IR 05000280/1981014
| ML18139B411 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/18/1981 |
| From: | Burke D, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139B410 | List: |
| References | |
| 50-280-81-14, 50-281-81-14, NUDOCS 8106230539 | |
| Download: ML18139B411 (4) | |
Text
e UNITED STATES e
NUCLEAR REGULATORY COMMISSION RE(!ION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/81-14 and 50-281/81-14 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Facility Name:
Surry Units 1 & 2 Docket No and 50-281 License Nos.DPR-32 and DPR-37 Inspection at Surry ~ite. N;)'_) Surry, Inspector -K. {I/, -~~
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H. C. Dance,\\Section Chief, Reactor Projects and Inspection Division SUMMARY Inspection on April 1-30, 1981 Areas Inspected
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ltl Date igned This inspection involved 90 resident inspector-hours on site in the areas of plant operations and operating records, plant maintenance, calibration and testing and plant security.*
Results Of the 4 areas inspected, no violations or deviations were identified.
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DETAILS Persons Contacted Licensee Employees
- J. L. Wilson, Station Manager
- R. F. Saunders, Assistant Station Manager
- G. E. Kane, Operations Superintendent
- D. A. Christian, Superintendent of Technical Services L.A. Johnson, Maintenance Superintendent S. P. Sarver, Health Physics Supervisor
- F. L. Rentz, Resident QC Engineer Other licensee employees contacted during this inspection included control room operators, shift supervisors, QC, HP, plant maintenance, security, engineering, chemistry, administrative, records and contractor personne *Attended exit interview Management Interviews The inspection scope and findings were summarized on a biweekly basis with those persons indicated in paragraph 1 abov.
Licensee Action on Previous Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inpectio.
Unit 1 Unit 1 remains shutdown for the Steam Generator Replacement Projec The hydrotesting of the secondary side of the steam generators is complete, and hydrotesting of the RCS primary loops is in progres During the reporting period, the inspector routinely toured the Unit 1 control room and other plant areas to verify that the plant testing, maintenance and repairs were being conducted in accordance with the technical specifications and facility procedures. Portions of the Unit 1 RCS hydrotesting were also observe Within the areas inspected, no violations or deviations were identified.
e 2 Unit 2 Operations Unit 2 operated at power during April 1981, except for the outages discussed belo During this time, the inspector routinely toured the Unit 2 control room and other plant areas to verify that the plant operations, testing and maintenance were being conducted in accordance with the facility technical specifications and procedure Within the areas inspected, no violations were identified. Specific areas of inspection and review included the following: Review of annunicated alarms in the control room and in.spection of safety-related valve and pump alignments on the consoles and in the plan Followup on the Unit 2 reactor trip which occurred at 10:47 a.m. on April 6, 198 Instrument technicians had r~paired the Channel II main Reactor Coolant System (RCS) loop C flow instrumentation, and were valving the flow instrument in when the RCS loop 3 low flow RPS trip occurre The high pressure side of the flow transmitter are common and apparently were sympathetically affected when the low pressure side of the Channel II FT 435 was being vented, causing the pressure pertur-bation and low flow trip. Periodic Test (PT) procedure 2-PT-2.2A was being used to perform venting and calibration of the Channe 1 II pressure (flow) transmitter. Although the PT states to slowly vent the instruments, the licensee is revising PT-2.2A to include additional CAUTION statements for venting. Following the reactor trip, the A main feedwater pump inboard seal began leaking and was replaced prior to F\\~
pump restart. Unit 2 was restarted and returned to full power some 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after the trip. The inspector verified that the actual critical condition was within the estimated critical prediction (ECP) limits, and had no further question The licensee ramped Unit 2 from full power to some 94% power on
April 15, 1981, due to the temporary loss (approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) of both trains of heat tracing on one of the borated water flow paths (Panel 10 and 11, circuit 6A).
The Unit rampdown was restricted due to the discharge canal temperature limitations (3°F/hr). Following repair of the heat tracing, the Unit was returned to full power operation. A similar Unit 2 rampdown occurred on Apri~ 29, 1981, when both Unit 2 charging pump service water pumps lOA and 108 were inoperable for approximately 1 hou The Service Water (SW) pumps provide cooling water to the charging pump lubricating oil coolers and CCW system seal coolers for the charging pumps; the charging pumps were operable during the SW pump even On April 17, 1981, Unit 2 shutdown was initiated for an inaccessible snubber inspection and various maintenance and modification wor During the power decrease, the licensee performed special testing which
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demonstrated the stability of the feedwater control system at low power (e.g. -
10% load rejection at approximately 35% power).
Unresolved item 281/80-39-06 is close During the Unit 2 snubber inspection, 7 hydraulic suppressors (snubbers) were visually determined to be inoperable due to low fluid levels and were repaired or replaced prior to startup on April 27, 198 The next Unit 2 snubber inspection will be conducted in 62 days (+/-25%) in accordance with Technical Specification 4.1 The inspector reviewed the results of 2-PT-18.11, RCS Pressure Isolation Valves and Low Head Safety Injection Check Valve-Leakage Determination, to verify that leakage tests were performed in accordance with the 4/20/81 NRC Operating License modification' letter (generic) prior to Unit 2 restart. The test results were satisfactor Genera 1 Items The inspector reviewed circumstances surrounding the April 26 and 27, 1981, loss of the process vent due to water accumulation in the system pipin The primary drains tank (PDT) level control system malfunctioned, and the PDT overflowed through its relief line into the gaseous waste and process vent system. While the process vent blowers were temporarily out of service the water did not reach the HEPA and cha rcoa 1 filters (verified by inspection).
The process vent system was subsequently drained of water and retucned to servic Plant airborne radiation levels were evaluated with area and ventilation monitors while the process vent was inoperabl The inspector verified the following by observations: Gates and doors in protected and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plans were not compromise or obstructe Personnel were properly identified, searched, authorized, badged and escorted as necessary for plant_ access control.