ML20234E576
| ML20234E576 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/29/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8707070615 | |
| Download: ML20234E576 (3) | |
Text
l BALTIMORE
)
GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 BALTIMORE, MARYLAND 21203 l
JOSEPH A.TIERNAN -'
. Vice PatsiotNT
, NUCLEAR ENERGY June 29,1987 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. ;l & 2; Docket Nos. 50-317 & 50-318 Safety Parameter Disolav System Ouarterly Renort
REFERENCE:
(a) Letter from Mr. F. J.
Miraglia (NRC), to Mr. J.
A.
Tiernan (BG&E), dated September 30,' 1986,- Extension of Parameter Display System Operational Deadlines Gentlemen:
in granting our request for an extension to the operational deadlines for the Safety Parameter Display System ' (SPDS), Reference (a), you required us to provide quarterly progress reports beginning January 1,
1987.
Attached is the third of these reports covering the progress of the SPDS project for the second quarter of 1987. As you specified in Reference (a), we are providing:
our progress in establishing the fully operational SPDS for each unit, the status of the SPDS software development and testing, and the identification and status of the critical path item.
Please contact us if you have any questions. regarding this matter.
]
l Very truly yours,
}
f,
'. L(_, -
J. A. Tiernan JAT/LSL/ dim i
h Attachment.
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8707070615 870629 DR -ADOCK 05000317 p
D'ocument Control Desk June 29,1987 Page 2 cc:
D. A. Brune, Esquire J. E.
Silberg, Esquire R. A.Capra, NRC S. A.McNeil, NRC W. T. Russell, NRC T. Foley/D. C. Trimble, NRC l
ATTACH MENT SAFETY PARAMETER DISPLAY SYSTEM PROGRESS REPORT -
2nd QUARTER 1987 A. SPDS Progress
.l.
The Unit Two plant computer was' installed. this " spring. Over one-hundred new instruments used by the Safety. Parameter Display System (SPDS) have been added to the : computer.
2.
Training'. on SPDS,' which included general - logic, color. schemes, and controls -
was : completed. In addition, specific training on core / reactor coolant system
. heat removal, radiation : control, and reactivity Critical Safety Functions was.
also completed.
I 3.
New Control Room furniture which incorporates SPDS displays is being manufac,
tured. Installation is planned for late - July, i
B. Status of' Software Development and Testina 1.
Site acceptance testing of the SPDS, as well as the generation of various Software Problem Reports (SPRs), is ongoing. All but one vendor SPR has been resolved. Work on Baltimore Gas and Electric's SPRs will commence following the refueling outage.
2.
Ten accident scenarios, requiring no operator.. action', were played and recorded on the plant simulator. These were then processed, and run on' the Unit Two plant computer. The results demonstrated the SPDS displays performed as intended. Scenarios requiring operator actions will be. created-and run on the Unit One computer following its expected delivery in late July.
3.
We have successfully integrated the. data acquisition system with the plant computer and SPDS.
4.
Computer capacity is still a concern but no longer critical' path. Although system screen display response times are quite good, we are working with our vendor to provide even faster response.
C. Critical Path Item 1.
On-site testing and associated software changes constitute the critical path.
e