IR 05000410/1989015
| ML17056A224 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/04/1989 |
| From: | Briggs L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17056A223 | List: |
| References | |
| 50-410-89-15, NUDOCS 8908220422 | |
| Download: ML17056A224 (12) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
License No.
Licensee:
50"410/89"15 NPF-69 Niagara Mohawk Power Corporation 301 Plainfield Road Syracuse, New York Facility Name:
Nine Mile Point Unit 2
'A Inspection Conducted:
May 22 - 26, 1989 Inspectors:
L ry iggs, Senio perations Engineer
a Date Approved by:
Peter W.
selgroth, Chief, P
Section Operations Branch, DRS Date Ins ection Summar:
Inspection on May 22 - 26, 1989 (Report No. 50-410/89-15).
A~l:R l, f
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f surveillance activities and review of surveillance procedures to verify Techni-cal Specifications requirements were satisfied.
Results:
The activities observed were well controlled and performed in a competent manner.
The survei.llance procedures reviewed provided good direction to the person performing the task, although the format for step checkoff and data. recording was. not, always "user. friendly".
This is in the process of being corrected by the licensee.
Review of the emergency diesel generator monthly surveillance test identified an unresolved item concerning adequacy of testing of diesel generator air start solenoid valve DETAILS 1.0 Persons Contacted
- R. Abbott, Station Superintendent, Unit 2
- C. Beckham, Manager, Nuclear guality Assurance Department
"M. Colomb, Nuclear Regulatory Compliance Engineer M. Esposito, Chief Instrument and Control Technician, Nuclear T. Jacot, Instrument and Control Technician, Nuclear
"J. Kinsley, Supervisor, Instrument and Control department, Unit 2
"L. Lagoe, Maintenance Superintendent, Unit 2
"P.
MacEwan, Site Representative, New York State Electric and Gas Co.
"P. Mangano, Site Engineering
- J. Manly, Nuclear Regulatory Compliance Engineer
"R. Pasternak, Manager, Site Engineering
"G. Sanford, Supervisor, Nuclear Regulatory Compliance NRC Personnel
- W. Cook, Senior Resident Inspector
"R. Laura, Resident Inspector
"Denotes those present at the exit meeting on May 26, 1989.
2.0 Surveillance Program Scope The inspection was conducted to review and observe performance of a sampling of surveillance procedures.
The procedures were reviewed to verify:
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That prerequisites and precautions specified were appropriate for plant conditions.
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That appropriate acceptance criteria were specified.
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That steps were specified to return the system to an operable status following testing.
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That tests were in conformance with Technical Specifications (TS),
In-Service Testing (IST) program, and procedural requirements.
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That tests were performed by qualified individuals.
Several procedures were also reviewed to determine.if the testing performed adequately verified system or component operability as defined in TS and/or design documents.
This review is discussed in. more detail in Paragraph 2.2.
Procedures reviewed and observed are listed in Attachment xj
2.1 Surveil lance Observations SCOPE The inspector observed partial performance of the four (4) surveill-ance procedures identified in Attachment A.
FINDINGS During the performance of surveillance activities observed by the inspector; The operations staff exercised positive test control.
The instrument and control technicians and the operations staff involved in the actual performance of the surveillance tests were knowledgeable of the equipment and the activities being conducted.
The procedures were being performed in accordance with program and Station General Order 89-03, Procedure Adequacy and Compliance requirements.
2.2 Procedure Review SCOPE The procedures identified in Attachment A were reviewed either on si'te or at the NRC Region I office to verify that they adequately verified TS and design operability requirements.
FINDINGS All procedures reviewed with one exception appeared to adequately verify system/component operability.
The procedure identified as deficient was N2-0SP-EGS-M001,
"Diesel Generator and Diesel Air Start Yalve Operability Test Division I/II.
One of the functions of this procedure is to verify the operability of the diesel air start valves.
The valves are solenoid operated, 2.5 inch valves.
