IR 05000395/1987033
| ML20237A488 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/08/1987 |
| From: | Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20237A477 | List: |
| References | |
| 50-395-87-33, NUDOCS 8712150035 | |
| Download: ML20237A488 (9) | |
Text
UNITED STATES d'p P MEcug*
NUCLEAR REGULATORY COMMISSION
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REGION 11 j
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Report No.-
50-395/87-33 Licensee:
South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.:
50-395 License No.
NPF-12 Facility Name: V. C. Summer j
i Inspection Conducted: November 1-30, 13 7 j
Incpectors:
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R'ic ard L. Prepatte D/it / Signed
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Per y0C, Hopki s i
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Approved by:
i Hugh (/. Dancer Section Chief Dite' Si gned Division of Reactor Projects
SUMMARY Scope:
This routine, announced inspection was conducted by the resident inspectors onsite, in the areas of licensee action on previous inspection findings, onsite followup of events and subsequent written reports, monthly surveillance observations, engineered safety features system walkdown, monthly maintenance observation, operational safety verification, cold weather preparations, information meeting with local officials and other areas.
Results: No violations or deviations were identified.
j 8712150035 871210 I
PDR ADOCK 05000393 G
PDR l
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I REPORT DETAILS I
1.
Persons Contacted i
Licensee Employees D. Nauman, Vice President, Nuclear Operations
- 0. Brad. nn, Director, Nuclear Plant Operations l
D. Moore, Director, Quality and Procurement Services
- J. Skolds, Deputy Director, Operations and Maintenance
- G. Soult, Manager, Operations M. Browne, Group Manager, Technical and Support Services M. Quinton, Manager, Maintenance Services
- A. Koon, Manager, Technical Support j
G. Putt, Manager, Scheduling and Materials Management K. Woodward, Manager, Nuclear Education and Training L. Blue, Manager, Support Services S. Hunt, Manager, Quality Assurance Surveillance Systems
K. E. Beale, Manager Nuclear Protection Services A. Paglia, Manager Licensing i
- W. Higgins, Associate Manager, Regulatory Compliance
- B. Williams, Supervisor, Operations
NRC Resident Inspectors
- R. Prevatte, Senior Resident Inspector P. Hopkins, Resident Inspector Other licensee employees contacted included engineers, technicians, operators, mechanics, recurity force members, and office personnel.
- Attended exit interview 2.
Exit Interview (30702,30703)
The inspection scope and findings were summarized on November 30, 1987, with those persons indicated i ri paragraph 1 above.
The inspectors described the areas inspected and discussed the inspection findings.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during the inspection.
3.
Licensee Action on Previous Inspection Findings (92701, 92702)
(Closed) TI2500/19, Inspection of licensee's actions taken to implement unresolved safety i.i ma A-26; Reactor Vessel Pressure Transient Protection for Pressurized Water Reactors.
This issue addresses the requirements to resolve the safety margin-to-failure for PWRs should they
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be subject to severe pressure transients while at a relatively low l
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temperature.
The licensee design to provide the overpressure protection i
consists of a passive system with two spring loaded relief valves, one on (
each train, on the suction side of the Residual Heal Removal (RHR) pumps.
These valves were designed in accordance with ASME,Section III, Class 2 requirements and each value has a relief area of 2.853 square inches when j
full open.
The opening pressure is set at 450 psig.
This design was reviewed and approved by NRR as a part of Amendment No. 26 to the facility J
operating licensee, which was issued on September 24, 1984.
A 10 CFR i
50.59 evaluation of this design was provided to NRR on October 21, 1983, as a part of the request for this design change.
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i In the area of administrative controls and procedures no strict administrative control exists to minimize the time the reactor coolant j
system is in a solid condition.
However, the plant General Operating j
Procedure (GOP), Plant Shutdown and Cooldown From Hot Shutdowns to Cold
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Shutdowns GOP-7 directs that once the Reactor Coolant System (RCS) is placed in a solid condition that the RCS should be placed in a nitrogen float or the loops drained to a half pipe condition.
GOP, Appendix A, limits the temperature differential between the steam generators and the reactor vessel to 50 degrees F when the pressurizer level is greater than 92 percent.
GOP 1 and GOP 7 require that two of the three charging /high pressure safety injection pumps be secured and tagged out. prior to placing the RCS in a solid condition. A pressurizer relief tank high temperature alarm set at 113 degrees F will alert the operator if a RHR suction relief valve actuates to relieve an overpressure condition in the RCS. The two installed relief valves are in accordance with the plant license.
The operator training and requalification training program covers the
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installed system. Emphasis is also placed on low temperature events that have occurred at other plants.
System Operating Procedure.101 (Residual Heat ROVAC System) directs the operator to trip all pressurizer heaters
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prior to taking system solid. An alarm is available to alert the operator if RCS temperature is less than 300 degrees F and any RHR suction valve is not fully open.
There is also an alarm for the RHR pump discharge pressure set at 550 psi to alert the operator of impending overpressure.
In the areas of surveillance, Surveillance Test Procedure (STP) 401.005, RHR Inlet Header Relief Valve Test, is performed on one of the two valves every 18 months to verify the set point and operability.
