ML20154P289
| ML20154P289 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/20/1988 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM TAC-62924, NUDOCS 8806030287 | |
| Download: ML20154P289 (2) | |
Text
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4 Va 4y Pwer Staton SNppngport. 'A 1507MX)o4
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Ocea,G a o 6412t 60 5255 May 20, 1988 U.
S. Nuclear Regulatory Commission
- Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Supplemental Response to NUREG 0737, Item III.D.l.1 (TAC 62924)
Gentlemen:
on August 7,
1986, DLCo provided a preliminary response to this issue.
Due to the status of plant construction and procedure development at that time, DLCo did not address the safety injection system (for other than recirculation mode) and the radiation monitoring system in its responre.
Subsequently, SSER-5 indicated that the list 'of plant equipment contained in the preliminary response was not comprehensive enough but operation through the first refueling was justified.
The following information supplements the preliminary response for those systems not already addressed.
Safety Injection System An Operating Surveillance
- Test, "High Energy Line and ECCS Inspection" is performed on a
quarterly frequency.
This procedure employs a
visual examination of lines outside containment to detect external leakage.
Another test, "Safety Injection Recirc. Mode Leak Test", provides visual inspection for leaks in many components which are common to both the injection and recirculation mode.
This test is performed on a refueling frequency.
Both tests result in corrective actions through the maintenance program when deficiencies are noted.
padiation Monitoring System Portions of the radiation monitoring system outside containment which use piping or ducting to carry fluid samples outside of the monitored system have been reviewed.
These monitors fit at least one of the following criteria:
1.
The monitor is not conducting fluid from a system which requires leakage monitoring.
2.
Fluid activity of the monitored system is not affected by an ph accident in containment.
I 8806030287 880520 PDR ADOCK 05000412 P
DCD I j
r rhenvsrValley.PowsrStation,UnitNo. 2 ca Dockst No. 50-412, Licanso No. NPF-73
, Supplemental Response to NUREG 0737, Item III.D.l.1 (TAC 62924)
Page 2 3.
The monitor would not conduct highly radioactive fluids as a result of an accident.
- 4..
The monitor is isolated by containment isolation or high radiation signals.
5.
The monitor checks fluids which are already in the environment or being released to the environment.
Therefore, a
leak reduction program described in NUREG 0737 is not applicable to this system.
DLCo plans to continue its program of testing, maintenance, training and administrative controls previously discussed for other systems.
Therefore, if additional concerns exist which would impact operation of BVPS-2 beyond the first refueling, please identify them as early as possible.
Sincerely, b AO
. D.
Sieber Vice President Nuclear Group cc:
Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr.
P. Tam, Project Manager