ML20214F915
| ML20214F915 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/03/1986 |
| From: | Foster D GEORGIA POWER CO. |
| To: | Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| GN-1098, NUDOCS 8611250480 | |
| Download: ML20214F915 (3) | |
Text
Georg<a Power Corrpany Q
Post Office Box 282 l
Waynesboro. Georga 30830 Telephone 404 554 9961, Ext. 3300 404 724-8114. Ext. 3360 k
h M 0M 9 A9*2 3 Georgia Power D. O. Foste, v
re y
p w w _, w,,em October 3, 1986 United States Nuclear Regulatory Commission Region II File:
X7BG10 Suite 2900 Log:
GN-1098 101 fiarietta Street, Northwest Atlanta, Georgia 30323
Reference:
50-424/86-60, 50-425/86-27 Attention: fir. Roger D. Walker The Georgia Power Company wishes to submit the following information concerning the violation identified in your inspection report 50-424/86-60 and 50-425/86-27:
Violation 50-424/86-60-01, 50-425/86-27-01, " Failure to Implement Adequate Design Control" - Severity Level IV Georgia Power Company acknowledges the violation as identified in the USNRC inspection report.
1.
The original design intent for the Vogtle Plant Safety lionitoring System (PSMS) was to display only Category 1 variables as defined in Regulatory Guide 1.97, Revision 2.
The pressurizer safety valve position indication status was classified as Type D, Category 2 since it is used by the operator to verify system operation.
How-ever, during an early engineering review of Regulatory Guide 1.97 and existing plant variables, it was decided to provide control room indication for the pressurizer safety valve status even though it was a D2 variable.
In the original design, the pressurizer safety valve position switch signals were routed through the non-safety remote processing unit (RPU) to the Emergency Response Facility for display on the Safety Parameter Display System (SPDS).
Following the engineering review, the switch signals were re-routed to safety RPU's to allow for the use of Class 1E power supplies, but the display remained on the SPDS.
FSAR Table 7.5.2-1 was issued with the pressurizer safety valve status listed as plasma display for control room indication.
Westinghouse has reviewed FSAR Table 7.5.2-1 and confirmed that the other indications listed as plasma display are correct and are displayed in the Plasma Display Module.
It is therefore con-cluded that the pressurizer safety valve status discrepancy repre-
{(g sents an isolated case of human error.
This D2 variable is currently 8611250480 861003 PDR ADOCK 05000424 G
Page Two displayed on the SPDS, which is consistent with the original design intent, and the safe operation of the plant is not affected by this oversight.
The Plasma Display Module will be ' modified to display the pressurizer safety valve position status as required by FSAR Table 7.5.2-1.
The modification kit is expected to be available on site by November 30, 1986, and should be installed prior to Unit 1 fuel load.
Bechtel specification X5AH01 was closed out in 1982.
Since the Plasma Display flodule is part of the NSSS package, no revision to X5AH01 is necessary.
Revisions to the Westinghouse Plant Safety tionitoring System Design Specification 955827, Revision 0 (Bechtel File X6AZ02-18-1) are not required to incorporate this modification.
2.
The violation identified five FCR's on which the " Unit 2 change required" block was checked "no" and should have been checked "yes".
Three of these FCR's (E-FCRB-14,686 -14,687 and -14,688) are against vendor drawings for which the vendor supplied the same drawing for both units.
This occurs occasionally since, per specification requirements, the vendor submits common drawings of this type twice; once for Unit 1 and again for Unit 2.
He resubmits the drawings concurrently each time a change is made to the Unit 1 (or Unit
- 2) drawing by the vendor itself or due to a design change notice issued by Bechtel (DCN-S).
The design engineer dispositioning the FCR was aware of the vendor drawing submittals and knew that a Unit I change would automatically result in a Unit 2 change and, therefore, checked "no" under the " Unit 2 change required" block.
The remaining two FCR's (E-FCRB-14,678 and -14,681) are on Unit I wiring diagrams for which no Unit 2 drawing existed at the time of the FCR issue.
Agreements reached between field and design office required that the FCR dispositioner refer to a computer file which advised him whether or not the Unit 2 drawing was issued.
If not issued, the " Unit 2 change required" block would be checked "no".
The establishment of this agreement and the vendor drawing cases above resulted from a misunderstanding by the responsible engineers of the intent of the " Unit 2 change required" block.
It should be noted that it is standard practice for the designer to review the latest revision (including outstanding FCR's/DCN's) of the Unit 1 drawing for input, when the original (Revision 0)
Unit 2 drawing is prepared.
Responsible engineering personnel have been instructed to indicate "yes" on the " Unit 2 Change Required" block whenever the Unit 2 design is affected by the Unit 1 change.
Section C-4 of the Project Reference flanual (PRil), which governs the preparation, approval, and issuance of design drawings, will be revised to clarify require-l ments for processing Unit I changes which affect the Unit 2 design.
l
4 Page Three When the PRM revision is completed Bechtel Desk Instruction PFE-X3DIO8 will be revised accordingly or deleted (whereby work will be performed to the clarified PRM procedure).
Responsible engineer-ing personnel will be trained on the revised PRM procedure.
All the actions described above are expected to be completed by November 7,1986.
This response contains no proprietary information and may be placed in the USNRC Public Document Room.
Yours truly,
' lL' D. O. Foster s>--
REF/00F/tdm xc:
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 J. H. Miller R. A. Thomas L. T. Gucwa J. P. O'Reilly D. R. Altman C. W. Hayes G. F. Head P. R. Bemis G. A. McCarley R. E. Conway J. A. Bailey R. W. McManus J. T. Beckham
- 0. Batum D. S. Read R. H. Pinson G. Bockhold Sr. Resident (NRC)
P. D. Rice C. E. Belflower C. C. Garrett (0PC)
B. M. Guthrie J. F. D'Amico J. E. Joiner (TSLA)
D. E. Dutton E. D. Groover D. Feig (GANE)
,