STP 127.003, Overpressure Protection Alignment, is performed once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when this system is in use to verify that the RHR suction valves are open.
J There are no electronics associated with these mechanical relief valves.
(Closed) Violation 87-14-01, Failure to properly evaluate and classify an event.
The licensee provided a written response to this violation in a letter to Region 11 dated July 14, 1987.
The inspector i ewed the licensee's responses and the corrective actions taken ts prevent
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recurrence.
These actions included additional training of shift
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supervisors, interim emergency directors, and management duty supervisors.
This training has additionally been incorporated into lesson plans for requalification training.
This item is closed.
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4.
Monthly Surveillance Observation (61726)
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The inspectors observed surveillance activities of safety related systems and components to ascertain that these activities were conductad in
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accordance with license requirements. The inspectors observed poi sons of selected surveillance tests including all aspects of one major surveil-lance test involving safety related systems. The inspectors also verified that required administrative approvals were obtained prior to initiating the test, testing was accomplished by qualified personnel, required test instrumentation was properly calibrated, data met Technical Specification (TS) requirements, that discrepancies were rectified, and the systems were properly returned to service.
The following specific surveillance
act'vities were observed:
STP 125.001 Electric Power System Weekly Test STP 125.002 Diesel Generator Operability Test l
STP 148.001 Feedwater Valve Operability Test STP 302.025 Steam Generator "A" Narrow Range Level III Instrument i
(LT-476) Operational Test STP 502.003 120 VAC and 125 VDC Circuit Breaker Test STP 503.003 Functional Test Of Swing Water To Emergency Feedwater Cross Connect Circuitry STP 506.002 Reactor Coolant Pump Undervoltage Unit Trip Actuating Device Operational Test STP 506.003 Reactor Coolant Pump Underfrequency Unit Trip Actuating Device Operational Test STP 105.003 Safety Injection Valve Operability Test STP 112.003 Reactor Building Spray System Valve Operability Test STP 123.003 Service Water Valve Operability Test STP 302.001 Delta T - Tavg Protection Loop 1 Operational Test No violations or deviations were identifie,
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5.
Monthly Maintenance Observation (62703)
The inspectors observed maintenance activities of safety related systems and components to ascertain that these activities were conducted in
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accordance with approved procedures, TS and appropriate industry codes and I
standards. The inspectors also determined that the procedures used were adequate to control the activity, and that these activities were accom-plished by qualified personnel.
The inspectors independently verified j
that equipment was properly tested before being returned to service.
l Additionally, the inspectors reviewed several outstanding job orders to determine that the licensee was giving priority to safety related I
maintenance and a backlog which might affect its performance was not developing on a given systenn The following specific maintenance activities were observed:
MWR3195200V4 Reinstall the overcurrent swing relay and perform wiring changes on relay XIT5908 cabinet l
l PMTSP198754 Perform MOVATS test on limitorque valve XVG02899C-MS PMTS0172 Perform limitorque on high pressure operator headers to the main steam drain valve l
MWR205280033 Modify breaker enclosure and install cell switch linkage hardware on service water system pump PMTSP0093527 Inspect and clean air start distributor air inlet filter on
"B" diesel generator MWR870170 Inspect and clean strainer elements en "B" diesel generator l
MWR8701700 Rep ~ lace "0" ring seals on No. 10 cylinder lower valve train on "B" diesel generator PMTS0094141 Inspect, lubricate and repair "B" diesel generator crankcase vacuum pump motor PMTSP0094086 Inspect, lubricate and check resistance on
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diesel generator air start compressor air dryer motor l
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PMTSP0094106 Inspect and check winding resistance on "B" diesel
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generator fuel oil transfer pump 4B motor i
PMTS0094140 Inspect, lubricate and check winding resistance on fuel oil transfer pump 141B on "B" diesel generator PMTSP0094921 Inspect and lubricate
"B" diesel generator outboard alternator bearing
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j PMTS0094386 Inspect, adjust and lubricate injection pump rack and fuel control linkage on
"B" diesel generator i
i PMTSP0094668 Perform inspectien on and lubricate rocker arm, fuel linkages, injection pump rockers and turbocharger on I
diesel generator "B" l
PMTSP0094667 Perform inspection on and lubricate rocker arm, fuel linkages, injection pump rockers and turbocharger on diesel generator "A" MWR8700129 Repair recirculating line on the boron condensate system
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MWR87M0374 Pressure test snubbers SN1644 and SN1648 MWR20528009 Modify breaker enclosure and install cell switch linkage hardware in spray pump "B" breaker cubicle (
PMTSP0094757 Two year electrical maintenance inspection and test of service water booster pump "A" breaker l
No violations or deviations were identified.
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6.
Operational Safety Verification (71707)
The inspectors toured the control room, reviewed plant logs, records and i
held discussions with plant staff personnel to verify that the plant was j
being operated safely and in conformance with applicable requirements.
