IR 05000244/1987025
| ML17261A762 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/23/1987 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17261A760 | List: |
| References | |
| 50-244-87-25, NUDOCS 8801120332 | |
| Download: ML17261A762 (20) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION RcGION Report No. 50-244/87-25 Docket No. 50-244 Licensee No.
DPR-18 Priority Category C
Licensee:
Rochester Gas and Electric Corporation 49 East Avenue Rochester, New York Facility Name:
R.
E. Ginna Nuclear Power Plant Inspection at: Ontario, New York Inspection Conducted:
October 4,
1987 through November 30, 1987 Inspectors:
T. J. Polich, Senior Resident Inspector, Ginna N.
S. Perry, Resident Inspector, Ginna Approved by:.
C. J.
Cowgill Chief, Reactor Projects'Sec ion No.
1A, DRP Date Ins ection Summar
Ins ection on October
1987 throu h November
1987 Re ort No.
50-244/87-25 d:
R i
i
d hi<later System", effective September 11, 1987.
PT-2.8,
"Component Cooling Mater Pump System", effective July 24, 1987.
PT-17.3,
"RMS Channel Response to Portable Radiation Source Area Monitor R9 Process 10A & 10B, R11 thru R22, R31, and R32", effective May 13, 1987.
No unacceptable conditions were identifie.
Plant Maintenance During the inspection period, the inspectors observed maintenance and problem investigation activities to verify:
compliance with regulatory requirements, including those stated in the Technical Specifications; compliance with administrative and maintenance procedures; requi red gA/(}C involvement; proper use of safety tags; qualifications; and reportabi lity as requi red by Technical Specifications.
b.
The inspectors witnessed selected portions of the following maintenance activities:
Maintenance Work Order and Trouble Report 87-5392 concerning the blocking device installation on AOVs 897 and 898.
Maintenance Procedure (M)-11.30.2, "Diesel Fire Pump Angle Drive Maintenance",
effective April 28, 1986.
M-38. 1, "Diesel Fire Pump Engine Maintenance and Inspection",
effective November 18, 1986.
M-106, "Replacement Or Inspection Of D.C. Fuses",
effective October 8, 1987.
The inspectors observed various fuses being replaced during the inspection period.
No unacceptable conditions were identified.
7.
Licensee Technical Services Meetin 8.
On November 19, 1987, seven RG5E representatives, corporate and plant engineers and management, met with five NRC representatives, Division of Reactor Safety and Division of Reactor Projects
.(DRP) personnel, at Region I, King of Prussia.
The licensee described their Technical Services Department and outlined present and future plans with regards to the Ginna Nuclear Power Plant.
The NRC DRP Branch I Chief described future plans of the NRC.
The meeting was general in nature and described the basic programmatic structure of the Technical Services Department.
Positive and open communications between the two groups were established and reinforced.
Additional meetings will be planned for next year.
Licensee Event Re orts LERs The inspector reviewed the following LERs to verify that the details of the event were clearly reported, the description of the cause was accurate, and adequate corrective action was taken.
The inspector also determined whether further information was required, and whether generic implications were involved.
The inspector further verified that the reporting requirements of Technical Specifications and s ation
"10" administrative and operating procedures had been met; that the event was reviewed by the plant Operations Review Committee and that continued operation of the facility was conducted within the Technical Specification limits.
LER 87-005:
Inadvertent Containment Ventilation Isolation During Performance of Monthly Periodic Test of Containment Particulate Radiation Monitor Due to a Frayed Conductor.
~
On May 14, 1987, with the reactor at 100% power, a containment ventilation isolation occurred due to a spurious signal from containment particulate radiation monitor (R-11).
All containment ventilation isolation valves that were open, closed as designed.
The R-11 digital display was lost and a control board annunciator alarmed.
The R-11 fuse was checked and although not blown was replaced.
When the fuse was replaced the display returned and the test was complet d satisfactorily.
Further investigation determined the cause to be a manufacturing defect (frayed conductor) internal to the R-11 drawer.
The licensee subsequently inspected all other radiation monitor drawers and found one other frayed conductor on R-2 (Containment Area Radiation Monitor).
The licensee notified the manufacturer of the radiation monitors (Victoreen)
and performed a
CFR 21 evaluation on R-11.
The evaluation determined the defect was not reportable under
CFR 21.
Review of Periodic and S ecial Re orts Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9. 1 and 6.9.3 were reviewed by the inspectors.
This review included the following considerations:
the reports contained the information required to be reported by NRC requirements; test results and/or supporting information were consistent with design predictions and performance specifications; and the reported information was valid.
Within this scope, the following reports were reviewed by the inspectors:
Monthly Operating Reports for September and October 1987.
No unacceptable conditions were identified.
Exit Meetin At periodic intervals during the inspection, meetings were held with senior facility management to discuss the inspection scope and findings.
Based on the NRC Region I review of this report and discussion held with licensee representatives, it was determined that this report does not contain information subject to
CFR 2.790 restrictions.