ML20077F479
| ML20077F479 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/13/1991 |
| From: | Vaughn G CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NLS-91-137, TAC-73637, TAC-73638, NUDOCS 9106190002 | |
| Download: ML20077F479 (2) | |
Text
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3 1991 G E.VAUGHN Vice President Nuclear Services Department United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50 325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 STATUS OF SPDS AND DCRDR PROJECTS (TAC NOS. 73637 AND 73638)
Gentlemen:
In an April 12, 1991 telephone conversation with the NRR Project Manager, CP&L was requested to provide a status of the progress on completion of the Safety Parameter Display System (SPDS) and the Detailed Control Room Design Review (DCRDR) projec ts at Brunswick.
The purpose of this letter is to provide the current status of each proj ect.
The SPDS proj ect is proceeding on schedule.
In an October 24, 1990 submittal (Serial:
NLS-90-170), CP&L detailed 30 separate tasks to be completed in order to achieve SPDS certification and provided the status of each item.
To date, a total of 16 of the 30 tasks have been completed.
By the end of June an additional 6 tasks will be completed.
Seven of the remaining 8 tasks will be completed by mid-August with the remaining task, Toshiba Replacement, to be completed in September 1991.
It should De noted that changes to the SPDS at Brunswick will continue even after the system has been upgraded to fully meet the requirements of NUREG-0737, Supplement 1.
As plant modifications are made, additions to or deletions from the SPDS will be necessary to reflect plant configuration.
For example, modifications have been made to create a primary containment isolation valve Group 10 consisting of two instrument air isolation valves.
These instrument air isolation valves were previously part of Group 6.
Modifications to the SPDS to reflect this change will be made during the Unit 1 Reload 8 outage, currently scheduled to begin in April 1992, and Unit 2 Reload 10 outage, currently scheduled to begin in March 1993.
If future plant modifications necessitate any other SPDS modifications, they will be scheduled appropriately.
The DCRDR project will be completed by the end of the Reload 8 outage for Unit 1, currently scheduled to begin in April 1992, and the Reload 10 outage for Unit 2, currently scheduled to begin in March 1993.
This is in accordance with the schedule previously reported to the staff, as documented in the staff's Detailed Control Room Design Review, dated November 2, 1989.
A total of 72 modifications have been identified to correct the remaining human
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Installation has been completed on 32 of-these modifications. Of the remaining 40 modifications, 19 are scheduled for installation in 1991, 16 in 1992, and the. remaining 5 in 1993.
Please refer any questions regarding this submittal to Mr. M. R, Oates at.
(919) 545-6063.
Yours very truly, 0
C. E. Vaughn GEV/ MAT cc:
Mr. S. D. Ebneter Mr. N. B. Le Mr. R. L. Prevatte l
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