ML19289C217
| ML19289C217 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/28/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7812140379 | |
| Download: ML19289C217 (6) | |
Text
9 TEM
[
UNITED STATES
[
/ *g NUCLEAR REGULATORY COMMISSION
'.j WASHINGTON, D. C. 20555 s,
8 e
November 28, 1978 j
Dockets Nos.: ~50,d11 and 50-318 Mr. A. E. Lundvall, Jr.
Vice President - Supply Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, Maryland 21203
Dear Mr. Lundvall:
As previously discussed with Mr. Robert Denton of your staff, representatives of the Nuclear Regulatory Commission's Office of Nuclear Rogulatory Research and their contractors will meet with your representatives at the Calvert Cliffs Nuclear Fower Plant on December 12, 1978. The purpose of this meeting is to obtain the specific information, contained in the enclosure, for use in the research project entitled, " Reactor Safety Study Methodology Applications Program." This study is to examine the engineering insights obtained in the Reactor Safety Study (WASH-1400) relative to a spectrum of additional LWR designs. This site visit was the subject of your Mr. John Gore's letter to Dr. Ian Wall of our staff, dated July 19, 1977.
The NRC and contractor representatives that will attend the meeting are:
Merrill Taylor NRC Mark Cunningham NRC Peter Cybulskis Batelle Columbus Gregory Kolb Sandia Laboratories Gary Boyd Sandia Laboratories Robert Kliber Evaluation Associates Tony Jacobi Evaluation Associates We appreciate your continuing cooperation in this program.
Please contact me if you require any further information on this meeting.
Sincerely,
/.
m Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Discussion Topics cc: See next page 7812140 377
- Baltimore Gas & Electric Company cc:
James A. Biddison, Jr.
Mr, R. M. Douglass, Manager General Counsel Quality Assurance Department G and E Building Room 923 Gas & Electric Building Charles Center P. O. Box 1475 Bal timcre, Maryland 21203 Baltimore, Maryland 21203 George F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridae 1800 M Street, N.U.
Washington, D. C.
2003G Mr. R. C. L. Olson Baltimore Gas and Electric Company Room 922 - G and E Building Post Office Box 1475 Bal tinore, Maryland 21203 Mr. Leon B. Russell, Chief Engineer Calvert Cliffs Nuclear Power Plant Baltinore Gas and Electric Company Lusoy, Maryland 20657 Bechtel Power Corporation ATTN:
Mr. J. C. Judd Chief Nuclear Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Conbustion Engineering, Inc.
ATIN: Mr. P. W. Kruse, Manager Engineering Services Post Office Box 500 Windsor, Connecticut 06095 Calvert County Library Prince Frederick, Maryland 20678
Enclosure Discussion Topics for Reactor Safety Study Methodology Applications Program A.
Discussion Topics 1.
Plant Procedures System (s)
Topic a.
Procedures for transfering Recirculation (CSRS) containment heat removal Low Pressure Recircu-from CSRS to LPRS or combina-lation (LPRS) tion of LPRS and HPRS.
High Pressure Recircu-lation (HPRS) b.
Test and Maintenance System Procedures.
c.
AC Power c.
For LOCA with loss of off-site power - procedures for realigning needed systems back to net AC from diesel-generators.
2.
Plant Design Information System (s)
Design Information a.
Compressed Air System a.
More detailed description (schematics) of system.
b.
Containment Building b.(1) Distribution of contain-ment volumes, subcompartments.
b.(2)
Emergency sump parameters -
location, volume, proximity to reactor cavity.
'3.
Specific Questions System (s)
Question a.
Safety Injection and a.(1) Actuation signal override Containment Systens capabilities.
Actuation a.(2) Human interaction (and error potential) with actuation signal alignments.
a.(3) Test frequencies for contain-ment systems actuation logic.
b.
High Pressure Injection b (1) CSRS heat exchanger and Recirculation Pumps performance characteristics.
Low Pressure Injection and Recirculation Pumps b.(2)
ECC, containment spray Containment Spray Injection recirculation pump NPSH and Recirculation Pumps requirements, b.(3)
Pump capabilities without cooling water.
b.(4)
Lube oil circulation in idle pumps.
b.(5)
Limiting conditions for operation on HPIS - specifi-cally for one pump out or service of two pumps with common header.
b.(6) High pressure - low pressure interface in LPIS - location, relief capability, etc.
b.(7) Experience in ECC pump repair times b.(8) Pump protection from flood-out (due to pipe breaks, etc.; not external floods).
' c.
Auxiliary Feedwater c.(1) Availability of back-up System water supplies to condensate storage tanks.
c.(2)
Power source (s) for valves and controls.
c.(3) Test override capability, c.(4) Time to switchover from steam generator to auxiliary steam supply.
d.
Auxiliary Steam Supply d.
Power source (s) for valves System and controls.
e.
Service Water System e.
Repair / realignment potential for valves in service water supply to reactor building cooling units (fans and spray heat exchangers).
f.
DC Power Supply f.
Plant response to loss of 1 train of DC power.
B.
Plant Areas Desired to be Seen.
Auxiliary Building Turbine Building Level Level 69' Electrical Room (MCC's) 45' Control Room AC Switchgear Diesel Generators 27' Cable Spreading Room Battery Room AC Switchgear Piping Penetration Rooms 5-10' Service Water Pumps 12 Auxiliary Feedwater Pumps and Heat Exchangers Emergency Control Panel Component Cooling Pumps Feedwater Pumps and Heat Exchangers Condensate Booster Pumps w**-
. Auxiliary Building Turbine Building Level level
-10' Charging Pumps
-15' HP Safety Injection Pumps LP Safety Injection Pumps Containment Spray Pumps Shutdown Heat Exchangers 6