IR 05000280/1985034
| ML18144A038 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/15/1985 |
| From: | Burke D, Marlone Davis, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18144A037 | List: |
| References | |
| 50-280-85-34, 50-281-85-34, NUDOCS 8512050443 | |
| Download: ML18144A038 (6) | |
Text
Report Nos. :
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 50-280/85-34 and 50-281/85-34 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 License Nos.:
DPR-32 and DPR-37 Facility Name:
Surry 1 and 2 Inspection Con~cted: Oct~;r 8 - November 4, 1985 c.-=-.,
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Inspectors: __,, C t*~
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D. J. Burk_e, S~~,ior Resident Inspector 5. ~\\t~ ~
M. J. Davis, Res~9ent Inspector Approved by: S * 6\\,~~ ~
S. Elrod, Section Chief Division of Reactor Projects SUMMARY Date Signed Date Signed J\\l DV I} 1'*5 Date Signed Scope:
This inspection involved 210 inspector-hours in the areas of plant operations and operating records, plant maintenance and surveillance, plant security, follow-up of events, 1 icensee actions on previous enforcement items, and Licensee Event Reports (LER).
Results:
In the areas inspected, no violations or deviations were identified. Persons Contacted Licensee Employees REPORT DETAILS 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 D. Rickeard, Supervisor, 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, healthy physics, plant maintenance, security, engineering, administrative, records, contractor personnel and supervisor Exit Interview The inspection scope and findings were summarized on a b~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 inspectio.
Licensee Action on Previous Enforcement Matters This was not inspected during this reporting perio.
Unresolved Items Unresolved Items were not identified during this inspectio.
Operations Units 1 and 2 were inspected and reviewed during the inspection perio The inspectors 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 inspectors verified that monitoring equipment was recording as required, that equipment was properly tagged, and that plant housekeeping efforts were adequat The inspectors also deter-mined that appropriate radiation contra 1 s were properly es tab 1 i shed, that clean areas were being controlled in accordance with procedures, that excess materi a 1 or equipment was stored properly, and that
combustible material and debris were disposed of expeditiously. During tours, the inspectors monitored the plant for unusual fluid leaks, piping vibrations, piping 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 backshift Inspections included areas in the Units 1 and 2 cable vaults, vital battery rooms, fire pump house, Unit 2 containment, emergency switchgear rooms, diesel generator rooms, control room, auxiliary building, and cable penetration areas to verify certain breaker and equipment conditions and positions for safety-related component The inspectors routinely conducted partial wa lkdowns of emergency core cooling systems and engineered safety features systems to verify operabi 1 i ty and observe maintenance and testing of certain equipment and components in these system While in the Unit 2 containment, the inspectors observed that solid, threaded plugs were installed in certain motor housings on auxiliary feedwater (AFW) system motor operated valves, MOV-FW-251A through The licensee replaced the solid plugs with T-drain plugs, similar to those installed in Unit 1, and is reviewing the impact of the solid plugs on the Limitorque MOV environmental qualification This is identified as inspector follow-up item (IFI) (281/85-34-01). Unit 1 operated at power for the duration of the reporting perio No trips or shutdowns occurre Unit 2 began the reporting period operating at powe On October 18, 1985, operators commenced a normal power rampdown in preparation for a snubber inspection and maintenance outag The unit was shutdown on October 19, 198 The unit was returned to hot standby on October 31, 1985, in preparation for startu Accumulator leakage into the residual heat remova 1 ( RHR) system through MOV-RH-2720B, with the unit at hot standby, caused increasing pressure in the RHR system and necessitated a return to cold shutdown for valve seat repair The valve disc and seats have been relapped and satisfactorily teste The maximum pressure in the RHR system due to the leakage was less than 500 psig (design is 1200 psig).
The inspectors verified that the requirements of TS 3.1.A.1.d were met; two reactor coolant loops were operable, and one reactor coolant pump and loop were in operation during isolation of the RHR system and repair of the valv The unit ended the reporting period in a cold shutdown condition with the RHR system isolated and drained for repair of MOV-RH-2720.
