IR 05000244/1990025
| ML17262A254 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/26/1990 |
| From: | Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17262A253 | List: |
| References | |
| 50-244-90-25, NUDOCS 9012040162 | |
| Download: ML17262A254 (17) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No:
50-244/90-25 License No. DPR-18 Licensee:
Rochester Gas and Electric Corporation (RG&E)
Facility: '. E. Ginna Nuclear Power Plant Dates:
October 10 through November 14, 1990 Inspectors:
T. A. Moslak, Senior Resident Inspector, Ginna N. S. Perry, Resident Inspector, Ginna Approved by:
E. C. McCabe, Chief, Reactor Projects Section 3B n l2<(Vb Date OVERVIEW PLANT OPERATI NS:
The plant operated stably at approximately full power.
Throughout this period, power operation was conducted in a safe, competent manner, with appropriate management involvement.
Plant housekeeping was assessed as excellent.
RADIOL GICALCONTR:
Locked high radiation areas were appropriately controlled.
MAINTENAN E/S RVEILLANCE:Management actively supported preventiveand corrective programs for balance of plant systems.
The Quality Control organization was actively involved in monitoring balance of plant maintenance.
Repair and post-maintenance testing of Feedwater Regulating Valve FRV-A were assessed as well planned and coordinated.
~SE URITY:
Changes have been made in the guardhouse to inc'rease the effectiveness of detection equipment.
EMER EN Y PREPARED S: A planning drill received strong management support and involvement.
EN INEERING/TE HNI AL S PPORT:
To address previously identified weaknesses, communication was better formalized between corporate and site engineering staffs,
~ 0t2040162 5'01126 PLir~
ADOCK 05000244 IQ PDC
TABLE F C NTENTS
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Plant Operations.... ~..... ~.......
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1.1 Control Room Observations...........:................
Radiological Controls,...................................
Maintenance/Surveillance 3.1 Maintenance Observations 3.2 Corrective Maintenance
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3.3 Unresolved Item (50-244/89-04-03)
Maintenance Building Valves (Closed)..........,....
3.4 Violation (50-244/89-17-01) Inappropriate Use of (Closed)
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3.5 Surveillance Observations..............
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Neglect of Turbine
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Torque Specification
3 Security
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Emergency Preparedness..............
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Engineering/Technical Support..............................
6.1 Violation (50-244/89-17-03) Failure to Promptly Identify and Correct a Design Deficiency (Closed)
6.2 Unresolved Item (50-244/90-88-01)
10 CFR 21 Notification Regarding MOV Loose Screws (Closed)
6.3 Unresolved Item (50-244/90-88-02)
10 CFR 21 Notification Regarding OT-2 Type Switches (Closed)
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5 Safety Assessment/Quality Verification............. ~........
7.1 Periodic and Special Reports..........."
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7.2 Written Report of Nonroutine Events...................
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Administrative........
8.1 Licensee Activities.
8.2 Inspection Hours..
8.3 Exit Meetings....
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DETAILS 1.1 C ntrol Ro m servati ns The inspectors found that the R. E. Ginna Nuclear Power Plant was being operated safely and in conformance with NRC requirements.
Control room staffing was adequate and operators exercised appropriate control over access to the control room.
Shift Supervisors consistently maintained authority over activities and provided detailed turnover briefings to relief crews.
Operators adhered to approved procedures and understood the reasons for lighted annunciators.
Documents reviewed included Ginna Station Event Reports (A-25.1) 90-93 through 90-106.
These Ginna Station Event Reports were reviewed to ensure that plant personnel took appropriate corrective action and observed the appropr'iate Limiting Conditions for Operation..
The inspectors reviewed control room log books to obtain information concerning trends and activities, and observed recorder traces for abnormalities.
During normal work hours and on backshifts, accessible areas of the plant were toured and plant conditions and activities were observed.
The inspectors verified compliance with plant Technical Specifications and audited selected safety-related tagouts.
No inadequacies were identified.
2.
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The resident inspectors periodically confirmed that radiation work permits were effectively implemented, dosimetry was correctly worn in controlled areas and dosimeter readings were accurately recorded, access to high radiation areas was appropriately controlled, and postings and labeling were in compliance with procedures and regulations.
Through observations of ongoing activities and discussions with plant personnel, the inspectors determined that radiological controls were conscientiously implemented.
During the inspection period, the inspectors entered two (2) normally locked high radiation areas, the residual heat removal heat exchanger rooms and the area behind the refueling water storage tank.
The heat exchanger rooms were properly controlled and a current survey was posted.
Both rooms exhibited excellent housekeeping and were adequately lit. No leaks were observed.
