ML20197J937
| ML20197J937 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/05/1986 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-81-10, NUDOCS 8605200212 | |
| Download: ML20197J937 (4) | |
Text
W 3a B ALTIMORE GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN Vice PatsIDENT NucLEAn ENERGY May 5,1986 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 ATTENTION:
Mr. A. C. Thadani, Project 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 Technical Support Center Computer
REFERENCES:
(a)
Letter from D.
G.
Eisenhut, to All Licensees, Post-TMI Requirements for the Emergency Operations Facility (Generic Letter 81-10), dated February 18, 1981 (b)
Letter from A. E. Lundvall, Jr., to D. G. Eisenhut, Emergency Response Facilities Conceptual Design, dated June 1,1981 (c)
Letter from A. E. Lundvall, Jr., to D. G. Eisenhut, Post-TMI Requirements, dated June 4,1982 (d)
Letter from D. G. Eisenhut, to All Licensees, Supplement I to NUREG-0737 (Generic Letter No. 82-33), dated December 17,1982 (e)
Letter from A. E. Lundvall, Jr., to R. A. Clark, Supplement I to NUREG-0737, dated April 15,1983 Gentlemen:
The purpose of this letter is to clarify the list of variables to be displayed in the Technical Support Center (TSC) at Calvert Cliffs Nuclear Power Plant. The following discussion summarizes the history of TSC correspondence between the Baltimore Gas and Electric Company (BG&E) and the Nuclear Regulatory Commission (NRC).
Reference (a) promulgated the initial NRC requirements for the TSC. Our response was forwarded in Reference (b), which transmitted our conceptual TSC design including a list of parameters which we anticipated would be available. In Reference (c), we notified the Commission when our updated TSC became operational.
Reference (d) was issued six months later with much more explicit requirements for upgraded emergency response facilities. One of these requirements was that Regulatory Guide 1.97 variables essential for TSC functions shall be available in the TSC.
A b
B605200212 860505 o
PDR ADOCK O 37
Mr. A. C. Thadani 2
May 5,1986 proposed schedule for completing each of the basic requirements was also requested. We responded with Reference (e), identifying Reference (b) as providing a detailed description of the upgraded TSC, stating that the upgraded TSC was previously declared operational by Reference (c), and that any instrumentation necessary as a result of the new requirements in Reference (d) would be installed.
Recently, our Plant Operations and Safety Review Committee requested that we review the status of, and commitments relative to, the TSC cornputer. As a result of this review, we feel it appropriate to provide the following clarification regarding Reference (e). The upgraded TSC was declared operational in Reference (c) because we determined that it met all of the NRC Staff's requirements in Reference (a). The upgraded TSC did not then, nor does it now, have available all of the variables listed in Reference (b).
Reference (d) allows licensees to exercise management prerogatives in designing and building emergency response facilities provided they meet all NRC requirements. The backfitting of our upgraded TSC to include all parameters we feel are necessary to meet the Reference (d) requirements is not yet complete, as explained below.
We have supplemented our Regulatory Guide 1.97 program plan by reevaluating the variables that should be available in the TSC. The Regulatory Guide 1.97 variables that we have determined to be essential for the performance of TSC functions are listed in Attachment A.
The implementation schedule for backfitting those variables not presently available is also noted in Attachment A.
Additional variables are, or will be, available in the TSC besides those listed in Attachment A. Although not essential for performing TSC functions, we have found that some variables are essential for conducting post-trip reviews. Although our Safety Parameter Display System (SPDS) will also be displayed in the TSC, many of the variables on SPDS are not essential for performing TSC functions.
In summary, our existing TSC computer continues to satisfy our interpretation of the requirements of Reference (a). Further, we are continuing to backfit the TSC computer based upon the more explicit requirements of Reference (d), in accordance with the schedule in Attachment A.
Should you have additional questions regarding this matter, please do not hesitate to contact us.
Very tru rs,
'1wu n cc:
D. A. Brune, Esquire J. E. Silberg, Esquire Mr. D. H. Jaffe, NRC Mr. T. Foley, NRC
Mr. A. C. Thadani Attachment A May 5,1986 Variables That Are Essential for the Performance of Technical Support Center FunctionsII)
A).
Variables on the Technical Support Center Computer (2) 1.
Pressurizer Level 2.
Pressurizer Pressure 3.
Steam Generator Level 4.
Steam Generator Pressure 5.
Quench Tank PressureI3) 6.
Refueling Water Tank Level 7.
Condensate Storage Tank Level I3) 8.
Containment Sump Level-Wide Range 9.
Reactor Coolant System Temperature - Hot
- 10. Reactor Coolant System Temperature - Cold
- 11. Subcooled Margin
- 13. Auxiliary Feedwater FlowI4)
- 14. High Pressure Safety Injection Flow
- 15. Low Pressure Safety Injection Flow
- 16. Decay Heat Removal Flow
- 17. Decay Heat Removal Temperature
- 18. Boric Acid Charging Flow I3)
- 19. Neutron Flux
- 20. Containment Pressure I3)
- 21. Containment Temperature
- 22. Containment Hydrogen Concentration
- 23. Containment Cooler Service Water Flow (3)
- 24. Containment Spray Flow
- 25. Component Cooling Water to Engineered Safety Features I3)
Temperature
- 26. Component Cooling Water to Engineered Safety Features - Flow I3)
- 27. Containment Area Radiation I3}
- 28. Condenser Offgas Radiation
- 29. Main Vent Radiation /FlowI3)
- 30. Main Steam Radiation (3)
'Mr. A. C. Thadani A-2 May 5,1986 B).
Variables on the Safety Parameter Display System (5) 1.
Pressurizer Heater Status 2.
Reactor Coolant System Safety Valve and Power Operated Relief Valve Position / Flow 3.
Reactor Level Monitoring 4.
Containment Isolation Valve Position 5.
Emergency Vent-Damper Position 6.
Status of Standby Power Notes:
1 As required by Generic Letter No. 82-33, Section 8.2.1.h(i).
2 The Technical Support Center Computer is described in Reference (a).
3 These variables are not available at this time, but all will be available prior to startup following the cycle 10 refueling outage Unit 1 (estimated to be Spring 1988) and the cycle 9 refueling outage Unit 2 (estimated to be Spring _1989).
Complete for the steam-driven pumps. Flow indication for motor-driven pump is not available at this time but will be available prior to startup following the cycle 10 refueling outage Unit 1 (estimated to be Spring 1988) and the cycle 9 refueling outage Unit 2 (estimated to be Spring 1989).
5 The Safety Parameter Display System is described in References (b) and (c).
References a.
Letter from A. E. Lundvall, Jr., to D. G. Eisenhut, Emergency Response Facilities Conceptual Design, dated June 1,1981.
b.
Letter from A. E. Lundvall, Jr., to J. R. Miller, SPDS Safety Analysis, dated June 6,1984.
c.
Letter from A. E. Lundvall, Jr., to J. R. Miller, Safety Parameter Display System (SPDS), dated February 4,1985.