Each diesel has two (2) valves in parallel.
There is no position indica-tion on the individual valves.
Operation of either valve, by design, will start the diesel generator within the JS required time.
The acceptance criteria specified in the test procedure to verify valve operability was that the diesel started within the TS required time.
The inspector noted that true operability of each valve was not adequately demonstrated by the surveillance procedure since either valve will start the diesel.
The licensee agreed to evaluate the test method and modify the surveillance procedure to ensure adequate testing of the diesel air start valves.
The test method initially selected was to record the
diesel air receiver pressure just before starting the diesel and then immediately after it started.
This method would be acceptable if a sufficient pressure drop occurred in each air receiver when the diesel started to positively identify a failed air start valve.
These air pressure readings are currently taken in N2-0P-100A, Standby Diesel Generators, which is used to perform the surveillance test.
The readings have not been used to verify valve operability in the past but could be by a record review, if the proposed test method is satisfactory.
Subsequent testing by the licensee did determine the test method to be acceptable.
This item is unresolved pending NRC review of licensee corrective actions (410/89-15-01).
The inspector also performed a brief review of the Logic System Functional Testing (LSFT) Program.
The program was designed to verify that all components of a logic system that are required to be tested by Technical Specifications (TS) are tested.
The system compares the surveillance procedure to the circuit drawing and each component that is tested is color coded.
Only those components required to be tested by TS are color coded.
The circuit diagrams reviewed by the inspector indicated all required components were tested and were easily cross referenced to surveillance procedures and TS.
The in place system appears to ensure adequate overlap and
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interface testing of components exists.
3.0 General Comments and Observations SAFETY RELATED COOLER PERFORMANCE Because of recent problems experi.enced with corrosion and/or silt buildup in the cooling water side of safety related. heat exchangers, principally room coolers, the inspector, questioned the licensee about their plans to do performance based testing of installed safety related room cooler heat exchangers.
The licensee stated that plans were in progress and were being tracked through their commitment tracking list.
Current plans are to conduct a heat balance on each cooler during the upcoming refueling outage.
The licensee'
commitment number is 503378.
CARBON DIOXIDE FULL DISCHARGE TEST A recent NRC, Technical Issue Summary addressed surveillance testing of C02 systems that had never been tested by a full discharge test to verify design C02 concentration levels in their respective fire areas.
The inspector requested a copy of the full discharge test of one of the vital switchgear rooms.
The licensee provided a copy of two (2) procedures, N2-POT-49, Fire Protection C02, which tested the various C02 system components and NS.0045.002, C02 Concentration Verification, which verified C02 concentration, rate of 'increase of concentration, and duration of concentration.
All data were within established acceptance value.0 Exit Meeting At the conclusion of the site inspection, on May 26, 1989, an exit meeting was held with the licensee's senior available representative (denoted in
,Paragraph 1.0) to discuss the scope and findings as detailed in this report.
At no time during this inspection was written material provided to the..
licensee by the inspector.
Based on the NRC Region I review of this report and discussions held with licensee representatives during this inspection, it was determined that this report does not contain informa-tion subject to
CFR 2.790 restriction ATTACHMENT A PROCEDURES REVIEWED AND WITNESSED
"¹ N2-OSP-EGS-M001 Diesel Generator and Diesel Air Start Valve Operability Test Division I/II
"¹ N2-ISP-CMS-M011 Monthly Functional Test of Suppression Pool Water Temperature Indication Channels 2CMS"TE67A-70A
"¹ N2-ISP-NMS-Q107 APRM/LPRM Channel Calibration
"¹ N2-ISP-NMS-WQ007 APRM Channel Functional Test N2-OSP-SLS-Q002 Standby Liquid Control Motor Operated Valve Operability Test N2-OSP-RHS-Q004 RHR System Loop A Pump and Valve Operability Test and System Integrity Test Indicates Procedure was reviewed either at site or in-office Indicates at least partial procedure performance wa observed