The access to the area behind the refueling water storage tank was properly posted with a current survey and activities were monitored by a health physics technician.
Housekeeping in this area was assessed as adequate, with minor discrepancies corrected by personnel present.
No unacceptable conditions were identifie.
Maintenance/
urveillance 3.1 aintenance Observations On October 24, plant personnel adjusted the packing gland on the "A" feedwater regulating valve, which had been leaking. A maintenance work package (Work Order 9001905) with specific work instructions detailed how the work was to be accomplished.
The instructions required the support of the operations and QC departments and required signoffs for each step.
In addition, post-maintenance testing was performed, by partially stroking the valve, and the process was repeated approximately eight hours later to verify that no relaxation had occurred.
The adjustment and post-maintenance testing was witnessed by maintenance supervision, QC and operations personnel.
The inspectors determined, through observation of the activity, review of the instructions and discussions with the personnel involved, that the activity was properly planned, performed and supervised.
Detailed work instructions were followed and Engineering was involved to specify the appropriate torque values.
Personnel performing the activity were qualified and knowledgeable.
Good coordination of the activity with all groups involved was observed.
Post-maintenance testing verified freedom of travel of the valve stem.
A minor steam leak exists in the flange/gasket interface to this valve. A proposed work package has been developed for repair by sealant injection.
RGB'orporate management is presently evaluating this proposal.
No unacceptable conditions were identified.
3.2 During a routine monthly Containment entry on November 7, plant personnel found two indications of primary coolant leakage.
Boric acid buildup was observed on the packing of a pressurizer spray valve and at a flange on a reactor coolant pump seal bypass flow indicator.
On November 8, another containment entry was made.
The boric acid was then cleaned from the area around the pressurizer spray valve.
No observable leakage was indicated from the valve packing.
Boric acid also was cleaned from the area around the reactor coolant pump seal bypass flow indicator, which was determined to be leaking slightly from a flange. The vendor was contacted for the proper torque specifications for the flange, but values were not available. RGB plans to determine appropriate torque specifications using the. data available and retorque the flange during the next routine containment entr k
Primary system leakage remained within Technical Specification limits.
No unacceptable conditions were identified.
3.3 nre lv I em-244/
- 4-Maintenance Ne lect f r ine Buildin Valve losed During a past inspection, numerous valves in the turbine building appeared to be neglected.
The inspectors reviewed Maintenance Procedure M-1306, Ginna Station Material Condition Inspection Program, Revision 4, effective June 22, 1990, and Maintenance Department Guidelines (SHARP Program) concerning work practice and equipment condition monitoring and found them adequate in regard to material condition deficiencies.
In addition, the inspectors periodically observed the condition of turbine building valves and found them to be in good condition.
Deficiencies were marked with a maintenance identification tag, indicating that the deficiency was identified and tracked for repair.
3.4 Vi lati n SO-244-17-l Ina r
ri te e fTor ueS ecification
During a past inspection, a failure to adequately control torquing of a packing gland was observed.
Ginna administrative procedures were subsequently revised to include a policy statement regarding consideration of inherent inaccuracies of calibrated measuring and test equipment, and direction for establishing appropriate acceptance criteria. In addition, a new procedure is in place for adjusting valve packing as part of the Valve Packing Improvement Program, This procedure provides specific direction for valve packing adjustments and provides a method for tracking valve packing data.
The inspectors reviewed the procedures and
. concluded that the concern was adequately addressed.
3.5 urveillance bservati ns Inspectors observed portions of the following surveillance to verify proper calibration of test instrumentation,use of approved procedures, performance of work by qualified personnel, conformance to Limiting Conditions for Operation, and correct system restoration following testing.
Periodic Test (PT)-3M, Containment Spray Pump MonthlyTest, Revision 2, effective June 29, 1990, observed October 23, 1990...
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Throughout the test, good communication and coordination was established between personnel performing the surveillance and the control room.
Test personnel strictly adhered to the surveillance procedure.
Independent verification was performed, as required, on system alignments and instrument readings.
Containment spray systems were expeditiously reconfigured to their normal alignment following test completion. The inspectors verified that test data met the performance criteria of Technical Specification 4.5.2.1.
No unacceptable conditions were identified.
4.
ecurit During this inspection, the resident inspectors verified that x-ray machines and metal and explosive detectors were operable, that protected area and vital area barriers were well maintained, that personnel were properly badged for unescorted or escorted access, and that compensatory measures were implemented when necessary.
The interior of the guardhouse was reorganized late in the inspection period.
This was done to address a prior weakness in the processing of personnel into the protected area.
