IR 05000280/1986007
| ML18149A124 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/28/1986 |
| From: | Marlone Davis, Ignatonis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18149A123 | List: |
| References | |
| 50-280-86-07, 50-280-86-7, 50-281-86-07, 50-281-86-7, NUDOCS 8605050145 | |
| Download: ML18149A124 (5) | |
Text
Report Nos. :
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTA STREET. ATLANTA, GEORGIA 30323 50-280/86-07 and 50-281/86-07 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 Facility Name:
Surry 1 and 2 License Nos.:
DPR-32 and DPR-37 Inspection Conducted:
March 4 - April 7, 1986 Inspec~r:
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M. J. Da'Q,s
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Approved by:
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A. J. Igon~~ection Chief Division of Reac or Projects
!Jate Signed ff J_g/g/,
te sA gned SUMMARY Scope:
This inspection involved 150 inspector-hours in the area of plant ope rat i ans and operating records, p 1 ant maintenance and survei 11 ance, p 1 ant security, followup of events, and open item Results:
In the areas inspected, no violations or deviations were identified.
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REPORT DETAILS Persons Contacted Licensee Employees R. F. Saunders, Station Manager D. L. Benson, Assistant Station Manager H. L. Miller, Assistant Station Manager D. A. Christian, Superintendent of Operations E. S. Grecheck, Superintendent of Technical Services J. W. Patrick, Superintendent of Maintenance J. Logan, Supervi -;or, Safety Engineering Staff S. Sarver, Superintendent of Health Physics R. Johnson, Operations Supervisor D. Driscoll, Site Quality Assurance Manager Other licensee employees contacted included control room operators, shift technical advisors, shift supervisors, chemistry, health physics, plant maintenance, security, engineering, administrative, records, contractor personnel and supervisor Exit Interview The inspection scope and findings were summarized on a weekly basis with certain individuals identified in paragraph The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection:
Licensee Action on Previous Enforcement Matters This item was not inspected during this reporting perio.
Operations Units 1 and 2 were inspected and reviewed during the inspection perio The inspector routinely toured the control room and other plant areas to verify that plant operations, testing and maintenance were being conducted in accordance with the facility Technical Specifications (TS)
and procedure The inspector verified that monitoring equipment was recording as re qui red, that equipment was properly tagged, and that plant housekeeping efforts were adequat The inspector also determined that appropriate radiation controls were properly established, that clean areas were being controlled in accordance with procedures, that excess material or equipment was stored properly, and that combustible material and debris were disposed of expeditiousl During tours, the inspector monitored the plant for unusual fluid
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leaks, p1p1ng vibrations, p1p1ng hanger and seismic restraint settings, various valve and breaker positions, equipment caution and danger tags, component positions, adequacy of fire fighting equipment and instrument calibration date Certain tours were conducted on back shifts. Inspections included areas in the Un its 1 and 2 cab 1 e vaults, vi ta 1 battery rooms, fire pumps house, 1 ow 1 eve 1 intake structure, fue 1 storage bui 1 ding, emergency switchgear rooms, diesel generator rooms, control room, auxiliary building, and cable penetration areas to verify certain breaker and equipment conditons and positions for safety-related component The inspector routinely conducted partial walkdowns of emergency core coo 1 i ng systems and engineered safety f ea tu res systems to verify operability and observe maintenance and testing of certain equipment and components in these system Unit 1 operated at power for the duration of the reporting period; no reactor trips or shutdowns occurre At 3:40 p.m. on April 3, 1986, during realignment of the ventilation system in preparation for returning filtered exhaust fan 1-VS-F-58A to service the 11Auxil i a ry Ventilation System Safety Mode Initiated 11 alarm was received a:'d four auxiliary building ventilation fans tripped. These actions occurred as bc,th switches for the de con building (A0D-VS-l03A and 1038) were shifted to filter mode position prior to testing fan 1-VS-F-58 The vent i 1 at ion system was promptly returned to normal a 1 i gnmen The cause of the event is still under investigation by the licensee. The malfunction could not be duplicated. The NRC was not notified of the partial ESF actuation until 11:37 The failure to meet the four hour reporting time limit of 10 CFR 50.72 was identified by the licensee and corrective action was taken to alert operations personnel concerning reporting requirements; consequently a notice of violation will not be issue Unit 2 operated at power for the duration of the reporting period; no reactor trips or shutdowns occurre Other than the licensee identified violation mentioned in paragraph 4.b., no violations or deviations were identifie.
