IR 05000395/1986016
| ML20215K492 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/20/1986 |
| From: | Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20215K469 | List: |
| References | |
| 50-395-86-16, NUDOCS 8610280192 | |
| Download: ML20215K492 (10) | |
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o UNITED STATES
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- NUCLEAR REGULATORY COMMISSION o
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Report No.:
50-395/86-16 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.:
50-395 License No.:
NPF-12 Facility Name:
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C.. Summer Inspection Conducted:
September 1-30, 1986 Inspect rs:
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Richard L'. Prevatte Da'te Signed 4' f AU-Per C.'Hopki ls
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Date S'igned
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Approved by-(
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/I 20 N Hugh/C. Dance,\\ Section Chief
'Date SAgned Division of Reactor Projects SUMMARY l
Scope:
This routine, announced inspection was conducted by the resident l
inspectors onsite, in the areas of licensee action on previous enforcement I
matters, onsite followup of events and subsequent written reports, monthly i
surveillance observations, engineered safety features system walkdown, monthly maintenance observation, operational safety verification, design changes and l
modification and, other areas.
Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees D. Nauman, Vice President, Nuclear Operations 0. Bradham, Director, Nuclear Plant Operations 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 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 W. Higgins, Associate Manager, Regulatory Compliance J. Sefick, Manager, Nuclear Security B. Williams, Supervisor, Operations Other licensee employees contacted included engineers, technicians, operators, mechanics, security force members, and office personnel.
2.
Exit Interview (30702, 30703)
The inspection scope and findings were summarized on October 2,1986, with those persons indicated in 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 (92702)
(Closed)
Unresolved Item 85-15-03, Requirement to verify tightness of battery terminals. This item expressed a concern with tne IEEE-450 standard requirement for checking tightness of battery connections.
The licensee committed to IEEE-450-1975, which requires that tightness be verified. This is accomplished by resistance measurements.
This approach is considered adequate by The Division of Reactor Safety in Region II and the resident inspector.
This item is closed.
(Closed)
Inspector Followup Item 83-36-02, Master cross reference of Technical Specifications (TS) components with LCO's, action statement, and the surveillance requirement.
This item identified the need to develop a master cross reference for TS.
General Test Procedures 701 and 702 have been issued and are currently being used to meet this requirement.
The licensee is additionally developing a computerized system to further enhance and improve this manual cross reference.
This item is close.
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(Closed)
Inspector Followup Item 83-15-10, Formal documentation of SAP 139 responsibilities. This item addressed concerns with formal documentation to cover the location of master copies of procedures, and the individuals responsible for their revision. A review of the current revision (7) of SAP 139, attachment III, indicates that the above items have been satisfactorily addressed.
This item is closed.
(Closed) Violation 84-37-01, Fai'ure to establish required fire watch for inoperable fire door.
The licensee provided a written response to this violation in a letter to Region II dated March 1,1985.
The inspectors reviewed the licensee's response and corrective actions.
These actions appear adequate to prevent recurrence.
This item is closed.
(Closed)
Inspector Followup Item 85-30-01, Licensee commitment to enhance commitment tracking system.
The inspector has reviewed the licensee procedure for Regulatory Tracking Systems which assigns an " Issue Manager" for each item that requires any type of followup of regulatory items.
The procedure appears to be working well. This item is closed.
(Closed) Special Report 84-018, RHR "B" Train suction relief valve actuated due to reactor coolant system pressure transient. The licensee submitted a special report to Region II on the above item in a letter dated January 3, 1985. The inspector reviewed the action taken by the licensee to correct this item and to preclude recurrence.
These actions are considered satisfactory to correct this item and prevent recurrence.
This item is closed.
.(Closed) Inspector Followup Item 86-05-02, Revise Attachment V to procedure HPP-904, to reflect the entire meter range.
The item identified an inconsistency between the instrument reading and the graphs used to convert the reactor building purge exhaust noble gas instrument readings from millirem / hour (mrem /hr) to microcuries/ milliliter (mci /ml), for use in manual dose calculations.
The instrument meter range was 0.1 mrem /hr to 1,000,000 mrem /hr and the graph range was 1 mrem /hr to 1,000,000 mrem /hr.
