ML14178A168
| ML14178A168 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/05/1991 |
| From: | Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Eury L CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 9112240105 | |
| Download: ML14178A168 (4) | |
See also: IR 05000261/1991201
Text
December 5, 1991
Docket No. 50-261
License No. DPR-23
Carolina Power and Light Company
ATTN:
Mr. Lynn W. Eury
Executive Vice President
Power Supply
P. 0. Box 1551
Raleigh, NC 27602
Gentlemen:
SUBJECT:
NRC INSPECTION REPORT NO. 50-261/91-201
We have completed our review of your response, dated November 2, 1991, to the
Notice of Violation identified in Inspection Report 50-261/91-201.
After
careful review of your response, we have concluded that the violation occurred
as written.
The basis for our conclusion is discussed -in the enclosure.
Please respond to the four questions presented in our Notice of Violation dated
October 4,
1991.
We appreciate your cooperation with us.
Sincerely,
Original signed by
Stuart D. Rubin/for
Albert F. Gibson, Director
Division of Reactor Safety
Enclosure:
As stated
cc w/encl:
C. R. Dietz, Manager
Robinson Nuclear Project Department
H. B. Robinson Steam Electric Plant
P. 0. Box 790
Hartsville, SC
29550
R. H. Chambers, Plant General Manager
H. B. Robinson Steam Electric Plant
P. 0. Box 790
Hartsville, SC
29550
(cc cont'd - See page 2)
9112240105 911205
ADOCK 05000261
G
Carolina Power and Light Company
2
December 5, 1991
(cc cont'd)
Heyward G. Shealy, Chief
Bureau of Radiolooical Health
Dept. of Health and Environmental
Control
2600 Bull Street
Columbia, SC 29201
Dayne H. Brown, Director
Division of Radiation Protection
N. C. Department of Environment,
Health & Natural Resources
P. 0. Box 27687
Raleigh, NC
27611-7687
McCuen Morrell, Chairman
Darlington County Board of Supervisors
County Courthouse
Darlington, SC 29535
Mr. H. Ray Starling
Manager -
Legal Department
P. 0. Box 1551
Raleigh, NC 27602
H. A. Cole
Special Deputy Attorney General
State of North Carolina
P. 0. Box 629
Raleigh, NC 27602
Robert Gruber
Executive Director
Public Staff -
NCUC
P. 0. Box 29520
Raleigh, NC 27626-0520
J. D. Kloosterman, Director
Regulatory Compliance
H. B. Robinson Steam
Electric Plant
P. 0. Box 790
Hartsville, SC 29550
Carolina Power and Light Company
3
December 5, 1991
bcc w/encl:
Document Control Desk
H. Christensen, RII
R. Lo, NRR
NRC Resident Inspector
U.S. Nuclear Regulatory Commission
Route 5, Box 413
Hartsville, SC
29550
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ENCLOSURE
The violation was written against 10 CFR 50, Appendix B Criterion XVI,
Cor
rective Action, because we believe that actions taken on April 15,
1991 and
shortly thereafter were not in agreement with your corrective action program in
effect at that time. Procedure PLP-026, Rev. 5 states, in Attachment 7.3, that
an ACR should be-prepared if a deficiency meets the following:
17.
Deficiency in Equipment Subject to 10 CFR 50, Appendix B - Failures,
malfunctions,
deficiencies, deviations,
defective material
and
equipment as they pertain to safety-related activities, processes,
equipment (not covered by a subprogram).
The galled stem of Valve V-2-6A is an example of a component deficiency subject
Instead only a work request was initiated.
Work
requests were not considered part of the subprogram in PL-026 at the time this
issue was found.
The actions taken to correct Valve V-2-6A deficiencies and
determine operability were not documented as they would have been if
an ACR
had been prepared.
We recognize that the actions taken were essentially the
same and that Valve V2-6A was subsequentially tested on August 16,
1991 and
found to be "operable."
In your November 2, 1991 response you stated that the feedwater block valves
and the feedwater regulating valves are redundant in so far as the safety
analysis for this valve. We believe that the feedwater regulating valve is not
credited in safety analyses for which the block valve provides the required
integrity for the auxiliary feedwater system. In the analyses the regulating
valve is assumed to fail open.
With regard to the question on adequate motor operator size for opening V2-6A
we request that you provide the basis for your calculation and have it avail
able on site for our review during a followup inspection.
The calculation
performed by the NRC used 1525 psid since this was considered to be the worst
case.
We understand that you have modified the design basis calculation to
around 365 psid.
At this differential, NRC would agree that the operator size
is satisfactory. We would like to review your reason for this change in design
basis durina a followup inspection.