ML20154G825
| ML20154G825 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/18/1986 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8805250111 | |
| Download: ML20154G825 (5) | |
Text
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j B ALTIMORE GAS AND ELECTRIC V
b CHARLES CENTER R O. BOX 1475 ' BALTIMORE, MARYLAND 21203 JostPH A.TIERNAN Vics PatslDENT NUCLEAR ENcnov April 18,1986 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION:
Mr. Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Generic Letter 83-28, Item 1.2, Post-Trip Review -
REFERENCES:
(a)
Conference call between NRC Staff ano BG&E Staff on January 6,1986, concerning Post-Trip Review at Calvert Cliffs (b)
Letter from Mr. A. E. Lundvall, Jr., to Mr. D. G. Eisenhut, dated
_November 5,1983, Generic Letter 83-28 Gentlemen:
Reference (a) was convened to permit discussions concerning the NRC Staff review of our response to Generic Letter 83-28, Item 1.2.
We informed your staff in Reference (a) that Attachment 4 to Reference (b) has been discovered to be now incorrect.
We agreed to submit an updated Attachment 4 to replace that transmitted in 1983.
Accordingly, we have enclosed an updated Attachment 4. This shows the current list of process parameters in the Technical Support Center Computer. In addition, the new attachment identifies our expected additions to the list.' Please note that the items marked with asterisks were part of the original list of inputs. The updated attachment now reflects the true status ar.d our current intentions.
We understand that with this information you will be able to closecut item 1.2 of Generic Letter 83-28.
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w Mr. Ashok C. Thadani April 18,1986 Page 2 Should you have further questions regarding this matter, we would be pleased to discuss them with you.
Very truly yours, f
@h JAT/SRC/dlm Attachment cc:
D. A. Brune, Esquire J. E. Silberg, Esquire D. H. Jaffe, NRC T. Foley, NRC 1
ATTACHMENT 4 TECHNICAL SUPPORT CENTER INPUTS UNIT SYSTEM PROCESS PARAMETER 1
2 CONTAINMENT Containment 11 Pressure Indication X
- Containment Dome Temperature X
X Containment 21 Pressure Indication X
Hydrogen Concentration X
X
- Containment Water Level X
X EMERGENCY CORE COOLING HPSI Flow to Loop ll A X
HPSI Flow to Loop llB X
HPSI Flow to Loop 12A X
HPSI Flow to Loop 12B X
LPSI Flow to Loop ll A X
LPSI Flow to Loop llB X
LPSI Flow to Loop 12A X
LPSI Flow to Loop 12B X
Coatainment Spray Header 11 Flow X
Containment Spray Header 12 Flow X
LPSI Flow Control X
X HPSI Flow to Loop 21B X
HPSI Flow to Loop 21 A X
HPSI Flow to Loop 22B X
HPSI Flow to Loop 22A X
LPSI Flow to Loop 21B X
LPSI Flovc to Loop 21 A X
LPSI Flow to Loop 22B X
LPSI Flow to Loop 22A X
Containment Spray Header 21 Flow X
Containment Spray Header 22 Flow X
- Charging Pumps Discharge Flow X
X Salt Water Pumps Discharge Header Pressure X
X Salt Water Pumps Pressure X
X Component Cooling Pump 11 Discharge Pressure X
Compor,ent Cooling Pump 12 Discharge Press!:re X
Shutdown Heat-Exchanger 11 Outlet Temperature X
Shutdown Heat-Exchanger 12 Outlet Temperature X
Refuel Water Tank 11 Level X
Service Water Header 11 Pressure X
Component Cooling Pump 21 Discharge Pressure X
Component Cooling Pump 22 Dischar6c Pressure X
Shutdovcn Heat-Exchanger 21 Outlet Temperature X
Shutdown Heat-Exchanzer 22 Outlet Temperature X
Refuel Water Tank 21 Level X
Service Water Header 21 Pressure X
. ~..
AT'TACHMENT 4 TECHNICAL SUPPORT CENTER INPUTS UNIT SYSTEM PROCESS PARAMETER 1
2_
& MAKE-UP
- Auxiliary Feedwater Flow Steam Generator 11 X
- Auxiliary Feedwater Flow Steam Generator 12 X
Condensate Storage Tank t/12 Level X
- Auxiliary Feedwater Flow Steam Generator 21 X
- Auxiliary Feedwater Flow Steam Generator 22 X
Feedwater Flow to Steam Generator 11 X
Feedwater Flow to Steam Generator 12 X
Feedwater Flow to Steam Generator 21 X
Feedwater Flow to Steam Generator 22 X
Condensate Storage Tank 11 Level X
Condensate Storage Tank 21 Level X
MAIN STEAM Steam Generator Level 11 X
Steam Generator Level 12 X
Steam Generator 11 Pressure X
Steam Generator 12 Pressure X
Steam Generator Level 21 X
Steam Generator Level 22 X
Steam Generator 21 Pressure X
Steam Generator 22 Pressure X
NUCLEAR INSTRUMENTATION
- % Power (INTERMEDIATE)
X X
j
- Q-Power X
X Thermal Power X
X
- % Power Source Range X
X In-Core Flux Detectors X
X In-Core Thermocouples X
X RADIATION MONITORING Waste Processing Area Radiation Monitor X
X Liquid Waste Discharge Radiation X
X
- Containment High Range (East)
X X
- Containtnent High Range (West)
X X
- Noble Gas Main Vent Low Range X
X
- Noble Gas Main Vent Mid Range X
X
- Noble Gas Main Vent High Range X
X
- Main Vent Flow X
X
- Condensate Vacuum Pump Discharge Radiation X
X Condensate Vacuum Pump Flow Rate X
X s
.. =
I l
4 er ATTACHMENT 4 ECHNICAL SUPPORT CENTER INPUTS UNIT SYSTEM PROCESS PARAMETER
_l, 2_.
REACTOR COOLANT SYSTEM RCS Flow Loop llB X
RCS Flow Loop 12B X
Subcooled Margin Loop 11 X
Subcooled Margin Loop 12 X
Pressurizer Level Hot X
X l
Pressurizer Level Cold X X Pressurizer Pressure X
X RCS Hot Leg Temperature Loop 11 X
RCS Hot Leg Temperature Loop 12 X
RCS Cold Leg Temperature Loop 11 A X
RCS Cold Leg Temperature Loop 11B X
RCS Cold Leg Temperature Loop 12A X
RCS Cold Leg Temperature Loop 12B X
RCS Flow Loop 21B X
RCS Flow Loop 22B X
Subcooled Margin Loop 21 X
)
Subcooled Margin Loop 22 X
RCS Hot Leg Temperature Loop 21 X
RCS Hot Leg Temperature Loop 22 X-RCS Cold Leg Temperature Loop 21 A X
l RCS Cold Leg Temperature Loop 21B X
RCS Cold Leg Temperature Loop 22A X
RCS Cold Leg Temperature Loop 22B X
i
- 1hese parameters are not available at this time but will be added at a later date.
- Complete for steam-driven pumps. Motor-driven pump will be added at a later date.
- These parameters are not available at this time.
.