The licensee replaced the two applicable graphs with revised graphs that were implemented into procedure HPP-904 under revision 4, change B, on August 21, 1984.
The inspector verified that these changes were implemented.
This item is closed.
(Closed)
TMI Action Plan Item II.B.I.2, Install reactor coolant system vents.
The requirements of this item were superseded by
10CFR50.44(C)(3)(iii). A telephone conference with the NRR Project Manager on September 16, 1986, indicated that this item has been closed by NRR, and
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the review of the procedures associated with this item is being accomplished
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by NRR under TMI Item I.C.1.3.B.
The reactor coolant system vents were
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installed prior to initial fuel loading. The procedures associated with
system operation are covered in Emergency Operating Procedure (EOP) 18.2,
Hesponse to Voids in the Reactor Vessel, which was implemented on August 29,
1984. This item is closed.
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(Closed)
Inspector Followup Item 86-12-03, Error in 5 cals program.
The resident inspectors followed this item until a Region II Inspection Report No. 50-395/86-14, cleared the item.
Paragraph SC of the above report classified the item as a Licensee Identified Violation (LIV 395/86-14-02):
Failure to Perform an Adequate 50.59 Review.
Corrective action will be tracked by Region II as an Inspector Followup Item 86-14-0I. This item is closed.
(Closed)
Unresolved Item 86-09-01, Battery room temperature setpoints.
The licensee conducted an extensive study which indicates that the temperature setpoints were not exceeded. The inspectors reviewed this study and concur with the licensee's conclusion. This item is closed.
(Closed)
Inspector Followup Item 84-11-04, Galvanized plug replacement.
This item was closed in Report 84-12, under item 9C. A typographical error resulted in this item being identified as item 84-11-03. Item 84-11-03 was
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closed in report 84-34 under item 11. To clear these administrative errors,
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this item is closed in this report.
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(Closed)
Violation 85-37-01, Feedwater isolation valve inoperable by isolation of its instrument air supply. The licensee provided a written response to this violation in letters to Region II, dated November 27, 1985 and June 6, 1986.
The inspector reviewed the licensee's response and corrective actions and they appear to be adequate. This item is closed.
(Closed)
Licensee Identified Item 83-15-09, Part 21 SA-1 relay problem.
This problem was initially identified to the licensee by IE Information
Notice 83-63, Supplement 1, which addressed leaking tantalum capacitors.
Rather than replacing the faulty capacitors, Westinghoase recommended replacing the printed circuit board module. The installed relays for Diesel Generator (DG) A and B differential relays, had their circuit boards replaced under MWR's 86E0033 and 8600730. The inspector verified that the l
correct circuit boards model 408C673G01, revision 36, are installed in both DG relays.
The licensee has one defective relay onsite in shop stores.
j This item is controlled under nonconformance NCN 1590 and QC hold tag
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86E0033.
A replacement for this relay has been received onsite and is currently awaiting calibration.
Upon completion of this calibration, the defective spare relay will be returned to Colt Industries for circuit board replacement.
The inspector considers the licensee's controls adequate to insure that this remaining spare will be returned to the vendor for repair and/or replacement as required.
This item is closed.
4.
Monthly Surveillance Observation (61726)
The inspectors observed surveillance activities of safety related systems l
and components to ascertain that these activities were conducted in accordance with license requirements.
The inspectors observed portions of selected surveillance tests including all aspects of one major surveillance
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test involving safety related systems.
The inspectors also verified that the required administrative approvals were obtained prior to initiating the test, that the testing was accomplished by qualified personnel, that required test instrumentation was properly calibrated, that data met TS requirements, that test discrepancies were rectified, and that the systems were properly returned to service.