Surveillance and Maintenance Inspections During the reporting period, the inspectors reviewed various surveillance and maintenance activities to assure compliance with the appropriate proce-dures and TS Inspection areas included the following:
3 Maintenance activities concerned with the repacking of the motor-driven fire pump were observe Work was performed in accordance with Mechanical Maintenance Procedure MMP-C-G-15 No problems were note The inspectors observed concrete pouring operations for the Independent Spent Fuel Storage Installation; no discrepancies were observe The inspectors toured the low level (intake structure) facilities on October 15, 1985, and again on October 18, 1985, when emergency service water pump ( ESWP)
lA II smoked
a pump shaft gland packing during performance of its periodic testing following packing replacemen The 7/16 inch packing utilized was too tight for the low discharge pressure pump and blocked water leak-off and lubrication for the sea The packing was removed and 3/8 inch packing installed; the pump and seal were then satisfactorily teste The packing leak-off was slightly above normal on ESWP-lB and excessive on ESWP-lC; the licensee stated that the packings will be adjusted and/or replaced. * In addition, the ESWP-lC diesel had several seconds of delay between the actuation of the 11Start 11 button and the diesel engine start and ru The relays are being inspecte The inspectors also observed that some anchor bolts which secured the lB and lC diesel exhaust manifold piping supports to the ESWP room roof were missin Licensee analysis of and action on these items is identified as IFI (280/85-34-01). * *Reactor coolant system leak rates were reviewed to ensure that detected or suspected leakage from the system was recorded, investigated and evaluated and that appropriate actions were taken if require No abnormal leakage was observe The surveillance inspection included a review of several Periodic Test ( PT) procedures for both uni t Snubber visual inspection tests ( PT 39A-1, 39A-2, 39B-1 and 39B-2) were reviewed to ensure that inspections were being conducted within the required visual inspection interval Installed snubbers and supports were also inspected during plant tours and system inspection In the areas inspected, no violations were identifie The inspectors observed stroke testing of the Unit 2 recirculation spray (RS) MOVs (255A and B, 256A and B).
RS-MOV-255A rotated about 130 degrees at the Limitorque operator and 80 degrees at the tapered plug valve; 2558 rotated about 150 degrees at the operator and 100 degrees at the valv The 50 foot driveshaft between the valve and operator apparently accounts for the difference in rotatio The valves were satisfactorily Type C leak-tested (when closed) and subsequently adjusted to ensure complete and repetitive 90 degree trave The limit switches were al so changed to ensure adequate bypassing of the MDV torque switch during the open cycle, although the valves are open during normal plant operations and accident condition The RS-256A and B MOVs tested satisfactoril *
4 The inspectors requested that the 1 i censee operate one motor-driven AFW pump prior to the Unit 2 startup to ensure that the AFW fl ow rates to the steam generators ( SG) exceeded the minimum specified in Westinghouse Technical Bulletin 84-06 (105 gpm per SG).
Unit 2 AFW pump 3B delivered about 160 gpm to each SG at 980 psig; this item is close The inspectors reviewed NRC Inspection and Enforcement Information Notice 85-82, Emergency Diesel Generator Differential Protection Relay Not Seismically Qualified, and discussed it with licensee engineer The Genera 1 Electric re 1 ays specified in the Notice a re not used at Surry; Westinghouse relays are utilized and are being inspecte.
Licensee Event Report (LER) Review The inspectors reviewed the LERs 1 i sted be 1 ow 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 a nee with the TS and other regulatory requirement The review included examination of logbooks, internal correspondence and records, review of Station Nuclear Safety and Operat*ing Committee meeting minutes, and discussions with various staff member (Closed) LER 280/85-18 concerned a turbine trip/reactor trip caused by the reactor operator inadvertently closing the condenser inlet valves (MOV-CW-106 A,B,C and D) when attempting to throttle the condenser outlet valve Covers were subsequently placed on the condenser inlet valve control switches for both units to prevent inadvertent operatio The operator was reinstructed in the proper manipulation of valve control switches, specifically, that only one valve is to be operated at a tim (Closed) LERs 280/85-16, 85-17, and 85-20 concerned activity spikes of dose equivalent Iodine-131 following unit trips or shutdown The activity levels exceeded the TS limit of 1.0 microcuries/c The maximum activity was 1.89 microcuries/c The activity spike was caused by known, but not specifically located fuel element defect Post-shutdown conditions enhanced the re 1 ease of fission products, specifically I-131, thereby causing an increase in reactor coolant specific activit The level of activity was monitored at least once every four hours until it returned to less than 1.0 microcuries/c (Closed) LER 280/85-19 concerned two events where i ndi vi dua 1 rod position indication (!RPI) deviated more than 12 steps from the bank demand position for two rods in one grou For both events, at least one !RPI was returned to service within two hour The cause was believed to be instrumentation drift, s i nee the system was tested and no prob 1 ems could be foun Core data was monitored in accordance with the TS until the indicators were returned to servic..
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5 Plant Physical Protection 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 compromised or obstructe Personnel were properly identified, searched, authorized, badged and escorted as necessary for plant access control.