on May 8 thru May 12, 1979.
Written system description (as built) including:
- List of Support Systems for Auxiliary Feed System Operation (Ecth Electric and Steam) l Water Supplies for AFWS (primary and backup) j Current operating procedures and test and maintenance requirements including:
- All LC0's for AFWS, main FW system and related support systems.
- Listing of operator actions (local and/or control roo-) and timing require-ments for such actions.
Procedures for reinitiating main feedwater flow.
As' Built P& ids with symbol keys including condensate and steam side Led 9ible Equipment layouts drawings includir.g:
Isometric.s, if available Identification of inhibits preventing accessibility to AFWS components and related electrical equipment Relevant control systems description including:
- Schematic or logic control diagrams
- Listing of actuation signals / logic and control MSIS logic for isolating AFWS, if installed
- electric power dependences i
All " readouts" available in control room for.AFWS operation AC & DC Power One line diagrams (normal and emergency power supplies)
- Divisional designation e.g., Train A, Train B, requirements on all AFWS components and support systems List of normal valve states and loss-of-actuation power failure position Operating Experience, including Number of main feedwater interruptions per year experienced to date for each unit Number of demands on AFWS per year to date (test and actual) for each unit
- Summary of AFWS malfunctions, problems, failures Provide Available reliability analyses Steam Generator dry-out times (assuming loss of all feeceater flow, with 100%
initial power, with Reactor trip, no line breaks)
System design bases including:
- Seismic and environmental qualification Code and Quality, QA 2237 293 I
AFW MEETING WITH BG&E May 17, 1979 NRC BG&E Alan Thornton Monte Conner Carl Yoder Mark Cunningham C. H. Cruse Robert J. Giardina R. E. Denton 2237 294
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