The following specific surveillance activities were observed:
STP 114-002 Operational Leak Test STP 142-001 Reactor Coolant Systems Valve Operability Test STP 118-004 Reactor Building Purge Isolation Verification STP 125-001 Electrical Power System Weekly Test STP 125-002 Diesel Generator Operability Test STP 112-002 Reactor Building Spray Pump Test STP 345-040 Emergency Safety Feature Actuation Slave Relay Test STP 345-057 Steam Generator "C" - Wide Range Level Instrument ILT 497A Calibration STP 396-014 Emergency Feedpump Suction Pressure Instrument IPT 3635 Operational Test STP 102-002 NIS Power Range Heat Balance Calculation STP 115-001 Penetration Isolation Verification STP 123-001 Service Water System Valve Lineup Verification STP 303-011 Steam Generator
"A" - Steam Pressure IPT 0476 Instrument Operational Test STP 303-012 Steam Generator
"B" - Steam Pressure IPT 0486 Instrument Operational Test STP 104-003 Boron System Valve Lineup Verification STP 303-013 Steam Generator
"C" - Steam Pressure IPT 0496 Instrument Operational Test STP 112-003 Reactor Building Spray System Valve Operability Test STP 120-001 Motor Driven Emergency Feedwater Pump Operability Test STP 506-009 Reactor Trip Breaker Shunt Trip Verification
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STP 302-031 Steam Generator "A" - Steam /Feedwater Flow Instrument IFT-475 and IFT-476 Operational Test STP 127-001 Pressurizer Block Valve Operability Test STP 396-006 Emergency Feedpump Suction Pressure Instrument IPT 3633 Calibration STP 345-074 Solid State Protection System Activation Logic and Master Relay Test for Train "B" STP 345.075 Solid State Protection System Monthly Actuation of Train "A" Reactor Trip Breaker and Test of SI Time Delay STP 360.064 Liquid Waste Effluent Liquid Radiation Monitor (RM LS)
Operational Test No violations or deviations were identified.
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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 accordance with approved procedures, TS and appropriate industry code; and standards.
The inspectors also determined that the procedures used were adequate to control the activity, and that these activities were accomplished by qualified personnel. The inspectors. independently verified that equipment was properly tested before being returned to service.
Additionally, the inspectors reviewed several outstanding job orders to determine that the licensee was giving priority to safety related maintenance and a backlog which might affect its performance was not developing on a given system.
The following specific maintenance activities were observed:
MWR 8610303 Replacement of Temperature Indicator Diesel Generator "A" EMP 295-004 Inspection and Post Maintenance of Electric Motors MMP 180.030 Diesel Generator Injection Pump Racks and Fuel Control Linkage Inspection and Maintenance Check MMP 180.033 Emergency Diesel Generator Quarterly Valve Maintenance MWR 8601022 Repair of Inlet Screen Check Valve on Service Water System MWR 20919001 Install Permanent Jumper in Terminal Box CS 38 MWR 85M00413 Repair Service Water Inlet Valve
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No violations or deviations were identified, i
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6.
Operational Safety Verification (71707)
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The inspectors toured the control room, reviewed plant logs, records and
held discussions with plant staff personnel to verify that the plant was being operated safely and in conformance with applicable requirements.
Specific items inspected in the control room included: adequacy of 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 were conducted to verify equipment operability; control of ignition sources and combustible materials; the condition of fire detection and extinguishing equipment; the control of maintenance and surveillance activities in progress; the
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implementation of radiation protective controls and the physical security plan. Tours were conducted during normal and random off hour periods.
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No 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 l
control room normal and emergency air handling systems.
The inspectors
confirmed that the licensee's system lineup procedures matched plant drawings and.the as-built configuration.
The inspectors looked for
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equipment conditions and items that might degrade performance (hangers and
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supports were operable, housekeeping, etc.) and inspected the interiors of electrical and instrumentation cabinets fer debris, loose material, jumpers, evidence of rodents, etc. 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 l
both local and remote position indications.
i No violations or deviations were identified.
8.
Onsite Followup of Events and Subsequent Written Reports (92700, 90713, 93702)
The inspectors reviewed the following Part 21 Reports, Licensee Event
Reports (LER's) and Special Procedure Reports (SPR's) to ascertain whether j
the licensee's review, corrective action and report of the identified event j
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:
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(Closed)
10 CFR 21 Report p2184-01, Emergency D/G fuel injection pump holder fatigue crack.
The licensee's survey of existing shelf stock and rebuilt pumps revealed that two pumps had been rebuilt by Colt Industries after
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January 1982. These two pumps have been returned to Colt Industries for reinspection and replacement of defective parts as required. The review of all other installed or spare replacement parts by the licensee did not identify any additional deficiencies associated with this item. This item is closed.
