IR 05000280/1985036
| ML18144A152 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/19/1985 |
| From: | Burke D, Marlone Davis, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18144A151 | List: |
| References | |
| 50-280-85-36, 50-281-85-36, NUDOCS 8512310333 | |
| Download: ML18144A152 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30323 Report Nos.:
50-280/85-36 and 50-281/85-36 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 Conducted: ~ovembftr 5 - December 2, 1985 Inspectors:
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M. J. ~~v:s, Riident Inspector Approved by: ~~!'7fo S. Elrod, Section Chief Division of Reactor Projects SUMMARY v(l(. '"*'"~
Date Signed 1)(.. l'\\11ikS'
Date Signed Scope:
This inspection involved 150 inspector-hours onstte in the areas of plant operations and operating records, pl ant maintenance and survei 11 ance, pl ant security, followup of events, licensee actions on previous enforcement items and licensee event reports (LERs).
Results:
In the areas inspected, no violations or deviations were identified.
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8512310333 851223 PDR ADOCK 05000280 G
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 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, health physics, plant maintenance, security, engineering, administrative, records, contractor personnel, and supervisor.
Exit Interview The inspection scope and findings were summarized on a biweekly basis with certain individuals 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 and Open Items (Closed) Infraction (281/80-24-05) concerned the auxiliary feedwater pumps which failed to meet start time acceptance criteria during testin Also an outside recirculation spray pump failed to start due to an improperly racked-in circuit breake Management review of test procedures failed to resolve problems or identify required retestin Components have subsequently been retested satisfactorily, and the procedures strengthene (Closed) Violation (280/85-01-02) failure to perform adequate Technical Specification (TS) 4.1 surveillance testing on control room chlorine detectors, containment hydrogen analyzers, and locks on the reactor vessel head ven Surveillance and administrative procedures have been revised and adequate testing implemente All of the administrative procedures (e.g., AP-24) were not revised by June 30, 1985, although the delays were discussed with the NRC.
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2 (Closed) Violation (280, 281/85-19-01), failure to properly prescribe or accomplish proper installation of safety-related EQ [environmentally qua 1 i fi ed] e 1 ectri ca 1 components in accordance with Criterion V of Appendix B to 10 CFR 5 A programmatic review and inspection of the electrical components has been performed and corrective actions have been implemented on discrepancies identifie (Closed) Open Item (281/80-26-01) concerned di ese 1 exhaust fumes accumulating in adjacent diesel rooms, apparently due to the horizontal exhausts on the emergency diesel generator (EOG) building roo Exhaust deflectors were subsequently installe (Closed) Unresolved Item (281/80-43-02) concerned bottom stoplogs inadvertently 1 eft in the Unit 2 high 1 eve 1 intake structure screenwe 11 A 1 so two portab 1 e pumps that had been 1 eft in the 2A screenwell could not be locate The stoplogs were subsequently removed and the pumps located, one was found previously removed but not documented, the second pump was found in the intake water box and remove (Closed) Open Item (280/84-04-02) concerned the malfunction of the auto reset of the Source Range (SR) high voltage following reactor trip when power level decayed to below the permissive setpoin The electronic circuitry has been adjusted and now appears to operate satisfactoril Reactor trip recovery procedures require operators to check SR indication and manually re-energize the detectors, if require (Closed) Open Item (280/85-01-04) concerned the improvement of the accuracy of the estimated critical positions (ECPs).
The licensee has completed an engineering study of estimated critical conditions, and has implemented refinements to the plant procedures and data in the plant curve books; recent predictions have been more accurat (Closed) Inspector Followup Item (280/85-32-03), correct containment isolation valve identification tags in the control roo The safety injection (SI) initiating signal was inscribed on the valve tag.
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 faci 1 i ty TS and procedure The inspector verified that monitoring equipment was recording as required, that equipment was properly tagged, and that
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plant housekeeping efforts were adequat The inspectors 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 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, 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 walkdowns of emergency core cooling systems and engineered safety features 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 perio No trips or shutdowns occurre Unit 2 began the reporting period in the last week of a 20 day snubber inspection and maintenance outag A reactor startup was conducted on November 6, 198 During power ascension on November 7, the reactor tripped from 22 percent power due to a high level signal from the
1 steam generator caused by manual overfeedin All systems functioned normally and the unit was restarted later that da Unit 2 operated at power for the remainder of the reporting perio.
Surveillance and Maintenance During the month, the inspectors verified that the surveillance or testing of various safety-related systems and components was performed in accordance with TS requirement Testing of the auxiliary feedwater pump(s), certain nuclear instrumentation and reactor protective system (RPS) channels, and motor operated valves (MOVs) was observe Maintenance or testing on certain MOVs was also verified to be in accordance with the procedures and requirement Within the areas inspected, no violations were identifie.
Licensee Event Report Review The inspectors reviewed the LERs listed below to ascertain that NRC reporting requirements were being met and to determine the appropriateness of corrective action taken and planne..
Certain LERs were reviewed in greater detail to verify corrective action and determine compliance with TS and other regulatory requirement The review included examination of logbooks, internal correspondence and records; review of Station Nuclear Safety and Operating Committee meeting minutes and discussions with various staff member (Closed) LER 280/83-23 concerned unmonitored steam generator (SG) blowdown to the condenser water boxe The radiation monitor (RM) flow isolation valves were not properly adjusted to allow for adequate blowdown flow through the RM when the monitoring system was placed in servic Startup checklists for the SG blowdown system were modified to ensure RM flow is monitored and verified correc The current practice is to recirculate SG b 1 owdown fl ow to the condenser hotwe 11 to reduce condensate rel ease and make-up requirement (Closed) LER 280/83-28 concerned a low level condition in the low pressure carbon dioxide (CO 2 ) storage tan The tank was being used to purge the Unit 2 main generator of hydroge The operator failed to monitor the purge and allowed the tank level to drop below the minimum required leve Fire watches were posted unt i 1 the tank was refi 11 e The generator purge procedure was changed to add a precaution to maintain the TS minimum level in the CO2 storage tan (Closed) LERs 280/83-50 and 83-56 concerned heat tracing panel feeder breakers tripping on ground fault during maintenanc Ground fault circuitry for heat tracing feeder breakers was subsequently modified to correct the feeder breaker ground fault circuitry; the thermal overload trip settings remain intac (Closed) LER 281/83-60 concerned the tripping of the feeder breaker for heat tracing pane 1 28 The breaker tripped due to a ground fault that occurred when the power supply AC fuse ble The redundant heat tracing panel was verified operabl The heat tracing panel was checked for grounds but no prob 1 ems were foun The fuse was rep 1 aced and the feeder breaker was rese (Closed) LER 281/83-56 concerned the tripping of containment spray pump motor breakers during attempted starts for periodic testin The motor breakers' instantaneous delay trip times were set lower than the optimum setting of.07 second The instantaneous delay trip times for the pump motor breakers were subsequently reset to. 07 seconds, tested sat i sfac-tori ly, and.returned to operable statu (Closed) LER 281/83-25 concerned the failure of service water motor operated valve, MOV-SW-202B, to cycle closed (electrically) due to a malfunctioning mechanis The clutch failed to disengage due to rust buildup between the clutch shaft and the motor operator housin The rust was removed and the valve was satisfactorily tested and returned to servic The valve is included in the licensee's programmatic review of safety-related MOVs (see Open Item 281/85-07-02).
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5 Plant Physical Protection The inspectors verified the following by observation: Gaies and doors in protected and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plan were not compromised or obstructe Personnel were properly identified, searched, authorized, badged, and escorted as necessary for plant access control.