Specific items inspected in the control room included: adequacy of j
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staffing and attentiveness of control room personnel, TS and procedural adherence, operability of equipment and indicated control room status, control room logs, tagout books, operating orders, jumper / bypass
controls, computer printouts and annunciators. Tours of other plant areas i
were conducted to verify equipment operability, control of ignition
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sources and combustible materials, the condition of fire detection and I
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extinguishing equipment, the control of maintenance and surveillance l
activities in progress, the implementation of radiation protective centrols and the physical security plan.
Tours were conducted during normal and random off hour periods.
O November 3, 1987, the licensee discovered that STP 505.001, Diesel
. iven Fire Pump Weekly Battery Test, was performed outside the grace period allowed.
The test was scheduled to be performed on October 30, 1987, with an end date of November 1, 1987, and was performed on November 2, 1987. This period was within the 1.25 x 7 day period allowed for a waekly STP but was not within the 3.25 x frequency for three consecut\\ve test.
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This is contrary to the requirements of TS 4.7.9.1.3 which requires that this test be accomplished every 7 days.
TS 4.0.2 specifies the maximum allowable extension in intervals between these tests.
Further review of this problem indicated that this test was missed by approximately two j
hours. This was only the second STP missed by the licensee in the past year.
The licensee took immediate corrective action to preclude i
recurrence of this problem.
k The NRC wishes to encourage and support licensee initiative for self-
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i identification and correction of problems and since this item meets the applicable guidance of NRC enforcement policies for licensee identified items, contained in 10 CFR 2, Appendix C, no violation will be issued.
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No other violations or deviations were identified.
7.
ESF System Walkdown (71710)
The inspectors verified the operability of an engineered safety features (ESF) system by performing a walkdown of the accessible portions of the 7.2 kV Switchgear, Emergency Diesel Generator "A" and "B" and the Diesel Fuel Oil System.
The inspectors confirmed that the licensee's system j
lineup procedures matched plant drawings and the as-built configuration.
The inspectors looked for equipment conditions and items that might degrade performance (hangers and supports were operable, housekeeping, etc.) and inspected the interiors of electrical and instrumentation cabinets for debris, loose material, jumpers, evidence of rodents, etc.
I The inspectors verified that valves, including instrumentation isolation valves, were in proper position, power was available, and valves were locked as appropriate.
The inspectors compared both local and remote position indications. Minor deficiencies were brought to the attention of the licensee and were immediately corrected.
No violations or deviations were identified.
8.
Onsite Followup of Events and Subsequent Written Reports (92700,93713, 93702)
The inspectors reviewed the following Licensee Event Reports (LERs) and Special Procedures Reports (SPRs) to ascertain whether the licensee's review, corrective action and report of the identified event or deficiency was in conformance with regulatory requirements, technical specifications, license conditions and licensee procedures and controls. Based upon this review the following items are closed.
SPR 87-007 Inoperable reactor building purge supply and exhaust system noble gas effluent monitor LER 87-24 Negative rate trip due to technician deenergizing rod control power supply
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SPR 87-003 Downgraded vital area l
SPR 86-09 Diesel generator "B" high cylinder temperature
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SPR 86-07 RM-A14 out of service for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LER 87-23 Control room ventilation aligns to recirculation mode due to spurious high radiation signal
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LER 87-019 Instrument air supply to control room ventilation intake dampers LER 87-005 Pressurizer safety valve setpoints out of tolerance f
No violations or deviations were identified.
9.
Cold Weather Preparations (71714)
The inspectors conducted a review of the licensee's cold weather preparations to ascertain tnat the licensee maintained effective implementation of protective measures for extreme cold weather, The inspectors verified that the licensee had inspected systems susceptible to freezing to verify the operability of heat tracing, space heaters, and the condition of installed insulation.
The inspectors also verifiad that systems which had been subjected to maintenance or modification during the past year had had the heat tracing and/or insulation returned to an i
operable condition.
External systems that provide cooling during hot weather only, have been drained to preclude freezing and external doors were verified closed.
No violations or deviations were identified.
10.
Information Meeting With Locai Officials (94600)
The resident inspectors met with the County Administrator, the Director of Emergency Preparedness and the County Sheriff for Fairfield County on November 12, 1987, and with the County Administrator and the Director of Emergency Preparedness for Newberry County on November 19, 1987.
This meeting was held to update these officials on the NRC mission and changes in the NRC organization since the last meeting.
In addition, an informal visit and review of the materials in the Public Document Room at the Fairfield County Library was conducted.
The materials were well main-tained and readily available for public use.
11.
Other Areas The inspectors attended a meeting of the Licensee's Management Review Board on November 3, 1987. This board, comprised of the Vice President, Nuclear Operations and the Directors for Plant Operations, Quality Services and Technical Services, reviews all reactor trips - and other
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significant plant events.
This meeting reviewed the reactor trips that occurred on October 29 and 30,1987.
The boards review of these events were open and frank and appeared to focus on determining the root cause and required corrective actions to preclude reoccurrence of these events.
Observation of the meeting indicated that the board will emphasis corrective and preventive action rather than strict disciplinary action for errors.
A Swiss Physical Protection Team composed of Mr. Eric Chabloz and Mr.
Paul Laug of the Swiss Federal Office of Energy visited the V.C. Summer
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Plant on November 4, 1987.
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