In addition, to speed up processing (especially during outages),
another lane is planned for processing personnel.
Site security has recently implemented measures to enhance the effectiveness of the explosive detection system and to increase the coverage of intrusion detection systems, The inspectors verified that these measures were completed without compromising existing systems.
No unacceptable conditions were identified.
5.
Emer enc Pre arednes The inspectors observed various aspects of an emergency preparedness drill on October 17, 1990 and attended the drill critique on October 18, 1990.
The drill was well coordinated with active involvement by the entire site organization.
Senior corporate management also actively participated.
Through candid feedback by drill participants, the critique identified areas where performance could be improved, and remedial actions were proposed.
No significant problem areas were identifie.
En ineerin /Technical Su ort 6.1 Vi lati n-244/
-17-Failure Pr m tl Identif n
orrect a Desi n
Deficienc I
ed During a past inspection, it was determined that Corporate Engineering failed to promptly identify a safety injection switch design deficiency to the plant staff.
Subsequently, RG&E developed a procedure to provide formal guidance concerning communications between corporate and site personnel on potential
'conditions adverse to quality. Engineering procedure QE-1603, Documenting and Reporting Potential Conditions Adverse to Quality (PCAQs), Revision 0, effective August 31, 1990, established the means. for corporate engineers to document and report PCAQs.
This procedure assigned responsibilities and placed time constraints on the process for reviewing PCAQs and formally notifying site personnel.
Through discussions with personnel and review of the procedure, the inspectors concluded that corrective actions were adequate to address the concern.
6.2 nresolved Item 50-244/90-8-01
FR 21 Notification Re ardin MOV Loose Screws Closed During the refueling outage, plant personnel found 10 of 26 MOV (motor-operated valve) torque switches with loose socket head mounting screws.
Nine of the 26 exhibited loose wire termination bolts. The loose bolting was tightened, and the potentially defective torque switches are being replaced with a newer model.'n addition, the MOV actuators are now in the preventive maintenance inspection program. The inspectors concluded that actions taken were appropriate and had no further concerns.
6.3 ~d50-2<</
tl-88-0 10>>
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di Switches losed h
As identified by RG&E during a review, seven switches on the main control board could disable both trains of their safeguard function ifthe switch failed in the reset position. Allsuch switches were verified to be in the proper position by verifying that the plungers were in the proper position.
Also, after each such switch is manipulated, operators verify proper plunger position.
Long-term corrective actions being evaluated include the'ddition of separate, independent switches for each train, and rewiring/reconfiguring the existing switches.
The inspectors concluded that the concern is being adequately addressed,
7.
Safet Assessment/
ualit Verification 7.1 Peri dic and ecial Re rts The following report submitted by the licensee pursuant to Technical Specifications 6.9.1 and 6.9.3 was reviewed.
Inspectors verified that the report contained information required by the NRC, that test results and/or supporting information were consistent with design predictions and, performance specifications, and that reported information was accurate.
Monthly Operating Report for September 1990.
No unacceptable conditions were identified.
7.2 Written Re ort of N nroutine Event A written report submitted to the NRC was reviewed to determine whether details were clearly reported, causes were properly identified, and corrective actions were'ppropriate.
The inspectors also assessed whether potential safety consequences had been properly evaluated, generic implications were indicated, events warranted onsite follow-up, reporting requirements of 10 CFR 72 were applicable, and requirements of 10 CFR 73 had been met.
The following LER was reviewed (Note: date indicated is event date):
90-012, Turbine Trip Relay Actuation Due to Dropped Flashlight. in Relay Rack (Personnel Error), Causes Reactor Trip, September 26, 1990.
This event was reviewed in detail by an NRC Augmented Inspection Team and document in Inspection Report 50-244/90-19.
The inspectors concluded that the LER was accurate and met regulatory req'uirements.
No unacceptable conditions were identified.
8.
.8.1 Licensee Activities The plant was operating at approximately full power throughout the inspection period.
On November 7, during a routine containment entry, plant personnel found two indications of primary coolant leakage.
Boric acid buildup was observed from the packing of a pressurizer spray valve and at a flange on a reactor coolant pump seal bypass flow indicator (see Detail 3.2, Corrective Maintenance).
8.2 This inspection involved 137 inspection hours, including 6 backshift and 4.5 deep backshift hours.
8.3 E~iM At periodic intervals and at the end of the inspection, meetings were held with senior station management to discuss inspection findings. In addition, NRC exit meetings were held for the following inspections: 50-244/90-20 on October 19, 1990 and 50-244/90-24 on October 20, 1990.