IR 05000244/1994002
| ML17263A541 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/15/1994 |
| From: | Eapen P, Gregg H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17263A540 | List: |
| References | |
| 50-244-94-02, 50-244-94-2, NUDOCS 9403010060 | |
| Download: ML17263A541 (7) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
DOCKET/REPORT NO.
50-244/94-02 LICENSE NO.
.LICENSEE:
FACILITYNAME:
INSPECTION AT'PR-18 Rochester Gas and Electric Corporation 49 East Avenue Rochester, New York 14649 Rochester Gas and Electric Corporation (RGB')
RGB'uclear Engineering Services Corporate Office and R. E, Ginna Nuclear Power Plant INSPECTION DATES:
January 10-14, 1994 INSPECTOR:
Harold Gregg, Sr. Reac ngineer Systems Section, EB, DRS Date APPROVED BY:
Dr. Plackeel K. Eapen, C
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9 di dgy engineering to benefit plant safety and performance.
Engineering at the corporate office and the site respond quickly to resolve problems as evident in the AMSAC problem identification and resolution.
There appeared to be effective communication between the engineering staffs and other departments.
The site engineering organization change to a system engineering concept is taking hold.
Evaluation of an improved check valve design was a good engineering initiative.
One violation item 50-244/93-08-01, and one unresolved item 50-244/93-23-01 were close DETAILS 1.0 DESIGN CHANGES AND ENGINEERING SUPPORT (37700)
The objectives of this'inspection were to review the licensee's engineering activities in support of design changes and modifications, and to assess the licensee's safety perspective related to these changes.
Other new and ongoing corporate engineering programs were also assessed from a safety and performance perspective.
2.0 DESIGN MODIFICATIONS Several selected modifications planned for the 1994 and 1995 outages, as detailed below, were reviewed by the inspector to assess the adequacy of the implementation of the licensee's modification program.
In particular, the inspector reviewed design descriptions, drawings, calculations, and required installation testing to verify compliance with the applicable NRC requirements.
The planned modifications exhibited effective engineering and management oversight and were noted to benefit plant safety and performance.
Service Water Pump Discharge Check Valve Replacements (engineering work request (EWR) 5284B).
To address maintenance and operational problems and a nonconformance report that identified loss of body material at seat locations, the licensee initiated a request for replacement of Crane Company swing check valves.
An engineering objective of this modification included evaluations and selection of an improved check valve design.
The selected replacement valves are flanged in-line nozzle type check valves manufactured by Mannesmann AG. The valves have a short stroke and the catalog information descr'ibes shock-free closure of these check valves.
The "A" service water loop valves 4601 and 4602 are to be installed in the 1994 outage and the "B" loop valves 4603 and 4604 are scheduled for the 1995 outage.
The evaluation and selection of an improved check valve design that included contacts with users, was a good initiative.
Component Cooling Water (CCW) Check Valve Replacements (EWR 5284).
To address maintenance and operational problems of obtaining replacement parts, seat cracking indications, and hydraulics conditions suspected of pump motor pad concrete damage, the licensee initiated the replacement of Velan Company swing check valves.
Replacement of valves 750 A/B and 870 A/B are to be with like kind valves.
Replacement valves 723 A/B (CCW pump discharge check valves), suspected of contributing to motor pad concrete damage, are to be with flanged in-line nozzle check valves manufactured by Mannesman AG. This valve design with a short stroke in-line guided spindle type disc has the potential to provide shock-free closure.
Reactor Coolant Pump (RCP) "A" Oil Level Monitoring (EWR 5434 B). The licensee processed this EWR to improve the reliability and calibration capabilities of the "A" RCP oil level monitoring system.
This modification is similar to that installed on the "B" RCP that has provided good result Radiation Level Steam Line Monitoring Improvement (EWR 5161)
~ This modification addresses an NRC Inspection Report 89-80 issue that identified difficult to discern readings of main steam line control room recorders and the capability to quantify radioactive release from the main steam safety valves (MSSV), Atmospheric relief valves, and turbine-driven feedwater pump exhaust:
The new system will replace the three existing recorders with two continuous indicating digital displays in the control room and inputs of MSSV openings willbe fed to the plant process computer system.
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Condenser Retube/Interference Removal (EWR 4607).
Numerous piping interferences willbe removed and replaced with flanged segments during the 1994 outage in preparation for the condenser retubing scheduled for the 1995 outage.
The 1995 retubing of the condensers with type 316 stainless steel willreplace existing copper laden tubing.
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Service Water Pipe Access (EWR 5405).
This modification responds to NRC Generic Letter 89-13 and commitments documented in NRC Inspection Report 89-08.
The existing welded end cap of the "A" header willbe replaced with a bolted blind flange to provide access for robotic inspection of the underground piping during the 1994 outage.
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3.0 ENGINEERING PROBLEM RESOLUTIONS The inspector reviewed several recent problems and the engineering corrective actions and performance to address them as described below.