Surveillance and Maintenance Inspections During the reporting period, the inspector reviewed various surveillance and maintenance activities to assure compliance with the appropriate procedures and T Inspection areas included the following: The inspector observed new fuel handling and receipt inspection operations in accordance with OP Receipt and Storage of New Fuel.
Fuel assemblies were unloaded from shipping containers, inspected, and transported to the new fuel storage are.,
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3 The inspector observed the performance of Unit 2 Periodic Test PT-Analog Rod Position Instrumentation" which verified operability of rod bottom bistable actio During performance of the test, the individual rod position indicator for rod F-10 was sticking at approximately 30 step The indicator was replaced in accordance with 2-PT-Analog Rod Position Instrumentation Calibration." A walkdown inspection of Circulating Water and Emergency Service Water systems was conducted at the low level intake structure. The inspector observed maintenance in progress on the screen wash systems for the Circulating Water Pump The inspector also toured the Independent Spent Fuel Storage Installation site and observed electricians installing intrusion detection security system On March 27, 1986, the inspector observed fire team participation in a fire drill at the Unit 1 high level intake structur Reactor coolant system leak rates were reviewed to ensure that detected or suspected 1 eakage from the system was recorded, investigated, and ev2luated and that appropriate actions were taken, if require Within the areas inspected, no violations or deviations were identifie.
Review of Open Itefils Open Item 280/281/78-CI-18 concerned findings of an Underwriters Laboratory Fire Test of cable tray The item was reviewed in inspection report numbers 280/79-63, 281/79-83 and was left open pending issuance of the Surry Fire Protection Safety Evaluation Report (SER).
The SER was issued on September 19, 1979, and stated that the design and i nsta 11 at ion of water suppression systems conformed to NFPA Standard Recommended improvements such as providing heat collector plates over those sprinkler heads in the turbine building installed under grating walkways have been accomplishe This item is considered close.
Licensee Event Report (LER) Review The inspector reviewed the LERs listed below to ascertain whether NRC reporting requirements were being met and to determine the appropriateness of corrective actions taken and planne Certain LERs were reviewed in greater detail to verify corrective action and determine comp 1 i ance with the TS and other regulatory requirement The review included examination of the logbooks, internal correspondence and review of Station Nuclear Safety and Operating Committee meeting minutes and discussion with vafious staff member...
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(Closed)
LER 281/84-13 concerned a reactor trip caused by technicians troubleshooting a failed delta flux indicator (NI-43). A blown fuse in instrument drawer NI-43 resulted when an ungrounded power lead with a digital voltmeter was used to obtain a detector current measuremen The blown fuse resulted in completion of the NIS dropped rod protection circuitry which caused a turbine runbac A reactor trip occurred approximately two minutes later from completion of the two of three logic matrix on overpower (OP) delta T protection. Initiation of the OP delta T trip function was caused by a* decreasing OP delta T setpoin Adequate instructions have been furnished for test equipment setu During a subsequent outage, OP delta T setpoi nt and computation electronics were tested and found to be within specification (Closed) LER 281/86-04 concerned a turbine trip from 16% power during a unit rampdown due to a high level in 1B1 steam generator which resulted in a reactor trip. The high level condition was caused by the 1B1 main feedwater bypass valve failing to close on deman Blockage in the air pilot relay prevented proper air flow to the valve operato Following the trip, the blockage was dislodged and the valve was cycled satisfactoril (Closed) LER 280/86-03 concerned 2 manual reactor trip following a turbine runback causerJ by four dropped control rod Technicians had installed an electrical jumper in the control rod logic cabinet. The jumper slipped off its lead and shorted other connections resulting in an urgent failure which prevented normal rod motio In addition, the short caused four symmetrical control rods located in control bank A to drop into the core initiating a turbine runbac The manual trip decision was made due to delta flux concern Both 100 V power supplies in the logic cabinet and the A-708 card were subsequently replaced. Abnormal procedure 1.4 was changed to instruct the operator to trip the reactor if two or more rods have been droppe.
Plant Physical Protection The inspector verified the following by observation: Gates and doors in protected areas and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plans were not compromised or obstructe Personne 1 were properly i dent ifi ed, searched, authorized, badged and escorted as necessary for plant access control.