(Closed)
10 DFR 21 Report P2185-01, Unqualified terminal blocks for hydraulic actuators. This item involved a deficiency in Connection Model NU2, special replacement terminal blocks for Anchor / Darling valves.
Spare / replacement terminal blocks that are manufactured out of nylon are not 1EEE qualified.
The licensee has verified that no spare / replacement terminal blocks have been ordered. A search of warehouse parts and records did not reveal any of the above mentioned items presently existing in replacement stock.
This item is not applicable and is, therefore, closed.
(Closed)
10 CFR 21 Report P2184-02, Deficient gimpel valve for auxiliary feedwater pump drive turbine. This item involved a deficiency in the design of a 4 inch valve spring that could prevent the valve from closing under high inlet pressure and Icw steam flow.
The licensee purchased and installed the manufacturers recommended replacement springs. The licensee has additionally verified that none of these defective parts are in stock as replacement parts.
This item is closed.
LER 83-110 RCS TAVG Exceeded limits at T.S.3.2.5 due to failure of PM6-22 LER 84-039 Degraded fire barrier LER 85-021 Missed hourly fire watch due to personnel error LER 85-022 Reactor trip problem with overpower delta temperature setpoint LER 85-024 Reactor trip non-conservative response on the overpower delta femperature setpoint LER 85-020 Valve not tested prior to return to service LER 86-004 Missed instrument channel operability checks LER 86-012 Loss of offsite power LER 86-006 Turbine trip - Reactor trip LER 85-031 Steam Generator eddy current examination LER 85-032 Failure of D/G Excitor Regulator LER 85-017 Separation of vital power cable trays LER 86-008 High temperature setpoint associated with Station Battery Room A/B was such that T.S. limits could have exceeded prior to receipt of an alarm
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LER 85-027 Reactor Trip; Inoperable Feedwater isolation valves
LER 86-001 Significant safety hazard attributable to Anchor / Darling check valves SPR 86-007 High temperature differential between Diesel Generator exhaust cylinders
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SPR 86-001 Inoperable fire barrier i
SPR 86-004 Reactor building temperature monitor SPR 85-078 Inoperable Diesel Generater l
SPR 86-002 Inoperable fire barrier
SPR 84-018 RHR
"B" train suction rel:ef valve actuation due to RCS pressure transient No violations or deviations were identified.
J 9.
Design Changes and Modifications (37700)
i The inspectors reviewed four design changes, listed below, not previously approved by NRR, to assure that the changes had been reviewed and approved in accordance with the Technical Specifications (TS) and 10 CFR 50.59.
i During the review, the inspectors verified (1) that the design changes were
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reviewed and approved in accordance with TS and established QA/QC controls, l
(2) that design changes were controlled by established procedures, (3) that i
the licensee conducted a review and evaluation of test results and that
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these test results wera within previously established acceptance criteria
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and'that any test deviations were resolved and necessary retesting was
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accomplished as appropriate, (4) that operating procedure modifications were made and approved in accordance with TS, and (5) that as-built drawings were changed to reflect the modifications.
The inspectors observed (1) that
change activities were conducted in accordance with the appropriate i
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specifications, drawings, and other requirements, (2) that acceptance and startup testing of modifications were conducted in accordance with
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j technically adequate and approved procedures, and (3) that appropriate i
controls were implemented, (e.g.,
firewatch, portable fire fighting i
equipment, welding and cutting permit, etc.).
Additionally, the inspectors
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reviewed the outstanding facility change requests (FCR's) and determined
that an excessive backlog was not developing.
MRF 20811 Limit switches for control room position indication on air
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i handling dampers MRF 20944 Modification to the under voltage relays for the reactor coolant pumps
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MRF 20840 Appendix "R" modi,fications for emergency lighting MRF 21056 Installation of summing amplifiers for main steam flow transmitters No violations or deviations were identified.
10. Other Areas (71707) (TI 2515/68)
The resident inspector completed the safeguards training for resident inspectors prescribed in Temporary Instruction (TI)
2515/68, on September 17, 1986.
This training was conducted by a Region II Safeguards Specialist during a regularly scheduled site inspection visit.