ATWS Mitigation System Actuation Circuitry (AMSAC). The inspector reviewed the engineering performance in identifying and addressing an AMSAC deficiency.
A lock-in feature of the variable timer was not a defined requirement of the generic design package document.
On September 21, 1993, the licensee's engineering review of NRC IN 92-06 Supplement 1, identified that the lock-in feature was not included in the auxiliary feedwater pump start logic. Expedient revisions were made to the system and new software was installed on November 11, 1993.
The problem identification, safety evaluations, corrective actions as well as the notification to the industry were particularly well and expediently performed by the corporate engineering staff.
Packing Leak Repair of Feedwater Control Valves 4269 and 4270.
These valves had packing gland leaks and the area was restricted in September 1993.
The inspector observed the feedwater control valves (4269 and 4270) in the auxiliary building during this inspection to verify the licensee's actions to correct packing leaks were implemented.
The valves were free of packing leaks and the work order reviewed by the inspector was found to be effective for repackin Steam Generator Replacement Activities. The inspector reviewed the licensee's steam generator replacement activity. The licensee informed the inspector that the initial samples of the Inconel 690 preproduction tubing produced by Sumitomo did not meet the material specification requirements and grain structure.
The licensee was actively pursuing this issue and alternate sources of tubing material suppliers were being reviewed.
The inspector concluded that the corporate and site engineering staff responded quickly to resolve problems and there were good communications between engineering staffs and other departments.
4.0 ENGINEERING ORGANIZATION The site engineering organization has recently undergone significant change.
In mid October 1993, a systems engineering organization was established and staffed.
Technical engineers, liaison'engineers, and maintenance engineers were assigned system engineering functions.
Site engineering was restructured to have a systems engineering group and a modifications/special projects/licensing group reporting to the manager, technical engineering.
Systems engineering has a lead engineer and thirteen staff engineers.
The modifications, special projects licensing group has a lead engineer and six staff engineers.
The new engineering organization was structured to be at one location, with well-defined responsibilities to enhance effectiveness.
5.0 LICENSEE MEETINGS During this inspection, the inspector attended a monthly outage planning meeting, the daily morning priority action meeting, and a motor-operated valve meeting.
Each of these meetings were attended by site and corporate engineering staff members and their participation contributed to effective and productive meeting performances.
6.0 PREVIOUSLY IDENTIFIED NRC ITEMS l sed Viol ti n-244
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- 1: Failed service water valves.
A violation was issued because of inadequate action that led to failure of Crane model 101XU valves.
Appropriate actions, preventive maintenance activities, and planned detection methods to enable early identification of degradation or failures similar to the Crane model 101XU valves were presented by the licensee at the enforcement conference held on July 16, 1993.
The inspector verified that the licensee's commitments to replace the remaining Crane 101XU valves were implemented as stated in the licensee's letter dated August 23, 1993.
Additionally, actions to establish a preventive maintenance frequency was being developed.
The inspector verified that valves 4027, 4028, 4013, and 4663 were newly installed.
This item is close Unre olved Item 0-244-2 -01: Root cause analyses of steam generator blowdown line "B" elbow weld leak.
The leak was identified on November 17, 1993.
The plant was shut down and the piping was replaced on November 18, 1993.
This unresolved item was issued to track the completion of root cause analysis.
The inspector reviewed the licensee's November 24, 1993, documented analysis of the pipe leak and the root cause determination provided in the report.
The leak was at a 2" elbow to pipe filletweld and was attributed to an original weld pore or slag inclusion defect.
Gradual degradation over years of service and.blowdown cyclic stresses enlarged discontinuity until the leak path developed at the weld surface.
The inspector found the licensee's root cause determination to be acceptable.
This item is closed.
7.0 EXITMEETING The inspector met with the licensee's representatives on January 14, 1994, to summarize the findings of this inspection.
Attendees at the exit meeting are listed in Attachment 1.
The licensee acknowledged the inspector's finding ATTACHMENT1 Persons Contacted Roch ter nd Electric Co rati n
- R. Baker J. Cook
- C. Forkell T. Harding J. Hotchkiss R. Jaquin
- M. Kennedy
- D: Markowski T. Marlow T. Newberry
- L. Rochino T. Schuler E. Voci J. Wayland J. Widay P. Wilkens
- G. Wrobel II Electrical Engineer Manager, Planning and Scheduling Manager, Electrical Engineering Lead Engineer, Modifications/Special Projects Modifications Project Director Nuclear Safety and Licensing Engineer Director, Configuration Management Mechanical Engineer Department Manager, Quality Performance Lead Mechanical Engineer Lead Mechanical Engineer Manager, Technical Engineering Manager, Mechanical Engineering Lead Engineer, Systems Engineering Plant Manager, Ginna Department Manager, Nuclear Engineering Services Manager, Nuclear Safety and Licensing Nu lear Re ulato ommi i n T. Knutson T. Moslak Resident Inspector Senior Resident Inspector
- Denotes presence at exit meeting on January 14, 1994.